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TAC:MF0404, Control Room Habitability (Approved, Closed) |
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MONTHYEAR2CAN121202, License Amendment Request to Adopt NFPA-805 Performance-Based Standard for Fire Protection for Light Water Reactor Electric Generating Plants (2001 Edition)2012-12-17017 December 2012 License Amendment Request to Adopt NFPA-805 Performance-Based Standard for Fire Protection for Light Water Reactor Electric Generating Plants (2001 Edition) Project stage: Request ML13043A1342013-02-15015 February 2013 Acceptance Review, Request to Adopt National Fire Protection Association Standard NFPA-805, Performance-Based Standard for Fire Protections for Light-Water Reactor Electric Generating Plants, 2001 Project stage: Acceptance Review ML13235A0052013-09-11011 September 2013 Request for Additional Information, Request to Adopt National Fire Protection Association Standard NFPA-805, Performance-Based Standard for Fire Protections for Light-Water Reactor Electric Generating Plants, 2001 Project stage: RAI 2CAN111301, Response to Request for Additional Information, Adoption of National Fire Protection Association Standard NFPA-8052013-11-0707 November 2013 Response to Request for Additional Information, Adoption of National Fire Protection Association Standard NFPA-805 Project stage: Response to RAI 2CAN121302, Response to Request for Additional Information Adoption of National Fire Protection Association Standard NFPA-8052013-12-0404 December 2013 Response to Request for Additional Information Adoption of National Fire Protection Association Standard NFPA-805 Project stage: Response to RAI 2CAN011401, Response to Request for Additional Information, Adoption of National Fire Protection Association Standard NFPA-8052014-01-0606 January 2014 Response to Request for Additional Information, Adoption of National Fire Protection Association Standard NFPA-805 Project stage: Response to RAI ML14085A2252014-03-28028 March 2014 Request for Additional Information, Request to Adopt National Fire Protection Association Standard NFPA-805, Performance-Based Standard for Fire Protections for Light-Water Reactor Electric Generating Plants, 2001 Project stage: RAI 2CAN051404, Response to Request for Additional Information Adoption of National Fire Protection Association Standard NFPA-8052014-05-22022 May 2014 Response to Request for Additional Information Adoption of National Fire Protection Association Standard NFPA-805 Project stage: Response to RAI ML14155A1332014-06-0909 June 2014 Request for Additional Information, Nrr/Dra/Apla Request to Adopt NFPA-805, Performance-Based Standard for Fire Protections for Light-Water Reactor Electric Generating Plants, 2001 Edition Project stage: RAI 2CAN061406, Arkansas, Unit 2 - Response to Request for Additional Information Adoption of National Fire Protection Association Standard NFPA-8052014-06-30030 June 2014 Arkansas, Unit 2 - Response to Request for Additional Information Adoption of National Fire Protection Association Standard NFPA-805 Project stage: Response to RAI 2CAN081401, Response to Request for Additional Information Adoption of National Fire Protection Association Standard NFPA-8052014-08-0707 August 2014 Response to Request for Additional Information Adoption of National Fire Protection Association Standard NFPA-805 Project stage: Response to RAI ML14329A4112014-08-15015 August 2014 U.S. Nuclear Regulatory Commission, Record of Review, Arkansas Nuclear One Unit 2 (ANO-2), LAR Attachment V- Table V-1 Internal Events PRA Facts and Observations (F&Os) Project stage: Other 2CAN091402, License Amendment Request Supplemental Adoption of National Fire Protection Association Standard NFPA-8052014-09-24024 September 2014 License Amendment Request Supplemental Adoption of National Fire Protection Association Standard NFPA-805 Project stage: Supplement ML14329A4262014-10-22022 October 2014 U.S. Nuclear Regulatory Commission, Record of Review, Arkansas Nuclear One Unit 2 (ANO-2), LAR Attachment V-Table V-1 Fire PRA Facts and Observations (F&Os). Project stage: Other ML14343A6022014-12-0505 December 