1. Readiness Review Course November 2006

2. Nov 20062 Readiness Review Course Introduction – Mod 1

3. Nov 20063 Learning Objectives Understanding the definition and purpose of a Readiness Review; Understanding the differences between an Operational Readiness Review and a Readiness Assessment; Knowledge of current DOE Orders, Directives, and References for the Readiness Review process; Knowledge of general terms used in the Readiness Review Process.

4. Nov 20064 Definition of a Readiness Review A disciplined, systematic, documented, performance-based review of: Facilities Equipment and Systems Personnel Procedures Safety Management Programs (e.g., Emergency Management, Safety Analysis, Conduct of Operations, Integrated Safety Management, Quality Assurance, Industrial Hyg and Safety, Waste Management, etc.)

5. Nov 20065 Purpose of a RR Ensure readiness of facility and personnel to start the facility within the bounds of acceptable risk defined by: –The Safety Basis/Authorization Agreement; –Applicable ES&H regulations. Ensure the facility/activity has adequate Safety Management Programs implemented and sufficient controls in place to start and continue operations within those bounds.

6. Nov 20066 RR Historical Summary 9-23-86, DOE 5480.6, Safety of DOE-owned Nuclear Reactors; 9-23-86, DOE 5480.6, Safety of DOE-owned Nuclear Reactors; 3-3-90, DNFSB 90-4, Rocky Flats Restart; 3-3-90, DNFSB 90-4, Rocky Flats Restart; 11-12-91, SEN-16B-91, Approval for Restart of Facilities Shutdown for Safety Reasons and for Startup of Major New Facilities; 11-12-91, SEN-16B-91, Approval for Restart of Facilities Shutdown for Safety Reasons and for Startup of Major New Facilities; 2-26-92, NE-1 Procedure for Restart of Reactor & Non-reactor Nuclear Facilities; 2-26-92, NE-1 Procedure for Restart of Reactor & Non-reactor Nuclear Facilities; 8-26-92, DNFSB 92-6, Order/Standard Development; 8-26-92, DNFSB 92-6, Order/Standard Development; 9-17-92, EM Policy and Guidance for Readiness Determinations; 9-17-92, EM Policy and Guidance for Readiness Determinations; 9-15-93, DOE O 5480.31/ 425.1, Startup and Restart of Nuclear Facilities; 9-15-93, DOE O 5480.31/ 425.1, Startup and Restart of Nuclear Facilities; 12-93, DOE-STD-3006-95, Planning and Conduct of ORRs/RAs, updated; 12-93, DOE-STD-3006-95, Planning and Conduct of ORRs/RAs, updated; 9-26-99, DNFSB Letter on ORR/RA inadequacies, leading to 425.1B and 3006-00; 9-26-99, DNFSB Letter on ORR/RA inadequacies, leading to 425.1B and 3006-00; 10-00, DOE ORR/RA Course created, developed, conducted as needed/as requested ; 10-00, DOE ORR/RA Course created, developed, conducted as needed/as requested ; 6-15-00, DOE-STD-3006-00 (series); 6-15-00, DOE-STD-3006-00 (series); 3-13-03, 425.1C (series); 3-13-03, 425.1C (series); 12-15-03, DOE 3012-2003 (series). 12-15-03, DOE 3012-2003 (series).

7. Nov 20067 DOE O 425.1C, Startup and Restart of Nuclear Facilities – For Startup and Restart of Hazard Category 1, 2, and 3 Nuclear Facilities – Delineates whether an Operational Readiness Review (ORR) or a Readiness Assessment (RA) is required – Delineates the Authorization Authority – Defines the 18 Minimum Core Requirements – References the use of DOE-STD-3006-2000 Orders and Directives Cont.

8. Nov 20068 Orders and Directives Cont. DOE-STD-3006-2000, Planning and Conduct of Operational Readiness Reviews – Provides guidance regarding the implementation of DOE O 425.1C; – Provides for a consistent approach in planning and performing a readiness review; – Provides templates and sample documents which can be used in organizing and performing a readiness review; – Can be used as guidance in the development of Site Office procedures.

