ML18100A427
| ML18100A427 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 06/15/1993 |
| From: | Labruna S Public Service Enterprise Group |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| NLR-N93076, NUDOCS 9306280253 | |
| Download: ML18100A427 (2) | |
Text
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Public Service Electric and Gas Company
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Stanley LaBruna Public Service Electric and Gas Company P.O. Box 236, Hancocks Bridge, NJ 08038 609-339-1700 Vice President - Nuclear Engineering JUN 15 1993 NLR-N93076 United States Nuclear Regulatory Commission Document Control Desk Washington, D.C.
20555 Gentlemen:
MECHANICAL SEAL CLAMP ASSEMBLIES SALEM GENERATING STATION UNIT 2 DOCKET NO. 50-311 In 1987, Public Service Electric and Gas Company (PSE&G) detected a leaking canopy seal weld on a spare Control Rod Drive Mechanism (CROM) reactor vessel head penetration.
A Mechanical Seal Clamp Assembly (MSCA) was installed on the leaking penetration as an alternative to seal welding the canopy.
In addition, three non~leaking spare CROM reactor vessel head penetrations had MSCAs installed as a precaution against leakage.
These MSCAs were procured as non-safety-related, non-ASME Code items since PSE&G believed that the Code excluded canopy welds from its jurisdiction *. Subsequent meetings with the NRC Staff revealed that the Staff found the MSCA concept acceptable, however, they concluded that the MSCAs were indeed safety-related and under the jurisdiction of the ASME Code.
The Staff suggested that PSE&G seek temporary Code relief for the MSCAs, per 10CFR50.55a (g) (5)
(iii), to allow time for development of a permanent problem solution.
By letter dated October 13, 1988, Public Service Electric and Gas Company (PSE&G) requested temporary relief from the requirements of ASME Boiler and Pressure Vessel Code,Section III, for the use of the MSCAs.
In a letter dated November 17, 1988, the NRC staff stated that they had reviewed our submittal and determined that the use of MSCA as an alternative to repairing the seal weld was acceptable for a maximum of three fuel cycles.
During the Unit 2 7th refueling outage, the.four non-ASME Code MSCAs were removed and replaced with new MSCAs that are in full compliance with ASME Code requirements.
PSE&G previously committed to MSCA preload verification every cycle.
The new
Document Control Desk NLR-N93076 2
JUN 15 1993 MSCAs are of an improved design that precludes loss of bolt pre-tension while in-service.
The vendor has recommended a preload verification every 5th cycle.
Salem will conduct a preload verification after the 3rd cycle.
If the preload remains unchanged, we will increase the cerification to the vendor recommended frequency of every 5th cycle.
PSE&G considers this issue closed on Salem Unit 2.
Should you have any questions on this transmittal, please contact us.
Sincerely,
,4~~
- s. LaBruna Vice President -
Nuclear Engineering C
Mr. T. T. Martin, Administrator - Region I
- u. s. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406 Mr. J. c. Stone, Licensing Project Manager -
Salem U. s. Nuclear Regulatory Commission One White Flint North 11555 Rockville Pike Rockville, MD 20852 Mr. T. P. Johnson (S09)
USNRC Senior Resident Inspector Mr. K. Tosch, Manager, IV NJ Department of Environmental Protection Division of Environmental Quality Bureau of Nuclear Engineering CN 415 Trenton, NJ 08625