2014 NRR E-mail Capture - ANO-2 NFPA-805 LAR Revised License Condition Necessitates Updated Enclosures 2 and 3 to Original LAR Project stage: Other 2CAN121404, Arkansas, Unit 2 - Adoption of National Fire Protection Association Standard NFPA-805, License Amendment Request Supplemental2014-12-0909 December 2014 Arkansas, Unit 2 - Adoption of National Fire Protection Association Standard NFPA-805, License Amendment Request Supplemental Project stage: Supplement ML14356A1722014-12-22022 December 2014 Summary of Site Audit to Support the Review of a License Amendment Request for Arkansas Nuclear One, Unit 2 to Transition to the National Fire Protection Association (NFPA) Standard 805 Fire Protection Licensing Basis Project stage: Approval ML14356A1852014-12-22022 December 2014 ANO2 Exit Project stage: Request ML15007A4782015-01-15015 January 2015 Summary of July 15-18, 2013, Arkansas Nuclear One, Unit 2, Audit Associated with License Amendment Request to Transition to National Fire Protection Association Standard 805 Project stage: Other ML15050A1932015-01-22022 January 2015 NRR E-mail Capture - Action: Request for NFPA 805 License Amendment Sunsi/Factual Accuracy Review Project stage: Request ML14356A2272015-02-18018 February 2015 Issuance of Amendment No. 300, Request to Adopt National Fire Protection Association Standard NFPA 805, Performance-Based Standard for Fire Protection for Light Water Reactor Electric Generating Plants Project stage: Approval 1CAN031602, Response to PRA RAI 03, Adoption of National Fire Protection Association Standard NFPA 8052016-03-25025 March 2016 Response to PRA RAI 03, Adoption of National Fire Protection Association Standard NFPA 805 Project stage: Other 2CAN121602, Supplemental Information to License Amendment Request to Revise the National Fire Protection Association (NFPA) Standard 805 Modifications2016-12-0202 December 2016 Supplemental Information to License Amendment Request to Revise the National Fire Protection Association (NFPA) Standard 805 Modifications Project stage: Supplement 2014-03-28
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MONTHYEAR2CAN012401, U.S. Additional Protocol2024-01-17017 January 2024 U.S. Additional Protocol 2CAN012403, Supplemental Information - Adopt Risk-Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 42024-01-11011 January 2024 Supplemental Information - Adopt Risk-Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4 0CAN012401, Registration of Cask Use2024-01-10010 January 2024 Registration of Cask Use 1CAN122301, Responses to Request for Additional Information for Request for Alternative for Implementation of Extended Reactor Vessel Inservice Inspection Interval (ANO1-ISl-037)2023-12-14014 December 2023 Responses to Request for Additional Information for Request for Alternative for Implementation of Extended Reactor Vessel Inservice Inspection Interval (ANO1-ISl-037) 2CAN112302, Submittal of Amendment 31 to Safety Analysis Report2023-11-16016 November 2023 Submittal of Amendment 31 to Safety Analysis Report 0CAN102303, Registration of Cask Use2023-10-24024 October 2023 Registration of Cask Use 0CAN102302, (ANO) Emergency Plan Revision 49 and Emergency Plan On-Shift Staffing Analysis Revision 32023-10-11011 October 2023 (ANO) Emergency Plan Revision 49 and Emergency Plan On-Shift Staffing Analysis Revision 3 0CAN102301, Evacuation Time Estimate (ETE) Study2023-10-0404 October 2023 Evacuation Time Estimate (ETE) Study 1CAN092301, Supplemental Information - Adopt Risk-Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 42023-09-21021 September 2023 Supplemental Information - Adopt Risk-Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4 0CAN092302, Supplement to Request for Alternative Frequency to Containment Unbonded Post-Tensioning System Inservice Inspection (ANO-CISI-002)2023-09-14014 September 2023 Supplement to Request for Alternative Frequency to Containment Unbonded Post-Tensioning System Inservice Inspection (ANO-CISI-002) 2CAN092301, Reply to a Notice of Violation2023-09-0808 September 2023 Reply to a Notice of Violation 0CAN092301, Emergency Plan Implementing Procedure Revision2023-09-0505 