ML20082N579
| ML20082N579 | |
| Person / Time | |
|---|---|
| Site: | Hope Creek  |
| Issue date: | 08/30/1991 |
| From: | Crimmins T Public Service Enterprise Group |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| NLR-N91152, NUDOCS 9109090251 | |
| Download: ML20082N579 (3) | |
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4 Putac Se#vice Decine and Gas Company Th: mas M. Crimmins, Jr.
Putu Serva t%ctuc and Ga; Company P O Gm 236. Hancocks (Mdge. NJ 08038 009-339-4700 wer,, u. a w W.,
4 AUG 3 01991 NLR-N91152 U.S.
Nuclear Regulatcry Commission Document Control Detk Washington, DC 20555 Gentlemen:
IN-SERVICE TESTING REQUIREMENTS REQUEST FOR EXTENSION OF EXEMPTION HOPE CREEK GENERATING STATION DOCKET NO. 50-354 On September 27, 1990, the NRC issued a Safety Evaluation Report (SER) approving Public Service Electric and Gas Company's (PSE&G)
In-Serv.'Oc Testing (IST) program.
The SER, in part, allowed a one year relief to develop a suitable method for solenoid valvo actuation testing.
This relief applies to Category B, Category B/C, and Rapid Acting Valves (Sections 4.4.1.1, 4.3.3.1, and 4.1.6.1 of the TER and Items 5, 7,
and 6 of Appendix C) and expires on September 1, 1991.
In a letter dated April 1, 1991, PSE&G explained that the primary method of solenoid valve actuation testing under investigation was the use of acoustic monitoring but that preliminary results of the testing were not encouraging.
Based on this, it was expected that another method would need to be developed and the one year relief extended.
The letter went on to say that if an extension of the one year relief became necessary, a revised relief request would be submitted.
This was acknowledged by the NRC in a letter dated May 13, 1991.
The purpose of this letter is to hereby request an extension to the one year relief applicable to Category B and Rapid Acting Valves (Sections 4.4.1.1 and 4.1.6.1 of the TER and Items 5 and 6 of Appendix C).
When the relief was originally requested, the BWR Owners' Group (BWROG) was attempting to develop a method of testing solenoid valves that could be utilized on a generic level.
PSE&G, an active participant in the BWROG effort, intended to utilize the resulting method.
However, in late 1990 it became apparent that a generic approach to solenoid valve testing could not be established.
At that time, PSE&G initiated an independent effort to investigate various options.
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Document Control Desk 2
NLR-N91152 In February, 1991, PSE&G purchased the " Checkmate II" Check Valve Analysis System.
This approach combines nonintrusive ultrasonic and acoustic signals to provide positive indication of valve position.
At the time of the purchase, the acoustic portion of the system was still under development; consequently, the manufacturer agreed to backfit this modification when development was complete.
In August, 1991, the system was fully functional and factory training of PSE&G technicians commenced.
This training has now been completed and the system has recently been received on-site.
In situ testing to verify feasibility and final acceptability of the system will take place during the week of September 2.
After final acceptance, revisions of all effected procedures will have to be completed prior to full implementation of the system.
Upon implementation, testing of the effected valves will commence as it does not require outage conditions.
Based on the above discussion, PSE&G requests that the one year relief applicable to Category B and Rapid Acting Valves (Sections 4.4.1.1 and 4.1.6.1 of the TER and Items 5 and 6 of Appendix C) be extended to November 1, 1991.
PSE&G further requests that Category B/C Valves (Section 4.3.3.1 of 'he TER and Item 7 of Appendix C) be deleted froa. this relief.
Thir. category applies to Automatic Depressurization System valves 1-AT-PSV-F013A, B,
C, D,
and E.
These valves are shipped to an off-site laboratory during each refueling outage for set-pressure tessing.
It was determined during the third refueling outage (Wircer, 1991) that the offsite laboratory would also perform stru.e-time testing of the associated valves.
This will take place in all future refueling outages and fulfills the requirement to determine an alternate method of stroke-time testing these valves.
If you have any questions regarding this transmittal, please do not hesitate to contact us.
Sincerely, a9-rnup,o
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0 AUG 3 01hl Document Control Desk 3
NLR-N91152 c
Mr. Stephen Dombek Licensing Project Manager Mr. T.
P. Johnson Senior Resident Inspector Mr. T. Martin, Administrator Rogion I Mr. Kent Tosch, Chief Now Jersey Department of Environmental Protection Division of Environmental Quality Bureau of Nuclear Engincoring CN (15 Trent on, 1;J 00625 i
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