ML031070440

Inservice Inspection Program Relief Request Hope Creek Station

ML031070440
Person / Time
Site:	Hope Creek
Issue date:	04/09/2003
From:	Salamon G Public Service Enterprise Group
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
LRN-03-0157
Download: ML031070440 (4)

Text

PSED Nuclear LLC P.O. Box 236, Hancocks Bridge, New Jersey 08038-0236 APR 0 9 2003 LRN-03-0157 0 PSEG United States Nuclear Regulatory Commission NuclearLLC Document Control Desk Washington, DC 20555 Gentlemen:

REQUEST FOR ADDITIONAL INFORMATION INSERVICE INSPECTION PROGRAM RELIEF REQUEST HOPE CREEK GENERATING STATION FACILITY OPERATING LICENSE NPF-67 DOCKET NO. 50-354 By letter dated February 14, 2003, PSEG Nuclear LLC (PSEG) requested relief (HC-RR-A06) from the requirements of sub paragraph IWA-5250 (a) (2) of the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code, Section Xl, 1989 Edition, in order to implement the alternative requirements of Code Case N-566-2, Corrective Action for Leakage at Bolted Connections, Section Xl, DMsion 1,at the Hope Creek Generating Station. The request for relief is for the second 10-year Inservice inspection (ISI) interval.

The Nuclear Regulatory Commission staff discussed the subject relief request with PSEG staff on April 1,2003 and requested additional Information be provided. Pursuant to that request, PSEG is submitting the enclosed response to the request for additional information.

Should you have any questions regarding this request, please contact Mr. Howard Berrick at 856-339-1862.

Since1 G. Salamon Manager - Nuclear Safety and Licensing Enclosure - Relief Request HC-RR-A06 Request for Additional Information 95-2168 REV. 7199

Document Control Desk 2

'LRN 0167 APR 09 2003 C Mr. H. Miller Regional Administrator - Region I U. S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406 U.S. Nuclear Regulatory Commission ATTN: Mr. G. Wunder Licensing Project Manager - Hope Creek Mail Stop 08B1 Washington DC 20555-001 USNRC Senior Resident Inspector - Hope Creek (X24)

(wlo enclosure)

Mr. K.Tosch, Manager IV Bureau of Nuclear Engineering P.O. Box 415 Trenton, NJ 08625 (wlo enclosure)

Document Control Desk ENCLOSURE LRN- 03-0157 REQUEST FOR ADDITIONAL INFORMATION HOPE CREEK GENERATING STATION By letter dated February 14, 2003 PSEG Nuclear LLC (PSEG) submitted relief request HC-RR-A06 for relief from the requirements of the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code, Section Xl sub paragraph IWA-5250 (a) (2), for Hope Creek Generating Station. The request for relief is for the second 10-year inservice inspection (ISI) interval in which Hope Creek adopted the 1989 Edition of ASME Section Xi, as the Code of record.

The Nuclear Regulatory Commission staff has requested answers to the following questions regarding the relief request submittal:

1. The request does not address what actions would be taken In the event that the evaluation of Code Case N-666-2, paragraphs (a) or (b) determines that the relevant condition cannot be accepted for continuing operation. Please specify what actions would be taken In this event and the requirements directing those actions, e.g., code, procedures.

PSEG Response: In the event that the relevant condition cannot be accepted for continuing operation using Code Case N-566-2 paragraphs (a) or (b), Hope Creek Generating Station would correct the condition in accordance with Its ASME Xi Article IWA-4000 Repair/Replacement Activities and PSEGs ASME Xi Repair Program requirements.

2. The relief request does not address what subsequent Inspections would be performed In the event that the evaluation of Code Case N-666-2, paragraphs (a) or (b) determines that the relevant condition can be accepted for continuing service. This Is of particular Interest for Code Class 2 and 3 components. Please specify what actions would be taken In this event and the requirements directing those actions, e.g., code, procedures.

PSEG Response:

In the event that the evaluation of Code Case N-566-2 paragraphs (a) or (b) determines that the relevant condition can be accepted for continuing service, Hope Creek Generating Station would periodically conduct visual inspections of affected components to verify operating conditions have not changed affecting earlier calculation assumptions. These activities would be completed in accordance with PSEGs ASME Xi Repair Program requirements.

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Document Control Desk ENCLOSURE LRN- 03-0157 If the component's operating conditions have changed, then an additional calculation would be prepared using the newly acquired Information to support assumptions made. If the calculation determines that the relevant condition cannot be accepted for continuing operation or PSEG elects to correct the condition, the condition would be corrected in accordance with its ASME XI Article IWA-4000 Repair/Replacement Activities and PSEG Nuclear's ASME XI Repair Program requirements.

Coordination of these work activities is governed by PSEG procedure NC.WM-AP.ZZ-0001 (Q)

Work Management Process.

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