ML18106A376

Monthly Operating Rept for Feb 1998 for Salem Generating Station,Unit 2.W/980316 Ltr

ML18106A376
Person / Time
Site:	Salem
Issue date:	02/28/1998
From:	Bakken A, Knieriem R Public Service Enterprise Group
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
LR-N98-0133, LR-N98-133, NUDOCS 9803200105
Download: ML18106A376 (5)

Text

Pul:llic Serv'ice Electric and Gas Company P.O. Box 236 Hancocks Bridge, New Jersey 08038-0236 Nuclear Business Unit March 16, 1998 LR-N98-0133 U.S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 Attn: Document Control Desk MONTHLY OPERATING REPORT SALEM UNIT NO. 2 DOCKET NO. 50-311 Gentlemen:

In compliance with Section 6.9.1.6, Reporting Requirements for the Salem Technical Specifications, the original Monthly Operating report for February, 1998, is attached.

I Sincerely, A C. Bakken Ill General Manager -

Salem Operations RBK/rbk Enclosures C Mr. H. J. Miller Regional Administrator USNRG, Region 1 475 Allendale Road King of Prussia, PA 19046 980320o1o5-98o22e____ -----. ff IIf111/ I/II llll Jllll fI/I~ 1111)11/ If11 PDR ADOCK 05000311 '

R PDR The power is in your hands.  :~...~; u 1..1 :i 'j 95-2168 REV. 6/94

DOCKET NO.: 50-311 UNIT: Salem 2 DATE: 3/15/98 COMPLETED BY: R. Knieriem TELEPHONE: (609) 339-1782 Reporting Period: February 1998 OPERATING DATA REPORT Design Electrical Rating (MWe-Net) 1115 Maximum Dependable Capacity (MWe-Net) 1106 Month Cumulative No. of hours reactor was critical 266 82216 No. of hours generator was on line (service 265 1009 79072 hours)

Unit reserve shutdown hours 0.0 0.0 0.0 Net Electrical Energy (MWH) 284620 1078200 78253785 UNIT SHUTDOWNS NO. DATE TYPE DURATION REASON METHOD OF CORRECTIVE F=FORCED (HOURS) (1) SHUTTING ACTION/COMMENT S=SCHEDULED DOWN THE REACTOR (2) 1 2/12/98 F 268.9 A 1 2A Emergency Diesel

- Generator Failure 2/23/98 2 2/23/98 s 138.4 B Power Operated Relief

- Valve Repair 2/28/98 (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 2 began the month of February operating at full power. On February 11, Unit 2 was shutdown as required by Technical Specifications following the failure of the 2A Emergency Diesel Generator (EOG) turbocharger. This shutdown was reported in Licensee Event Report 311/98-005-00. The 2A EOG was returned to service on February 23, but the unit remained shutdown for the remainder of the month to address Pressurizer Safety valve and Power Operated Relief valve seat leakage.

DOCKET NO.: 50-311 UNIT: Salem 2 DATE: 3/15/98 COMPLETED BY: R. B. Knieriem TELEPHONE: (609) 339-1782

SUMMARY

OF CHANGES, TESTS. AND EXPERIMENTS FOR THE SALEM UNIT 2 GENERATING STATION MONTH February 1998 The following items completed during FEBRUARY 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 2EC-3329, Pkg. 1, Condenser Hotwell Level Control Modifications. This modification removed the existing *condenser hotwell level instrumentation from all six hotwell bays and installed new level instrumentation on the same six hotwells. Additionally, Control Room instrumentation was modified to provide level indication for all six hotwells and a recorder was added for trend recording of condensate overflow.

This design change does not negatively impact any accident response. This design change does not increase the probability or consequences of either an accident or a malfunction of equipment important to safety. Therefore, this design change does not involve an Unreviewed Safety Question.

2EC-3444, Alternate Shutdown System Inverter Replacement. This modification replaced the existing 15 KVA Alternate Shutdown system inverter with a new 3 KVA inverter. A reduction in the capacity of the inverter was possible since this inverter will be dedicated to Alternate Shutdown system service only.

This design change does not negatively impact any accident response. This design change does not increase the probability or consequences of either an

accident or a malfunction of equipment important to safety. Therefore, this de,sign change does not involve an Unreviewed Safety Question.

2EC-3471, Pkg. 1, Reconfiguration Of Main Generator Cooling Water System Runback Logic. This modification upgraded the Main Generator non-safety related water cooling system runback logic from one out of one logic to a two out of three logic to minimize unnecessary generator trips.

This design change does not negatively impact any accident response. This design change does not increase the probability or consequences of either an accident or a malfunction of equipment important to safety. Therefore, this design change does not involve an Unreviewed Safety Question.

Minor Modification, S97-065, Station Air (SA) Supply Header To Penetration Coolers Strainer Installation Modification. This modification provides a normal and backup Station Air supply to Salem Unit 1 and Unit 2 Penetration Cooling with a "Y" strainer capable of removing and collecting Station Air system debris before it enters the SA 107 regulating valves and the Penetration Area.

This design change does not negatively impact any accident response. This design change does not increase the probability or consequences of either an accident or a malfunction of equipment important to safety. Therefore, this design change does not involve an Unreviewed Safety Question.

Minor Modification, S97-175, Rerouting Of Non-Reactor Coolant System Leakage To The Containment Sump Instead Of The Pressurizer Relief Tank. This modification reroutes non-Reactor Coolant system (RCS) leakage to the Containment Sump in lieu of the Pressurizer Relief tank (PRT). This will aid in the determination of identified and unidentified RCS leakage. By removing the sources of non-RCS leakage into the PRT, the remaining leakage into the PRT can then be classified as identified RCS leakage.

This design change does not negatively impact any accident response. This design change does not increase the probability or consequences of either an accident or a malfunction of equipment important to safety. Therefore, this design change does not involve an Unreviewed Safety Question.

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

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

. UESAR Change Notices Summary of Safety Evaluations UFSAR CN 98-002, Minimum Ambient Temperature For The Service Water Intake Structure. This evaluates a change to the minimum ambient room temperature within the Service Water Intake Structure from 60°F to 40°F. The safety evaluation assessed the operability of the safety related and non-safety related electrical and instrumentation and controls equipment within the Pump Bays and Control Rooms.

Deficiency Reports Summary of Safety Evaluations There were no changes in this category implemented during January, 1998.

Other Summary of Safety Evaluations Safety Evaluation S97-011, Modify Salem Units 1 & 2 Monthly Operating Report Contents To Reflect The Requirements Of Genric Letter 97-02. This evaluates a change to the contents of the Salem Units 1 & 2 Monthly Operating Report to incorporate the reporting requirements of Generic Letter 97-02. This change reduced scope of the plant operating data that was required to be reported.

This evaluation does not negatively impact any accident response. This procedure revision does not increase the probability or consequences of either an accident or a malfunction of equipment important to safety. Therefore, this procedure revision does not involve an Unreviewed Safety Question.