ML18092A174
| ML18092A174 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 05/11/1984 |
| From: | Liden E Public Service Enterprise Group |
| To: | Varga S Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML18092A175 | List: |
| References | |
| REF-GTECI-A-36, REF-GTECI-SF, RTR-NUREG-0612, RTR-NUREG-612, TASK-A-36, TASK-OR NUDOCS 8405170220 | |
| Download: ML18092A174 (2) | |
Text
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Public Service Electric and Gas Company P.O. Box 236 Hancocks Bridge, New Jersey 08038 Nuclear Department May 11, 1984
- u. s. Nuclear Regulatory Commission Office of Nuclear Reactor Regulation Division of Licensing Washington, D. C.
20555 I
Attention:
Mr. Steven A. Varga, Chief Operating Reactors Branch, No. 1
Dear Mr. Varga:
CONTROL OF HEAVY LOADS NUREG-0612 SALEM GENERATING STATION UNITS NO.
1 AND 2 DOCKET NOS. 50-272 AND 50-311 In an April 12, 1984, telephone conversation with PSE&G personnel, Mr. Singh of the NRC staff and Mr. C. Bomberger of Westek, indicated certain items needed to be resolved to close out our-phase one program for control of heavy loads.
The open items were on the reactor vessel head and internals lifting devices initial design and design margins, proof of workmanship, and a program of continued compliance.
To resolve these issues, we are providing a copy of Westinghouse's WCAP-10167 "Evaluation of the Acceptability of the Reactor Vessel Head Lift Rig, Reactor Vessel Internal Lift Rig, Load Cell, and Load Cell Linkage to the Requirements of NUREG-0612", which provides a detailed design analysis, makes recommendations on maintenance, testing, and repair, and concludes that the devices comply with the intent of NUREG-0612 and ANSI Nl4.6-1978.
These findings have been reviewed by Quadrex Corporation in QUAD-1-84-006, "Evaluation of RPV Head and Internals Lift Rigs", which also concludes that the devices comply with the intent of ANSI Nl4.6-1978.
r--84os170220-84o51_:1_ -- --- ~
PDR ADOCK 05000272 P
PDR The Energy People 95-2168 (75M) 12-83
Mr. Steven 5/11/84 Quadrex found one small omission in Westinghouse's technical evaluation concerning the moment on the backing block of the internals lift rig spreader assembly (see paragraph 3.1 of QUAD-1-84-006).
PSE&G is now requesting further analysis from Westinghouse and expects to resolve this item in the near future.
The testing, maintenance, and repair recommendations have been incorporated into Salem Maintenance Procedures.
Should you have any questions, do not hesitate to contact us.
Enclosures C
Mr. Donald C. Fischer Licensing Project Manager Mr. James Linville Senior Resident Inspector Amargit Singh Sincerely, E. A. Liden Manager -
Nuclear Licensing and Regulation w/att.
NRC - Auxiliary Systems Branch