9. Nov 20069 Orders and Directives Cont. DOE-HDBK-3012-2003, Team Leader's Preparation Guide for Operational Readiness Reviews (ORR) DOE-HDBK-3012-2003, Team Leader's Preparation Guide for Operational Readiness Reviews (ORR) – Provides guidance to the Team Leader on how to plan, manage, perform, and document a RR; – Defines the Team Leader, Team Members, and Administrators roles and responsibilities; – Provides templates and forms to assist in developing RR

10. Nov 200610 Readiness Review Operational Readiness ReviewReadiness Assessment Startup Hazard Category 1, 2, 3 Restarts Hazard Category 1 & 2 – Unplanned shutdown – Extended shutdown – Substantial process/system/ – Facility changes Major changes to safety basis Whenever deemed appropriate by DOE Restarts – Nuclear Facilities – Hazard Category 3 Startup/restart nonnuclear – High, Moderate, or Low hazard When deemed necessary by Site Office Operational Readiness Review and Readiness Assessment

11. Nov 200611 A readiness review required for: A readiness review required for: – Startup of new hazard categories 1, 2, and 3 nuclear facilities – Restart of hazard categories 1 and 2 nuclear facilities – Whenever deemed appropriate by DOE Management Officials for any nuclear facility Operational Readiness Review

12. Nov 200612 Readiness Assessment A readiness review required for: – Restart of nuclear facilities not requiring an ORR, as defined in DOE O 425.1C – Graded approach to application of the 18 minimum core requirements

13. Nov 200613 Exemption Process DOE-STD-3006-2000, Ch 4.6 & 5.11 references DOE O and M 251.1-1, Ch X which describes: General Provisions; Exemption Approval Process (Approval Authority, CSO, OPI, EH, NNSA CTS); Exemption Request (Information needed); and Approval Criteria. DOE-STD-3006-2000, Ch 4.6 & 5.11 references DOE O and M 251.1-1, Ch X which describes: General Provisions; Exemption Approval Process (Approval Authority, CSO, OPI, EH, NNSA CTS); Exemption Request (Information needed); and Approval Criteria.

14. Nov 200614 Definitions

15. Nov 200615 Definitions Readiness-to-Proceed Memorandum – A formal document from the Contractor to the Authorization Authority stating that the facility has been brought to a state of readiness to start operations (DOE-STD-3006-2000)

16. Nov 200616 Authorization Authority – DOE Management Official that will approve the startup or restart of a facility – Specified by the type of readiness review (ORR or RA) and the category of the facility (DOE O 425.1C) Definitions (cont)

17. Nov 200617 Startup/Restart Notification Report (SNR) – A report issued by the responsible contractor to identify a startup or restart of a nuclear or hazardous non-nuclear facility. – Issued annually with a one year projection of expected readiness reviews – Update (addendum) issued prior to commencement of the Contractor Readiness Review Definitions (cont)

18. Nov 200618 Plan-of-Action (POA) –The document prepared by line management which describes the breadth of the RR and the prerequisites which must be met to start the RR. It is the document by which line management defines what will be evaluated by the RR. –Both the Contractor and DOE prepare a POA –Submitted to the authorization authority for approval. (DOE-STD-3006-2000) (DOE-STD-3006-2000) Definitions (cont)

19. Nov 200619 Implementation Plan (IP) –The procedural document by which the RR is conducted. This document implements the scope and direction approved in the RR POA and define the depth of the review (DOE-STD-3006-2000) Definitions (cont)

20. Nov 200620 Independent – Independent of operation being reviewed – Will not review their own work or work for which they are responsible – NOT from line organization responsible for the operation Fully Objective – Striving to do what is right – May be from the line organization, but not responsible for that operation or work – May still work for the Authorization Authority Definitions (cont)

21. Nov 200621 Definitions (cont) SER DSA (or equivalent) TSR, HAR, FHA, BIO, USQ WSS PHA Drawings (facility, tooling, etc.) Technical Manuals Engineering Calculation Notes Contractor Safety Programs Authorization Basis (AB) Authorization Agreement S/RID EIS ORR/R A NESS Defined Work Scope Special Terms & Conditions Environmental Permits Site S&S Plan Emergency Preparedness Plan Safety Basis (SB)

