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The licensee commented that it had not intended to use the current SFP criticality analyses to bound the MUR. The licensee's proposed schedule indicated a pre-submittal meeting for the MUR and the SFP criticality analyses approximately two months prior to the planned submittal dates. The NRC staff suggested the licensee consider earlier pre-submittal meetings and/or public conference calls to discuss any potential technical issues or questions during its development of the LARs. The NRC staff explained that an ample lead time for NRG/public discussion prior to the docketing of the licensee's SFP criticality analyses and MUR LARs better informs the application process, resulting in higher quality submittals.
The licensee commented that it had not intended to use the current SFP criticality analyses to bound the MUR. The licensee's proposed schedule indicated a pre-submittal meeting for the MUR and the SFP criticality analyses approximately two months prior to the planned submittal dates. The NRC staff suggested the licensee consider earlier pre-submittal meetings and/or public conference calls to discuss any potential technical issues or questions during its development of the LARs. The NRC staff explained that an ample lead time for NRG/public discussion prior to the docketing of the licensee's SFP criticality analyses and MUR LARs better informs the application process, resulting in higher quality submittals.
Closed Meeting Enclosure 4 to the November 8, 2018, letter included a non-proprietary version of the presentation slides used during the closed meeting. The closed meeting focused on technical details of the SFP criticality analyses.
Closed Meeting Enclosure 4 to the November 8, 2018, letter included a non-proprietary version of the presentation slides used during the closed meeting. The closed meeting focused on technical details of the SFP criticality analyses.
The following comments and/or discussion points were included as part of the closed portion of the meeting. 1. The licensee stated that it does not plan to credit any neutron absorbing material in its SFP criticality analyses.  
The following comments and/or discussion points were included as part of the closed portion of the meeting. 1. The licensee stated that it does not plan to credit any neutron absorbing material in its SFP criticality analyses.
: 2. The NRC staff suggested the licensee consider including in the application a discussion of mid-cycle shutdowns.  
: 2. The NRC staff suggested the licensee consider including in the application a discussion of mid-cycle shutdowns.
: 3. Regarding the depletion inputs to the depletion analysis, the NRC staff questioned the use of the maximum lifetime average soluble boron instead of cycle average. 4. The NRC staff suggested including in the application a discussion of any special circumstances regarding the fuel, such as inadvertent insertions of rods, failed rod, lead test assemblies, etc. 5. The NRC staff suggested the licensee include in the SFP reactivity analysis the potential for fuel reconstitution.  
: 3. Regarding the depletion inputs to the depletion analysis, the NRC staff questioned the use of the maximum lifetime average soluble boron instead of cycle average. 4. The NRC staff suggested including in the application a discussion of any special circumstances regarding the fuel, such as inadvertent insertions of rods, failed rod, lead test assemblies, etc. 5. The NRC staff suggested the licensee include in the SFP reactivity analysis the potential for fuel reconstitution.
: 6. The NRC staff suggested the licensee consider physical change to fuel cells (i.e., fuel diameter, etc.) and suggested if this information was previously submitted on the Joseph M. Farley Nuclear Plant docket, then only a reference to the previous submittal is needed. 7. The NRC staff suggested the licensee include a discussion of fuel handing evolutions in the reactivity analysis.  
: 6. The NRC staff suggested the licensee consider physical change to fuel cells (i.e., fuel diameter, etc.) and suggested if this information was previously submitted on the Joseph M. Farley Nuclear Plant docket, then only a reference to the previous submittal is needed. 7. The NRC staff suggested the licensee include a discussion of fuel handing evolutions in the reactivity analysis.
: 8. Regarding the licensee's planned approach to only provide the multiple mislead accident in the application, the NRC staff suggested the licensee include a discussion on how this accident bounds all other accidents and consider the effects to boron dilution.
: 8. Regarding the licensee's planned approach to only provide the multiple mislead accident in the application, the NRC staff suggested the licensee include a discussion on how this accident bounds all other accidents and consider the effects to boron dilution.
The NRC staff suggested the licensee consider Entergy Operations, lnc.'s LAR for fuel assembly mislead (ADAMS Accession No. ML 18068A705).  
The NRC staff suggested the licensee consider Entergy Operations, lnc.'s LAR for fuel assembly mislead (ADAMS Accession No. ML 18068A705).
: 9. The NRC staff suggested the licensee have a contingency for standard fuel and consider if the new fuel vault was analyzed for standard and optimized fuel assembly fuel. 10. The NRC staff suggested the application include a discussion of any unique or first-of-a-kind approaches, and cite references for any precedence.  
: 9. The NRC staff suggested the licensee have a contingency for standard fuel and consider if the new fuel vault was analyzed for standard and optimized fuel assembly fuel. 10. The NRC staff suggested the application include a discussion of any unique or first-of-a-kind approaches, and cite references for any precedence.
: 11. The NRC staff, SNC, and Westinghouse discussed utilizing an audit to improve the efficiency of the review and any requests for additional information.
: 11. The NRC staff, SNC, and Westinghouse discussed utilizing an audit to improve the efficiency of the review and any requests for additional information.
No regulatory decisions or commitments were made during the meeting. No members of the public participated.
No regulatory decisions or commitments were made during the meeting. No members of the public participated.

