ML18093A207
| ML18093A207 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 07/01/1987 |
| From: | Corbin McNeil Public Service Enterprise Group |
| To: | NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM) |
| References | |
| NLR-N87115, NUDOCS 8707080037 | |
| Download: ML18093A207 (2) | |
Text
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Public Service Electric and Gas Company Corbin A. McNeill, Jr.
Senior Vice President -
Nuclear Public Service Electric and Gas Company P.O. Box236, Han cocks Bridge, NJ 08038 609 339-4800 July 1, 1987 NLR-N87115 United States Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 Gentlemen:
FEEDWATER VALVE MAINTENANCE SALEM GENERATING STATION UNIT NO. 2 DOCKET NO. 50-311 This letter documents two telecons held with NRC staff members on June 8 and 12, 1987, concerning maintenance performed on Feedwater Isolation Valve 23 BF-19.
On Monday, June 8, 1987, a packing leak of approximately 1 gallon per minute was observed on the 23 BF-19 valve.
The corrective action proposed to stop the leak was to tighten the packing holdown nuts.
This action is considered to be a maintenance item in accordance with ASME Section XI, Article IWV-3200, and as such the valve should be tested prior to return to service to demonstrate performance parameters are within acceptable limits.
When the valve packing nuts were tightened, initial 'loadings were found to be about 10 ft-lbs., which was below the manufacturer's recommended torque of 13 to 17 ft-lbs.
The valve packing nuts were tightened to 13 ft-lbs., and then to 17 ft-lbs.
- However, the leak did not diminish.
After further consultations with the valve packing vendor and a telecon with the NRC Project Manager, the following actions were taken on June 12, 1987.
The packing load was increased from 17 ft-lbs. to 19 ft-lbs., and the leak stopped.
The packing was then adjusted an additional 2 ft-lbs. to 21 ft-lbs.
Again, there was not evidence of seal leakage&
In the vendors judgement, the only consequence of leaving the packing at this setting would be a decrease in the packing life.
,,- 9707080037 a7o701 PDR ADOCK 05000311 p
Document Control Desk 2
7-1-87 ASME Section XI requires that a timed full stroke test be performed after maintenance on this type of valve.
Performance of this test requires shutdown of the unit.
In lieu of this test, the valve was partially stroked and responded satis-factorily.
Stern movement was observed, thus indicating that the valve stern was not bound by the packing adjustment.
A work order was initiated to repack the valve at the next available opportunity.
It should be noted that the 23 BF-13 valve acts as a backup to the main feedwater isolation valve 23 BF-19.
Thus the main feedwater system could have been isolated, if necessary, even if the 23 BF-19 stroke time was affected.
If you should have any questions concerning this matter, feel free to contact us.
Sincerely, C
Mr. D. c. Fischer USNRC Licensing Project Manager Mr. T. J. Kenny USNRC Senior Resident Inspector Mr. w. T. Russell, Administrator USNRC Region I Mr. D. M. Scott, Chief Bureau of Nuclear Engineering Department of Environmental Protection 380 Scotch Road Trenton, NJ 08628