ML18106A980

Monthly Operating Rept for Nov 1998 for Salem,Unit 1.With 981214 Ltr

ML18106A980
Person / Time
Site:	Salem
Issue date:	11/30/1998
From:	Bakken A, Knieriem R Public Service Enterprise Group
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
LR-N98-0571, LR-N98-571, NUDOCS 9812210197
Download: ML18106A980 (6)

Text

. , e OPS~G

• Public. Service, Electric and Gas Company P.O. Box 236 Hancocks Bridge, New Jersey 08038-0236 Nuclear Business Unit DEC 141998 LR-N98-0571 U.S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 Attn: Document Control Desk MONTHLY OPERA TING REPORT SALEM UNIT NO. 1 DOCKET NO. 50-272 Gentlemen:

In compliance with Section 6.9.1.6, Reporting Requirements for the Salem Technical I

Specifications, the original Monthly Operating report for November 1998 is attached.

Sincerely, A. C. Bakken Ill General Manager -

Salem Operations

/rbk Enclosures ,- '~ ..

C Mr. H. J. Miller Regional Administrator USNRC, Region 1 475 Allendale Road

__ ____15ir}g of Prussia, PA 19046 9812210197 981130 . * - - -

PDR ADOCK 05000272 R PDR.

The power is in your hands.

95-2168 REV. 6/94

_J

9 *DEC 14*1998 DOCKET NO.: 50-272 UNIT: Salem 1 DATE: 12/15/98 COMPLETED BY: R. Knieriem TELEPHONE: (609) 339-1782 Reporting Period: November 1998 OPERATING DATA REPORT Design Electrical Rating (MWe-Net) 1115 Maximum Dependable Capacity (MWe-Net) 1106 Month Year-to-date Cumulative No. of hours reactor was critical 720 5696 110077 No. of hours generator was on line (service 720 5455 105844 hours)

Unit reserve shutdown hours 0 0 0 Net Electrical Energy (MWH) 788192 5656038 105792581 UNIT SHUTDOWNS NO. DATE TYPE DURATION REASON METHOD OF CORRECTIVE F=FORCED (HOURS) (1) SHUTTING ACTION/COMMENT -

S=SCHEDULED DOWN THE REACTOR(2)

(1) Reason (2) Method A - Equipment Failure (Explain) 1 - Manual B - Maintenance or Test 2 - Manual Trip/Scram C - Refueling 3 - Automatic Trip/Scram D - Regulatory Restriction 4 - Continuation E - Operator Training/License Examination 5 - Other (Explain)

F - Administrative G - Operational Error (Explain)

H -Other Summary:

Salem Unit 1 began the month of November 1998, operating at full power. Full power operation continued until November 3, when power was reduced to 93% to remove the 15C Feedwater Heater from service to repair a valve leak. The unit returned to full power on November 5. Full power operation continued for the remainder of the month.

• DEC 14*1998 DOCKET NO.: 50-272

• UN IT: Salem 1 DATE: 12715798 COMPLETED BY: R. B. Knieriem TELEPHONE: {609) 339-1782

SUMMARY

OF CHANGES, TESTS, AND EXPERIMENTS FOR THE SALEM UNIT 1 GENERATING STATION MONTH: November 1998 The following items completed during November 1998 have been evaluated to determine:

1. If the probability of occurrence or the consequences of an accident or malfunction of equipment important to safety previously evaluated in the safety analysis report may be increased; or

2. If a possibility for an accident or malfunction of a different type than any evaluated previously in the safety analysis report may be created; or

3. If the margin of safety as defined in the basis for any technical specification is reduced.

The 10CFR50.59 Safety Evaluations showed that these items did not create a new safety hazard to the plant; nor did they affect the safe shutdown of the reactor. These items did not change the plant effluent releases and did not alter the existing environmental impact. The 10CFR50.59 Safety Evaluations determined that no unreviewed safety or environmental questions are involved.

Design Changes - Summary of Safety Evaluations Design Change Package 1EX-2287, Package 1, Monoethanolamine (ETA)

Feedwater Iron Transport Reduction Test This design change package tested the use of ETA as a supplement to or as a substitute for ammonium hydroxide to provide enhanced secondary system pH and corrosion control. Review of this modification under 10CFR50.59 was required because the modification constituted a change to the facility as described in the Safety Analysis Report (SAR), changed procedures as described in the SAR, and involved a test not described in the SAR.

