ML20211B971

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Monthly Operating Rept for Sept 1986
ML20211B971
Person / Time
Site: Salem PSEG icon.png
Issue date: 09/30/1986
From: White P, Zupko J
Public Service Enterprise Group
To:
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE)
References
NUDOCS 8610210239
Download: ML20211B971 (15)
v • d • e


Text

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AVERAGE DAILY UNIT POWER LEVEL Docket No. 50-272 Unit Name Salem # 1

. Date- October 10,1986 Completed by Pell White Telephone 609-935-6000 Extension 4451 Month September 1986 Day Average Daily Power Level Day Average Daily Power Level (MWe-NET) (MWe-NET) 1- 1104 17 0 2 897 18 0 3 867 19 0 4 833 20 0 5 875 21 0 1

6 889 22 0

~7 884 23 0 8 879 24 306 9 879 25 889 10 900 26 882 11 899 27 867 12 899 28 866

13 882 29 877 14 891 30 875 l

15 903 31 l 16 740 1

P. 8.1-7 R1 i

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8610210239 DR 860930 ADOCK 05000272 PDR 1

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OPERATINGDAhAREPORT-Docket No.50-272 Date October 10,1986

. Telephone 935-6000 Completed by Pell White Extension 4451 Operating Status

1. Unit Name Salem No. 1 Notes
2. ' Reporting Period September 1986
3. Licensed Thermal Power (MWt) 3411
4. Nameplate Rating (Gross MWe) 1170
5. Design Electrical Rating (Net MWe) IITY 6.- Maximum Dependable Capacity (Gross MWe)1149
7. Maximum ~ Dependable Capacity (Net MWe) 1106 l
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) 85%
10. Reasons for Restrictions, if any Due to power distribution on station power transformers This Month Year to Date Cumulative
11. Hours in Reporting Period 720 6551 81120
12. No. of. Hrs. Reactor was Critical 546.4 4888.2 49073.6
13. Reactor Reserve Shutdown Hrs. 0 0 0
14. Hours Generator On-Line 539 4714.8 47219.6
15. Unit Reserve Shutdown Hours 0 0 0
16. Gross Thermal Energy Generated (MWH) 1529129 14713558- 145197587
17. Gross Elec. Energy Generated

. (MWH) 498930 4866410 48162420

18. Net Elec. Energy Generated (MWH) 471116 4632833 45738325
19. Unit Service Factor 74.8 72.0- 58.2
20. Unit Availability Factor 74.8 72.0 58.2-
21. Unit Capacity Factor (using MDC Net) 59.2 '63.9 51.0
22. Unit Capacity Factor (using DER Net) 58.7 63.4 50.6 23.' Unit Forced Outage Rate 20.1 10.0- 27.4
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 12/25/76

' Commercial Operation 12/20/76 6/30/77 8-1-7.R2

UNIT SHUTDOWN AND POWER REDUCTIONS Docket No.50-272 -

REPORT MONTH SEPTEMBER 1986 Unit Name salem No.1 I Date October 10,1986 .

I Completed by Pell White Telephone 609-935-6000 .

Extension 4451 I Method of I Duration Shutting License Cause and Corrective No. Date Type Hours Reason Down Event System Component .

Action to 1 2 Reactor Report Code 4 Code 5 Prevent Recurrence

! Nuc. Reg. Proceedings 1 666 0902 F 4.9 D 5 ----

EG TRANSF and Hearings i Nuc. Reg. Proceedings 1 668 0902 F 6.7 D 5 ----

EG TRANSF and Hearings Nuc. Reg. Proceedings l! 670 0902 P 15.0 D 5 ----

EG TRANSF and Hearings ,

Nuc. Reg. Proceedings

] EG TRANSF and Hearings

672 0903 F 71.2 D 5 ----

i Nuc. Reg. Proceedings 682 0906 F 70.2 D 5 ----

EG TRANSF and Hearings j Nuc. Reg. Proceedings 684 0909 _F 182.2 D 5 ----

EG TRANSF and Hearings l Steam Extraction l 698 0916 F 181 A 1 ----

HB PIPEXX Piping Station Service Jl Transformer station 700 0924 F 113.8 B 5 ----