September 2023 Emergency Plan Implementing Procedure Revision 0CAN082301, Units 1 and 2 - Changes to the Quality Assurance Program Approval Form for Radioactive Material Package No. 03412023-08-17017 August 2023 Units 1 and 2 - Changes to the Quality Assurance Program Approval Form for Radioactive Material Package No. 0341 2CAN082301, Inservice Inspection Summary Report for the Arkansas Nuclear One, Unit 2, Twenty-Ninth Refueling Outage (2R29)2023-08-10010 August 2023 Inservice Inspection Summary Report for the Arkansas Nuclear One, Unit 2, Twenty-Ninth Refueling Outage (2R29) 0CAN072301, Registration of Cask Use2023-07-18018 July 2023 Registration of Cask Use 1CAN062304, Supplement Related to License Amendment Request to Remove Technical Specification Condition Allowing Two Reactor Coolant Pump Operation2023-06-29029 June 2023 Supplement Related to License Amendment Request to Remove Technical Specification Condition Allowing Two Reactor Coolant Pump Operation 0CAN062301, Status of Actions to Return to Compliance2023-06-26026 June 2023 Status of Actions to Return to Compliance 0CAN062302, Submittal of Revision 22 of the ANO Fire Hazards Analysis2023-06-20020 June 2023 Submittal of Revision 22 of the ANO Fire Hazards Analysis 1CAN062301, Request for Alternative for Implementation of Extended Reactor Vessel Inservice Inspection Interval (ANO1-ISI-037)2023-06-0808 June 2023 Request for Alternative for Implementation of Extended Reactor Vessel Inservice Inspection Interval (ANO1-ISI-037) 0CAN052303, Annual 10 CFR 50.46 Report for Calendar Year 20222023-05-24024 May 2023 Annual 10 CFR 50.46 Report for Calendar Year 2022 0CAN052302, Emergency Plan Rev. 482023-05-11011 May 2023 Emergency Plan Rev. 48 0CAN052301, Units 1 and 2 - Annual Radiological Environmental Operating Report for 20222023-05-0909 May 2023 Units 1 and 2 - Annual Radiological Environmental Operating Report for 2022 2CAN052301, Cycle 30 Core Operating Limits Report (COLR)2023-05-0303 May 2023 Cycle 30 Core Operating Limits Report (COLR) 0CAN042302, Annual Occupational Radiation Exposure Report for 20222023-04-27027 April 2023 Annual Occupational Radiation Exposure Report for 2022 0CAN042301, Radioactive Effluent Release Report for 20222023-04-14014 April 2023 Radioactive Effluent Release Report for 2022 2CAN042301, License Amendment Request to Revise Technical Specifications to Adopt Risk-Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 42023-04-0505 April 2023 License Amendment Request to Revise Technical Specifications to Adopt Risk-Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4 1CAN032301, License Amendment Request to Modify the Arkansas Nuclear One, Unit 1, Technical Specification 3.3.1, Reactor Protection System Instrumentation, Turbine Trip Function on Low Control Oil Pressure2023-03-30030 March 2023 License Amendment Request to Modify the Arkansas Nuclear One, Unit 1, Technical Specification 3.3.1, Reactor Protection System Instrumentation, Turbine Trip Function on Low Control Oil Pressure 2CAN032303, Responses to Request for Additional Information Concerning the Request for Alternative Regarding the Half-Nozzle Repair of Reactor Vessel Closure Head Penetration 462023-03-29029 March 2023 Responses to Request for Additional Information Concerning the Request for Alternative Regarding the Half-Nozzle Repair of Reactor Vessel Closure Head Penetration 46 2CAN032304, Supplement to the Request for Alternative Regarding the Half-Nozzle Repair of Reactor Vessel Closure Head Penetration 462023-03-29029 March 2023 Supplement to the Request for Alternative Regarding the Half-Nozzle Repair of Reactor Vessel Closure Head Penetration 46 2CAN032305, 03 Post Examination Analysis2023-03-23023 March 2023 03 Post Examination Analysis 1CAN032302, Inspection Summary Report for the Thirtieth Refueling Outage (1R30)2023-03-20020 March 2023 Inspection Summary Report for the Thirtieth Refueling Outage (1R30) 1CAN012301, Responses to Request for Additional Information for Request for Relief ANO1-ISI-0352023-01-30030 January 2023 Responses to Request for Additional Information for Request for Relief ANO1-ISI-035 2CAN012303, U.S. Additional