ML14240A612
| ML14240A612 | |
| Person / Time | |
|---|---|
| Site: | FitzPatrick  |
| Issue date: | 09/24/2014 |
| From: | Pickett D Plant Licensing Branch 1 |
| To: | Entergy Nuclear Operations |
| Pickett D | |
| References | |
| TAC MF2897 | |
| Download: ML14240A612 (4) | |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 September 24, 2014 Vice-President, Operations Entergy Nuclear Operations, Inc.
James A. FitzPatrick Nuclear Power Plant P.O. Box 110 Lycoming, NY 13093
SUBJECT:
JAMES A. FITZPATRICK NUCLEAR POWER PLANT-REQUEST FOR ADDITIONAL INFORMATION REGARDING PROPOSED CHANGES TO THE TECHNICAL SPECIFICATION LOW PRESSURE SAFETY LIMIT (TAC NO. MF2897)
Dear Sir or Madam:
By letter dated October 8, 2013, Entergy Nuclear Operations, Inc., proposed changes to James A. FitzPatrick Nuclear Power Plant Technical Specification (TS) 2.0, "Safety Limits (SLs)," to reduce the reactor pressure associated with the Reactor Core Safety Limits from 785 psig to 685 psig in TSs 2.1.1.1 and 2.1.1.2.
The Nuclear Regulatory Commission staff is reviewing the submittal and has determined that additional information is needed to complete its review. The specific questions are found in the enclosed request for additional information (RAI). Based on our discussions we understand that a response to the RAI will be provided by November 18, 2014.
Please contact me at (301) 415-1364 if you have any questions on this issue.
Docket No. 50-333
Enclosure:
Request for Additional Information cc w/encl: Distribution via Listserv Sincerely, Douglas V. Pickett, Senior Project Manager Plant Licensing Branch 1-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
REQUEST FOR ADDITIONAL INFORMATION RELATED TO LICENSE AMENDMENT REQUEST FOR TECHNICAL SPECIFICATION CHANGES TO LOW PRESSURE SAFETY LIMIT ENTERGY NUCLEAR OPERATIONS, INC JAMES A FITZPATRICK NUCLEAR POWER PLANT DOCKET NO. 50-333 By letter to the Nuclear Regulatory Commission (NRC) dated October 8, 2013, Entergy Nuclear Operations, Inc. (Entergy), licensee for the James A FitzPatrick Nuclear Power Plant (JAF),
submitted a License Amendment Request (LAR) for review and approval of a revision to the JAF Technical Specification (TS) Section 2.1.1 to reflect a lower reactor steam dome pressure for Reactor Core Safety Limits 2.1.1.1 and 2.1.1.2. Entergy states that the revision is needed to address the potential to exceed the low pressure TS safety limit. The NRC staff has reviewed the request submitted by the licensee and determined that the following additional information is needed.
RAI-01
The LAR references GESTAR II Compliance report, NEDC-33270P, Rev 4 that is only applicable to the GNF2 fuel type. TS Section 4.2.1 (Fuel Assemblies) states that a limited number of lead test assemblies (L TA) that have not completed representative testing may be placed in nonlimiting core regions. Provide the fuel type(s) in the JAF core.
RAI-02
Discuss how the potential of operating the JAF with a core with mixed fuel design might impact the LAR. Address in particular the scenario where the critical power ratio (CPR) correlations for the different fuel types have different lower bound pressure ranges.
RAI-03
TS 2.1.1.2 specifies the safety limit (SL) on the minimum critical power ratio (MCPR).
The proposed change in TS 2.1.1.2 expands the range of applicability of the SL on the MCPR to a lower pressure. The LAR will result in the SL on MCPR becoming applicable at a lower pressure. Discuss the impact of the proposed change in TS 2.1.1.2 on the determination of the MCPR core operating limits (Specification 3.2.2) in the core operating limit report as specified in TS Section 5.6.5.
Enclosure
RAI-04
RAI-05: The proposed change in TS 2.1.1.2 expands the range of applicability of the SL on the MCPR to a lower pressure. Discuss if there is any reduction in the margin of safety because of the expanded range of applicability of the SL on the MCPR. Also provide the MCPRs for the JAF when the reactor is at a rated thermal power (RTP) of 25 percent and 10 percent core flow with steam dome pressures of 785 psig and 685 psig, respectively.
The proposed change in TS 2.1.1.1 modified the pressure from 785 psig to 685 psig.
Why do the bases forTS 2.1.1.1 still refer to 785 psig on page 8 2.1.1-2 of the LAR?
RAI-06
The SL in TS 2.1.1.1 is intended to provide fuel cladding integrity protection during start-up conditions. For operation at low pressures or low flows the thermal power limit of 25 percent RTP is based on full scale ATLAS test data. What would be the corresponding thermal power limit at 10 percent rated core flow and a reactor steam dome pressure of 685 psig if the GEXL 17 was used in formulating the basis?
RAI-07
GE Safety Communication SC05-03 presented a typical pressure regulator failure open response for a low pressure isolation setpoint-analytical limit (LPIS-AL) of 720 psig.
What is the LPIS-AL for the JAF? Discuss the applicability of the generic transient analysis in SC05-03 to the JAF. Discuss expected differences, if any, in the JAF plant response as compared to the generic transient analysis in SC05-03.
September 24, 2014 Vice-President, Operations Entergy Nuclear Operations, Inc.
James A. FitzPatrick Nuclear Power Plant P.O. Box 110 Lycoming, NY 13093
SUBJECT:
JAMES A. FITZPATRICK NUCLEAR POWER PLANT-REQUEST FOR ADDITIONAL INFORMATION REGARDING PROPOSED CHANGES TO THE TECHNICAL SPECIFICATION LOW PRESSURE SAFETY LIMIT (TAC NO. MF2897)
Dear Sir or Madam:
By letter dated October 8, 2013, Entergy Nuclear Operations, Inc., proposed changes to James A. FitzPatrick Nuclear Power Plant Technical Specification (TS) 2.0, "Safety Limits (SLs)," to reduce the reactor pressure associated with the Reactor Core Safety Limits from 785 psig to 685 psig in TSs 2.1.1.1 and 2.1.1.2.
The Nuclear Regulatory Commission staff is reviewing the submittal and has determined that additional information is needed to complete its review. The specific questions are found in the enclosed request for additional information (RAI). Based on our discussions we understand that a response to the RAI will be provided by November 18, 2014.
Please contact me at (301) 415-1364 if you have any questions on this issue.
Docket No. 50-333
Enclosure:
Sincerely, IRA/
Douglas V. Pickett, Senior Project Manager Plant Licensing Branch 1-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Request for Additional Information cc w/encl: Distribution via Listserv DISTRIBUTION:
PUBLIC MRazzaque, SRXB RidsNrrLAKGoldstein RidsRgn1 MaiiCenter RidsNrrPMFitzPatrick LPL 1-1 Reading File RidsAcrsAcnw_MaiiCTR ABurritt, R1 RidsNrrDssSrxb FForsaty, SRXB RidsNrrDoriDpr RidsNrrDoriLpl1-1 ADAMS ACCESSION NO.: ML14240A612 OFFICE LPL 1-1/PM LPL1-1/LA SRXB/BC LPL1-1/BC NAME DPickett KGoldstein UShoop (A)
BBeasley DATE 09/22/2014 09/19/2014 09/23/2014 09/24/2014 OFFICIAL RECORD COPY