22. Nov 200622 Graded Approach – Used to adjust the depth of detail required and magnitude of resources expended; – Based on the potential impact on safety, environmental compliance, safeguards and security, and its programmatic importance, including present and future mission; – Justification required for any of the 18 minimum core requirements not being reviewed for an ORR, but not a RA (DOE-STD-3006-2000) Definitions (cont)

23. Nov 200623 Definitions For Reference

24. Nov 200624 Other Definitions Nuclear Facility – Reactor - Any apparatus that is designed or used to sustain nuclear chain reactions in a controlled manner, including critical and pulsed assemblies, and research, test, and power reactors. – Nonreactor Nuclear Facility - Activities or operations that involve radioactive and/or fissionable materials in such form and quantity that a nuclear hazard potentially exists to the employees or the general public. – Accelerator - Device that speeds up charged particles, such as electrons or protons

25. Nov 200625 Nuclear Hazard Category 1, 2, and 3 Nonnuclear Hazardous Category High, Moderate, Low, Standard Industrial Nuclear Facility Nonnuclear Hazardous Facility Other Definitions (cont)

26. Nov 200626 Nuclear Hazard Category 1 Facilities – Facilities with potential for “significant off-site consequences.” Based on total curie content, potential material forms, and maximum energy for dispersion available. One class of facilities which possess this hazard potential is Class A nuclear reactors. – DOE Management Officials may designate other facilities as Category1 if it is felt that there exists the potential for “significant off-site consequences.” (DOE-STD-1027-92) Other Definitions (cont)

27. Nov 200627 Nuclear Hazard Category 2 Facilities – Facilities that contain threshold quantities (TQ) of radioactive materials which present the potential for “significant on-site consequences.” The TQ values for Category 2 facilities are provided in Table A.1 of DOE-STD-1027-92. (DOE-STD-1027-92) Other Definitions (cont)

28. Nov 200628 Nuclear Hazard Category 3 Facilities – Largely includes laboratory operations, low level waste handling facilities, and research machines which possess less than the Category 2 quantities of material and are considered to represent a low hazard. There is only the potential for “significant localized consequences.” (DOE-STD-1027-92) Other Definitions (cont)

29. Nov 200629 Non-Nuclear Hazardous Facility – Buildings, utilities, structures, operations or services, and related activities whose use is directed to a common purpose at a single location that uses, stores, or otherwise has hazardous non-nuclear materials. (DOE G 450.4-1A, Integrated Safety Management System Guide) Other Definitions (cont)

30. Nov 200630 Non-Nuclear Hazardous Materials – A material, energy source, or operation with the potential to cause illness, injury, or death to personnel or damage to a facility or to the environment (without regard to the likelihood or credibility of accident scenarios or consequence mitigation). (DOE G 450.4-1A, Integrated Safety Management System Guide) Other Definitions (cont)

31. Nov 200631 Non-Nuclear Hazardous Facilities Categorization – Contractor will determine, in their Integrated Safety Management System Description and associated Hazard Analysis (HA) the category of a hazardous non-nuclear facility. – Categorization must be coordinated with DOE Other Definitions (cont)

32. Nov 200632 Classification of Non-Nuclear Hazardous Facilities – High Hazard: Potential for onsite or offsite impacts to large numbers of persons or major impacts to the environment. – Moderate Hazard: Considerable potential for onsite impacts to people or the environment, but at most, only minor offsite impacts. – Low Hazard: Minor onsite and negligible offsite impacts to people or the environment. Other Definitions (cont)

33. Nov 200633 Other Definitions (cont) Authorization Basis –Combination of information relating to the control of hazards at a nuclear facility (including design, engineering analyses, and administrative controls) upon which DOE depends for its conclusion that activities at the facility can be conducted safely.

34. Nov 200634 Other Definitions (cont) The Authorization Basis is described in documents such as: Facility DSA/SERs/SARs/BIOs/HAR/TSRs, other safety analyses documents;  Facility-specific implementing mechanisms to comply w/ DOE Orders, policies, or other contract provisions (infrastructure program);  Permits...

35. Nov 200635 Other Definitions (cont) Safety Basis – Combination of information relating to the control of hazards at a nuclear facility (including design, engineering analysis, and administrative controls) upon which DOE depends for its conclusion that activities at the facility can be conducted safely.

