Letter Sequence Supplement |
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Initiation
- Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request
- Acceptance
- Supplement, Supplement, Supplement, Supplement, Supplement, Supplement
Results
Other: LIC-13-0142, Probabilistic Risk Assessment (PRA) RAI Response - NFPA-805 Transition, LIC-13-0158, Probabilistic Risk Assessment (PRA) RAI Responses 19.01, 24, and 26 - NFPA-805 Transition, LIC-13-0179, Probabilistic Risk Assessment (PRA) RAI Responses 01.j.04, 01.j.05, and 01.j.06 - NFPA-805 Transition, LIC-14-0004, Probabilistic Risk Assessment (PRA) RAI Responses 26.01 and 24.01 - NPFA-805 Transition, ML113260423, ML13256A110, ML14163A002
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MONTHYEARLIC-11-0099, Table B-2 Nuclear Safety Capability Assessment Methodology Review2011-09-28028 September 2011
Table B-2 Nuclear Safety Capability Assessment Methodology Review
Project stage: Request
ML11276A1182011-09-28028 September 2011
License Amendment Request 10-07, Proposed Changes to Adopt NFPA 805, Performance-Based Standard for Fire Protection for Light Water Reactor Generating Plants (2001 Edition)
Project stage: Request
ML1132604232011-12-13013 December 2011
Online Reference Portal for National Fire Protection Association Standard (NFPA) 805 License Amendment Request
Project stage: Other
ML1135403342011-12-19019 December 2011
Supplement to License Amendment Request (LAR) 10-07, Proposed Changes to Adopt NFPA 805, Performance-Based Standard for Fire Protection for Light Water Reactor Generating Plants (2001 Edition)
Project stage: Supplement
LIC-11-0136, Clarification of Supplement to License Amendment Request (LAR) 10-07, Proposed Changes to Adopt NFPA 805, Performance-Based Standard for Fire Protection for Light Water Reactor Generating Plants (2011 Edition)2011-12-22022 December 2011
Clarification of Supplement to License Amendment Request (LAR) 10-07, Proposed Changes to Adopt NFPA 805, Performance-Based Standard for Fire Protection for Light Water Reactor Generating Plants (2011 Edition)
Project stage: Supplement
ML1136300832011-12-29029 December 2011
Acceptance Review Email, License Amendment Request to Adopt National Fire Protection Standard NFPA -805 Performance-Based Standard for Fire Protection for Light-Water Reactor Electric Generation Plants,
Project stage: Acceptance Review
LIC-12-0033, Submittal of Fire Dynamic Simulator (FDS) Input Files in Response to NRC NFPA 805 Transition License Amendment Request Audit Team Request at Fort Calhoun Station2012-03-20020 March 2012
Submittal of Fire Dynamic Simulator (FDS) Input Files in Response to NRC NFPA 805 Transition License Amendment Request Audit Team Request at Fort Calhoun Station
Project stage: Request
ML1210205742012-04-11011 April 2012
Draft Request for Additional Information, Request to Adopt National Fire Protection Association Standard 805, Performance-Based Standard for Fire Protection for Light-Water Reactor Generating Plants (2001 Edition)
Project stage: Draft RAI
ML1210205612012-04-11011 April 2012
Draft Request for Additional Information Email, Request to Adopt National Fire Protection Association Standard 805, Performance-Based Standard for Fire Protection for Light-Water Reactor Generating Plants (2001 Edition)
Project stage: Draft RAI
ML1210400482012-04-26026 April 2012
Request for Additional Information, Request to Adopt National Fire Protection Association Standard 805, Performance-Based Standard for Fire Protection for Light Water Reactor Generating Plants (2001 Edition)
Project stage: RAI
LIC-12-0083, Responses to Requests for Additional Information License Amendment Request 10-07 to Adopt NFPA 805, Performance-Based Standard for Fire Protection for Light Water Reactor Generating Plants, 2001 Edition2012-07-24024 July 2012
Responses to Requests for Additional Information License Amendment Request 10-07 to Adopt NFPA 805, Performance-Based Standard for Fire Protection for Light Water Reactor Generating Plants, 2001 Edition
Project stage: Response to RAI
LIC-12-0120, Responses to Requests for Additional Information License Amendment Request 10-07 to Adopt NFPA 805, Performance-Based Standard for Fire Protection for Light Water Reactor Generating Plants, 2001 Edition, at Fort Calhoun Station2012-08-24024 August 2012
