ML20155E330

Monthly Operating Rept for Mar 1986

ML20155E330
Person / Time
Site:	Salem
Issue date:	03/31/1986
From:	White P, Zupko J Public Service Enterprise Group
To:	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE)
References
NUDOCS 8604170566
Download: ML20155E330 (19)

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, AVERAGE DAILY UNIT POWER LEVEL Docket No. 50-272 Unit Name Salem # 1 Date April 10,1986 Completed by -Pell White Telephone 609-935-6000 j Extension 4455 Month March 1986 Day Average Daily Power Level Day Average Daily Power Level (MWe-NET) .(MWe-NET) 1 1037 17 804 2 1041 18 1008 i

l 3 937 19 954 4 1022 20 978 l 5 1042 21 822 1

6 1038 22 0 7 1012 23 0 8 1035 24 0 9 1041 25 0 10 1046 26 0 11 1033 27 0 12 1053 28 0 13 1045 29 0 14 1045 30 0 15 779 31 0 16 930 l

l P. 8.1-7 R1 8604170566 860331 PDR ADOCK 05000272

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OPERATING DATA REPORT Docket No.50-272 Date April 10, 1986 Telephone 935-6000 Completed by Pell White Extension 4455 Operating Status

1. Unit Name Salem No. 1 Notes

2. Reporting Period March 1986

3. Licensed Thermal Power (MWt) 3338

4. Nameplate Rating (GroFd MWe) 1170

5. Design Electrical Rating (Net MWe) 1090

6. Maximum Dependable Capacity (Gross MWe) 1124

7. Maximum Dependable Capacity (Net MWe) 1079

8. If Changes Occur in Capacity Ratings (items 3 through 7) since Last Report, Give Reason N/A

9. Power Level to Which Restricted, if any (Net MWe) N/A

10. Reasons for Restr ctions, if any N/A This Month Year to Date Cumulative

11. Hours in Reporting Period 744 2160 76729

12. No. of Hrs. Reactor was Critical 502.2 1834.0 46019.4

13. Reactor Reserve Shutdown Hrs. 0.0 0.0 3088.4

14. Hours Generator On-Line 502.0 1763.2 44268

15. Unit Reserve Shutdown Hours 0.0 0.0 0.0

16. Gross Thermal Energy Generated (MWH) 1572262 5651424 136135453

17. Gross Elec. Energy Generated (MWH) 518360 1872860 45168870

18. Net Elec. Energy Generated (MWH) 494697 1790381 42895873

19. Unit Service Factor 67.5 81.6 57.7

20. Unit Availability Factor 67.5 81.6 57.7

21. Unit Capacity Factor (using MDC Net) 61.6 76.8 ~~

51.8

22. Unit Capacity Factor (using DER Net) 61.0 76.0 51.3

23. Unit Forced Outage Rate 0 8.1 28.0

24. Shutdowns scheduled over next 6 months (type, date and duration of each)

N/A

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25. If shutdown at end of Report Period, Estimated Date of Startup 5-2-86

26. Units in Test Status (Prior to Commercial Operation):

Forecast Achieved Initial Criticality 9/30/76 12/11/76 Initial Electricity 11/1/76 12/25/76 i Commercial Operation 12/20/76 6/30/77 8-1-7.R2 Page of

I' NIT SHUTDOWN AND POWER REDUCTIONS Docket No.50-272 REPORT MONTH MARCH 1986 Unit Name Salem No.1 Date April 10,1986 Telephone 609-935-6000 Completed by Pell White Extension 4455 Method of Duration Shutting License Cause and Corrective Hours Reason Down Event System Component Action to No. Date Type Prevent Recurrence 1 2 Reactor Report Code 4 Code 5 D 5 - RC ZZZZZZ Core Tilt 86-278 0303 F 8.9 Restrictions A 5 -

HC HTEXCH Loss of Vacuum /High 86-330 0315 P 0.3 Back Pressure A 5 - HC HTEXCH Loss of Vacuum /High 86-332 0315 F 0.2 Back Pressure 5 HC HTEXCH Loss of Vacuum /High 86-336 0315 F 12.5 A -

Back Pressure 5 HC HTEXCH Conenser Tube Fouling 86-348 0317 F 2.7 B -

5 HC HTEXCH Conenser Tube Fouling 86-350 e'17 F 5.7 B -

0321 S 1.0 C 5 - FC ZZZZZ Core Coastdown Nuclear 86-380 86-382 0321 S 1.0 C 5 -

RC ZZZZZ Core Coastdown Nuclear 0321 C 5 - RC ZZZZZ Core Coastdcwn Nuclear 86-384 S 1.0 86-386 0321 S 242.0 C 1 - RC ZZZZZ Nuclear Normal Refuelina 3 Method 4 Exhibit G 5 Exhibit 1 1 2 Reason Salem as A-Equipment Failure-explain 1-Manual Instructions F: Forced for Prepara- Source 2-Manual Scram.