36. Nov 200636 Other Definitions (cont) Documented Safety Analysis Report (DSA) –Documents the adequacy of safety the analysis for a nuclear facility

37. Nov 200637 Other Definitions (cont) Safety Evaluation Report (SER) –A documented review of a SAR which may impose conditions of approval, which might include constraints on TSRs, or alterations to other commitments

38. Nov 200638 Other Definitions (cont) Technical Safety Requirement (TSR) –A document that defines the safety boundaries and management or administration controls

39. Nov 200639 Other Definitions (cont) Hazard Analysis Report (HAR) – The HAR documents the HA required of a Nuclear Explosives Operation and associated activities

40. Nov 200640 Other Definitions (cont) Justification for Continued Operations (JCO) – Documents that procedures and policies are in place that will ensure safe operations until a SAR can be finalized

41. Nov 200641 Other Definitions (cont) Basis for Interim Operation (BIO) – A document which establishes interim safety basis until SAR and TSRs are developed and approved

42. Nov 200642 Other Definitions (cont) Unreviewed Safety Question (USQ) – Allows for making physical and procedural changes and continue to operate without DOE approval as long as Safety Basis is not affected

43. Nov 200643 Abbreviations and Acronyms AA Authorization Agreement AB Authorization Basis ASA Audited Safety Analysis CORR Contractor Operational Readiness Review CR Core Requirement CRAD Criteria and Review Approach Document DSA Documented Safety Analysis IP Implementation Plan JCO Justification for Continued Operations MSA Management Self Assessment OSR Operational Safety Requirements (TSR)

44. Nov 200644 Abbreviations and Acronyms (cont) ORR Operational Readiness Review POA Plan of Action RA Readiness Assessment SAR Safety Analysis Report (DSA) SER Safety Evaluation Report SNR Startup Notification Report S/RID Standards/Requirements identification Doc SSC Structures, Systems, and Components TSR Technical Safety Requirements WSS Work Smart Standards

45. Nov 200645 Questions

46. Readiness Review Course November 2006

47. Nov 200647 Readiness Review Course Introduction – Mod 1

48. Nov 200648 Learning Objectives Understanding the definition and purpose of a Readiness Review; Understanding the differences between an Operational Readiness Review and a Readiness Assessment; Knowledge of current DOE Orders, Directives, and References for the Readiness Review process; Knowledge of general terms used in the Readiness Review Process.

49. Nov 200649 Definition of a Readiness Review A disciplined, systematic, documented, performance-based review of: Facilities Equipment and Systems Personnel Procedures Safety Management Programs (e.g., Emergency Management, Safety Analysis, Conduct of Operations, Integrated Safety Management, Quality Assurance, Industrial Hyg and Safety, Waste Management, etc.)

50. Nov 200650 Purpose of a RR Ensure readiness of facility and personnel to start the facility within the bounds of acceptable risk defined by: –The Safety Basis/Authorization Agreement; –Applicable ES&H regulations. Ensure the facility/activity has adequate Safety Management Programs implemented and sufficient controls in place to start and continue operations within those bounds.

51. Nov 200651 RR Historical Summary 9-23-86, DOE 5480.6, Safety of DOE-owned Nuclear Reactors; 9-23-86, DOE 5480.6, Safety of DOE-owned Nuclear Reactors; 3-3-90, DNFSB 90-4, Rocky Flats Restart; 3-3-90, DNFSB 90-4, Rocky Flats Restart; 11-12-91, SEN-16B-91, Approval for Restart of Facilities Shutdown for Safety Reasons and for Startup of Major New Facilities; 11-12-91, SEN-16B-91, Approval for Restart of Facilities Shutdown for Safety Reasons and for Startup of Major New Facilities; 2-26-92, NE-1 Procedure for Restart of Reactor & Non-reactor Nuclear Facilities; 2-26-92, NE-1 Procedure for Restart of Reactor & Non-reactor Nuclear Facilities; 8-26-92, DNFSB 92-6, Order/Standard Development; 8-26-92, DNFSB 92-6, Order/Standard Development; 9-17-92, EM Policy and Guidance for Readiness Determinations; 9-17-92, EM Policy and Guidance for Readiness Determinations; 9-15-93, DOE O 5480.31/ 425.1, Startup and Restart of Nuclear Facilities; 9-15-93, DOE O 5480.31/ 425.1, Startup and Restart of Nuclear Facilities; 12-93, DOE-STD-3006-95, Planning and Conduct of ORRs/RAs, updated; 12-93, DOE-STD-3006-95, Planning and Conduct of ORRs/RAs, updated; 9-26-99, DNFSB Letter on ORR/RA inadequacies, leading to 425.1B and 3006-00; 9-26-99, DNFSB Letter on ORR/RA inadequacies, leading to 425.1B and 3006-00; 10-00, DOE ORR/RA Course created, developed, conducted as needed/as requested ; 10-00, DOE ORR/RA Course created, developed, conducted as needed/as requested ; 6-15-00, DOE-STD-3006-00 (series); 6-15-00, DOE-STD-3006-00 (series); 3-13-03, 425.1C (series); 3-13-03, 425.1C (series); 12-15-03, DOE 3012-2003 (series). 12-15-03, DOE 3012-2003 (series).

