ML100630161

RAI Related to Salem, Units 1 and 2 LRA Section 4.2, Reactor Vessel Neutron Embrittlement, Section 4.4.1, Reactor Vessel Underclad Cracking Analyses, and Section 4.4.2, Reactor Coolant Pump Flywheel Fatigue Crack Growth Analyses

ML100630161
Person / Time
Site:	Salem
Issue date:	03/22/2010
From:	Ashley D License Renewal Projects Branch 1
To:	Joyce T Public Service Enterprise Group
Ashley D
References
Download: ML100630161 (7)

Text

March 22, 2010 Mr. Thomas Joyce President and Chief Nuclear Officer PSEG Nuclear LLC P.O. Box 236 Hancocks Bridge, NJ 08038

SUBJECT:

REQUEST FOR ADDITIONAL INFORMATION RELATED TO SALEM NUCLEAR GENERATING STATION, UNITS 1 AND 2 LICENSE RENEWAL APPLICATION SECTION 4.2, REACTOR VESSEL NEUTRON EMBRITTLEMENT, SECTION 4.4.1, REACTOR VESSEL UNDERCLAD CRACKING ANALYSES, AND SECTION 4.4.2, REACTOR COOLANT PUMP FLYWHEEL FATIGUE CRACK GROWTH ANALYSES

Dear Mr. Joyce:

By letter dated August 18, 2009, as supplemented by letter dated January 23, 2009, Public Service Enterprise Group Nuclear, LLC, submitted an application pursuant to Title 10 of the Code of Federal Regulation Part 54 (10 CFR Part 54) for renewal of Operating License Nos.

DPR-70 and DPR-75 for Salem Nuclear Generating Station Units 1 and 2, respectively. The staff of the U.S. Nuclear Regulatory Commission (NRC or the staff) is reviewing this application in accordance with the guidance in NUREG-1800, Standard Review Plan for Review of License Renewal Applications for Nuclear Power Plants. During its review, the staff has identified areas where additional information is needed to complete the review. The staffs requests for additional information are included in the Enclosure. Further requests for additional information may be issued in the future.

Items in the enclosure were discussed with John Hufnagel and other members of your staff during a telephone call on January 28, 2010, and a mutually agreeable date for the response is within 30 days from the date of this letter. If you have any questions, please contact me by telephone at 301-415-3191 or by e-mail at shley.ashley@nrc.gov.

Sincerely,

/RA/

Donnie J. Ashley, Senior Project Manager Projects Branch 1 Division of License Renewal Office of Nuclear Reactor Regulation Docket Nos. 50-272 and 50-311

Enclosure:

As stated cc w/encl: See next page

ML100630161 OFFICE LA:DLR PM:DLR:RPB1 BC:DLR:RPB1 PM:DLR:RPB1 NAME Y. Edmonds D. Ashley B. Pham D. Ashley DATE 03/16/10 03/17/10 03/22/10 03/22/10 REQUEST FOR ADDITIONAL INFORMATION RELATED TO SALEM NUCLEAR GENERATING STATION, UNITS 1 AND 2 LICENSE RENEWAL APPLICATION SECTION 4.2, REACTOR VESSEL NEUTRON EMBRITTLEMENT, SECTION 4.4.1, REACTOR VESSEL UNDERCLAD CRACKING ANALYSES, AND SECTION 4.4.2, REACTOR COOLANT PUMP FLYWHEEL FATIGUE CRACK GROWTH ANALYSES RAI 4.2.1-1 License renewal application (LRA) Section 4.2.1, Neutron Fluence Analyses, stated The current reactor vessel embrittlement analyses that evaluate reduction of fracture toughness of the Salem Nuclear Generating Station, Units 1 and 2 (Salem) reactor vessel beltline materials are based on predicted 40-year end-of-license (EOL) fluence values of 32 Effective Full Power Years (EFPY).