Responses to Requests for Additional Information License Amendment Request 10-07 to Adopt NFPA 805, Performance-Based Standard for Fire Protection for Light Water Reactor Generating Plants, 2001 Edition, at Fort Calhoun Station
Project stage: Response to RAI
LIC-12-0135, Responses to Requests for Additional Information License Amendment Request 10-07 to Adopt NFPA 805, Performance-Based Standard for Fire Protection for Light Water Reactor Generating Plants, 2001 Edition, at Fort Calhoun Station2012-09-27027 September 2012
Responses to Requests for Additional Information License Amendment Request 10-07 to Adopt NFPA 805, Performance-Based Standard for Fire Protection for Light Water Reactor Generating Plants, 2001 Edition, at Fort Calhoun Station
Project stage: Response to RAI
ML13016A4322013-01-16016 January 2013
E-mail, Request for Additional Information, Round 2, Request to Adopt National Fire Protection Association Standard 805, Performance-Based Standard for Fire Protection for Light-Water Reactor Generating Plants (2001 Edition)
Project stage: RAI
ML13053A2262013-02-22022 February 2013
Email, Second Round Draft Request for Additional Information, Request to Adopt National Fire Protection Association Standard 805, Performance-Based Standard for Fire Protection for Light-Water Reactor Generating Plants
Project stage: Draft RAI
05000285/LER-2013-004, Regarding Inverters Inoperable During Emergency Diesel Generator Operation2013-04-23023 April 2013
Regarding Inverters Inoperable During Emergency Diesel Generator Operation
Project stage: Request
LIC-13-0033, Omaha Public Power Districts, Responses to Second Request for Additional Information License Amendment Request to Adopt NFPA 805 at Fort Calhoun Station2013-04-23023 April 2013
Omaha Public Power Districts, Responses to Second Request for Additional Information License Amendment Request to Adopt NFPA 805 at Fort Calhoun Station
Project stage: Request
W3F1-2013-0022, Response to 2nd Round Request for Additional Information Regarding Adoption of National Fire Protection Association Standard NFPA 8052013-05-16016 May 2013
Response to 2nd Round Request for Additional Information Regarding Adoption of National Fire Protection Association Standard NFPA 805
Project stage: Request
LIC-13-0060, Omaha Public Power District - Remaining Responses to Second Request for Additional Information License Amendment Request to Adopt NFPA 805 at Fort Calhoun Station2013-05-21021 May 2013
Omaha Public Power District - Remaining Responses to Second Request for Additional Information License Amendment Request to Adopt NFPA 805 at Fort Calhoun Station
Project stage: Request
ML13178A0352013-06-27027 June 2013
Email Request for Additional Information Round 3 (Afpb), Request to Adopt National Fire Protection Association Standard 805, Performance-Based Standard for Fire Protection for Light-Water Reactor Generating Plants (2001 Edition)
Project stage: RAI
LIC-13-0096, Responses to Third Request for Additional Information Regarding License Amendment Request to Adopt NFPA 8052013-07-29029 July 2013
Responses to Third Request for Additional Information Regarding License Amendment Request to Adopt NFPA 805
Project stage: Request
ML13226A1222013-08-14014 August 2013
Email, Request for Additional Information Round 3 (Apla), Request to Adopt National Fire Protection Association Standard 805, Performance-Based Standard for Fire Protection for Light-Water Reactor Generating Plants (2001 Edition)
Project stage: RAI
ML13256A1102013-09-12012 September 2013
Safe Shutdown Analysis (SSA) RAI Response - NFPA-805 Transition (ME7244)
Project stage: Other
ML13270A2872013-09-27027 September 2013
Email, Request for Additional Information Round 4 (Apla), Request to Adopt National Fire Protection Association Standard 805, Performance-Based Standard for Fire Protection for Light-Water Reactor Generating Plants (2001 Edition)
Project stage: RAI
LIC-13-0142, Probabilistic Risk Assessment (PRA) RAI Response - NFPA-805 Transition2013-10-11011 October 2013
Probabilistic Risk Assessment (PRA) RAI Response - NFPA-805 Transition
Project stage: Other
LIC-13-0158, Probabilistic Risk Assessment (PRA) RAI Responses 19.01, 24, and 26 - NFPA-805 Transition2013-11-0404 November 2013
Probabilistic Risk Assessment (PRA) RAI Responses 19.01, 24, and 26 - NFPA-805 Transition
Project stage: Other