Revision as of 20:29, 22 April 2019

11/13/2018 Summary of Pre-Application Meeting to Discuss the Joseph M. Farley Nuclear Plant, Units 1 and 2, Spent Fuel Pool Criticality Analyses and Measurement Uncertainty Recapture Amendments
ML18318A253
Person / Time
Site: Farley  Southern Nuclear icon.png
Issue date: 11/26/2018
From: Williams S A
Plant Licensing Branch II
To:
Southern Nuclear Operating Co
Williams S A, 415-1009
References
EPID L-2018-LRM-0063
Download: ML18318A253 (5)


Text

LICENSEE:

FACILITY:

SUBJECT:

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 November 26, 2018 Southern Nuclear Operating Company, Inc. Joseph M. Farley Nuclear Plant, Units 1 and 2

SUMMARY

OF NOVEMBER 13, 2018, PRE-APPLICATION MEETING TO DISCUSS THE JOSEPH M. FARLEY NUCLEAR PLANT, UNITS 1 AND 2, SPENT FUEL POOL CRITICALITY ANALYSES AND MEASUREMENT UNCERTAINTY RECAPTURE AMENDMENTS (EPID L-2018-LRM-0063)

On November 13, 2018, an open Category 1 public meeting and closed meeting was held between the U.S. Nuclear Regulatory Commission (NRC) and representatives of Southern Nuclear Operating Company, Inc. (SNC) and Westinghouse Electric Company (Westinghouse) at NRC Headquarters, One White Flint North, 11555 Rockville Pike, Rockville, Maryland.

The purpose of the meeting was to discuss various aspects of a future spent fuel pool (SFP) criticality analyses license amendment request (LAR) and a measurement uncertainty recapture (MUR) amendment.

The meeting notice and agenda, dated October 24, 2018, are available in the NRC Public Meeting website and at Agencywide Documents Access and Management System (ADAMS) Accession No. ML 18303A060.

A list of attendees is enclosed.

By letter dated November 8, 2018 (ADAMS Accession No. ML 18316A017), SNC submitted a letter and affidavit requesting Enclosure 3, proprietary presentation slides, be withheld from public disclosure pursuant to Title 10 of the Code of Federal Regulations ( 10 CFR) Section 2.390. By letter dated November 15, 2018 (ADAMS Accession No. ML 18312A241

), the NRC issued an approval for the request for withholding.

The November 8, 2018, letter included a non-proprietary version of the presentation slides discussed during the closed meeting.

Public Meeting Enclosure 1 to the November 8, 2018, letter included the presentation slides used during the public meeting. The public meeting primarily focused on the MUR and the schedule for the MUR and SFP criticality analyses LARs. During the discussion of the MUR and SFP criticality LAR schedule, the NRC staff suggested that the licensee submit the SFP criticality LAR at least 6 months prior to the MUR submittal date, because the approval of the MUR has the potential to be dependent on the approval of the SFP criticality LAR. The NRC staff shared that its goal is to complete the SFP criticality analyses LAR within 1 year; however, historically, the review has taken longer due to various complexities in these types of licensing actions. The NRC staff commented that if the current SFP criticality analyses of record provide enough margin to bound the proposed power uprate of the MUR, then the new proposed SFP criticality analyses LAR would not delay the potential MUR approval.

The licensee commented that it had not intended to use the current SFP criticality analyses to bound the MUR. The licensee's proposed schedule indicated a pre-submittal meeting for the MUR and the SFP criticality analyses approximately two months prior to the planned submittal dates. The NRC staff suggested the licensee consider earlier pre-submittal meetings and/or public conference calls to discuss any potential technical issues or questions during its development of the LARs. The NRC staff explained that an ample lead time for NRG/public discussion prior to the docketing of the licensee's SFP criticality analyses and MUR LARs better informs the application process, resulting in higher quality submittals.