Protocol2023-01-23023 January 2023 U.S. Additional Protocol 2CAN012302, Relief Request ANO2-RR-23-001, Half-Nozzle Repair of Reactor Vessel Closure Head Penetration 462023-01-20020 January 2023 Relief Request ANO2-RR-23-001, Half-Nozzle Repair of Reactor Vessel Closure Head Penetration 46 1CAN122201, License Amendment Request to Revise Technical Specifications to Adopt Risk-Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 42022-12-22022 December 2022 License Amendment Request to Revise Technical Specifications to Adopt Risk-Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4 0CAN122202, Registration of Cask Use2022-12-21021 December 2022 Registration of Cask Use 0CAN122201, Reply to a Notice of Violation; EA-22-0992022-12-0808 December 2022 Reply to a Notice of Violation; EA-22-099 0CAN112201, Request for Alternative Frequency to Containment Unbonded Post-Tensioning System Inservice Inspection (ANO-CISI-002)2022-11-10010 November 2022 Request for Alternative Frequency to Containment Unbonded Post-Tensioning System Inservice Inspection (ANO-CISI-002) 1CAN102202, Application to Remove Technical Specification Condition Allowing Two Reactor Coolant Pump Operation2022-10-31031 October 2022 Application to Remove Technical Specification Condition Allowing Two Reactor Coolant Pump Operation 1CAN102203, Cycle 31 Core Operating Limits Report2022-10-24024 October 2022 Cycle 31 Core Operating Limits Report 1CAN102201, Supplement to Proposed Technical Specifications 3.4.12 and 3.4.13 Revised Dose Calculations2022-10-13013 October 2022 Supplement to Proposed Technical Specifications 3.4.12 and 3.4.13 Revised Dose Calculations 0CAN092201, Supplement to License Amendment Request for Approval of Changes to the Emergency Plan Staffing Requirements2022-09-29029 September 2022 Supplement to License Amendment Request for Approval of Changes to the Emergency Plan Staffing Requirements 1CAN092201, Supplement to Request for Relief from American Society of Mechanical Engineers Section XI Volumetric Examination Requirements - Fifth 10-Year Interval, First Period2022-09-0808 September 2022 Supplement to Request for Relief from American Society of Mechanical Engineers Section XI Volumetric Examination Requirements - Fifth 10-Year Interval, First Period 0CAN082201, License Amendment Request for Approval of Changes to the Emergency Plan Staffing Requirements2022-08-30030 August 2022 License Amendment Request for Approval of Changes to the Emergency Plan Staffing Requirements 1CAN082201, Request for Relief from American Society of Mechanical Engineers Section XI Volumetric Examination Requirements - Fifth 10-Year Interval, First Period2022-08-24024 August 2022 Request for Relief from American Society of Mechanical Engineers Section XI Volumetric Examination Requirements - Fifth 10-Year Interval, First Period 2CAN072201, Response to Request for Additional Information Requests for Relief from American Society of Mechanical Engineers Section XI Volumetric Examination Requirements - Fourth 10-Year Interval, Second and Third Periods2022-07-20020 July 2022 Response to Request for Additional Information Requests for Relief from American Society of Mechanical Engineers Section XI Volumetric Examination Requirements - Fourth 10-Year Interval, Second and Third Periods 0CAN072201, Registration of Cask Use2022-07-14014 July 2022 Registration of Cask Use 0CAN062202, Registration of Cask Use2022-06-0909 June 2022 Registration of Cask Use 1CAN062201, Response to the Request for Additional Information Proposed Technical Specifications 3.4.12 and 3.4.13 Revised Dose Calculations2022-06-0202 June 2022 Response to the Request for Additional Information Proposed Technical Specifications 3.4.12 and 3.4.13 Revised Dose Calculations 1CAN052201, Request for Relief Related to American Society of Mechanical Engineers (ASME) Code Case N-729-6 Augmented Examination Requirements ANO1-ISI-0352022-05-31031 May 2022 Request for Relief Related to American Society of Mechanical Engineers (ASME) Code Case N-729-6 Augmented Examination Requirements ANO1-ISI-035 2024-01-17
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Text
s Entergy Operations, Inc.
