ML18107A297

Monthly Operating Rept for Apr 1999 for Salem Unit 2.With 990514 Ltr

ML18107A297
Person / Time
Site:	Salem
Issue date:	04/30/1999
From:	Garchow D, Knieriem R Public Service Enterprise Group
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
LR-N99-0226, LR-N99-226, NUDOCS 9905250092
Download: ML18107A297 (6)

Text

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• Public Sel'\iice Electric and Gas Company P.O. Box 236 Hancocks Bridge, New Jersey 08038-0236 Nuclear Business Unit IAY141999 LR-N99-0226 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 April 1999 is attached.

General Manager -

-- - 99os2soo92-99o43o- --~ Salem Operations PDR ADOCK 05000311 R PDR

/rbk Enclosures C Mr. H. J. Miller Regional Administrator USNRC, Region 1 475 Allendale Road King of Prussia, PA 19046 The power is in your hands.

95-2168 REV. 6/94

• DOCKET NO.:

UNIT:

DATE:

50-311 Salem 2 5/15/99 COMPLETED BY: R. Knieriem TELEPHONE: (609) 339-1782 Reporting Period: April 1999 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 50 2210 90828 No. of hours generator was on line (service 49 2209 87560 hours)

Unit reserve shutdown hours 0.0 0.0 0.0 Net Electrical Energy (MWH) 32804 2393082 87365913 UNIT SHUTDOWNS NO. DATE TYPE DURATION REASON METHOD OF CORRECTIVE F=FORCED (HOURS) (1) SHUTTING ACTION/COMMENT S=SCHEDULED DOWN THE REACTOR (2) 1 4/3/99 s 670 c 1 Refueling Outage 4/30/99 (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 April 1999, at 75% power. At that time power was being reduced in preparation for shutdown for the unit's 1oth refueling outage. The shutdown of the unit was completed on April 3, 1999. Salem Unit 2 remained shutdown for the rest of the month.

DOCKET NO.: 50-311 UNIT: Salem 2 DATE: 5/15/99

• COMPLETED BY: R. B. Knieriem TELEPHONE: (609) 339-1782

SUMMARY

OF CHANGES, TESTS, AND EXPERIMENTS FOR THE SALEM UNIT 2 GENERATING STATION MONTH: April 1999 The following items completed during April 1999 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 (DCP) 2EC-3590, Pkg. 19, Service Water System Containment Fan Coil Unit (CFCU) Thermal Overpressure Protection This modification installed a 1" bypass line for each of the five CFCU Service Water return lines. Installation of the bypass lines will eliminate the potential for overpressure in the fan coils in the event of a Loss Of Off-site Power (LOOP) associated with a Main Steam Line Break (MSLB) or Loss of Coolant Accident (LOCA).

Review of this modification under 10CFR50.59 was required because the installation of 1" CFCU bypass lines constituted a change to the facility as described in the Safety Analysis Report (SAR). This modification did not constitute an Unreviewed Safety Question (USQ) because the modification maintained the existing design basis by ensuring that the structural integrity of the Service Water system is maintained during a LOOP coincident with a LOCA

or a MSLB. Therefore this modification did not increase the consequence or probability of an accident previously analyzed. The modification did not increase the probability or consequences of a malfunction of equipment important to safety. This modification would not create any new accidents or malfunctions since no new failure modes were introduced and failure modes considered applicable to this modification are within the existing design basis. In addition the Technical Specification Bases were not affected and no changes to the Technical Specifications were required.

Temporary Modifications - Summary of Safety Evaluations There were no changes in this category implemented during April 1999.

Procedures - Summary of Safety Evaluations There were no changes in this category implemented during April 1999.

UFSAR Change Notices - Summary of Safety Evaluations UFSAR Change Notice S98-039, Engineering Evaluation Of The Spent Fuel Pool Cooling (SFPC) System This UFSAR change incorporated the results of the above referenced engineering evaluation. This evaluation demonstrated that the Salem SFPC system is seismic class I, its components have been seismically evaluated under Seismic Qualification Utility Group, Generic Implementation Procedure (SQUG GIP) methodology. Therefore the SFPC system possesses reliability and hazards protection to the extent that pool temperature will be maintained at or below 180°F and boiling can be eliminated as a credible event.

Review of this evaluation under 10CFR50.59 was required because the previous

• licensing basis of SFPC did not preclude SFPC boiling. Because sustained loss of SFPC has been eliminated as a credible event, the review determined that the change did not increase the probability or consequences of an accident previously evaluated in the SAR. The change did not increase the probability or consequences of a malfunction of equipment important to safety, and did not create the possibility of an accident or malfunction of a different type from any previously evaluated. Because the change did not affect the existing analysis that forms the basis for the Technical Specifications, and did not violate Technical Specification and Updated Final Safety Analysis Report (UFSAR) requirements, the change did not reduce the margin of safety as defined in the basis for the Technical Specifications.

UFSAR Change Notice 599-009, 500 kV Hope Creek-Red Lion Line Trip-A-Unit This UFSAR Change Notice incorporated changes to the off-site power distribution system and the affect of those changes on features used to protect grid stability during off-site power distribution line outages.

Review of this change under 10CFR50.59 was required because the changes to the offsite power distribution system constituted a change to the facility as described in the Safety Analysis Report (SAR). This change did not affect the original design function of the off-site distribution system or the features used to protect grid stability. Therefore, the review determined that the change did not increase the probability or consequences of an accident previously evaluated in the SAR. The change also did not increase the probability or consequences of a malfunction of equipment important to safety and did not create the possibility of an accident or malfunction of a different type from any previously evaluated.

Because the change did not affect the existing analysis that forms the basis for the Technical Specifications, and did not violate Technical Specification and Updated Final Safety Analysis Report (UFSAR) requirements, the change did not reduce the margin of safety as defined in the basis for the Technical Specifications.

Deficiency Reports - Summary of Safety Evaluations There were no changes in this category implemented during April 1999.

Other - Summary of Safety Evaluations Calculations ES-13.005, Revision 6 and ES-13.01 O(Q), Revision 4, Electrical Penetration Overcurrent Protection This change revised Calculations ES-13.005(Q), Revision 6 and ES-13.010(Q),

Revision 4, Electrical Penetration Overcurrent Protection. These calculations contain the controlled list of electrical penetration protection devices that was originally a part of the Technical Specifications and the UFSAR. The list was deleted from those documents and is now controlled by Attachment 3 of the above referenced calculations. This Safety Evaluation evaluates changes made to the list contained in Attachment 3.

Review of this modification under 10CFR50.59 was required because this change constituted a change to the facility as described in the Safety Analysis Report (SAR). The revised calculation concluded that the penetration conductors are electrically loaded within their continuous ratings and are protected against the maximum available short circuit current by the required primary and backup protection devices. No physical changes to the plant were identified by the subject revisions to these calculations. These calculation revisions do not require physical changes to the plant or changes to existing

protection devices. The function of the electrical penetrations in providing part of the Containment boundary is not affected by this proposal. No new accidents or malfunctions are created, and the margin of safety as defined in plant Technical Specifications for affected equipment is not reduced. Therefore, this change did not represent an Unreviewed Safety Question.