Closed Meeting Enclosure 4 to the November 8, 2018, letter included a non-proprietary version of the presentation slides used during the closed meeting. The closed meeting focused on technical details of the SFP criticality analyses.

The following comments and/or discussion points were included as part of the closed portion of the meeting. 1. The licensee stated that it does not plan to credit any neutron absorbing material in its SFP criticality analyses.

2. The NRC staff suggested the licensee consider including in the application a discussion of mid-cycle shutdowns.
3. Regarding the depletion inputs to the depletion analysis, the NRC staff questioned the use of the maximum lifetime average soluble boron instead of cycle average. 4. The NRC staff suggested including in the application a discussion of any special circumstances regarding the fuel, such as inadvertent insertions of rods, failed rod, lead test assemblies, etc. 5. The NRC staff suggested the licensee include in the SFP reactivity analysis the potential for fuel reconstitution.
6. The NRC staff suggested the licensee consider physical change to fuel cells (i.e., fuel diameter, etc.) and suggested if this information was previously submitted on the Joseph M. Farley Nuclear Plant docket, then only a reference to the previous submittal is needed. 7. The NRC staff suggested the licensee include a discussion of fuel handing evolutions in the reactivity analysis.
8. Regarding the licensee's planned approach to only provide the multiple mislead accident in the application, the NRC staff suggested the licensee include a discussion on how this accident bounds all other accidents and consider the effects to boron dilution.

The NRC staff suggested the licensee consider Entergy Operations, lnc.'s LAR for fuel assembly mislead (ADAMS Accession No. ML 18068A705).

9. The NRC staff suggested the licensee have a contingency for standard fuel and consider if the new fuel vault was analyzed for standard and optimized fuel assembly fuel. 10. The NRC staff suggested the application include a discussion of any unique or first-of-a-kind approaches, and cite references for any precedence.
11. The NRC staff, SNC, and Westinghouse discussed utilizing an audit to improve the efficiency of the review and any requests for additional information.

No regulatory decisions or commitments were made during the meeting. No members of the public participated.

Docket Nos. 50-348 and 50-364

Enclosure:

List of Attendees cc: Listserv Shawn Williams, Senior Project Manager Plant Licensing Branch 11-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation LIST OF ATTENDEES NOVEMBER 13, 2018, PRE-APPLICATION MEETING WITH SOUTHERN NUCLEAR OPERATING COMPANY JOSEPH M. FARLEY, UNITS 1 AND 2 SPENT FUEL POOL CRITICALITY ANALYSES AND MEASUREMENT UNCERTAINTY RECOVERY AMENDMENTS U.S. Nuclear Regulatory Commission Staff Shawn Williams Michael Markley Kent Wood Fred Forsaty Ahsan Sallman Alexander Chereskin Matthew Hamm Philip Sahd Ed Miller Russell Haskell Robert Lukes Southern Nuclear Operating Company, Inc. Participants Ernest Bates Nicole Jackson Robin Jones Robert Sears Arthur Snow Stephen Schnelker Westinghouse Electric Company Participants Brian Beebe Andrew Blanco James Smith, Ill Dr. Michael Wenner Enclosure

SUBJECT:

SUMMARY

OF NOVEMBER 13, 2018, PRE-APPLICATION MEETING TO DISCUSS THE JOSEPH M. FARLEY NUCLEAR PLANT, UNITS 1 AND 2, SPENT FUEL POOL CRITICALITY ANALYSES AND MEASUREMENT UNCERTAINTY RECAPTURE AMENDMENTS (EPID L-2018-LRM-0063)

DATED NOVEMBER 26, 2018 DISTRIBUTION:

PUBLIC PM File Copy RidsACRS_MailCTR Resource RidsNrrDorlLpl2-1 Resource RidsRgn2MailCenter Resource RidsNrrPMFarley Resource RidsNrrLASRohrer Resource JJohnston, NRR JBowen, OEDO CCook, OEDO RidsNrrDorl Resource ADAMS Accession No.: ML 18318A253 OFFICE D0RL/LPL2-1/PM D0RL/LPL2-1/LA NAME SWilliams KGoldstein (LRonewicz for) DATE 11/21/2018 11/16/2018 KWood, NRR FForsaty, NRR ASallman, NR AChereskin, NRR MHamm, NRR PSahd, NRR EMiller, NRR RHaskell, NRR Rlukes, NRR LBurkhart, OEDO *by e-mail DSS/SNPB/BC*

D0RL/LPL2-1

/B D0RL/LPL2-1

/PM C Rlukes MMarkley SWilliams 11/15/2018 11/21/2018 11/26/2018 OFFICIAL RECORD COPY