ML18100A520
| ML18100A520 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 08/02/1993 |
| From: | Hagan J Public Service Enterprise Group |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| IEB-88-004, IEB-88-4, NLR-N93106, NUDOCS 9308110147 | |
| Download: ML18100A520 (3) | |
Text
Public Service Electric and Gas Company Joseph J. Hagan Public Service Electric and Gas Company P.O. Box 236, Hancocks Bridge, NJ '08038 609-339-1200 Vice President - Nuclear Operations AUG O 21993.
NLR-N93106 United States Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 Gentlemen:
NRC BULLETIN 88-04 SALEM GENERATING.STATION UNIT NO. 1 FACILITY OPERATING LICENSE NOS. DPR-70 DOCKET NO. 50-272
.By *1etters dated August 31, 1990, and supplemented in May.29, 1992 (Refs: NLR-N90172 and NLR-N92047 respectively) Public Service Electric and Gas Company (PSE&G) committed to install a permanent modification to the Residual Heat Removal (RHR) system to address the Bulletin 88-04 concerns on RHR Pump interactions.
As a result of conversations between the NRC Salem Project Manager and members of my staff, and PSE&G design engineering analysis; it was determined that the administratively controlled compensatory actions would suffice to meet the intent of Bulletin 88-04.
Accordingly, PSE&G will not implement any hardware*
modification to the RHR system as stated in our previous correspondence (Ref: NLR-N90172; dated August 31, 1990).
The Technical Specification surveillance program in accordance with 4. o. 5-P testing will be us.ed to monitor for. strong-weak pump interaction.
The test procedure has been verified to include provisions to monitor recirculation flows when both pumps are placed in paralleled operations.
Tracking and trending of these test results, including historical data, does not indicate that a significant strong-to-weak pump interaction has occurred.
Recirculation flows do not fluctuate by more than approximately 50 GPM, with both pumps developing recirculation flows of approximately 500 GPM.
100072 9308110147 930802 I PDR ADOCK 05000272 G
AUG 021993 Document Control Desk NLR-N93106.
2 Maximum recirculation flow to support at least 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> of operations has been determined to be 300 GPM.
The acceptance criteria for determining pump operability shall be reviewed to include guidance for recirculation flows less than 300 GPM.
If, during during parallel operations, recirculation flow should drop below 300 GPM.on any pump, that pump shall be declared inoperable.
As stated above, the surveillance acceptance criteria provides limits for required actions, thus ensuring action would be taken and degradation would not proceed and result in a dead-head condition.
PSE&G believes that this test can accurately predict pump performance, and when necessary appropriate corrective actions will be taken to ensure continued operability of the RHR pumps.
These corrective/preventative actions may include pump refurbishment, replacement, or other appropriate action as determined by PSE&G at the time of the event.
Should you have any questions regarding this transmittal, please do not hesitated to contact me.
Sincerely, I
I
_____ J
Dccument Control Desk NLR-N93106 Attachment c
Mr. J. c. Stone
_ Licensing Project Manager Mr. T. Johnson Senior Resident Inspector Mr. T. Martin, Administrator Region I Mr. Kent Tosch, Manager IV 3
New Jersey Department of Environmental Protection Division of Environmental Quality Bureau of Nuclear Engineering CN 415 Trenton, NJ 08625 AUG])2 1993