LIC-13-0179, Probabilistic Risk Assessment (PRA) RAI Responses 01.j.04, 01.j.05, and 01.j.06 - NFPA-805 Transition2013-12-18018 December 2013
Probabilistic Risk Assessment (PRA) RAI Responses 01.j.04, 01.j.05, and 01.j.06 - NFPA-805 Transition
Project stage: Other
LIC-14-0004, Probabilistic Risk Assessment (PRA) RAI Responses 26.01 and 24.01 - NPFA-805 Transition2014-01-24024 January 2014
Probabilistic Risk Assessment (PRA) RAI Responses 26.01 and 24.01 - NPFA-805 Transition
Project stage: Other
ML14036A0682014-02-18018 February 2014
Request for Withholding Information from Public Disclosure, 12/9/11 Affidavit Executed by C. M. Molnar, Westinghouse, LTR-RAM-II-10-046, Revision 1, Dated 4/22/2011
Project stage: Withholding Request Acceptance
ML14036A0832014-02-18018 February 2014
Request for Withholding Information from Public Disclosure, 3/14/12 Affidavit Executed by J. A. Gresham, Westinghouse, Re.: Compact Containing Fire Dynamic Simulator Input
Project stage: Withholding Request Acceptance
ML14070A5912014-02-28028 February 2014
Supplemental Response to Safe Shutdown Analyses (SSA) Request for Additional Information (RAI) 06 - NFPA-805 Transition
Project stage: Supplement
ML14115A2972014-04-10010 April 2014
Enclosure 1: Fort Calhoun Station, Unit 1 - Supplement to License Amendment Request 10-07, Proposed Changes to Adopt NFPA 805, Performance-Based Standard for Fire Protection for Light Water Reactor Generating Plants
Project stage: Supplement
ML14115A2982014-04-10010 April 2014
Supplement to License Amendment Request 10-07, Proposed Changes to Adopt NFPA 805, Performance -Based Standard for Fire Protection for Light Water Reactor Generating Plants
Project stage: Supplement
LIC-14-0042, Enclosure 2: Fort Calhoun Station, Unit 1 - Supplement to License Amendment Request 10-07, Proposed Changes to Adopt NFPA 805, Performance-Based Standard for Fire Protection for Light Water Reactor Generating Plants2014-04-10010 April 2014
Enclosure 2: Fort Calhoun Station, Unit 1 - Supplement to License Amendment Request 10-07, Proposed Changes to Adopt NFPA 805, Performance-Based Standard for Fire Protection for Light Water Reactor Generating Plants
Project stage: Supplement
ML14122A2452014-05-22022 May 2014
Request for Withholding Information from Public Disclosure, 3/26/13 Affidavit Executed by C. M. Molnar, Westinghouse, Re.: LTR-RAM-II-10-046, Rev. 3
Project stage: Withholding Request Acceptance
ML14098A0922014-06-16016 June 2014
Issuance of Amendment No. 275, Adopt National Fire Protection Association Standard 805, Performance-Based Standard for Fire Protection for Light-Water Reactor Generating Plants (2001 Edition)
Project stage: Approval
ML14163A0022014-06-16016 June 2014
Summary of Audit Conducted March 5-9, 2012, Request to Adopt National Fire Protection Association (NFPA) 805, Performance-Based Standard for Fire Protection for LWR Electric Generating Plants
Project stage: Other
ML16103A3482016-04-0404 April 2016
Ft. Calhoun, Unit 1 - License Amendment Request (LAR) 16-01; Revised Commitment to Modify FCS Plant Systems as Part of the Implementation of NFPA 805
Project stage: Request
LIC-16-0099, License Amendment Request (LAR) 16-06; Removal of License Condition 3.D., Fire Protection Program2016-11-18018 November 2016
License Amendment Request (LAR) 16-06; Removal of License Condition 3.D., Fire Protection Program
Project stage: Request
2013-02-22
[Table View] |
Text
Omaha Public Power District 444 South 16'h Street Mall Omaha, NE 68102-2247 LlC-11-0130 December 19, 2011 u.s. Nuclear Regulatory Commission ATTN: Document Controll Desk Washington, D.C. 20555-0001
References:
- 1. Docket No. 50-285
- 2. Letter from OPPD (J. A. Reinhart) to NRC (Document Control Desk),
License Amendment Request 110-07, Proposed Changes to Adopt NFPA 805, Performance-Based Standard for Fire Protection for Light Water Reactor Generating Plants (2001 Edition) at Fort Calhoun Station, dated September 28, 2011 (LlC-11-0099)(ML11276A118)
- 3. Teleconference between NRC (L. E. Wilkins, et. a!.) and OPPD (J. L.
McManis, et. a!.), Request for Additional Information for Acceptance of License Amendment Request Re:
Fort Calhoun Station NFPA 805 Transition, December 6, 2011
- 4. Letter from NRC (L. E. Wilkins) to OPPD (David J. Bannister), Fort Calhoun Station, Unit No. 1 -
National Fire Protection Association Standard 805 License Amendment Application Onl'ine Reference Portal (TAC No.
