ML18106A272

Monthly Operating Rept for Dec 1997 for Salem,Unit 2. W/980115 Ltr

ML18106A272
Person / Time
Site:	Salem
Issue date:	12/31/1997
From:	Bakken A, Knieriem R, Todd F Public Service Enterprise Group
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
LR-N98017, NUDOCS 9801260470
Download: ML18106A272 (7)

Text

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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 JAN 15 199r_J LR-N98017 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 December, 1997, is attached.

I Sincerely,

~A C. Bakken Ill General Manager -

Salem Operations RBK/tcp Enclosures c Mr. H. J. Miller Regional Administrator USNRC, Region 1 475 Allendale Road King of Prussia, PA 19046

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The power is in your hands. . " "

95-2168 REV. 6/94

SALEM GENERATING STATION DOCKET NO.:

• 50-311 UNIT: Salem 2 DATE: 1/15/98 COMPLETED BY: R. Knieriem TELEPHONE: (609) 339-1782 MONTHLY OPERATING

SUMMARY

MONTH DECEMBER 1997 Salem Unit 2 began the month of December operating at full power. Full power operation continued until December 21, when power was reduced to repair a broken stem on the 23 Heater Drain Pump Recirculation Valve. The unit returned to service on December 24, and completed the month at full power.

DOCKET NO.:

• 50-311 UNIT: Salem 2 DATE: 01/09/98 COMPLETED BY: F. Todd TELEPHONE: (609) 339-1316 OPERATING DATA REPORT OPERATING STATUS 1 Reporting Period DECEMBER 1997 Hours in Report Period 2 Currently Authorized Power Level (MWt) 3411 Max Dependable Capacity (MWe-Net) 1106 Design Electrical Rating (MWe-Net) 1115 3 Power level to which restricted (if any) (MWe Net) None 4 Reason For Restriction (if any)

This Month Yr To Date Cumulative 5 No. of hours reactor was critical 744 3123 81207 6 Reactor reserve shutdown hours 0.0 0.0 0.0 7 Hours generator on line 709 2834 78064 8 Unit reserve shutdown hours 0.0 0.0 0.0 9 Gross thermal energy generated (MWH) 2335319 8249240 196030245 10 Gross electrical energy generated (MWH) 778320 2700083 81348681 11 Net electrical energy generated (MWH) 745517 2472951 77175585 12 Unit Service Factor 95.3% 32.4% 49.2%

13 Unit Availability Factor 95.3% 32.4% 49.2%

14 Unit Capacity Factor (MDC) 90.6% 25.5% 43.9%

15 Unit Capacity Factor (DER) 89.9% 25.3% 43.6%

16 Unit Forced Outage Rate 7.7% 67.7% 33.4%

17 Shutdowns scheduled over next 6 months (type, date, duration):

18 If shutdown at end of report period, estimated date of Startup:

DOCKET NO.:

UN IT:

50-311 Salem 2 DATE: 01/09/98 COMPLETED BY: F. Todd TELEPHONE: (609) 339-1316 OPERATING DATA REPORT UNIT SHUTDOWNS AND POWER REDUCTIONS MONTH DECEMBER 1997 METHOD OF SHUTTING DOWN THE TYPE REACTOR OR F=FORCED DURATION REASON REDUCING CORRECTIVE NO. DATE S=SCHEDULED (HOURS) (1) POWER (2) ACTION/COMMENT 3504 12/21 F 0 A 4 Failed stem on the 23

- Heater Drain Pump 12/24 Recirculation Valve.

Power was reduced and the turbine was removed from service.

Reactor remained critical.

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

E - Operator Training/License Examination F - Administrative G - Operational Error (Explain)

H - Other

DOCKET NO.:

UNIT:

50-311 Salem 2 DATE: 01 /09/98 COMPLETED BY: F. Todd TELEPHONE: (609) 339-1316 AVERAGE DAILY UNIT POWER LEVEL MONTH DECEMBER 1997 DAY AVERAGE DAILY POWER DAY AVERAGE DAILY POWER LEVEL (MWe-Net) LEVEL (MWe-Net) 1 1, 103 17 1, 105 2 1, 103 18 1, 106 3 1, 104 19 1, 106 4 1, 105 20 1, 105 5 1, 106 21 905 6 1, 107 22 128 7 1, 102 23 194 8 1, 102 24 521 9 1, 103 25 955 10 1, 107 26 1,084 11 1, 106 27 1,099 12 1, 104 28 1, 104 13 1, 100 29 1, 105 14 1, 100 30 1, 101 15 1, 104 31 1, 102 16 1,105

• DOCKET NO.:

• 50-311 UNIT: Salem 2 DATE: 1/15/98 COMPLETED BY: R. B. Knieriem TELEPHONE: (609) 339-1782

SUMMARY

OF CHANGES, TESTS. AND EXPERIMENTS FOR THE SALEM UNIT 2 GENERATING STATION MONTH DECEMBER 1997 The following items completed during December 1997 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-3340, Pkg. 1 Background Subtraction Performance Upgrade &

Declassification Of Post-Accident Plant Vent Monitor 2R45A, B, C, and D.

This design installed a small, keep-alive source in the 2R45A and 2R45D detectors to prevent "low fail" occurrences and nuisance alarms. The modification also changed the classification of the 2R45 monitors to be non-safety related Reg Guide 1.97 Accident monitors.

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-3395, Pkg. 1, Moisture Separator Reheater Drain And Vent System Modifications. This design change involved piping replacement and rerouting for the MSR drain and vent system to reduce excessive vibration.

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 December, 1997.

Procedures Summary of Safety Evaluations There were no changes in this category implemented during December, 1997.

UFSAR Change Notices Summary of Safety Evaluations There were no changes in this category implemented during December, 1997.

Deficiency Reports Summary of Safety Evaluations There were no changes in this category implemented during December, 1997.

Other Summary of Safety Evaluation Safety Evaluation - Removal Of Insulation Of 23SG Main Steam Sensing Lines. This Safety Evaluation evaluated the temporary removal of insulation from the 23 Main Steam and process sensing lines to demonstrate the effects of condensate buildup in the sensing lines on steam flow indication.

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