1448 S.R. 333 Russellville, AR 72802 Tel 479-858-3110 Jeremy G. Browning Vice President - Operations Arkansas Nuclear One 2CAN091402 September 24, 2014 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555
SUBJECT:
License Amendment Request Supplemental Adoption of National Fire Protection Association Standard NFPA-805 Arkansas Nuclear One, Unit 2 Docket No. 50-368 License No. NPF-6
Dear Sir or Madam:
By letter dated December 17, 2012 (Reference 1), Entergy Operations, Inc. (Entergy) submitted a request to amend the Arkansas Nuclear One, Unit 2 (ANO-2) Technical Specifications (TS) and licensing bases to comply with the requirements in 10 CFR 50.48(a), 10 CFR 50.48(c), and the guidance in Regulatory Guide (RG) 1.205, Risk-Informed Performance-Based Fire Protection for Existing Light-Water Nuclear Power Plants. The amendment request followed Nuclear Energy Institute (NEI) 04-02, Guidance for Implementing a Risk-Informed, Performance-Based Fire Protection Program under 10 CFR 50.48(c). The submittal (Reference 1) described the methodology used to demonstrate compliance with, and transition to, National Fire Protection Association (NFPA)-805, and included regulatory evaluations, probabilistic risk assessment (PRA), change evaluations, proposed modifications for non-compliances, and supporting attachments.
On September 4, 2014, members of the NRC staff and ANO-2 NFPA 805 project personnel completed a conference call intended to provide clarifying information related to previous Entergy responses to NRC requests for additional information (RAI). Three NFPA 805 subject matter areas were discussed. The first of these, related to Control Room abandonment RAI responses, was sufficiently clarified and this item was closed. With regard to the second item for discussion, ANO personnel clarified that no joint human error probability (HEP) values of less than 1 x 10-5 were used in the NFPA 805 fire risk analysis. However, the aforementioned RAI responses were unclear in this regard; therefore, this supplemental letter confirms that no joint HEP values below 1 x 10-5 were utilized.
The final item of discussion involved ANO assumptions for fire propagation outside well-sealed motor control center (MCC) cabinets (panels of > 440 V which are not switchgear or load center power supplies). The current ANO-2 NFPA 805 analysis does not assume components outside a well-sealed MCC cabinet are damaged by a fire initiated within the well-sealed MCC cabinet.
2CAN091402 Page 2 of 4 The NRC referenced frequently asked question (FAQ) 14-0009, Revision F, which is intended to address generically what probability for fire propagation beyond such electrical cabinets should be utilized in plant fire risk models. The FAQ is currently open (unresolved); however, the NRC has determined that a 10% probability of fire propagation is reasonably conservative and can be utilized in fire risk analyses pending FAQ resolution. A value less than 10% probability of propagation beyond the well-sealed MCC cabinet is expected for ANO-2 given the use of IEEE-383 qualified/thermoset cables at ANO-2 versus the bounding analysis provided in the draft FAQ, which is based on non-IEEE-383 qualified/thermoplastic cables.
As a result of the electrical cabinet fire discussion, Entergy committed to perform a sensitivity study using the 10% probability factor to bound the NFPA 805 risk results. The sensitivity analysis conservatively applies 10% of the ignition frequency of the well-sealed MCC to a bounding fire scenario for the associated zone, typically the hot gas layer (HGL) scenario. This approach provides a bounding analysis which assumes that the fires propagating beyond the well-sealed MCC impact all targets in the fire zone for zones where a HGL scenario has already been developed, or applied to a similarly bounding scenario, if a HGL scenario is not applicable.
As reported on replacement License Amendment Request (LAR) page W-6 (Reference 10), the total Core Damage Frequency (CDF) including Fire and Internal events has a value of 7.7E-05/yr (Internal Events CDF (9.5E-7/year) + Internal Floods (8.0E-07/yr) + Fire CDF (7.5E-05)), and the total Large Early Release Frequency (LERF) has a value of 1.9E-06/yr (Internal Events LERF (1.1E-07/year) + Internal Floods (5.6E-08/yr) + Fire LERF (1.7E-06/yr)).
When the increase in risk from this sensitivity is added to these values, it results in a total CDF of 8.7E-05/yr and a total LERF of 2.2E-06/yr.
Also, as reported on replacement LAR page W-24 (Reference 10), the total changes in CDF and LERF from the transition to NFPA 805 are -1.29E-04/yr and -4.72E-6/yr, respectively.
When the increase in risk from this sensitivity is added to these values, it results in a total change in CDF of -1.19E-04/yr and a total change in LERF of -4.47E-06/yr.