S: Scheduled B-Maintenance or Test 3-Automati=: Scram, tion of Data C-Refueling D-Regulatory Restriction 4-Continuation of Entry Sheets E-Operator Training & Licensing Exam Previous Outage for Licensee F-Administrative 5-Load Reduction Event Report G-Operational Error-explain 9-Other (LER) File H-Other-explain (NUREG 0161)

MAJOR PLANT MODIFICATIONS DOCKET NO.:. 50-272 REPORT MONTH MARCH 1986 UNIT'NAME:. Salem 1 DATE: April 10, 1986 j COMPLETED BY: J. Ronafalvy TELEPHONE: 609/339-4455

• DC R NO . PRINCIPAL SYSTEM SUBJECT Y

a 1EC-0675 Fuel Handling Crane Revise limit switch protection i

arrangement as necessary to comply with intent of No. 2 Unit outstanding item No. 047043.

lEC-1413 Reactor Coolant Replacement of Reactor Coolant Wide Range RTD's with environmentally qualified i elements.

} lEC-1533 Bldg. & Equip. Drain; .

Change nuclear classification Flood & Sump Pumps of containment sump pumps from Nuclear Class III to Non-Nuclear j Safety.

! 1EC-1565 Chilled Water System Install a 10 psig relief valve CW Expansion Tank at the Chilled Water Expansion Tank. Inspect and repair j Nitrogen pressure reducing valve (ICH-147) by removing the l bonnet.  ;

1EC-1834 RVLIS Perform the-field modification j as per Westinghouse Procedure

No. NSID-EIS-83-16. Scope of j this change is under Section 5 4

of this procedure.which includes-environmental / seismic qualification changes and human j factors modifications.

1EC-1843 Neutron Flux Monit. Install a non-safety'related source range neutron flux monitor at the remote hot shutdown panel.

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• DCR - Design Change Request I

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MAJOR PLANT MODIFICATIONS (continued)

REPORT MONTH MARCH 1986

• DCR NO. PRINCIPLE SYSTEM SUBJECT lEC-1849 Main Steam Install additional steam stop valve hydraulic control bypass valve trouble light on control / console for each of four valves11-14MS167. Recently this condition hindered plant start-up on Unit #1.

LED-0014 Radiation Monitoring Add a new plant vent sampling system with apptopriate readouts and control functions. Three monitors - part iculate, iodine, and gaseous. 1-R41A,B,C.

ISC-0690 11-12-13 Chiller Change shaft sleeve material Cond. Recirc. Pump from (316) stainless steel to monel.

ISC-0948 Waste Gas Install two test connections on the Waste Gas System. Add one test connection between valves lWG6 and lWL99 on the vent header. Add the second test connection on the H.P. header downstream of valves 11WG22 and 12WG27. Locate both test connections in the Waste Gas System Valve Room.

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• DCR - Design Change Request

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FAJOR PLANT MODIFICATIONS DOCKET NO.: 50-272 REPORT MONTH MARCH 1986 UNIT NAME: Salem 1 DATE: April 10, 1986 COMPLETED BY: J. Ronafalvy TELEPHONE: 609/339-4455

• DCR SAFETY EVALUATION 10CFR 50.59 1EC-0675 Installation of the new upper limit switch and other hardware on the Fuel Handling Building Crane will not affect the safe shutdown of the reactor nor will it create a new fire hazard. This design change does not involve changes to the FSAR or the Technical Specifications. This design change complies with NUREG 0612 requirements for upgrading cranes at operating nuclear power plants. No plant process or discharge is affected by this design change. No unreviewed safety or environmental questions are involved.

1EC-1413 This design change involved a direct replacement of existing equipment. The system functions remain unchanged. No plant process or discharge is affected by this design change. No unreviewed safety or environmental questions are involved.

