ML063390051
| ML063390051 | |
| Person / Time | |
|---|---|
| Site: | Ginna  |
| Issue date: | 12/13/2006 |
| From: | Milano P NRC/NRR/ADRO/DORL/LPLI-1 |
| To: | Korsnick M Ginna |
| Milano P, NRR/DORL/LPLA, 415-1457 | |
| References | |
| TAC MD3118 | |
| Download: ML063390051 (5) | |
Text
December 13, 2006 Mrs. Mary G. Korsnick Vice President R.E. Ginna Nuclear Power Plant R.E. Ginna Nuclear Power Plant, LLC 1503 Lake Road Ontario, NY 14519
SUBJECT:
REQUEST FOR ADDITIONAL INFORMATION REGARDING SERVICE WATER PUMP OPERABILITY REQUIREMENTS, R.E. GINNA NUCLEAR POWER PLANT (TAC NO. MD3118)
Dear Mrs. Korsnick:
By letter dated September 29, 2006, R.E. Ginna Nuclear Power Plant, LCC, requested a change to Technical Specification (TS) 3.7.8, Service Water (SW) System, for R.E. Ginna Nuclear Power Plant (Ginna). The proposed TS change would require a specific number of SW pumps to be operable rather than the current requirement that two trains be operable.
The Nuclear Regulatory Commission (NRC) has reviewed the information provided in the application and has determined that additional information is needed to complete its review.
Enclosed is the NRC staffs request for additional information (RAI). This RAI was discussed with your staff on December 13, 2006, and it was agreed that your response would be provided within 60 days from the date of this letter.
Sincerely,
/RA/
Patrick D. Milano, Senior Project Manager Plant Licensing Branch I-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-244
Enclosure:
RAI cc w/encl: See next page
December 13, 2006 Mrs. Mary G. Korsnick Vice President R.E. Ginna Nuclear Power Plant R.E. Ginna Nuclear Power Plant, LLC 1503 Lake Road Ontario, NY 14519
SUBJECT:
REQUEST FOR ADDITIONAL INFORMATION REGARDING SERVICE WATER PUMP OPERABILITY REQUIREMENTS, R.E. GINNA NUCLEAR POWER PLANT (TAC NO. MD3118)
Dear Mrs. Korsnick:
By letter dated September 29, 2006, R.E. Ginna Nuclear Power Plant, LCC, requested a change to Technical Specification (TS) 3.7.8, Service Water (SW) System, for R.E. Ginna Nuclear Power Plant (Ginna). The proposed TS change would require a specific number of SW pumps to be operable rather than the current requirement that two trains be operable.
The Nuclear Regulatory Commission (NRC) has reviewed the information provided in the application and has determined that additional information is needed to complete its review.
Enclosed is the NRC staffs request for additional information (RAI). This RAI was discussed with your staff on December 13, 2006, and it was agreed that your response would be provided within 60 days from the date of this letter.
Sincerely,
/RA/
Patrick D. Milano, Senior Project Manager Plant Licensing Branch I-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-244
Enclosure:
RAI cc w/encl: See next page DISTRIBUTION:
PUBLIC PDI-1 Reading File R. Laufer RidsNrrDorlLplI-1 P. Milano RidsNrrPMPMilano S. Little RidsNrrLASLittle L. Mrowca RidsNrrDraAplb J. Segala RidsNrrDssSbpb E. Smith A. Howe DORL DPR ACRS RidsAcrsAcnwMailCenter OGC RidsOgcRp Accession Number: ML063390051 OFFICE LPL1-1/PM LPL1-1/LA APLB/BC SBPB/BC LPL1-1/BC NAME PMilano SLittle LMrowca JSegala RLaufer DATE 12/05/06 12/06/06 11/20/06 11/16/06 12/13/06 OFFICIAL RECORD COPY
R.E. Ginna Nuclear Power Plant cc:
Mr. Michael J. Wallace President R.E. Ginna Nuclear Power Plant, LLC c/o Constellation Energy 750 East Pratt Street Baltimore, MD 21202 Mr. John M. Heffley Senior Vice President and Chief Nuclear Officer Constellation Generation Group 1997 Annapolis Exchange Parkway Suite 500 Annapolis, MD 21401 Kenneth Kolaczyk, Sr. Resident Inspector R.E. Ginna Nuclear Power Plant U.S. Nuclear Regulatory Commission 1503 Lake Road Ontario, NY 14519 Regional Administrator, Region I U.S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406 Peter R. Smith, President New York State Energy, Research, and Development Authority 17 Columbia Circle Albany, NY 12203-6399 Carey W. Fleming, Esquire Senior Counsel - Nuclear Generation Constellation Generation Group, LLC 750 East Pratt Street, 17th Floor Baltimore, MD 21202 Charles Donaldson, Esquire Assistant Attorney General New York Department of Law 120 Broadway New York, NY 10271 Ms. Thelma Wideman, Director Wayne County Emergency Management Office Wayne County Emergency Operations Center 7336 Route 31 Lyons, NY 14489 Ms. Mary Louise Meisenzahl Administrator, Monroe County Office of Emergency Preparedness 1190 Scottsville Road, Suite 200 Rochester, NY 14624 Mr. Paul Eddy New York State Department of Public Service 3 Empire State Plaza, 10th Floor Albany, NY 12223
Enclosure REQUEST FOR ADDITIONAL INFORMATION (RAI)
R.E. GINNA NUCLEAR POWER PLANT SERVICE WATER SYSTEM OPERABLITY REQUIREMENTS DOCKET NO. 50-244 By letter dated September 29, 2006, R.E. Ginna Nuclear Power Plant, LCC (the licensee),
requested a change to Technical Specification (TS) 3.7.8, Service Water (SW) System, for R.E. Ginna Nuclear Power Plant (Ginna). The current TS 3.7.8 requires two SW trains and the SW loop header to be operable. The proposed change would require four SW pumps and the loop header to be operable.
