ML20135F696

Monthly Operating Rept for Aug 1985

ML20135F696
Person / Time
Site:	Salem
Issue date:	08/31/1985
From:	Ronafalvy J, Zupko J Public Service Enterprise Group
To:	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE)
References
NUDOCS 8509170360
Download: ML20135F696 (12)

Text

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AVERAGE DAILY UNIT POWER LEVEL Docket No. 50-272 Unit Name Salem # 1 DateSeptember 10,1985 Completed by J. P. Ronafalvy Telephone 609-935-6000 Extension 4455 Month August 1985 Day Average Daily Power Level Day Average-Daily Power Level (MWe-NET) (MWe-NET) 1 1068 17 1068 2 1069 18 1073 3 1065 19 1073 4 1044 20 1090 5 1075 21 1071 6 1077 22 1079 7 1070 23 1079 8 1084 24 1075 9 1085 25 1080 10 _

1064 26 1080' 11 1060 27 1075 12 1084 28 1118 13 1074 29 1046 14 1075 30 1108 15 1078 31 1019 16 1073 P. 8.1-7 R1 850917036085083b72

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c OPERATING DATA REPORT Docket No.50-272 Date September 10, 1985 Telephone 935-6000 Completed by J. P. Ronafalvy Extension 4455 Operating Status

1. Unit Name Salem No. 1 Notes

2. Reporting Deriod August 1985

3. Licensed Thermal Power (met) 3338

4. Nameplate Rating (Gross 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 Restrictions, if any N/A This Month Year to Date Cumulative

11. Hours in Reporting Period 744 5831 71640

12. No. of Hrs. Reactor was Critical 744 5813.6 41637.1

13. Reactor Reserve Shutdown Hrs. 0 0 3088.4

14. Hours Generator On-Line 744 5810.7 39969.3

15. Unit Reserve Shutdown Hours 0 0 0

16. Gross Thermal Energy Generated (MWH) 2490518 19345903 122113900

17. Gross Elec. Energy Generated (MWH) 831840 6572710 40488760

18. Net Elec. Energy Generated (MWH) 798663 6316931 38414913

19. Unit Service Factor 100 99.7 55.8

20. Unit Availability Factor 100 99.7 55.8

21. Unit Capacity Factor (using MDC Net) 99.5 100.4 49.7

22. Unit Capacity Factor (using DER Net) 98.5 99.4 49.2

23. Unit Forced Outage Rate 0 .3 29.8

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

N/A

25. If shutdown at end of Report Period, Estimated Date of Startup:

N/A

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

Forecast Achieved Initial Criticality 9/30/76 12/11/76 Initial Electricity 11/1/76 TY725/76 Commercial Operation 12/20/76 6/30/77 8-1-7.R2 Page of l

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UNIT SHUTDOWN AND POWER REDUCTIONS Docket No.50-272 REPORT MONTH August 1985 Unit Name Salem No.1 Date September 10,1985 '.

Completed by J.P. Ronafalvy Telephone 609-935-6000 Extension 4455 Method of Duration ' Shutting License Cause and Corrective No. Date Type Hours Reason Down Event System Component Action to 1 2 Rea cto r Report Code 4 Code 5 Prevent Recurrence

• There were no outages for the month of August resulting in a load reduction of greater than' 20%.

i 1 2 Reason 3 Method 4 Exhibit G 5 Exhibit 1 i

F: Forced A-Equipment Failure-explain 1-Manual Instructions Salem as i S: Scheduled B-Maintenance or Test 2-Manual Scram. for Prepara- Source C-Refueling 3-Automatic Scram. tion of Data 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) i 1

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MAJOR PLANT MODIFICATIONS DOCKET NO.: 50-272 REPORT MONTH August 1985 UNIT NAME: Salem 1 DATE: September 10, 1985 COMPLETED BY: J. Ronafalvy TELEPHONE: 609/339-4455

• DCR NO. PRINCIPLE SYSTEM SUBJECT lEC-0675 Fuel Handling Cranes Revise limit switch protection arrangement as necessary to comply with intent of No. 2 Unit Outstanding Item No.