This change did not increase the probability or the consequences of an accident previously evaluated in the SAR. Specifically, operational transients or design basis accidents associated with a release of a hazardous chemical to the atmosphere or a secondary system failure associated with corrosion. The change did not increase the probability of occurrence or the consequences of a malfunction of equipment importance to safety because no changes were made to any system or component required to safely operate or shut down the reactor.

The change did not increase the possibility of a different type from any previously

!DEC 14* 1998 evaluated in the SAR because no new failure modes were created by the change. Finally, the change maintained the margin of safety, as defined in the Technical Specification Bases by ensuring that secondary water chemistry parameters are maintained within control limits established by industry standards, thereby ensuring that steam generator tube corrosion is negligible.

Temporary Modifications - Summary of Safety Evaluations There were no changes in this category implemented during November 1998.

Procedures - Summary of Safety Evaluations There were no changes in this category implemented during November 1998.

UFSAR Change Notices - Summary of Safety Evaluations There were no changes in this category implemented during November 1998.

Deficiency Reports - Summary of Safety Evaluations Deficiency Report Safety Evaluations 03 and 04, Temporary Leak Repair Of Pressure Seal In Valve 12BF22, Feedwater Stop Check Containment Isolation Valve These Safety Evaluations addressed the temporary leak repair of the 12BF22 valve. Review of this modification under 10CFR50.59 was required because the modification constituted a change to the facility as described in the Safety Analysis Report (SAR). Specifically, the safety evaluations addressed additional injections of sealant subsequent to the original repair. The subsequent injections involved the drilling of additional injection ports in the valve body and injection of the sealant at a pressure higher than the maximum design pressure of the valve.

This repair method was analyzed and found to be acceptable with no impact to valve operability.

The safety evaluations concluded that the temporary leak repairs would not affect the design basis of the 12BF22 valve as it relates to its ability to perform its safety function or increase its susceptibility to failure. Therefore the probability or consequences of an accident previously evaluated in the SAR or the possibility of an accident of a different type were not increased. Additionally, because the temporary leak repairs would not affect the ability of the 12BF22 to perform its safety function or increase its susceptibility to failure, the probability or consequences of a malfunction of equipment important to safety or a malfunction of a different type were not increased. Finally, the temporary repair did not involve a change to the bases of any Technical Specifications and therefore did

evaluated' in the SAR because no new failure modes were created by the

. change. Finally, the change maintained the margin of safety, as defined in the DEC 14.* 1998 Technical Specification Bases by ensuring that secondary water chemistry parameters are maintained within control limits established by industry standards, thereby ensuring that steam generator tube corrosion is negligible.

Temporary Modifications - Summary of Safety Evaluations There were no changes in this category implemented during November 1998.

Procedures - Summary of Safety Evaluations There were no changes in this category implemented during November 1998.

UFSAR Change Notices - Summary of Safety Evaluations There were no changes in this category implemented during November 1998.

Deficiency Reports - Summary of Safety Evaluations Deficiency Report Safety Evaluations 03 and 04, Temporary Leak Repair Of Pressure Seal In Valve 12BF22, Feedwater Stop Check Containment Isolation Valve These Safety Evaluations addressed the temporary leak repair of the 12BF22 valve. Review of this modification under 10CFRS0.59 was required because the modification constituted a change to the facility as described in the Safety Analysis Report (SAR). Specifically, the safety evaluations addressed additional injections of sealant subsequent to the original repair. The subsequent injections involved the drilling of additional injection ports in the valve body and injection of the sealant at a pressure higher than the maximum design pressure of the valve.

These repairs were analyzed and found to be acceptable with no impact to valve operability.

The safety evaluations concluded that the temporary leak repairs would not affect the design basis of the 12BF22 valve as it relates to its ability to perform its safety function or increase its susceptibility to failure. Therefore the probability or consequences of an accident previously evaluated in the SAR or the possibility of an accident of a different type were not increased. Additionally, because the_

temporary leak repairs would not affect the ability of the 12BF22 to perform its safety function or increase its susceptibility to failure, the probability or consequences of a malfunction of equipment important to safety or a malfunction of a different type were not increased. Finally, the temporary repair did not involve a change to the bases of any Technical Specifications and therefore did

IOEC 14* 1998 not reduce the margin of safety as defined in the basis for any Technical

- Specifications.

Other - Summary of Safety Evaluations There were no changes in this category implemented during November 1998.