1EC-1533 The Containment Sump Pumps are not part of a safety related system and do not affect the safe shutdown of the plant. They are not required to mitigate consequences of an accident. No plant process or discharge is affected by this design change. No unreviewed safety or environmental questions are involved.

1EC-1565 The changes implemented via this design change do not jeopardize the pressure retaining boundary nor impact the operation of the basic design criteria of the Chilled Water System. The Chilled Water System is a closed loop system and therefore no

, environmental impact with this design change is involved. No plant process or discharge is affected by this design change. No unreviewed safety or environmental questions are involved.

• Design Change Request

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UNIT l' MAJOR PLANT MODIFICATIONS (continued)

REPORT MONTH -- MARCH 1986  ;

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• DCR SAFETY EVALUATION 10CFR 50.59 ,

-1EC-1834 All potential realistic failure modes have been considered but are not applicable with this design change. This change will make the RVLIS system-fully operable. No plant process or discharge is affected by this design change. No unreviewed safety or environmental questions are involved.

4 1EC-1843 All potential, realistic failure modes have been

considered. The monitor is non-safety related, however, a safety related' power source provides power for the non-safety related neutron flux monitoring system. Electronic isolation of the 7 j distribution panel is provided by the panel feeder breaker and the NIS source range monitor panel.

The installation of the source range neutron flux monitor instrument at the remote shutdown panel represents an enhancement of the capability of the l station to safely shut down the plant in the event of a fire emergency. No plant process or dischage j is affected by this design change. No unreviewed i safety or environmental questions are involved.

l 1EC-1849 This design change does not affect the intended function of the Main Steam System. No plant

process or discharge is affected by this design i change. No unreviewed safety or environmental questions are involved.

1ED-0014 The function of plant vent radiation monitoring is not changed by this design change. This change improves the monitoring capability by deleting l

f shared monitors. This change does not alter the production or quantity of radioactive materials.

No plant process or discharge is affected by this a

design change. No'unreviewed safety or j environmental questions'are involved.

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• Design Change Request l

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UNIT 1 MAJOR PLANT MODIFICATIONS (continued)

REPORT MONTH - MARCH 1986

• DCR SAFETY EVALUATION 10CPR 50.59 ISC-0690 The replacement sleeves are made of upgraded materials for the Chiller Condenser Water Recirculation Pumps. The change in sleeve material does not affect any previously performed safety analysis nor does it create any new safety hazards. The Tech. Spec. basis is not affected.

The new sleeve will be less subject to corrosion, pitting and wearing out as are the present i sleeves. No plant process or discharge is i affected by this design change. No unreviewed safety or environmen^ul questions are involved.

1SC-0948 The addition of two test connections to the Waste Gas System will not impact the safe operation of l the plant. The connections are to be used only

! for system testing and are to be blind flanged

! during system operation. Each test line will be

! normally isolated with a valve and a blind flange.

No plant process or discharge is affectad by this design change. No unreviewed safety or environmental questions are involved.

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I'esign Change Request i

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• PSE&G SALEM GENERATING STATION ,

SAFETY RELATED WORK ORDER LOG l SALEM UNIT 1 WO NO UNIT EQUIPMENT IDENTIFICATION 8603040222 1 1200A GE 4KV CIRCUIT l BREAKER ,

l FAILURE DESCRIPTION: BREAKER FAILED TO CLOSE IN THE CUBICLE AND AT THE TEST STATION. DR SMD-IE 86-059 HAS BEEN WRITTEN ,

AGAINST THIS BREAKER. ,

REPLACED MICRO Si', PERFORMED M3J, ALL SAT. IN-CORRECTIVE ACTION:

STALLED IN 1H6D 10SITION.

0099168316 1 #12 BAT FAILURE DESCRIPTION: SENSOR FOUND OUT OF CAL DURING A SENSOR CALIBRATION PROCEDURE.

CORRECTIVE ACTION: REPLACE OSCILLATOR IN TRANSMITTER; CALIBRATED AND RETURNED TO SERVICE. CALIBRATED AS PER IIC-2.9.001.

0099168413 1 VCT PRESSURE FAILURE DESCRIPTION: SENSOR FOUND OUT OF CALIBRATION DURING A SENSOR CAL PROCEDURE.

CORRECTIVE ACTION: CALIBRATED AS PER IIC-2.9.024.