047043.

lEC-1591 NPDES Thermal Relocate circ. water inlet Monitoring System and outlet temperature monitors from their present location at the condenser inlet and outlet waterboxes to the circ. water intake structure for measuring inlet ambient river water temperature and to the six outlet pipes for measuring combined plant discharge temperature.

1EC-2025 Fire Protection-Doors Addition of three fire rated doors. Two doors are located in the Aux Building and Mechanical / Electrical Penetration Areas, third door is located in the Service i Water Intake Structure. In addition, door #379 is to be removed. All three doors rated for 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> (Class A) .

1EC-2050A Communication New raceways for upgrading i

telephone ~and data transmission from Service

Building. Conduit must be l provided to house 300-pair 1

cable of telephone twister

! copper cable, lEC-2069 Radiation Monitoring Install field modification kits for waterproofing the R13 radiation monitors.

• Design Change Request l

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MAJOR PLANT MODIFICATIONS DOCKET NO.: 50-272 REPORT MONTH AUGUST 1985 UNIT NAME: Salem 1 DATE: September 10, 1985 COMPLETED BY: J. Ronafalvy TELEPHONE: 609/339-4455

• DC R NO . SAFETY EVALUATION 10 CFR 50.59 lEC-0675 The installation of the new upper limit switch and other hardware in the Fuel Handling Crane will not affect the safe shutdown of the reactor nor will it create any new fire hazard. No changes to the FSAR or the Tech. Specs.

are involved. Implementation of this DCP will comply with NUREG-0612 requirements for upgrading the cranes at operating nuclear power plants. No unreviewed safety or environmental questions are involved.

lEC-15 91 This DCP involves moving the location of the circulating water system temperature monitors and as such does not involve a change to the FSAR or the Tech. Specs. No unreviewed safety or environmental questions ae involved.

1EC-20 25 The new fire doors are not safety related. Their presence will not impact the operation of existing safety related equipment nor will they reduce the margin of safety related equipment as outlined in the Tech. Specs. Since the fire doors are relatively passive and " inert", a failure of the doors will not result in any damage or influence the operation of safety related equipment. The new fire doors will reduce the risk of fire damage to safety related equipment. No unreviewed safety or environmental questions are involved.

1EC-20 50 A This DCP involves the installation of telephone conduit between the Administration Building and the Service Building. No work is being performed in safety related areas of the plant. This DCP does not impinge or interfere with any safety related system. This package does not affect the basis for the Tech. Specs. or the FSAR from an electrical standpoint. No unreviewed safety or environmental questions are involved.

lEC-20 69 This design change enhances the operation of the five R-13 radiation monitors which are not safety related. This modification will not alter, affect or compromise the safety related components and systems in the plant. No unreviewed safety or environmental questions are involved.

• DCR - Design Change Request

PSE&G SALEM GENERATING STATION .

SAFETY RELATED WORK ORDER LOG SALEM UNIT 1 WO NO DEPT UNIT EQUIPMENT IDENTIFICATION 8508180021 SIC 1 DORIC 577/P250 T2609A FAILURE DESCRIPTION: 13 AUX. FEED PUMP TURBINE INBOARD BEARING TEMP.

INDICATION IS FAILED.

CORRECTIVE ACTION: REMOVED FIELD LEADS FROM DORIC AND P-250. PLACED JUMPERS ON APPROPRIATE POINTS P-250 READ 8.0.7 AND DORIC READ 82 DEGREES F. RECONNECTED FIELD LEADS.

8508060572 SIC 1 13 S/G FWR FLO CH 2 FAILURE DESCRIPTION: COMPARATOR TRIPPING OUT OF SPEC., REWORK AS NECESSARY, THEN COMPLETE CHANNEL FUNCTIONAL.

