ML18106A963

Monthly Operating Rept for Oct 1998 for Salem,Unit 1. with 981112 Ltr

ML18106A963
Person / Time
Site:	Salem
Issue date:	10/31/1998
From:	Bakken A, Knieriem R Public Service Enterprise Group
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
LR-N98-0540, LR-N98-540, NUDOCS 9811240168
Download: ML18106A963 (6)

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OPS~G Public Service Electric and Gas Company P.O. Box 236 Hancocks Bridge, New Jersey 08038-0236 Nuclear Business Unit NOV 12 1998 LR-N98-0540 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 October 1998 is attached.

Sincerely,

(-----

. Bakken Ill

- -- --- - --981-i240168- 981031- G neral Manager -

PDR ADOCK 05000272 Salem Operations 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.: 50-272 UNIT: Salem 1 DATE: 11 /15/98 COMPLETED BY: R. Knieriem TELEPHONE: (609) 339-1782 Reporting Period: October 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 745 4976 t09357 No. of hours generator was on line (service 745 4735 105124 hours)

Unit reserve shutdown hours 0 0 0 Net Electrical Energy (MWH) 810459 4867846 105004389 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 October 1998, operating at full power. Full power operation continued until October 25, when power was reduced to 95% to perform Circulating Water system routine maintenance. The unit returned to full power on the following day. Power was again reduced to 96% on October 28, to repair a leak on the

DOCKET NO.:

UNIT:

50-272 Salem 1 DATE: 11715798 COMPLETED BY: R. B. Knieriem TELEPHONE: (609) 339-1782 16C Feedwater Heater. Full power operation was restored on the same day and continued through the end of the month.

• DOCKET NO.:

UNIT:

50-272 Salem 1 DATE: 11715798 COMPLETED BY: R. B. Knieriem TELEPHONE: (609) 339-1782

SUMMARY

OF CHANGES, TESTS, AND EXPERIMENTS FOR THE SALEM UNIT 1 GENERATING STATION MONTH: October 1998 The following items completed during October 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 Minor Modification 598-029, Primary Water Storage Tank (PWST)

Diaphragm Modifications This modification supported minor physical changes to the PWSTs to facilitate the installation and operation of new diaphragms. The existing diaphragms were deteriorated and were replaced to reduce dissolved oxygen levels in the PWSTs.

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). This review determined that the change did not increase the probability or the consequences of an accident previously evaluated in the SAR because there are no specific anticipated operational transients or design basis accidents that are applicable to the modification. The review concluded that the change would not increase the probability or the consequences of a malfunction of equipment important to safety. The review also concluded that the modification would not create the possibility of an accident or malfunction of a different type from any previously evaluated in the SAR, because the change did not modify the operation or the design basis function of any safety*

equipment. Because the change did not affect the existing analysis that forms

the basis for the Technical Specifications, and will not violate Technical Specification and Updated Final Safety Analysis Report (UFSAR) requirements, the change will not reduce the margin of safety as defined in the basis for the Technical Specifications.

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

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

UFSAR Change Notices - Summary of Safety Evaluations UFSAR Change Notice S98-023, Addition Of Licensing To The Required Members Of The Station Operations Review Committee (SORC)

This change added a requirement for a Licensing Department representative, to the list contained in the UFSAR of disciplines that are represented on the SORG.

Licensing was added to provide additional insight into regulatory requirements, codes, and standards during the review of issues brought before SORG. Review of this change under 10CFR50.59 is required because it will result in changes to the facility as described in the SAR.

This change only affects the administrative requirements for the composition of the SORG listed in the UFSAR. As such, the change will not increase the probability or consequences of an accident previously analyzed, the malfunction of equipment important to safety, nor create the possibility of an accident or malfunction of a different type. In addition, this change will not reduce the margin of safety as defined in the basis for any Technical Specifications.

UFSAR Change Notice S98-037, Common Nuclear Business Unit (NBU)

Radiation Protection Organization This change consolidated the Salem, Hope Creek and Technical Services Radiation Protection (RP) organizations into a single NBU organization. The organization would be managed by a single Radiation Protection Manager (RPM) who would have responsibility for implementation of the Radiation Protection programs at both the Salem and Hope Creek stations, as well as directing the support functions previously performed by the RP Technical Services group. Review of this change under 10CFR50.59 is required because it will result in changes to procedures as described in the SAR.

Because this change consists only of the consolidation of the Radiation Protection organization, the change will not increase the probability or consequences of and accident previously evaluated or of a malfunction of equipment important to safety. The change will not create the possibility of an accident or malfunction of a different type. In addition, the change does not affect any Technical Specifications and therefore will not reduce the margin of safety as described in the basis for any Technical Specifications.

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

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