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SALEM UNIT 1 WO NO UNIT EQUIPMENT IDENTIFICATION 0099168413 1 VCT PRESS FAILURE DESCRIPTION: SENSOR FOUND OUT OF CALIBRATION DURING A SENSOR CALIBRATION PROCEDURE.

CORRECTIVE ACTION: CALIBRATED AS PER IIC-2.9.024 0099180090 1 STRAINER FAILURE DESCRIPTION: STRAINER HAS A BROKEN SIIEAR KEY.

CORRECTIVE ACTION: REPLACED STRAINERS-REPLACED SHEAR KEY AND i

REPLACED BARREL DISTRIBUTORS.

'0099180561 1 11SW223 FAILURE DESCRIPTION: 11 FAN COIL UNIT FLOW CONTROL VALVE HAS A~ SEVERE SW LEAK WHERE l

VALVE BODY IS BOLTED TO PIPING.

BOLTS ON FLANGE WERE TIGHT.

l PROCEDURE.

CORRECTIVE ACTION: REPLACED BOTTOM GASKET ON 11SW223.

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SALEM UNIT 1 .

NO NO UNIT EQUIPMENT IDENTIFICATION 8504110541 1 FLANGE ORIFICE /11SJ37&38 FAILURE DESCRIPTION: FL,mGE IS HEAVILY CORRODED WITH CRYSTALIZED BORIC ACID AND IS LEAKING.

CORRECTIVE ACTION: REPLACED GASKETS.

8510221197 1 12MS10 CONTROL VALVE FAILURE DESCRIPTION: REPACK WITH CHESTERTON PACKING ALSO VALVE LEAKS THRU.

CORRECTIVE ACTION: DISASSEMBLED, INSPECTED, CLEANED, REPLACED PISTON RINGS, REPLACED GASKET, BLUE CHECKED, REASSEMBLED &

REPACKED WITH CHESTERTON PACKING.

8511010106 1 LOW TURB. LOAD FAILURE DESCRIPTION: RECEIVED " LOW LOAD TURB. TRIP REQUIRED" ALARM ON THE. CONTROL ROOM BEZEL. THERE IS NO SIGNAL THAT SHOULD GIVE US THAT ALARM.

WIRE IN TP-14-1 2-2-U LIFTED LANDED 2-2-U. RE-CORRECTIVE ACTION:

CEIVED A GROUND.ON 1-A-125V BUS, LIFTED LEAD 2-2-U AS PER SS INSTRUCTIONS.

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SALEM UNIT 1 .

WO NO UNIT EQUIPMENT IDENTIFICATION 8512260181 1 #12 WGC RECIRC VALVE FAILURE DESCRIPTION: 12WG22 ON #12 WASTE GAS COMPRESSOR IS NOT CONTROLLING VALVE: STAYS FAILED OPEN AND COMPRESSOR TRIPS OUT ON FIVE MINUTE TIMER FOR DISCHARGE PRESSURE BEING LESS THAN 25 PSIG.

CORRECTIVE ACTION: FOUND FLAPPER / NOZZLE IN CONTROLLER BADLY .

PITTED AND WORN. REPLACED AND REALIGNED CONTROLLER. FUNCTIONALLY CHECKED CONTROLLER /

VALVE ACTION BY VARYING SETPOINT.

8602130511 1 12 ACCUM LEVEL CHANNEL B FAILURE DESCRIPTION: THE HI/LO LEVEL ALARM IS ILLUMINATED, ALTHOUGH THE ACTUAL LEVEL IS SATISFACTORY.

CORRECTIVE. ACTION: CHECKED TRANSMITTER VOLiAGE FOR CAPABILITY WITH INDICATION.

8602220235 1 11A & 11B STARTING AIR COMPRESSOR FAILURE DESCRIPTION: THE AIR COMPRESSOR DOES NOT START IN THE AUTO MODE.

CORRECTIVE ACTION: REPLACED PD 6476.

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%O NO UNIT EQUIPMENT IDENTIFICATION 8602261063

! 1 #1SW OVERPRESSURE PROTECTION l

FAILURE DESCRIPTION: VALVE DID NOT OPEN WITH FOUR SW PUMPS IN SERVICE AND HEADER PRESSURE AT 150#.

CORRECTIVE ACTION: VERIFIED OPERATION OF VALVE & POSITIONER VERIFIED CONTROLLER IS OPERATING CONNECTLY .