Please confirm that the current licensing basis 32 EFPY reactor vessel embrittlement analyses for Salem, Units 1 and 2 are those approved in a safety evaluation (SE) dated May 25, 2001, regarding a power uprate request. This request included a pressure-temperature (P-T) limits revision and an exemption request to use American Society of Mechanical Engineers Code Case N-640, Alternative Reference Fracture Toughness for Development of P-T Limit Curves.

WCAP-15565, Revision (Rev.) 1, Salem Unit 1 Heatup and Cooldown Curves for Normal Operation, and WCAP-15566, Rev. 1, Salem Unit 2 Heatup and Cooldown Curves for Normal Operation, are supplements to support the review of the P-T limits revision. Both are dated February 2001 and contain the 32 EFPY and the 48 EFPY fluence values for Salem reactor pressure vessel (RPV) materials.

Please (1) provide basis for reducing the RPV fluence value from 2.42E+19 at 48 EFPY (WCAP-15565, Rev. 1) to 1.83E+19 at 50 EFPY (LRA) for Unit 1 and from 2.66E+19 at 48 EFPY (WCAP-15566, Rev. 1) to 1.96E+19 at 50 EFPY (LRA) for Unit 2, and (2) supplement LRA Section 4.8, References, by providing additional list of references from which the fluence values in LRA Tables 4.2.1-1 (Unit 1) and 4.2.1-2 (Unit 2) were obtained.

RAI 4.2.2-1 LRA Section 4.2.2, Upper Shelf Energy [(USE)] Analyses, states that Charpy USE for the beltline forgings and welds of Salem, Units 1 and 2 were determined using surveillance data and the Charpy USE for the RPV extended beltline materials was determined without the use of surveillance data. This statement is not consistent with information in LRA Table 4.2.2-1 for Unit 1, which shows that surveillance data was used for evaluating only the intermediate shells, and information in LRA Table 4.2.2-2 for Unit 2, which shows that surveillance data was used for evaluating only one intermediate shell.

The Nuclear Regulatory Commissions (NRCs) Reactor Vessel Integrity Database (RVID) indicates that, in addition to the intermediate shells, Intermediate Shell Axial Weld 2-042 of the Unit 1 RPV has more than one surveillance data point; likewise, WCAP-15692, Analysis of Capsule Y from the Public Service Electric and Gas Company Salem Unit 2 Reactor Vessel Radiation Surveillance Program, indicates that, in addition to Intermediate Shell B4712-2, ENCLOSURE

Intermediate Shell Axial Weld 2-442 of the Unit 2 RPV has more than one surveillance data. For these weld materials having at least two surveillance data, please use Position 2.2 of the Regulatory Guide (RG) 1.99, Rev. 2, Radiation Embrittlement of Reactor Vessel Materials, to evaluate their USE values and revise the subject statement appropriately. Note that there are no criteria in RG 1.99, Rev. 2 to determine credibility of measured USE data.

RAI 4.2.2-2 Unlike LRA Tables 4.2.2-1 and 4.2.2-2, the NRCs RVID does not contain information for the extended beltline materials of the Salem, Units 1 and 2 RPVs. Please discuss the procedures that you used to determine the chemistry data, initial reference temperature (RTNDT), margins and initial USE values for the extended beltline materials to demonstrate that you have applied consistent approaches in determining the above mentioned material information for both beltline and extended beltline materials.

RAI 4.2.3-1 In LRA Tables 4.2.3-1 and 4.2.3-2, the applicant presented the pressurized thermal shock (PTS) reference temperature, RTPTS, values for 50 EFPY for Salem, Units 1 and 2. Also presented in these tables are input parameters necessary for calculating the RTPTS values. The staff found some discrepancies between these LRA Tables and those in the RVID, or WCAP-15565, Rev.

1, and requests the applicant to address them:

Unit 1

• LRA Table 4.2.3-1 shows that the chemistry factors based on surveillance data of intermediate shell plates, B2402-1, B2402-2, and B2402-3 are different from those documented in RVID, or WCAP-15565, Rev. 1. Provide basis for your revision.