ME7244), dated December 13, 2011 (NRC-11-0134)(ML113260423)
SUBJECT:
Supplement to License Amendment Request (LAR) 10-07, Proposed Changes to Adopt NIFPA 805, Performance-Based Standard for Fire Protection for Light Water Reactor Generating Plants (2001 Edition) at Fort Calhoun Station In the Reference 2 license amendment request (LAR), the Omaha Public Power District (OPPD) requested an amendment to Renewed Facility Operating License No. DPR-40 for Fort Calhoun Station (FCS), Unit No.1, to adopt National Fire Protection Association (NFPA) 805, Performance-Based Standard for Fire Protection for Light Water Reactor Generating Plants (2001 Edition). Implementation of the regulatory actions presented in the attachments to Reference 2 wi" enable FCS to adopt a new fire protection licensing basis which complies wit'h the requirements in 10 CFR 50.48(a), 10 CFR 50.48(c), and the guidance in Regulatory Guide 1.205, Revision 1.
Employl/lem with Equ(/l Opporlllllirv
U. S. Nuclear Regulatory Commission LlC-11-0130 Page 2 During the conference call held with the Nuclear Regulatory Commission (NRC) staff on December 6, 2011 (Reference 3), the staff provided OPPD with questions necessary for the NRC to complete its acceptance review of the NFPA 805 application (Reference 2). The NRC requested that OPPD submit a supplement to Reference 2 with the responses to the NRC's questions.
OPPD's responses to the NRC's questions are provided in the attachment to this LAR supplement.
The documents necessary to support OPPD's responses to the NRC's questions are available on the FCS online reference portal. As described in Reference 4, this allows the NRC staff and its contractors limited read-only access to these documents.
In accordance with the terms and conditions of Reference 4, the online reference portal is password-protected and passwords will be assigned to NRC staff directly involved in the review on a need-to-know basis. The online reference portal will be sufficiently secure to prevent NRC staff from printing, saving, or downloading any documents; and conditions of use of the onl,ine reference portal will be displayed on the log-in screen and willi require concurrence by each user.
There are no regulatory commitments being made in this letter.
If you should have any questions regarding this letter, or require additiona ~ information, please contact Mr. Bill R. Hansher at 402-533-6894.
- .rBa~er Vice President and Chief Nuclear Officer DJB/BJVS/dll1
Attachment:
OPPD Supplement to License Amendment Request 10-07 c:
E. E. Collins, Jr., NRC Regional Administrator, Region IV L. E. Wilkins, NRC Project Manager J. C. Kirkland, NRC Senior Resident Inspector
LlC-11-0130 Attachment Page 1 OPPD Supplement to License Amendment Request 10-07 As discussed in the December 6, 2011, teleconference, the Nuclear Regulatory Commission (NRC) staff has reviewed and evaluated the information provided by the licensee and has determined that the following information is needed in order to complete its acceptance review of the National Fire Protection Association (NFPA) 805 transition license amendment request (LAR) (Reference 1).
NRC Request #1:
It is unclear when the last full peer review occurred on the Internal Events Probabilistic Risk Assessment (PRA) and the wording in the LAR and information is insufficient to determine what facts and observations (F&Os) were carried forward or submitted to the NRC.
Action 1: Provide the date of the last full peer review and the F&Os from that full scope peer review and subsequent focused peer reviews and their disposition.
OPPD's Response to Request #1 :
The last full peer review on the Internal Events PRA was completed in March 1999.
Attachment U, page U-2 of the OPPD NFPA 805 transition LAR dated September 28, 201' 1 (Reference 1), was revisited and it was determined that by today's standards, the October 2001 and August 2003 reviews would be characterized as an "independent review" in lieu of a "peer review."
In addition, the February 2006 review would be characterized as a focused "deltas assessment" in lieu of a focused "peer review." The remaining "reviews" would remain as delineated in Reference 1, Attachment U, page U
- 2.
Please note that the LAR language comes from CFTC-11-95 (Reference 2); and the purpose of CFTC-11-95 was to document the ASME/ANS RA-Sa-2009 roadmap and peer review history for the Internal Events PRA and the Fire PRA of FCS.
OPPD understands the NRC is requesting that the review terminologies used in the LAR (page U-2) be further explained. CFTC-11-95, which provides the explanation of the review terminologies used in Reference 1, contains the history of the reviews, F&Os, and their resolution. CFTC-11-95 is available for NRC review on the FCS online reference portal, which has been established for the NFPA 805 transition LAR review process, in accordance with the terms and conditions delineated in Reference 4.
