ML18093A128
| ML18093A128 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 05/14/1987 |
| From: | Corbin McNeil Public Service Enterprise Group |
| To: | NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM) |
| References | |
| NLR-N87080, NUDOCS 8705220304 | |
| Download: ML18093A128 (2) | |
Text
Public Service Electric and Gas Company Corbin A. McNeill, Jr.
Senior Vice President -
Nucleq.r Public Service Electric and Gas Company P.O. Box236, Hancocks Bridge, NJ 08038 609 339-4800 MAY 1, 4 1987 NLR-N87080 United States Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 Gentlemen:
SALEM GENERATING STATION UNIT NO. 2 DOCKET NO. 50-311 FEEDWATER VALVE MAINTENANCE This letter documents a telecon held with NRC staff members on Friday, April 24, 1987, concerning maintenance performed on Feedwater Isolation Valve 22 BF-19.
On Thursday, April 23, 1987, a packing leak was noted from the 22 BF-19 valve.
On April 24, 1987 it was necessary to tighten the packing holddown nuts to stop the leak.
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 and 12 ft-lbs., which were below the manufacturer's recommended torque of 13 to 17 ft-lbs.
The valve packing nuts were tightened to 13 ft-lbs and the leakage halted.
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 placed in manual and the 22 steam generator level was increased slightly.
The valve was then returned to automatic and stern movement was observed, thus indicating that the valve stem was not bound up by the packing adjustment.
A work order was sent to the Maintenance Department to ensure that the valve be stroked and timed at the next shutdown.
It should also be noted that in the NRC Safety Evaluation dated August 12, 1983, relief was granted from full stroke exercising and stroke time testing these valves during power operation.
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Document Control Desk 2
Note that the 22 BF-13 valve acts as a backup to the main feedwater isolation valve 22 BF-19.
Thus the main feedwater system could have been isolated, if necessary, even if the 22 BF-19 stroke time was affected.
If you should have any questions, please feel free to contact us.
Sincerely, C. A. ~
- c. Ne.; 11,
C Mr. D. c. Fischer Licensing Project Manager Mr. T. J. Kenny 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