ML18100A819

Monthly Operating Rept for Dec 1993 for Salem Generating Station Unit 2.W/940112 Ltr

ML18100A819
Person / Time
Site:	Salem
Issue date:	12/31/1993
From:	HELLER R, SHEDLOCK M, VONDRA C A Public Service Enterprise Group
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 9401210133
Download: ML18100A819 (12)

Text

Pub'lic Service Electric and Gas Company P.O. Box 236 Hancocks Bridge, New Jersey 08038 Salem Generating Station January 12, 1994 U.S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555

Dear Sir:

MONTHLY OPERATING REPORT SALEM NO. 2 DOCKET NO. 50-311 In compliance with Section 6.9.1.6, Reporting Requirements for the Salem Technical Specifications, the original copy of the monthly operating reports for the month of December 1993 are being sent to you. RH:pc Average Daily Unit Power Level Operating Data Report Unit Shutdowns and Power Reductions Safety Related Maintenance 10CFR50.59 Evaluations Operating Summary Refueling Information Salem Operations cc: Mr. Thomas T. Martin Regional Administrator USNRC Region I 631 Park Avenue King of Prussia, PA 19046 Enclosures 8-l-7.R4 The Energy __ People 9401210133 ADOCK PDR 95-2189 (10M) 12-89

• I DAILY UNIT POWER Docket No.: 50-311 Unit Name: Salem #2 Date: 01-10-94 Completed by: Mark Shedlock Telephone:

339-2122 Month December 1994 Day Average Daily Power Level Day Average Daily Power Level (MWe-NET) (MWe-NET) 1 1064 17 0 2 1117 18 0 3 949 19 0 4 0 20 0 5 0 21 0 6 0 22 0 7 0 23 0 8 0 24 0 9 0 25 0 10 0 26 0 11 0 27 0 12 0 28 0 13 0 29 0 14 0 30 0 15 0 31 0 16 0 P. 8.1-7 R1 OPERATING DATA REPORT Docket No: 50-311 Date: 01/10/94 Completed by: Mark Shedlock Telephone:

339-2122 Operating Status 1. Unit Name Salem No. 2 Notes 2. Reporting Period December 1993 3. Licensed Thermal Power (MWt) 3411 4. Nameplate Rating (Gross MWe) 1170 5. Design Electrical Rating (Net MWe) 1115 6. Maximum Dependable Capacity(Gross MWe) 1149 7. Maximum Dependable Capacity (Net MWe) 1106 8. If Changes Occur in Capacity Ratings (items 3 through 7) since Last Report, Give Reason NA 9. Power Level to Which Restricted, if any (Net MWe) N/A 10. Reasons for Restrictions, if any

11. Hours in Reporting Period 12. No. of Hrs. Rx. was Critical 13. Reactor Reserve Shutdown Hrs. 14. Hours Generator On-Line 15. Unit Reserve Shutdown Hours 16. Gross Thermal Energy Generated (MWH) Gross Elec. Energy Generated (MWH) 18. Net Elec. Eriergy Gen. (MWH) 19. Unit Service Factor 20. Unit Availability Factor 21. Unit Capacity Factor (using MDC Net) 22. Unit Capacity Factor (using DER Net) 23. Unit Forced outage Rate This Month 744 71.85 0 71.85 0 230541. 6 78460 63068 9.7 9.7 7.7 7.6 90.3 Year to Date Cumulative 8760 107113 5513.96 69279.56 0 0 5331.06 66889.52 0 0 17367249.6 162462939.4 5839030 70546518 5541301 67127277 60.9 62.4 60.9 62.4 57.2 56.7 56.7 56.2 20.4 22.7 24. Shutdowns scheduled over next 6 months (type, date and duration of each) NONE 25. If shutdown at end of Report Period, Estimated Date of Startup: January 5, 1994. 8-l-7.R2 I NO. DATE 0053 12-03-93 1 F: Forced S: Scheduled DURATION TYPE 1 (HOURS) REASON 2 F 672.15 A 2 Reason A-Equipment Failure (explain)