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! FOUND SETPOINT AT 144 PSI AND RESET AT 135 PSI. CALIBRATED TRANSMITTER.

8602261071 1 JACKET WATER HI TEMP FAILURE DESCRIPTION: WHILE RUNNING DIESEL RECIEVED THE JACKET WATER HIGH TEMPERATURE ALARM. SET POINT FOR ALARM IS 175 DEG.F, THE ACTUAL TEMPERATURE AT THAT TIME WAS 165 DEG.F.

CORRECTIVE ACTION: RECALIBRATED ALL OF THE ABOVE TEMP DEVICES.

8603031193 1 15 SW PUMP STRAINER FAILURE DESCRIPTION: THE 15 SERVICE WATER PUl*P STRAINER HAS A 45 LB DIFF AND THE MOTOR SMELLS LIKE IT IS BURNT UP.

REPLACED TRANSFORMER IN CONTROL CIRCUIT. DIFF AT 6 CORRECTIVE ACTION:

STAINER SHUT OFF IN AUTO AT ABOUT 4 PSI DIFF.

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SALEM UNIT 1 t

i WO NO UNIT EQUIPMENT IDENTIFICATION 8603100233 j 1 ROD POSITION IND.

FAILURE DESCRIPTION: PLEASE CHECK THE CAL ON THE ROD POSITION IND..

SA-I&C 490 WAS FOUND OUT OF CAL ON.THE A.C. RANGE.

1 CORRECTIVE ACTION: CALIBRATED SIGNAL CONDITION MODULE AND

' POSITION INDICATOR. FOUND INSPEC. e

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,8603100241 1 ROD POSITION IND. ,

FAILURE DESCRIPTION: PLEASE-CHECK THE CAL ON THE ROD POSITION INDICATION SA-I&C 490 WAS OUT OF CAL ON THE AC RANGE.

1 CORRECTIVE ACTION: CALIBRATED SIGNAL CONDITION MODULE AND POSITION INDICATOR. .

-8603100373 1 1R13E' MONITOR FAILURE DESCRIPTION: 1R13E OBSERVED FAILED.

CORRECTIVE ACTION: FOUND CONDENSATE MOSITURE ON THE DETECTOR AND PREAMP. CLEANED ALL COMPONENTS AND REMOVED.HV ARCH ON PREAMP CONNECTOR BASE.

RETURNED TO SERVICE.

I 8603120188 1 # 1 UNIT POWER RANGE FAILURE DESCRIPTION: TWO OUT OF SPEC. READINGS FOUND WHILE DOING THE CHANNEL CAL. CHECK '(IPD16.3007)

THE OUT OF SPECS. WERE 1) NR41' OUT BY 2% AT THE BOTTOM. 2 LOWER FLUX OUT IN-THE MIDDLE BY .012 VDC..

CORRECTIVE' ACTION: MADE ADJUSTMENTS AND TOOK AS.LEFT DATA.

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SALEM UNIT 1. .

[O NO UNIT EQUIPMENT IDENTIFICATION 6603130124 1 11CV160 CONTROL VALVE FAILURE DESCRIPTION: THE CAL ON THE ROD POSITION INDICATION SA-I&C 490 WAS OUT OF CAL ON THE AC RANGE.

CORRECTIVE ACTION: CALIBRATED SIGNAL CONDITION MODULE AND POSITION INDICATOR.

8603170134 1 #1 UNIT SPARE RECORDER FAILURE DESCRIPTION: #1 UNIT SPARE RMS RECORDER FOUND IN RACK #75 DOES'NOT APPEAR TO BE FUNCTIONING CORRECTLY.

CORRECTIVE ACTION: PRINT WHEEL MISSING, FOUND WHEEL MISSING SCREW, REPLACED AND RETURNED TO SERVICE.

8603180032 1 RMS FAILURE DESCRIPTION: LOCAL RMS R-41B GOOD READING, OPERABLE.

CONTROL ROOM MONITOR FAILED.

CORRECTIVE ACTION: CLEARED RAMS RELOADED SETPTS. VERIFIED TRAIN A&B TRIPS & VLV CLOSURE.

8603200548 1 CONT DIFF PRESS INSTR FAILURE DESCRIPTION: METER FOR CONT DIFF PRESS IS HANGING UP AT A SLIGHT POSITIVE PRESSURE. DOES NOT REDUCE WHEN PERFORMING PRESSURE RELIEF. SUSPECT TRANSMITTER PROBLEM THIS INDICATION IS NECESSARY FOR UPCOMING OUTAGE PURGES.