CORRECTIVE ACTION: COMP. 1FC531 #1B OUTPUT OUT OF SPEC FOUND CAPS LEAKING C2 & C3 REG /MED ALSO REGISTOR. INSTALLED DCR lEC0575 R39.

8508060050 SIC 1 1 SW 308 I

FAILURE DESCRIPTION: THE MOORE CONTROLLER FOR THIS VALVE CAUSES THE VALVE TO GO OPEN WHEN PUT IN THE SEAL POSITION.

CORRECTIVE ACTION: REMOVED POSITIONER AND DISCONNECTED AIR SUPPLY AND PROCESS IMPACT LINE TO ISW308. 8/7/85 REINSTALLED POSITIONER. 8/7 /85 VERIFIED CONTROLLER OPERATION.

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SALEM UNIT 1 .

WO NO DEPT UNIT EQUIPMENT IDENTIFICATION 8508030177 SMD 1 14 AF920 FAILURE DESCRIPTION: THE 14AF920 (CHECK) VALVE IS LEAKING THRU, ALLOWING FLOW BACK FROM 14 S/G TO THE AFST.

CORRECTIVE ACTION: REMOVED BONNET, CLEANED INTERNALS, REPLACED BONNET i 8508010036 SIC 1 RX COOL FLO LOOP 12 CH1 FAILURE DESCRIPTION: COMPARATOR IS TRIPPING OUT OF SPEC.

CORRECTIVE ACTION: REPLACED COMPARATOR SINAO-997 WITH SINAO-962.

PERFORMED "AS LEFT" OF PAGE 9, STEPS 8.8.1.1. AND I LLUMINATED . - I&C SAYS THE PROBLEM IS IN THE CONSOLE, NO COMPARATOR IS TRIPPED TO GENERATE THE ALARM.

8507301797 SMD 1 llGB4 FAILURE DESCRIPTION: LEAKING AT VALVE BODY.

CORRECTIVE ACTION: TEMPERARILY REPAIRED VALVE BY FURMANITE. NEW WORK ORDER TO BE WRITTEN FOR PERMANENT REPAIR.

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[ 8507260357 l SOD 1 2" RECIRC HEADER .

FAILURE DESCRIPTION: CRUD BUILDUP IN S.F. PIT DEMINERALIZER RECIRC.

HEADER WHICH IS CAUSING A HIGH RAD AREA AND IS GETTING LARGER. WOULD LIKE 2" HEADER FLUSHED BY UTILIZING SF29 AND SF37 VIA REFUEL. WTR. PURIF PUMP. RECIRC LINE IN QUESTION HAS SF60 AND 61 FLOW GAGE TAPS.

CORRECTIVE ACTION: READINGS BEFORE STARTED 1.2R/HR SLUICED RESINS AND FLUSHED READINGS AFTER .2MR/HR RESTORED LINEUP ,

TO NORMAL.

SALEM UNIT 1 .

WO NO DEPT UNIT EQUIPMENT IDENTIFIC ATION 8505130472 SMD 1 130C19 7 FAILURE DESCRIPTION: THE VALVE HANDWHEEL IS BROKEN.

CORRECTIVE ACTION: REPLACED STRIPPED OUT HANDWHEEL.

0099178737 SMD 1 16 SERVICE WATER PUMP FAILURE DESCRIPTION: THE PUMP PACKING RING IS BLOWN.

CORRECTIVE ACTION: TIGHTENED TUBE TENSION AND REPLACED SEAL RING UNDER LOCK NUT.

0099178079 SIC 1 llWHUT LEVEL INDICATION FAILURE DESCRIPTION: LEVEL INDICATION FOR 11 WHUT IS NOT WORKING PROPERLY.

TANK OVERFLOWED WITH LEVEL INDICATING 82%. NO HIGH LEVEL ALARM WAS RECEIVED.

CORRECTIVE ACTION: CAL. RECEIVER GAUGE AND ALARM HI/LO LIS 1008 CAL.