Finally, as reported on replacement LAR page W-7 (Reference 10), a bounding estimate of the overall CDF risk due to external events (including seismic, external flooding, and off-site industry facility accidents) is estimated to be less than 1E-5/yr. A total bounding estimate for LERF external events is assumed to be 0.1 of the total CDF, which is less than 1E-6/yr.
Thus, with respect to the above sensitivity study, ANO-2 continues to meet the acceptance criteria.
In addition to the above, Entergy committed to monitor resolution of FAQ 14-0009 (current Revision F) and revise the ANO-2 fire risk model to be consistent with that found acceptable through the FAQ process. Therefore, Entergy has added a new line item (S2-10) to Attachment S, Table S-2, of the original NFPA 805 submittal (Reference 1). The revised table incorporates any previous changes made as a result of previous responses to RAIs; specifically, a revision of Item S2-3 by letter dated November 7, 2013, FPE RAI 01 response (Reference 3).
For completeness, a revised Table S-2, in its entirety, is included in Attachment 1 of this submittal.
Changes or additional information, as detailed in this letter, with respect to the original Entergy request (Reference 1) have been reviewed and Entergy has determined that the changes do not invalidate the no significant hazards consideration included in the Reference 1 letter.
2CAN091402 Page 3 of 4 In accordance with 10 CFR 50.91(b)(1), a copy of this application and the reasoned analysis about no significant hazards consideration is being provided to the designated Arkansas state official.
If you have any questions or require additional information, please contact Stephenie Pyle at 479-858-4704.
I declare under penalty of perjury that the foregoing is true and correct.
Executed on September 24, 2014.
Sincerely, ORIGINAL SIGNED BY JEREMY G. BROWNING JGB/dbb
Attachment:
Updated Attachment S, Table S Implementation Items
REFERENCES:
- 1. Entergy letter dated December 17, 2012, License Amendment Request to Adopt NFPA-805 Performance-Based Standard for Fire Protection for Light Water Reactor Electric Generating Plants (2001 Edition) (2CAN121202)
(ML12353A041)
- 2. NRC letter dated September 11, 2013, Arkansas Nuclear One, Unit 2 -
Request for Additional Information Regarding Adoption of National Fire Protection Association Standard NFPA-805 (TAC No. MF0404)
(2CNA091301) (ML13235A005)
- 3. Entergy letter dated November 7, 2013, Response to Request for Additional Information - Adoption of National Fire Protection Association Standard NFPA-805 (2CAN111301) (ML13312A877)
- 4. Entergy letter dated December 4, 2013, Response to Request for Additional Information - Adoption of National Fire Protection Association Standard NFPA-805 (2CAN121302) (ML13338A432)
- 5. Entergy letter dated January 6, 2014, Response to Request for Additional Information - Adoption of National Fire Protection Association Standard NFPA-805 (2CAN011401) (ML14006A315)
- 6. NRC letter dated March 28, 2014, Arkansas Nuclear One, Unit 2 -
Request for Additional Information Regarding Adoption of National Fire Protection Association Standard NFPA-805 (2CNA031401)
(ML14085A225)
- 7. Entergy letter dated May 22, 2014, Response to Request for Additional Information - Adoption of National Fire Protection Association Standard NFPA-805 (2CAN051404) (ML14142A410)
- 8. NRC letter dated June 9, 2014, Arkansas Nuclear One, Unit 2 - Request for Additional Information Regarding Adoption of National Fire Protection Association Standard NFPA-805 (2CNA061402) (ML14155A133)
2CAN091402 Page 4 of 4 (REFERENCES continued)
- 9. Entergy letter dated June 30, 2014, Response to Request for Additional Information - Adoption of National Fire Protection Association Standard NFPA-805 (2CAN061406)
- 10. Entergy letter dated August 7, 2014, Response to Request for Additional Information - Adoption of National Fire Protection Association Standard NFPA-805 (2CAN081401) cc: Mr. Marc L. Dapas Regional Administrator U. S. Nuclear Regulatory Commission Region IV 1600 East Lamar Boulevard Arlington, TX 76011-4511 NRC Senior Resident Inspector Arkansas Nuclear One P. O. Box 310 London, AR 72847 U. S. Nuclear Regulatory Commission Attn: Ms. Andrea E. George MS O-8B1 One White Flint North 11555 Rockville Pike Rockville, MD 20852 Mr. Bernard R. Bevill Arkansas Department of Health Radiation Control Section 4815 West Markham Street Slot #30 Little Rock, AR 72205
Attachment to 2CAN091402 Updated Attachment S, Table S-2 Implementation Items
Arkansas Nuclear One - Unit 2 Att. S - Plant Modifications and Items to be Completed Table S-2 items provided below are those items (procedure changes, process updates, and training to affected plant personnel) that will be completed prior to the implementation of new NFPA 805 fire protection program.