• LRA Table 4.2.3-1 shows that the chemistry data for the lower shell longitudinal weld 3-042C (the limiting beltline material of Salem, Unit 1) is different from those documented in WCAP-15565, Rev. 1 which is consistent with the RVID data. Provide basis for your revision.

Unit 2

• LRA Table 4.2.3-2 shows a chemistry factor of 189.1 °F based on the table of RG 1.99, Rev. 2 for Intermediate Shell Longitudinal Weld 2-442. However, WCAP-15692 shows a value of 194.53 °F based on surveillance data for this weld. Justify your approach of not using surveillance data to estimate the chemistry factor for this weld.

RAI 4.4.2-1 The WCAP-14535-A report, Topical Report on Reactor Coolant Pump [(RCP)] Flywheel Inspection Examination, is used to support the RCP flywheel analysis for the period of extended operation. To accept this, the Salem plant-specific experience of its RCP flywheels must support all assumptions made in the WCAP-14535-A report analysis. To demonstrate this, please discuss the past examination results of the RCP flywheels, including the associated flaw evaluations conducted.

Letter to T. Joyce from D. Ashley dated March, 22, 2010

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Salem Nuclear Generating Station, Units 1 and 2 cc:

Mr. Robert Braun Mr. Ali Fakhar Senior Vice President Nuclear Manager, License Renewal PSEG Nuclear LLC PSEG Nuclear LLC One Alloway Creek Neck Road One Alloway Creek Neck Road Hancocks Bridge, NJ 08038 Hancocks Bridge, NJ 08038 Mr. Carl Fricker Mr. William Mattingly Station Vice President - Salem Manager - Salem Regulatory Assurance PSEG Nuclear LLC PSEG Nuclear LLC One Alloway Creek Neck Road One Alloway Creek Neck Road Hancocks Bridge, NJ 08038 Hancocks Bridge, NJ 08038 Mr. Michael Gallagher Township Clerk Vice President - License Renewal Projects Lower Alloways Creek Township Exelon Nuclear LLC Municipal Building, P.O. Box 157 200 Exelon Way Hancocks Bridge, NJ 08038 Kennett Square, PA 19348 Mr. Paul Bauldauf, P.E., Asst. Director Mr. Ed Eilola Radiation Protection Programs Plant Manager - Salem NJ Department of Environmental PSEG Nuclear LLC Protection and Energy, CN 415 One Alloway Creek Neck Road Trenton, NJ 08625-0415 Hancocks Bridge, NJ 08038 Mr. Brian Beam Mr. Brian Booth Board of Public Utilities Director Nuclear Oversight 2 Gateway Center, Tenth Floor PSEG Nuclear Newark, NJ 07102 P.O. Box 236 Hancocks Bridge, NJ 08038 Regional Administrator, Region I U.S. Nuclear Regulatory Commission Mr. Jeffrie J. Keenan, Esquire 475 Allendale Road Manager - Licensing King of Prussia, PA 19406 PSEG Nuclear LLC One Alloway Creek Neck Road Mr. Greg Sosson Hancocks Bridge, NJ 08038 Director Corporate Engineering PSEG Nuclear LLC Senior Resident Inspector One Alloway Creek Neck Road Salem Nuclear Generating Station Hancocks Bridge, NJ 08038 U.S. Nuclear Regulatory Commission Drawer 0509 Mr. Paul Davison Hancocks Bridge, NJ 08038 Vice President, Operations Support PSEG Nuclear LLC One Alloway Creek Neck Road Hancocks Bridge, NJ 08038

Salem Nuclear Generating Station, Units 1 and 2 cc:

Ms. Christine Neely Director - Regulator Affairs PSEG Nuclear LLC One Alloway Creek Neck Road Hancocks Bridge, NJ 08038 Mr. Earl R. Gage Salem County Administrator Administration Building 94 Market Street Salem, NJ 08079