B-Maintenance or Test C-Refuel ing D-Requlatory Restriction UNIT SHUTDOWN AND POWER REDUCTIONS REPORT MONTH DECEMBER 1993 METHOD OF SHUTTING DOWN REACTOR 1 3 LICENSE EVENT REPORT # ---------Method: 1-Manual 2-Manual Scram SYSTEM CODE 4 EE E-Operator Training & License Examination F-Administrative 3-Automatic Scram 4-Continuation of Previous Outage 5-Load Reduction 9-0ther G-Operational Error (Explain)

H-Other (Explain) 4 DOCKET NO. UNIT NAME DATE COMPLETED BY TELEPHONE 50-272 Salem #2 01-10-94 Mark Shedlock 339-2122 COMPONENT CAUSE AND CORRECTIVE ACTION CODE 5 TO PREVENT RECURRENCE GENERA OTHER AC INSTRUMENT POWER PROBLEMS Exhibit G -Instructions for Preparation of Data Entry Sheets for Licensee Event Report CLER) File CNUREG-0161) 5 Exhibit 1 -Same Source

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RELATED MAINTEN.E MONTH: -DECEMBER 1993 DOCKETttO:

UNIT NAME: 50-311 SALEM 2 WO NO UNIT 930510124 2 931023099 2 931206134 2 DATE: COMPLETED BY: TELEPHONE:

JANUARY 10, 1994 R. HELLER (609)339-5162 EQUIPMENT IDENTIFICATION VALVE 2CC160 FAILURE DESCRIPTION:

VALVE NEEDS REPACK 24 ACCUMULATOR TANK LEVEL ALARM FAILURE DESCRIPTION:

NO ALARM INDICATION

-INVESTIGATE

& CORRECT 22 STEAM GENERATOR LEVEL INDICATION FAILURE DESCRIPTION:

23 S/G NARROW RANGE LEVEL INDICATION READS 5%> THE REST -INVESTIGATE

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931211129 2 931221135 2 931223059 2 931223098 2 931223146 2 931223147 2 . . 2C DIESEL GENERATOR FAILURE DESCRIPTION:

LEFT SIDE JACKET WATER LEAK -REWORK 2C DIESEL GENERATOR FAILURE DESCRIPTION:

INLET JACKET.WATER PUMP HEATER STARTUP CONTROL SWITCH ARCING -TROUBLESHOOT 2C DIESEL GENERATOR FAILURE DESCRIPTION:

PANEL 2PNL11833 ALARMING, UNABLE TO RESET -REWORK 23 ACCUMULATOR FAILURE DESCRIPTION:

LEVEL CHANNEL DISCREPANCY

-INVESTIGATE 2C DIESEL GENERATOR FAILURE DESCRIPTION:

LOW OIL PRESSURE TRIP ALARM NOT INDICATING

-TROUBLESHOOT 2C DIESEL GENERATOR FAILURE DESCRIPTION:

MECHANICAL OVERSPEED LIMIT SWITCH NOT MAKING UP -INVESTIGATE e SAFETY RELATED MAINTENANCE e DOCKET NO: 50-311 SALEM 2 MONTH: -DECEMBER 1993 UNIT NAME: (Cont'd) WO NO UNIT 931225121 2 931227086 2 931227096 2 931227117 2 931227119 2 931227135 2 931228088 2 931228089 2 931229107 2 DATE: COMPLETED BY: TELEPHONE:

JANUARY 10, 1994 R. HELLER (609)339-5162 EQUIPMENT IDENTIFICATION VALVE 22SW54 FAILURE DESCRIPTION:

VALVE OPERATOR CHATTERS -REPLACE SSPS TRAIN B FAILURE DESCRIPTION:

TRAIN B FAILED SLAVE RELAY TEST -REWORK 24 LOOP DELTA T INDICATION FAILURE DESCRIPTION:

24 LOOP DELTA T INDICATION DRIFTING -REWORK 2SWE76 EXPANSION JOINT FAILURE DESCRIPTION:

FLANGE GASKETS LEAK -REPLACE 2SWE79 EXPANSION JOINT FAILURE DESCRIPTION:

FLANGE GASKETS LEAK -REPLACE 2C DIESEL GENERATOR FAILURE DESCRIPTION:

LEFT SIDE ROCKER ARM CHECK VALVE LEAKS -REPAIR VALVE 22SW76 FAILURE DESCRIPTION:

VALVE OPERATOR CHATTERS -REPLACE 2C DIESEL GENERATOR FAILURE DESCRIPTION:

PRELUBE PUMP MOTOR OUTPUT FLOW CONTROL SWITCH NOT FUNCTIONING

-REWORK OR REPLACE 2R41 SAMPLE PUMP FAILURE DESCRIPTION:

SAMPLE PUMP LOW FLOW -INVESTIGATE

• RELATED MAINTEN,CE MONTH: -DECEMBER 1993 UNIT NAME: 50-311 SALEM 2 (Cont'd) WO NO UNIT 931229128 2 931229151 2 VALVE 2RH2 DATE: COMPLETED BY: TELEPHONE:

JANUARY 10, 1994 R. HELLER (609)339-5162 EQUIPMENT IDENTIFICATION FAILURE DESCRIPTION:

VALVE WILL NOT OPEN -TROUBLESHOOT AND CORRECT VALVE 22BF13 FAILURE DESCRIPTION:

22 S/G INLET MOV NOT STROKING OPEN -TROUBLESHOOT

& REPAIR e

• 10CFR50.59 EVALUATIONS

.. MONTH: -DECEMBER 1993 e DOCKET NO: UNIT NAME: DATE: COMPLETED BY: TELEPHONE:

50-311 SALEM 2 JANUARY 10, 1994 R. HELLER (609)339-5162 The following items were evaluated in accordance with the provisions of the Code of Federal Regulations 10CFR50.59.

The Station Operations Review Committee has reviewed and concurs with these evaluations.

ITEM

SUMMARY

A. Design Change Packages 2EC-3242 Pkg 1 "Fuel Handling Building Ventilation Upgrade" -This DCP entails modifications to the Unit 2 Fuel Handling Area Ventilation System which are summarized as follows: 1.) Replace backdraft dampers (2VHE505 & 2VHE506);

2.) Replace the inlet guide vanes and their operators on the Fuel Handling Area exhaust fans No. 21 & 22. 3.) Remove the existing control loop instrumentation for the Unit 2 Fuel Handling Area supply fan (2VHE24) inlet guide vanes; 4.) Remove the Unit 2 Fuel Handling Area Truck Bay exhaust fan 2VHE23, damper 2VHE504; 5.) Install gravity type pressure relief damper 2VHE868 and fixed louver 2VHE504 in the truck bay areas; 6.) Replace the adjustable motor sheaves and V-belts for the Unit 2 Fuel Handling Area supply fan (2VHE24);

7.) Replace the adjustable motor sheaves and V-belts for the No. 21 & 22 Fuel Handling Area exhaust fans 2VHE20 & 2VHE21; 8.) Replace inlet and discharge flexible connections on the Unit No. 2 Fuel Handling Area supply fan (1VHE24) and the No. 21 & 22 Fuel Handling Area exhaust fans 2VHE20 & 2VHE21; 9.) Install new flow and static pressure test ports on fan inlet and discharge ducts; 10.) Install discharge screens on the supply air duct openings; 11.) Replace Fuel Handling Area differential pressure switches; 12.) The Fuel Handling Area humidity monitoring system will be abandoned in place (This was previously evaluated in Safety Evaluation S-C-M941-MSE-234, Rev. O) and the applicable documentation will be revised under this DCP to reflect this abandonment.

These modifidations will not result in any changes to system operating parameters.

Therefore, this proposal will not reduce the margin of safety as defined in the basis for any Technical Specification. (SORC 93-105)

.. e

• 10CFR50.59 EVALUATIONS MONTH: -DECEMBER 1993 (cont'd) ITEM 2EC-3211 Pkg 1 2EC-3259 Pkg 1 e DOCKET NO: UNIT NAME: DATE: COMPLETED BY: TELEPHONE:

SUMMARY

50-311 SALEM 2 JANUARY 10, 1994 R. HELLER (609)339-5162 "SGFP/Condensate Pump/Feedwater Heaters System Design Pressure Modification" Rev. 4 -The purpose of this DCP is to provide a high pressure trip setpoint for the 21 and 22 Steam Generator Feedwater Pump (SGFP) turbines at 1620 psig. Two new transmitters will be installed on the discharge piping of each f eedwater pump and by modifying the existing trip circuitry, the feed pump will trip (2/2 logic) on a high feed pump discharge pressure.

The system pressure will be monitored by the P-250 computer.

High and Low alarm limits will be installed at 1350 psig and 700 psig to notify the operator when conditions have approached a pump trip pressure or a transmitter failure respectively.