Table S-2 Implementation Items Item Unit Description LAR Section / Source S2-1 C Develop a monitoring program required by NFPA 805 that will include a process to monitor and LAR Section 4.6 and Attachment A trend the fire protection program based on specific goals established to measure effectiveness. (NEI-04-02 B-1 Table) Section 3.2.3 (3)
S2-2 2 Revise or develop fire protection flushing activity to perform fixed water spray system flushing and Attachment A (NEI-04-02 B-1 Table) drainage of underground lead-in connections in accordance with NFPA 15, 1977 Edition Code. Section 3.9.1 (2)
S2-3 2 Perform an evaluation for NFPA 14, 1983 Edition Code non-compliance for standpipe manual Attachment A (NEI-04-02 B-1 Table) hose station 2HR-75 horizontal water header to determine if additional hangers are required, Section 3.6.1 since hose station water header wall hangers were found not secured.
S2-4 C Revise fire protection administrative procedure EN-DC-161, Control of Combustible, to include Attachment A (NEI-04-02 B-1 Table) the following: Sections 3.3.1.2 (5)
In accordance with FAQ 06-0020, the term applicable NFPA Standards is considered to be equivalent to those NFPA Standards identified in the current licensing basis (CLB) for existing procedures and systems in the fire protection program that are transitioning to NFPA-805. New Fire Protection Systems would be subject to the most current code or standard.
Terminology for zero transient combustibles and changes needed to support FPRA assumptions.
S2-5 2 Revise existing procedure(s) or develop a new procedure(s) for NPO required to transition to Attachment D (NEI-04-02 Non-Power NFPA 805 based upon insights gained from ANO-2 NPO calculation. Operational Modes) VFDR NPO-Procedure S2-6 2 Revise OMA procedures/documents to include feasibility criteria in FAQ 07-0030 for the recovery Attachment G (NEI-04-02 OMA) Step 4 actions listed in Table G-1 of Attachment G, Recovery Action Transition.
S2-7 C Develop or revise technical documents and procedures that relate to new FP design and LAR Sections 4.7.1, 4.7.2, and 4.7.3 licensing basis (e.g., ANO Fire Protection Program, OP-1003.014, Technical Requirements Manual, Design Basis Document, Pre-Fire Plans, Maintenance and Surveillance Procedures, Configuration Control Program, Training and Qualification Guidelines, etc.) as required for implementation of NFPA 805. to 2CAN121202 Page S-20
Arkansas Nuclear One - Unit 2 Att. S - Plant Modifications and Items to be Completed Table S-2 Implementation Items Item Unit Description LAR Section / Source S2-8 2 Revise technical documents for NFPA 13 for acceptance of the partial area sprinkler system in Attachment A (NEI-04-02 B-1 Table)
Fire Area G for NFPA 805. The existing partial area sprinkler system for Fire Area G has been Section 3.9.1 (1) previously approved by the NRC in an exemption under Appendix R. As transitioned to NFPA 805, the previously approved exemption is being withdrawn, so documentation updates will be needed to remove the reference to an exemption and provide an independent basis.
S2-9 C Develop or create a PRA review plan of action to revise the PRA model for each modification or LAR Section 4.8.2 implementation item completed that is credited either directly or indirectly by PRA. The PRA review plan will ensure the as-built change-in-risk from each modification or implementation item does not exceed the PRA model change-in-risk estimates reported in the LAR.
S2-10 C Following resolution of FAQ 14-0009 related to the potential for fire propagation outside Not Applicable well-sealed motor control center (MCC) cabinets, the fire risk model will be revised, as necessary, in accordance with the FAQ conclusions. Should resolution of FAQ 14-0009 not occur until after NFPA 805 implementation at the site, revisions, if any, to the fire risk model associated with FAQ 14-0009 will be completed prior to self-approval. to 2CAN121202 Page S-21