CORRECTIVE ACTION: FOUND TRANSMITTER OUTPUT SLIGHTLY HIGH FOR ACTUATOR CONTAINMENT BAROMETRIC PRESS.

SALEM UNIT 1 ..

WO NO UNIT- EQUIPMENT' IDENTIFICATION 8603230072 1 ISA118 FAILED LRT FAILURE-DESCRIPTION: VALVE FAILED LEAK RATE TEST.

CORRECTIVE ACTION: DISASSEMBLED & CLEANED VALVE, BLUE CHECK 100% ,.

REASSEMBLED VALVE & REPACKED WITH JOHN' CRANE 187-I PACKING (7 RINGS).

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SALEM GENERATING STATION MONTHLY OPERATING

SUMMARY

- UNIT NO. 1 MARCH 1986 SALEM NO. 1 The Unit began the period operating at 97% power. Between 3/15/86 and 3/17/86, river grasses and debris caused a series of' circulating water problems. Load reductions were performed as necessary to maintain condenser vacuum. On 3 /22/86 at 2158 hours0.025 days <br />0.599 hours <br />0.00357 weeks <br />8.21119e-4 months <br />, the Unit was removed from service'and commenced the sixth refueling cutage. Major work to be done this outage includes refueling, leak rate test of the Type "C" Containment Isolation Valves, 11E, 12E, and 13W MSR HP tube bundle replacement, valve replacements, valve repackings (as required),.

upgrade of the connectors on the Control Rod Drive mechanisms, and other miscellaneous maintenance and inspection work. The Unit remained in Mode V (Cold Shutdown), until 0715 hours0.00828 days <br />0.199 hours <br />0.00118 weeks <br />2.720575e-4 months <br />, on 3/28/86, when the reactor vessel head studs were detensioned and Mode VI (Refueling), was entered. The reactor vessel head was lifted on 3/30/86. As of this report, the Unit remains in Mode VI with outage work continuing and on schedule.

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REFUELING INFORMATION DOCKET NO.: 50-272 COMPLETED BY: J. Ronafalvy UNIT NAME: Salem 1 DATE: April 10, 1986 TELEPHONE: 609/935-6000 EXTENSION: 4455 Month March 1986

1. Refueling information has changed from last month:

YES NO X

2. Scheduled date for next refueling: March 22, 1986

3. Scheduled date for restart following refueling: May 20, 1986

4. A) Will Technical Specification changes or other license amendments be required?

YES NO X B) Has the reload fuel design been reviewed by the Station Operating Review Canmittee?

YES X NO If no, when is it scheduled?

5. Scheduled date(s) for submitting proposed licensing action':

N/A

6. Important licensing considerations associated with refueling:

NONE l

7. Number of Fuel Assemblies:

A) Incore 193 B) In Spent Fuel Storage 296

8. Present licensed spent fuel storage capacity: 1170 Future spent fuel storage capacity: 1170-

9. Date of last refueling that. can be discharged ,

to spent fuel pool assuming the present licensed capacity: September 2001 8-1-7.R4 l

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O PSEG Public Service Electric and Gas Company P.O. Box E Hancocks Bridge, New Jersey 08038 Salem Generating Station April 10, 1986 t

f Director, Office of Inspection and Enforcement U.S. Nuclear Regulatory Commission Washington, DC 20555

Dear Sir:

MONTHLY OPERATING REPORT SALEM NO. 1 DOCKET NO. 50-272 IncompliancewithSection6.9,ReportingRequirementsfo'[theSalem-Technical Specifications, 10 copies of. the following monthly operating reports for the month of March 1986 are ~ being sent to you.

Average Daily Unit Power Level Operating Data Report Unit Shutdowns and Power Reductions Major Plant Modification Safety Related Work Orders Operating Summary Refueling Information Sincerely yours, J. M. Zupko, Jr. .

, General Manager - Salem Operations JR:kcb cc: Dr. Thomas E. Murley Regional Administrator USNRC Region I 631 Park Avenue King of Prussia, PA 19406 Director, Office of Management Information and Program Control U.S. Nuclear Fegulatory Commission Washington, DC 20555 Enclosurer E-1-7.P4- fj' I

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. The Energy People

' 95-2189 (11 M) 12-84

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