ML20097E457
| ML20097E457 | |
| Person / Time | |
|---|---|
| Site: | Hope Creek  |
| Issue date: | 06/03/1992 |
| From: | Hagan J Public Service Enterprise Group |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| NLR-N92076, NUDOCS 9206120168 | |
| Download: ML20097E457 (2) | |
Text
O PSEG Pubhc Soroce Electric and Gas Company P.O. Box ?30 Hancock8 Bn@e, New Jersey 08038 Nuclesr Department j
'JUN 0 31992 N LR-N92076 U.S.
Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 Gentlenon:
RETEST SCHEDULE FOR DRYWELL TO SUPPRESSION CHAMLER VACUUM BREAKERS PER TECHNICAL SPECIFICATION 4. 6.2.1.g HOPE CREEK GENERATING STATION DOCKET NO. 50-354 On May 26, 1992, at 1000 hours0.0116 days <br />0.278 hours <br />0.00165 weeks <br />3.805e-4 months <br />, Hope Creek Generating Station (HCGS) entered Limiting Condition for Operation (LCO) 3.6.1.1 because the surveillance Requirements of 4.6.2.1.g could not be met.
The plant was subsequently brought to Hot Shutdown at 22.15 hours1.736111e-4 days <br />0.00417 hours <br />2.480159e-5 weeks <br />5.7075e-6 months <br /> on that date.
Inspection of the eight drywell to suppression chamber vacuum breakers revealed that three of the valves had indication of j
leakage at the valve seating areas.
The cause of this leakage was l
a loosening of the seat bolting ring hardware.
The loosening, I
caused by loss of torque on the nuts, is suspected to be the result of frequent cycling of the valves required by TS 4.6.4.1.b and valve cycling that occurs during nitrogen make-up to the drywell/ torus.
Details of the inspections and specific corrective actions will be provided in a Licensee Event Report due on June 25, 1992.
In accordance with the Surveillance Requirementa of TS 4.6.2.1.g and discussion with Mr.
S.
Deinbek - NRC Licensing Project l
Manager, Public Service Electric and Gas Company (PSE&G) provides the following proposed test schedule for Commission review and approval.
Prior to start-up from the forced outage, TS 4.6.2.1.g was successfully performed on May 30, 1992.
HCGS is scheduled to commence its fourth refueling outage on September 12, 1992.
Prior to start-up from that refueling outage, HCGS will again perform Surveillance Requirement 4.6.2.1.g, after which the eighteen month interval between tests will be re-established.
920612016e 920663 gDR ADOCK 05000354 gp The Energy Peop,e A
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o Document Control Desk 2
JUN O 31992 4
NLR-N92076 PSEGG is confident that this schedule is justified based on good past performance of these valves.
The TS surveillance has been successfully performed during the previous three eighteen-month surveillanen.; (approximately 54 months).
Although the inspections performed revealed no abnormal degradation of the valves seats, they were replaced with new material as a precautionary measure.
The other five drywell to torus vacuum breaker inspection results were satisfactory including a leak check and check on the tightness on the sea.
bolting ring hardware.
If you have any questions on this submittal, ploase do nob hesitate to concact us.
Sincerely,
(
J Ha an General anager -
Hope tr ek Opotations C
Ms. A. Keller Licensing Project Manager g
Mr. T. Martin, Administrator Region I Mr. T. Johnson Senior Resident Inspector Mr. Km.t Tosch, Chief New Jersey Department of Environmental Protection Division of Environmental Quality Bureau of Nuclear Engineering CN 415 Trenton, NJ 08625 k
O I '