52. Nov 200652 DOE O 425.1C, Startup and Restart of Nuclear Facilities DOE O 425.1C, Startup and Restart of Nuclear Facilities – For Startup and Restart of Hazard Category 1, 2, and 3 Nuclear Facilities – Delineates whether an Operational Readiness Review (ORR) or a Readiness Assessment (RA) is required – Delineates the Authorization Authority – Defines the 18 Minimum Core Requirements – References the use of DOE-STD-3006-2000 Orders and Directives Cont.

53. Nov 200653 Orders and Directives Cont. DOE-STD-3006-2000, Planning and Conduct of Operational Readiness Reviews DOE-STD-3006-2000, Planning and Conduct of Operational Readiness Reviews – Provides guidance regarding the implementation of DOE O 425.1C; – Provides for a consistent approach in planning and performing a readiness review; – Provides templates and sample documents which can be used in organizing and performing a readiness review; – Can be used as guidance in the development of Site Office procedures.

54. Nov 200654 Orders and Directives Cont. DOE-HDBK-3012-2003, Team Leader's Preparation Guide for Operational Readiness Reviews (ORR) DOE-HDBK-3012-2003, Team Leader's Preparation Guide for Operational Readiness Reviews (ORR) – Provides guidance to the Team Leader on how to plan, manage, perform, and document a RR; – Defines the Team Leader, Team Members, and Administrators roles and responsibilities; – Provides templates and forms to assist in developing RR

55. Nov 200655 Readiness Review Operational Readiness ReviewReadiness Assessment Startup Hazard Category 1, 2, 3 Restarts Hazard Category 1 & 2 – Unplanned shutdown – Extended shutdown – Substantial process/system/ – Facility changes Major changes to safety basis Whenever deemed appropriate by DOE Restarts – Nuclear Facilities – Hazard Category 3 Startup/restart nonnuclear – High, Moderate, or Low hazard When deemed necessary by Site Office Operational Readiness Review and Readiness Assessment

56. Nov 200656 A readiness review required for: A readiness review required for: – Startup of new hazard categories 1, 2, and 3 nuclear facilities – Restart of hazard categories 1 and 2 nuclear facilities – Whenever deemed appropriate by DOE Management Officials for any nuclear facility Operational Readiness Review

57. Nov 200657 Readiness Assessment A readiness review required for: – Restart of nuclear facilities not requiring an ORR, as defined in DOE O 425.1C – Graded approach to application of the 18 minimum core requirements

58. Nov 200658 Exemption Process DOE-STD-3006-2000DOE-STD-3006-2000, Ch 4.6 & 5.11 references DOE O and M 251.1-1, Ch X which describes: DOE-STD-3006-2000 General Provisions; Exemption Approval Process (Approval Authority, CSO, OPI, EH, NNSA CTS); Exemption Request (Information needed); and Approval Criteria. DOE-STD-3006-2000DOE-STD-3006-2000, Ch 4.6 & 5.11 references DOE O and M 251.1-1, Ch X which describes: DOE-STD-3006-2000 General Provisions; Exemption Approval Process (Approval Authority, CSO, OPI, EH, NNSA CTS); Exemption Request (Information needed); and Approval Criteria.

