ML18101B305
| ML18101B305 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 03/25/1996 |
| From: | Warren C Public Service Enterprise Group |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| LR-N96077, NUDOCS 9604010336 | |
| Download: ML18101B305 (5) | |
Text
e PS~G Public Service Electric and Gas Company P.O. Box 236 Hancocks Bridge, New Jersey 08038-0236 Nuclear Business Unit MAR 2 51996 LR-N96077 U. S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 Gentlemen:
SPECIAL REPORT 96-01 SALEM GENERATING STATION -
UNIT 1 FACILITY OPERATING LICENSE NO. DPR-70 DOCKET NO. 50-272 This Special Report regarding a valid failure of the lB Emergency Diesel Generator is being submitted pursuant to the requirements of Technical Specification 4.8.1.1.4.
Attachment SORC Mtg.96-036 KJD/tcp C
Distribution LER Fi.ie 3.7
,,., n"' n r.
9604010336 960325 PDR ADOCK 05000272 S
PDR The prnver is in your hands.
Sincerely,
~lJ:uu_
Clay Warren General Manager -
Salem Operations 95-2168 REV. 6/94
~.
SPECIAL REPORT 96-01 PLANT IDENTIFICATION:
Salem Generating Station - Unit 1 Facility Operating License No. DPR-70 Docket No. 50-272 DESCRIPTION OF OCCURRENCE:
On February 24, 1996, a valid failure of the lB Emergency Diesel Generator (EDG) was identified during surveillance testing.
The surveillance test was being performed in accordance with accelerated testing as required by Technical Specification 4.8.1.1.2a.
The lB EDG developed an unisolatable lubricating oil leak at a threaded piping nipple between the main lubricating oil header and an instrument root valve.
The instrument tap provided filter differential pressure and lubricating oil pressure sensing.
The lB EDG was shut down and subsequently declared inoperable.
PLANT CONDITIONS:
The reactor was defueled during the period that the lB EDG was not available.
The lC EDG was available.
The lA EDG and lA 4KV Bus were out of service for scheduled maintenance.
REPORTING REQUIREMENT:
This failure is being reported as required by Technical Specification 4.8.1.1.4 which states:
All diesel generator failures, valid or non-valid, shall be reported to the Commission in a Special Report pursuant to Specification 6.9.2 within 30 days.
Reports of diesel generator failures shall include the information recommended in Regulatory Position C.3.b of Regulatory Guide 1.108~ Revision 1, August 1977.
If the number of failures in the last 100 valid tests (on a per nuclear unit basis) is greater than or equal to 7, the report shall be supplemented to include the additional information recommended in Regulatory Position C.3.b of Regulatory Guide 1.108, Revision 1, August 1977.
I REPORT DETAILS:
The following information is provided as specified in Regulatory Position C.3.b of Regulatory Guide 1.108, Revision 1, August 1977:
- 1.
Diesel Generator unit involved:
lB
- 2.
Number of failures in the last 100 tests:
a)
This was the fourth failure of the lB EDG in the last 100 valid tests.
b)
This was the fifth failure of any Unit 1 EDG in the last 100 valid tests.
- 3.
Cause of the failure:
a)
The apparent cause of the lubricating oil leak was attributed to fatigue due to normal machine vibration based on an identical failure which occurred on lA EDG (described in Special Report 95-02) and a previous jacket water nipple failure on the lB EDG.
- 4.
Corrective Measures Taken a)
The threaded nipple was replaced, and the surveillance test on the lB EDG was satisfactorily completed on February 24, 1996.
b)
A Design Change Package (DCP) was previously initiated for all Unit 1 and 2 diesel generators to address vibration induced piping failures as described in Special Report 95-02.
The DCP is currently being implemented on the lA EDG and will be implemented on the lB EDG by Unit 1 restart.
c)
As committed to in Special Report 95-02, a trending analysis of the Unit 1 EDG failures was performed.
The only common failure mode identified by the analysis was related to vibration.
As described above, DCPs have been developed to address vibration induced failures for Unit 1 and Unit 2 EDGs.
- 5.
Length of time the EDG was out of service:
a)
The lB EDG was out of service for repairs to the lubricating oil instrument line for approximately 14 hours1.62037e-4 days <br />0.00389 hours <br />2.314815e-5 weeks <br />5.327e-6 months <br />.
REPORT DETAILS (Continued) :
- 6.
Define the current surveillance test interval:
a)
+he lB EDG is on a seven day surveillance test frequency as required by TS 4.8.l.1.2a.
This interval is required following two or more failures in the last twenty tests on a per diesel generator basis.
SAFETY CONSEQUENCES AND IMPLICATIONS There was no impact on plant safety due to the failure of the lB EDG unit.
The reactor core was off-loaded to the Spent Fuel Pool (SFP) and decay heat loads in the SFP were relatively low.
During the 14 hour1.62037e-4 days <br />0.00389 hours <br />2.314815e-5 weeks <br />5.327e-6 months <br /> period that the lB EDG was not available, SFP cooling would not have been jeopardized even if all other power sources had been lost.
Document Control Desk LR-N96077 Attachment A The following item represents a commitment that Public Service Electric & Gas (PSE&G) made to the Nuclear Regulatory Commission (NRC) relative to this Special Report(272/96-01).
The commitment is as follows:
"A Design Change Package (DCP) was previously initiated for all Unit 1 and 2 diesel generators to address vibration induced piping failures as described in Special Report 95-
- 02.
The DCP is currently being implemented on the lA EDG and will be implemented on the lB EDG by Unit 1 restart."