ML20154M301
| ML20154M301 | |
| Person / Time | |
|---|---|
| Site: | Hope Creek  |
| Issue date: | 05/26/1988 |
| From: | Miltenberger S Public Service Enterprise Group |
| To: | NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM) |
| References | |
| NLR-N88074, NUDOCS 8806010245 | |
| Download: ML20154M301 (2) | |
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i Public Service Electric and Gas Company St;ven E. Miltenberger Pubhc Service Electric and Gas Cornpany P.O. Box 236, Hancocks Bridge NJ 08038 609-339-4199 V<e Presdent at3 Chet Nvctear Onw May 26, 1988 NLR-N88074 United States Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 Gentlemen:
INSERVICE INSPECTION PROGRAM ASME SECTION XI, EXAMINATION CATEGORY B-A RELIEF REQUESTS HOPE CREEK GENERATING STATION DOCKET NO. 50-3 54 In your letter of December 11, 1987, the Hope Creek Generating Station Inservice Inspection (ISI) Program for the First 10-year Interval was determined to be acceptable and in compliance with 10CFR50. 5 5a(g ) ( 4).
All submitted relief requests were granted except for three concerning reactor vessel welds to be examined pursuant to ASME Saction XI, Table IWB-2 500-1, Examination Category B-A.
The NRC Safety Evaluation Report (SER) attached to the aforementioned letter indicates that these relief requests were not granted and that
...the procedure for the examination of these welds is under review by the regulatory staff at this time."
Although the staff does not agree at this time with the statements made in the INEL Technical Evaluation Report (TER)
EGG-SD-7829 attached to the SER regarding these reactor pressure vessel weld examinations, csrtain statements cannot be ignored with regard to PSE&G's ability to perform the examinations in accordance with the letter of the Code.
In particular, the INEL TER statement that
"...the reactor pressure vessel would have to be redesigned and refabricated in order to complete the remainder (of the examinations)" is not a matter of interpretation.
While PSE&G acknowledges the staff's prerogative to assess weld examination procedures before establishing a formal position, we l
ask that these relief requests remain under consideration while the procedures are reviewed until a firm NRC position is developed and a practical means for licensee compliance has been established.
Until that time, PSE&G contends that our prescribed
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program will accomplish volumetric examination of these welds to i
the maximum extent practical.
PSE&G also contends that 100%
j volumetric examination of these welds cannot practically be performed and that specific compliance with the requirements of ASME Section XI would result in undue hardship and unusual j
difficulties without a compensating increase in the level of quality and safety.
j 8DR ADOCK0500gg4 l (04N 8806010245 88052 q6
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4' Document Control Desk 2
05-26-88 Your cooperation in this matter is appreciated.
Should you have any further questions with regard to this submittal, please do not hesitate to contact us.
Sincerely, U
l C
Mr.
G.
W. Rivenbark USNRC Licensing Project Manager Mr. G. W. Meyer USNRC Senior Resident Inspector Mr. W. T. Russell, Administrator USNRC Region I 4
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Mr.
D.
M. Scott, Chief Bureau of Nuclear Engineering Department of Environmental Protection 380 Scotch Road Trenton, NJ 08628 1
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