ML18106A328
| ML18106A328 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 01/31/1998 |
| From: | Bakken A, Knieriem R Public Service Enterprise Group |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| LR-N98079, NUDOCS 9802240361 | |
| Download: ML18106A328 (4) | |
Text
Public Service Electric and Gas Company P.O. Box 236 Hancocks Bridge, New Jersey 08038-0236 Nuclear Business Unit U. S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 Attn: Document Control Desk MONTHLY OPERA TING REPORT SALEM UNIT NO. 2 DOCKET NO. 50-311 Gentlemen:
FEB 1 7 1998 LR-N98079 In compliance with Section 6.9.1.6, Reporting Requirements for the Salem Technical Specifications, the original Monthly Operating report for January, 1998, is attached.
This report has incorporated format changes to reflect the reporting requirements specified by Generic Letter 97-02.
RBK/rbk Enclosures C
Mr. H. J. Miller Sincerely, A. C. Bakken Ill General Manager -
Salem Operations Regional Administrator USNRC, Region 1 475 Allendale Road King of Prussia, PA 19046 9802240361 980131 PDR ADOCK 05000311 R
PDR The power is in your hands.
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95-2168 REV. 6/94
Reporting Period:
January 1998 DOCKET NO.: 50-311 UNIT: Salem 2 DATE: 2/15/98 COMPLETED BY:
R. Knieriem TELEPHONE: (609) 339-1782 OPERATING DATA REPORT Design Electrical Rating (MWe-Net)
Maximum Dependable Capacity (MWe-Net) 1115 1106 Wiii#?ifi?i.Wkii'iWM.!'d M@ttWWJtMMtt*?Y
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Month Year-to-date Cumulative No. of hours reactor was critical 744 744 81951 No. of hours generator was on line (service hours) 744 744 78808 0
0 0
Unit reserve shutdown hours Net Electrical Energy (MWH) 793580 793580 77969165 UNIT SHUTDOWNS NO.
DATE TYPE F=FORCED S =SCHEDULED (1) Reason A - Equipment Failure (Explain)
B - Maintenance or Test C - Refueling D - Regulatory Restriction DURATION (HOURS)
E - Operator Training/License Examination F - Administrative G - Operational Error (Explain)
H - Other Summary:
REASON (1)
METHOD OF CORRECTIVE SHUTTING ACTION/COMMENT DOWN THE REACTOR (2)
(2) Method 1 - Manual 2 - Manual Trip/Scram 3 - Automatic Trip/Scram 4 - Continuation 5 - Other (Explain)
Salem Unit 2 began the month of January at full power. On January 1, power was reduced to 10% to effect repairs to a Main Generator stator water temperature control valve. Repairs were completed and the unit was returned to full power on January 2. The unit operated at full power for the remainder of the month.
DOCKET NO.: 50-311 UNIT: Salem 2 DATE: 2/15/98 COMPLETED BY: R. B. Knieriem TELEPHONE: (609) 339-1782
SUMMARY
OF CHANGES, TESTS, AND EXPERIMENTS FOR THE SALEM UNIT 2 GENERATING STATION MONTH JANUARY 1998 The following items completed during JANUARY 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 1 OCFR50.59 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 1 OCFR50.59 Safety Evaluations determined that no unreviewed safety or environmental questions are involved.
Design Changes Summary of Safety Evaluations 2EC-3298, Pkg. 1 Switchgear and Penetration Area Ventilation System (SPAV) Upgrade. This modification provided design enhancements to the SPAV system in the form of improvements to return and exhaust fans, dampers, ductwork, instrumentation, and controls. These design enhancements were necessary to improve system performance and reliability.
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-3570, Pkg. 1, Nitrogen Purge/Blanket Of The Auxiliary Feedwater Storage Tank. This design change provided a nitrogen purge/blanket system for the Unit 2 Auxiliary Feedwater Storage Tank (AFST) to control the dissolved oxygen concentration in the Auxiliary feedwater.
- 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.
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Temporary Modifications Summary of Safety Evaluations There were no changes in this category implemented during January, 1998.
Procedures Summary of Safety Evaluations There were no changes in this category implemented during January, 1998.
UFSAR Change Notices Summary of Safety Evaluations UFSAR Change Notice 98-005, Nuclear Business Unit Organization Change.
This change adds the position of Executive Vice-President - Nuclear Business Unit (EVP-BU) who will report to the Chief Nuclear Officer/President Nuclear Business Unit (CNO-PNBU).
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.
Deficiency Reports Summary of Safety Evaluations There were no changes in this category implemented during January, 1998.
Other Summary of Safety Evaluation Safety Evaluation S97-318. Revise Technical Specification Bases 3/4.1.3 Movable Control Assemblies. This evaluates a revision to the Technical Specification Bases section 3/4.1.3 for the Movable Control Assemblies to indicate that rod position may be verified by either the control console rod position indicators or by the plant computer.
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.