-~--
UC-11-0130 Attachment Page 2 NRC Request #2:
What is the estimate of the seismic core damage frequency (CDF) for total CDF and large early release frequency (LERF)?
Action 2: Provide an estimate of the seismic CDF and LERF and the basis for the estimate (e.g., PRA, estimate based on seismic margins, etc.).
OPPD's Response to Request #2:
As documented in Section 3.1.4.3.1 of the Individual Plant Examination of External Events (IPEEE) for Fort Calhoun Station (Reference 3, page 3-91), the overall plant High Confidence Low Probability of Failure (HCLPF) capacity is reported as 0.25g. This capacity is governed by the potential for soil liquefaction outside the area of Category I structures.
NRC Request #3:
In Attachment W, for the compressor room 19, Fire Area [fire compartment] FC32, credi,ting the use of an administrative procedure restriction for transient combustibles in the overhead using a factor of.01 is an unreviewed alternate PRA method per the NRC. The factor.01 is already incorporated into the fire database and this would be double counting. It appears the factor should be 1 for no procedure.
Action 3: Perform/Incorporate the use of this factor into the sensitivity analysis.
OPPD's Response to Request #3:
A sensitivity study was performed and is documented in Reference 5. The results of this sensitivity study indicate that if the hot work procedural compliance factor of 0.01, which was applied to the FC32 (Compressor Area Room 19) cable fire caused by welding and cutting scenario, were removed (i.e., set to 1.0), the overall conclusions of the 10 CFR 50.48(c) LAR (Reference 1) would not be changed; and the variance from deterministic requirements (VFDR) assessment results would still remain within the acceptance criteria of Regulatory Guide 1.174.
Reference 5 provides additional background on the use of the 0.01 factor as well as the requested sensitivity study as related to the overall conclusions of the LAR.
NUREG/CR-6850 does not currently provide any specific guidance for crediting hot work procedural restrictions. In order to credit this procedural enhancement, the OPPD fire PRA currently assumes that Room 19 hot work fires wiU only be initiated if the plant
LlC-11-0130 Attachment Page 3 fails to comply with the revised standing order SO-M-9, "Hot Work Operations," and the probability of failing to comply with this procedure is assumed to be 0.01.
The NRC has questioned whether the 0.01 probability of failing to comply with this new procedure revision is independent of the fire frequency, which includes events where hot work controls fail. Reference 5 provides the sensitivity study of hot work procedure compliance unreviewed alternate method (UAM) and the sensitivity study of hot work procedure compliance UAM aggregated with all other UAM sensitivity studies.
Reflecting no credit for the 0.01 procedU'ral compliance factor, the total plant CDF and LERF values are less than 1.00E-04/yr for CDF and 1.00E-05/yr for LERF per the Region II acceptance criteria of Regulatory Guide 1.174.
Reference 5 is available for NRC review on the FCS online reference portal in accordance with the terms and conditions delineated in Reference 4.
References:
- 1. Letter from OPPD (J. A. Reinhart) to NRC (Document Control Desk), License Amendment Request 10-07, Proposed Changes to Adopt NFPA 805, Performance Based Standard for Fire Protection for Light Water Reactor Generating Plants (2001 Edition) at Fort Calhoun Station, dated September 28, 2011 (LlC-11-0099)
(ML11276A118)
- 2. Letter from Westinghouse Electric Company (C. M. Burton) to OPPD (J. McManis),
"Omaha Public Power District, Fort Calhoun Station, NFPA 805 Fire PRA, NFPA 805 - Task 7.17 PRA Peer Review History," dated April 1, 2011 (CFTC-11-95)
(Proprietary)
- 3. Letter from OPPD (T. L. Patterson) to NRC (Document Control Desk), "Phase II Response to Generic Letter 88-20, Supplement 4 Individual Plant Examination of External Events (IPEEE)," dated June 30, 1995 (LlC-95-0130)
- 4. Letter from NRC (L. E. Wilkins) to OPPD (David J. Bannister), Fort Calhoun Station, Unit No. 1 - National Fire Protection Association Standard 805 License Amendment Application Online Reference Portal (TAC No. ME7244), dated December 13, 2011 (NRC-11-0134)(ML113260423)
- 5. L TR-RAM-II-11-133, "Assessment of the Fort Calhoun Station Fire PRA Modeling of Improved Hot Work Controls in the Compressor Area (Room 19)," dated December 8, 2011, Westinghouse Letter from Clarence Worrell and Ashley Mossa to Mehran Golbabai (Proprietary)