59. Nov 200659 Definitions

60. Nov 200660 Definitions Readiness-to-Proceed Memorandum – A formal document from the Contractor to the Authorization Authority stating that the facility has been brought to a state of readiness to start operations (DOE-STD-3006-2000)

61. Nov 200661 Authorization Authority – DOE Management Official that will approve the startup or restart of a facility – Specified by the type of readiness review (ORR or RA) and the category of the facility (DOE O 425.1C) Definitions (cont)

62. Nov 200662 Startup/Restart Notification Report (SNR) – A report issued by the responsible contractor to identify a startup or restart of a nuclear or hazardous non-nuclear facility. – Issued annually with a one year projection of expected readiness reviews – Update (addendum) issued prior to commencement of the Contractor Readiness Review Definitions (cont) (DOE O 425.1C)

63. Nov 200663 Plan-of-Action (POA) –The document prepared by line management which describes the breadth of the RR and the prerequisites which must be met to start the RR. It is the document by which line management defines what will be evaluated by the RR. –Both the Contractor and DOE prepare a POA –Submitted to the authorization authority for approval. (DOE-STD-3006-2000) (DOE-STD-3006-2000) Definitions (cont)

64. Nov 200664 Implementation Plan (IP) –The procedural document by which the RR is conducted. This document implements the scope and direction approved in the RR POA and define the depth of the review (DOE-STD-3006-2000) Definitions (cont)

65. Nov 200665 Independent – Independent of operation being reviewed – Will not review their own work or work for which they are responsible – NOT from line organization responsible for the operation Fully Objective – Striving to do what is right – May be from the line organization, but not responsible for that operation or work – May still work for the Authorization Authority Definitions (cont)

66. Nov 200666 Definitions (cont) SER DSA (or equivalent) TSR, HAR, FHA, BIO, USQ WSS PHA Drawings (facility, tooling, etc.) Technical Manuals Engineering Calculation Notes Contractor Safety Programs Authorization Basis (AB) Authorization Agreement S/RID EIS ORR/R A NESS Defined Work Scope Special Terms & Conditions Environmental Permits Site S&S Plan Emergency Preparedness Plan Safety Basis (SB)

67. Nov 200667 Graded Approach Graded Approach – Used to adjust the depth of detail required and magnitude of resources expended; – Based on the potential impact on safety, environmental compliance, safeguards and security, and its programmatic importance, including present and future mission; – Justification required for any of the 18 minimum core requirements not being reviewed for an ORR, but not a RA (DOE-STD-3006-2000) Definitions (cont)

68. Nov 200668 Definitions For Reference

69. Nov 200669 Other Definitions Nuclear Facility – Reactor - Any apparatus that is designed or used to sustain nuclear chain reactions in a controlled manner, including critical and pulsed assemblies, and research, test, and power reactors. – Nonreactor Nuclear Facility - Activities or operations that involve radioactive and/or fissionable materials in such form and quantity that a nuclear hazard potentially exists to the employees or the general public. – Accelerator - Device that speeds up charged particles, such as electrons or protons

70. Nov 200670 Nuclear Hazard Category 1, 2, and 3 Nonnuclear Hazardous Category High, Moderate, Low, Standard Industrial Nuclear Facility Nonnuclear Hazardous Facility Other Definitions (cont)

71. Nov 200671 Nuclear Hazard Category 1 Facilities – Facilities with potential for “significant off-site consequences.” Based on total curie content, potential material forms, and maximum energy for dispersion available. One class of facilities which possess this hazard potential is Class A nuclear reactors. – DOE Management Officials may designate other facilities as Category1 if it is felt that there exists the potential for “significant off-site consequences.” (DOE-STD-1027-92) Other Definitions (cont)

72. Nov 200672 Nuclear Hazard Category 2 Facilities – Facilities that contain threshold quantities (TQ) of radioactive materials which present the potential for “significant on-site consequences.” The TQ values for Category 2 facilities are provided in Table A.1 of DOE-STD-1027-92. (DOE-STD-1027-92) Other Definitions (cont)

73. Nov 200673 Nuclear Hazard Category 3 Facilities – Largely includes laboratory operations, low level waste handling facilities, and research machines which possess less than the Category 2 quantities of material and are considered to represent a low hazard. There is only the potential for “significant localized consequences.” (DOE-STD-1027-92) Other Definitions (cont)