Setpoint corrections of 5000 gpm and 5500 gpm will be made to the 21, 22 and 23 condensate pump recirculation flow control loops to ensure a maximum sustained pressure of approximately 625 psig. There is no reduction in the margin of safety as defined in the basis for any Technical Specification. (SORC 93-107) "Service Water Pump Upgrade, No. 26 Pump" -The 2SWE6 replacement Service Water Pump will be compatible with brackish river water, able to withstand the high silt flows, and designed for a NPSHa at 76 feet river water level. The replacement pump will be designed to operate in parallel with the existing pumps, and will use the existing motor and floor opening. The new pump will be designed to operate over a wider range of flows based on past plant operating experience.

Minor modifications to the Service Water Intake structure are required.

This includes the removal of the Seismic Restraint on Elevation 70 feet. The installation of a vortex suppressor on elevation 70 feet. The and removal of the existing Service Water Pump's line shaft bearing lubrication supply piping. The replacement pump does not require line shaft bearing lubrication.

There is no reduction in the margin of safety as defined in the basis for any Technical Specification. (SORC 93-108) e

• 10CFR50.59 EVALUATIONS

.. e MONTH: -DECEMBER 1993 (cont'd) ITEM 2EC-3201 Pkg 1 DOCKET NO: UNIT NAME: DATE: COMPLETED BY: TELEPHONE:

SUMMARY

50-311 SALEM 2 JANUARY 10, 1994 R. HELLER (609)339-5162 "Circulating Bearing Lube Piping Replacement" -The design change package is summarized as follows: 1.) Replace existing CW pump bearing lube water header with ABCO A-150 fiberglass piping (SPS39). Existing piping material is cement-lined carbon steel; 2.) Replace existing heat tracing with a new Raychem system compatible with the new piping material; 3.) Install valve 2CW54 in accordance with design drawing; 4.) Replace existing 3/4 11 threaded valves 2CW44, 2CW5 and 2CW902 with new flanged globe valves; 5.) Install 8 new supports, one at each of the bearing lube water strainer discharges (to support valves 21CW4 and 22CW4) and one at each of the header; 6.) Modify existing supports along header line to accommodate new support arrangements for the fiberglass pipe, and 7.) Replace existing insulation with 1n fiberglass and stainless steel lagging. The reason for the above listed changes is to increase system durability under erosive/

• corrosive environment.

There is no reduction in the margin of safety as defined in the basis for any -Technical Specification. (SORC 93-108)

SALEM UNIT NO. 2 SALEM GENERATING STATION MONTHLY OPERATING

SUMMARY

-UNIT 2 DECEMBER 1993 The Unit began the period operating at full power and continued to operate at essentially full power until December 3, 1993, when it was shutdown due to the December 2, 1993 failure of the 2C Emergency Diesel Generator (EDG) 3R cylinder liner. The Unit remained offline throughout the remainder of the month while an extensive investigation of the 2C EDG cylinder liner failure was conducted.

The repairs and testing of 2C EDG were completed and the period ended with a Unit heatup in progress.

" . -REFUELING INFORMATION MONTH: -DECEMBER 1993 MONTH DECEMBER 1993

• DOCKET NO: UNIT NAME: DATE: COMPLETED BY: TELEPHONE:

1. Refueling information has changed from last month: YES X NO 50-311 SALEM 2 JANUARY 10, 1994 R. HELLER (609)339-5162

2. Scheduled date for next refueling:

SEPTEMBER 24, 1994 3. Scheduled date for restart following refueling:

NOVEMBER 22, 1994 4. a) Will Technical Specification changes or other license amendments be required?:

YES NO NOT DETERMINED TO DATE b) Has the reload fuel design been reviewed by the Station Operating Review Committee?:

YES NO If no, when is it scheduled?:

OCTOBER 94 5. Scheduled date(s) for submitting proposed licensing action: N/A 6. Important licensing considerations associated with refueling:

7. Number of Fuel Assemblies:

a. Incore 193 b. In Spent Fuel storage

• 492 8. Present licensed spent fuel storage capacity:

1170 Future spent fuel storage capacity:

1170 9. Date of last refueling that can be discharged to the spent fuel pool assuming the present licensed capacity:

March 2003 * -This figure has been corrected.

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