To complete its review, the Nuclear Regulatory Commission (NRC) staff requests the following additional information:
- 1.
Regulatory Guide (RG) 1.177, "An Approach for Plant-Specific, Risk-Informed Decisionmaking: Technical Specifications," indicates in Sections 2.1 and 2.2 that licensees should address compliance with current regulations and traditional engineering considerations, respectively, when requesting risk-informed changes to TS requirements. Provide this information consistent with the guidance provided in RG 1.177.
2.
In Section 1.1.7.4 of Attachment 2 of the application, credit is taken in the risk analysis for repair and recovery of an inoperable SW pump. The NRC staff does not consider it appropriate to assume recovery of inoperable equipment as part of the justification that the risk associated with that equipment being inoperable is small. Therefore, provide revised risk calculations that do not assume any credit for repair of inoperable SW pumps.
3.
In Section 1.1.3 of Attachment 2, no specific incremental conditional large early release probability (ICLERP) calculations were performed. The stated basis was that even if 100% of the sequences contributing to the incremental conditional core damage probability (ICCDP) became large early releases, all cases calculated would be at least a factor of 10 below the RG 1.177 criteria for ICLERP. This implicitly assumes that any increase in the large early release frequency (LERF) would only arise from sequences contributing to increases in core damage frequency (CDF), and not from existing core damage sequences, which would now become large early releases. Justify this assumption, or provide ICLERP analysis for the proposed changes.
4.
In Section 1.1.3 of Attachment 2, the licensee does not identify whether the evaluation of ICCDP was based on a zero maintenance model or on a average maintenance model. Identify the basis of the ICCDP and ICLERP calculations.
5.
Section 1.1.3 of Attachment 2, the licensee has not provided separate risk calculations for planned vs. unplanned maintenance assuming a higher common-cause failure rate, consistent with RG 1.177, Appendix A, Section A.1.3.2. Provide these calculations of ICCDP and, if necessary (based on the response for RAI 3), of ICLERP.
6.
Section 1.1.5 of Attachment 2, the Ginna probabilistic safety assessment (PSA) model covers both internal and external events, including fire and external flooding. However, the licensee has not provided any quality information for the fire and external flooding models, nor provided any disposition of other external events which are not quantitatively addressed by the Ginna PSA model. Since the potential risk increase due to the proposed changes is due to loss-of-coolant accidents (LOCAs) of size equivalent to 2-inches diameter or greater (Section 1.1.7.2), confirm that the external events included in the quantitative risk assessment model (i.e., fire and external floods) do not potentially induce LOCAs greater than 2 inches in diameter requiring two SW pumps for mitigation. Otherwise, provide quality information for the external events probabilistic risk assessment model used to support the risk evaluation. In either case, the licensee should disposition seismic risk and other external events risk for this application.
7.
In Section 1.1.2 of Attachment 2, it states that the Ginna PSA model, revision 6.2, has a calculated internal and external event CDF of less than 1E-4 per year, and therefore justifies the application of RG 1.174, An Approach for Using Probabilistic Risk Assessment in Risk-Informed Decisions on Plant-Specific Changes to the Licensing Basis, criteria for risk metrics. Provide the specific value of the CDF and LERF of the baseline model.
8.
In Section 1.1.10.1 of Attachment 2, it states that 33 of 35 B-level facts and observations (F&Os) from the licensees 2002 peer review have been addressed.
However, the NRC staff review of the detailed information on F&Os identified 36 B-level F&Os. It is not apparent which of the B-level F&Os have not yet been completed.
Therefore, specifically identify the F&Os not yet resolved and provide a disposition for each of these F&Os relevant to this application.
9.
In Section 1.3 of Attachment 2, the licensee identifies Sections 1.3.4 and 1.3.5 to address the risk of level 2 and external events in configuration risk management program. These sections are missing from the submittal. Provide this missing information.