74. Nov 200674 Non-Nuclear Hazardous Facility – Buildings, utilities, structures, operations or services, and related activities whose use is directed to a common purpose at a single location that uses, stores, or otherwise has hazardous non-nuclear materials. (DOE G 450.4-1A, Integrated Safety Management System Guide) Other Definitions (cont)

75. Nov 200675 Non-Nuclear Hazardous Materials – A material, energy source, or operation with the potential to cause illness, injury, or death to personnel or damage to a facility or to the environment (without regard to the likelihood or credibility of accident scenarios or consequence mitigation). (DOE G 450.4-1A, Integrated Safety Management System Guide) Other Definitions (cont)

76. Nov 200676 Non-Nuclear Hazardous Facilities Categorization – Contractor will determine, in their Integrated Safety Management System Description and associated Hazard Analysis (HA) the category of a hazardous non-nuclear facility. – Categorization must be coordinated with DOE Other Definitions (cont)

77. Nov 200677 Classification of Non-Nuclear Hazardous Facilities – High Hazard: Potential for onsite or offsite impacts to large numbers of persons or major impacts to the environment. – Moderate Hazard: Considerable potential for onsite impacts to people or the environment, but at most, only minor offsite impacts. – Low Hazard: Minor onsite and negligible offsite impacts to people or the environment. Other Definitions (cont)

78. Nov 200678 Other Definitions (cont) Authorization Basis –Combination of information relating to the control of hazards at a nuclear facility (including design, engineering analyses, and administrative controls) upon which DOE depends for its conclusion that activities at the facility can be conducted safely.

79. Nov 200679 Other Definitions (cont) The Authorization Basis is described in documents such as: Facility DSA/SERs/SARs/BIOs/HAR/TSRs, other safety analyses documents;  Facility-specific implementing mechanisms to comply w/ DOE Orders, policies, or other contract provisions (infrastructure program);  Permits...

80. Nov 200680 Other Definitions (cont) Safety Basis – Combination of information relating to the control of hazards at a nuclear facility (including design, engineering analysis, and administrative controls) upon which DOE depends for its conclusion that activities at the facility can be conducted safely.

81. Nov 200681 Other Definitions (cont) Documented Safety Analysis Report (DSA) –Documents the adequacy of safety the analysis for a nuclear facility

82. Nov 200682 Other Definitions (cont) Safety Evaluation Report (SER) –A documented review of a SAR which may impose conditions of approval, which might include constraints on TSRs, or alterations to other commitments

83. Nov 200683 Other Definitions (cont) Technical Safety Requirement (TSR) –A document that defines the safety boundaries and management or administration controls

84. Nov 200684 Other Definitions (cont) Hazard Analysis Report (HAR) – The HAR documents the HA required of a Nuclear Explosives Operation and associated activities

85. Nov 200685 Other Definitions (cont) Justification for Continued Operations (JCO) – Documents that procedures and policies are in place that will ensure safe operations until a SAR can be finalized

86. Nov 200686 Other Definitions (cont) Basis for Interim Operation (BIO) – A document which establishes interim safety basis until SAR and TSRs are developed and approved

87. Nov 200687 Other Definitions (cont) Unreviewed Safety Question (USQ) – Allows for making physical and procedural changes and continue to operate without DOE approval as long as Safety Basis is not affected

88. Nov 200688 Abbreviations and Acronyms AA Authorization Agreement AB Authorization Basis ASA Audited Safety Analysis CORR Contractor Operational Readiness Review CR Core Requirement CRAD Criteria and Review Approach Document DSA Documented Safety Analysis IP Implementation Plan JCO Justification for Continued Operations MSA Management Self Assessment OSR Operational Safety Requirements (TSR)

89. Nov 200689 Abbreviations and Acronyms (cont) ORR Operational Readiness Review POA Plan of Action RA Readiness Assessment SAR Safety Analysis Report (DSA) SER Safety Evaluation Report SNR Startup Notification Report S/RID Standards/Requirements identification Doc SSC Structures, Systems, and Components TSR Technical Safety Requirements WSS Work Smart Standards

90. Nov 200690 Questions