XMTR lLT 1008 AND SIMULATED INPUT TO TRANSMITTER AND VERIFIED CORRECTED READINGS AND ALARM POINTS ON RECEIVER GAUGE ON PNL 104 AND PNL 107 - ALSO BLEWDOWN INSTRUMENT LINE FROM TRANSMITTER TO #11 WHUT 0099178095 SIC 1 DORIC POINT 205 FAILURE DESCRIPTION: THE DORIC POINT IS FAILED.

CORRECTIVE ACTION: FOUND BROKEN LEAD TO TERMINAL 205 ON DORIC SATELLITE IN UNIT 1 RACK AREA. REPAIRED LEAD AND RECONNECTED TO TERMINAL BOARD. POINT NOW READING ON DORIC SCANNER.

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SALEM UNIT 1 .' I WO NO DEPT UNIT EQUIPMENT IDENTIFICATION

-0099176637 ,

SMD 1 llAF8 FAILURE DESCRIPTION: THIS VALVE LEAKS THRU CAUSING THE AFWST TO OVERFLOW.

1 CORRECTIVE ACTION: OPEN AND INSPECTED VALVE, CLEANED VALVE INTERNALS -

REASSEMBLED W/NEW GASKETS.

0099165533 SIC 1 LOOP 12 CH I RX COOL FLOW .

I FAILURE DESCRIPTION: CH I RX. COOL. FLOW IS INDICATING THREE % HIGHER

THAN OTHER CHANNELS.

CORRECTIVE ACTION: REPLACED TRANSMITTER, BENCH CALIBRATED NEW ,

1 TRANSMITTER AND PERFORMED TIME RESPONSE TEST PROCEDURE 1PD-2.8.006.

l 0099165392 1 SIC 1 ELANT VENT RMS MONITOR

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• FAILURE DESCRIPTION: PLEASE REPAIR "+" L.E.D. ON REMOTE DISPLAY MODULE.

PRESENTLY NOT VISIBLE.

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CORRECTIVE ACTION: REPLACED L.E.D. I.C. FOR "+" INDICATION ON REMOTE l DISPLAY 8/12/85. <

l 0099165121

! SIC 1 POWER RANGE CHAN.

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) FAILURE DESCRIPTION: NEGATIVE RATE TRIP INOPERABLE. FOUND DURING CHANNEL FUNCT.  ;

CORRECTIVE ACTION: FOUND NEG. RATE BISTABLE CARD BAD AND AN UN-LANDED SHIELD WIRE. LANDED WIRE AND REPLACED BISTABLE I' CARD. FINISHED FUNCTIONAL SAT.

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I SALEM GENERATING STATION MONTHLY OPERATING

SUMMARY

- UNIT NO. 1 AUGUST 1985 SALEM NO. 1 The Unit operated at full power for the entire period.

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. o REFUELING INFORMATION DOCK ET NO . : 50-272 COMPLETED BY: J. Ronafalvy UNIT NAME: Salem 1 DATE: September 10, 1985 TELEPHONE: 609/935-6000 EXTENSION: 4455 Month August 1985

1. Refueling information has changed from last month:

YES NO X

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

3. Scheduled date for restart following refueling: May 4,1986

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 X If no, when is it scheduled? January 1986

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

January 1986 if renuired

6. Important licensing considerations associated with refueling:

NONE

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 i

- O PSEG Public Sersice Electnc and Gas Company P.O. Box E Hancocks Bridge, New Jersey 08038 Salem Generating Station 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 I In compliance with Section 6.9, Reporting Requirements for the Salem '

Technical Specifications, 10 copies of the following monthly operating reports for the month of August 1985 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:shh

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Dr. Thomas E. Murley 4

Regional Administrator USNRC

Region I

, 631 Park Avenue t

King of Prussia, PA 19406 Director, Office of Management 4 Information and Program Control U.S. Nuclear Regulatory Commission Washington, DC 20555 i Enclosures

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The Energy People yg ,.y , ,, ,