ML101930496

Request for Additional Information for Salem Nuclear Generating Station Units 1 and 2 License Renewal Application (TAC No. ME1834 and Me 1836)

ML101930496
Person / Time
Site:	Salem
Issue date:	07/30/2010
From:	Bennett Brady License Renewal Projects Branch 1
To:	Joyce T Public Service Enterprise Group
CUADDRADO, SAMUEL NRR/DLR/RPB1 415-2946
References
TAC ME1834, TAC ME1836
Download: ML101930496 (5)

Text

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

SUBJECT:

REQUEST FOR ADDITIONAL INFORMATION FOR SALEM NUCLEAR GENERATING STATION, UNITS 1 AND 2 LICENSE RENEWAL APPLICATION (TAC NOS. ME 1834 AND ME 1836)

Dear Mr. Joyce:

By letter dated August 18, 2009, Public Service Enterprise Group Nuclear, LLC, submitted an application pursuant to Title 10 of the Code of Federal Regulations 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 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 staff's request for additional information is included in the Enclosure. Further requests for additional information may be issued in the future.

Items in the enclosure were provided to Mr. John Hufnagel and other members of your staff, 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 301-415-2981 or bye-mail at bennett. brady@nrc.gov.

Sincerely, Bennett M. Brady, 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: Distribution via Listserv

REQUEST FOR ADDITIONAL INFORMATION FOR SALEM NUCLEAR GENERATING STATION, UNITS 1 AND 2, LICENSE RENEWAL APPLICATION (TAC NOS. ME1834 AND ME1836)

RAI3.1.1.66-01

Background:

The applicant states that the aging effect of loss of material due to erosion for steel steam generator secondary manways (cover only) exposed to air with leaking secondary side water and/or steam addressed in license renewal application (LRA) Table 3.1.1, item 3.1.1-66 is not applicable. The applicant explains that these components are not exposed to air with leaking secondary side water and/or steam because there has been no operating experience at Salem Nuclear Generating Station (Salem) with leaking manways or handholds.

Issue:

The staff notes that even if the applicant has not observed any operating experience of leaking manways or handholes, it does not mean that this Material, Environment, Aging Effect/Mechanism, and aging management program combination can be totally and definitively excluded, especially during the extended period of operation, for these components. Therefore, the staff considers that the applicant has not provided enough information for justifying why LRA item 3.1.1-66 is not applicable.

Request:

Please demonstrate how the aging effect of loss of material due to erosion for steel steam generator secondary manways (cover only) exposed to air with leaking secondary side water and/or steam will never occur during the extended period of operation, or revise accordingly your proposed LRA Table 3.1.1, item 3.1.1-66.

RAI 3.1.1.84-01

Background:

The applicant states that the aging effect of cracking due to stress corrosion cracking (SCC) for nickel alloy steam generator components such as secondary side nozzles (vent, drain, and instrumentation) exposed to secondary feedwater and/or steam addressed in LRA Table 3.1.1, item 3.1.1-84 is not applicable. The applicant explains that this component, material, environment, and aging effect/mechanism combination does not apply because Salem does not have nickel alloy steam generator secondary side nozzles exposed to secondary feedwater and/or steam.

The staff notes that the applicant's description of its steam generators design in LRA Sections 2.3.1.4 and B.2.1.1 0, as well as in Updated Final Safety Analysis Report, Rev. 24, does not ENCLOSURE

- 2 provide sufficient details about the materials of steam generator secondary side nozzles to judge whether the aging effect of see is really not applicable for those components.

Moreover, the staff notes that in LRA Table 3.1.2-4 related to steam generators, the applicant includes nickel alloy spray nozzles exposed to treated water but does not address the aging effect of see.

Request:

Please clarify whether Salem steam generators contain any nickel alloy steam generator components exposed to secondary water and/or steam, or revise accordingly your proposed LRA Table 3.1.1, item 3.1.1-84. Please justify why cracking due to see is an aging effect that does not need to be addressed for the nickel alloy steam generator spray nozzles exposed to treated water.

July 30, 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 FOR SALEM NUCLEAR GENERATING STATION, UNITS 1 AND 2 LICENSE RENEWAL APPLICATION (TAC NOS. ME1834 AND ME1836)

Dear Mr. Joyce:

By letter dated August 18, 2009, Public Service Enterprise Group Nuclear, LLC, submitted an application pursuant to Title 10 of the Code of Federal Regulations 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 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 staff's request for additional information is included in the Enclosure. Further requests for additional information may be issued in the future.

Items in the enclosure were provided to Mr. John Hufnagel and other members of your staff, and a mutually qgreeable 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 301-415-2981 or bye-mail at ben nett. brady@nrc.gov.

Sincerely, IRA!

Bennett M. Brady, 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: Distribution via Listserv DISTRIBUTION:

See next page ADAMS Accession Number' ML101930496 OFFICE PM:DLR:RPB1 LA:DLR BC:DLR:RPB1 PM:DLR:RPB1 NAME B. Brady Y. Edmonds B. Pham B. Brady DATE 07/28/10 07/22110 07/29/10 07/30/10 OFFICIAL RECORD COPY

Letter to T. Joyce from B. Brady dated July 30, 2010 SUB.JECT:

REQUEST FOR ADDITIONAL INFORMATION FOR SALEM NUCLEAR GENERATING STATION, UNITS 1 AND 2 LICENSE RENEWAL APPLICATION (TAC NOS. ME1834 AND ME1836)

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