EG TRANSF power auxiliary

!j Station Service Transformer station i 702 0929 F 44.0 B 5 ----

EG TRANSF power auxiliary 1

1 2. Reason 3 Method 4 Exhibit G 5 Exhibit 1 F: Forced A-Equipment Failure-expl.ain 1-Manual Instructions Salem as

, S: Scheduled B-Maintenance or Test 2-Manual Scram. for Prepara- Source l

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 II

MAJOR PLANT MODIFICATIONS DOCKET NO.: 50-272 REPORT MONTH SEPTEMBER 1986 UNIT NAME: Salem 1 DATE: October 10, 1986 COMPLETED BY: L. Miller TELEPHONE: 609/339-4497

1SC-1268 Hydrogen Recombiners' Install ladder and platform in Unit No. 1 Containment to gain access to 11 and 12 Hydrogen Monitor System sensor assembly to perform maintenance.

ISC-1579 Main Steam Remove the lever #17, the Safety Valve forked lever #22 and the spindle nut #12 on all (20) safety valves. Above items are on Crosby print #G-52950 which is attached. Item #25 to be installed to protect spindle rod.

  • DCR - Design Change Request

a

  • l MAJOR PLANT MODIFICATIONS DOCKET NO.: 50-272 REPORT MONTH SEPTEMBER 1986 UNIT NAME: Salem 1 DATE: October 10, 1986 COMPLETED BY: L. Miller TELEPHONE: 609/339-4497
  • DCR SAFETY EVALUATION 10 CFR 50.59 1EC-1676A This design change enhanc'se plant safety by reducing the closing response times of the MS-7 and MS-8 valves. The 5.0 second response time provides a conservative limit relative to the accident analysis of the UFSAR. The modification does not alter any process or discharge and does not affect the existing plant impact. No unreviewed safety or. environmental questions are involved.

1SC-1268 The telescoping ladders and platforms conform to ANSI standards. Seismic restraints are provided to negate the effects that a seismic event would have on the platforms while they are in the stored position. The modification does not change any plant process or discharge and does not affect the existing plant impact. No unreviewed safety or environmental questions are involved.

ISC-1579 The intended operation of the valves and the function of the valves is in no way altered. The component removal does not result in a violation of Section III since the pressure setpoints will not be affected by the removal. The lifting lever requirement for safety valves has been deleted from ASME Section III since 1977. Due to the cleaner environment of the nuclear power plant over that of fossil plants, oxidation in the nozzle / disk area is precluded. Thus the manual lifting levers are unnecessary. This modification neither affects the seismic integrity of the valves or increases their likelihood of failure.

There is no impact on any Technical Specification basis or safety analysis. The modification does not change any plant process or discharge and does not affect the existing plant impact. No unreviewed safety or environmental questions are involved.

  • Design Change Request

PSE&G SALEM GENERATING STATION -

SAFETY RELATED WORK ORDER LOG -

SALEM UNIT 1 WO NO UNIT EQUIPMENT IDENTIFICATION 8605080850 1 GE 4KV BREAKER FAILURE DESCRIPTION: VISUALLY INSPECT AND TIME 4KV MAGNABLAST CIRCUIT BREAKER.

CORRECTIVE ACTION: 5YEAROVERHAULBYG.h.POPI-123227. SERIAL 0224A6261-018. INSTALLED 22BSD 22 SPT INFEED 2B 4KV B.

8608210479 1 4KV-1200A BREAKER FAILURE DESCRIPTION: TROUBLESHOOT G.E. MAG BLAST 4KV-1200A BREAKER SERIAL #0224A6268-002 IAW DR SMD-IE-86-257.

CORRECTIVE ACTION: REPLACED PROP SPRINGS. PERFORMED PROCEDURES M3D AND M3J.

8608290014 1 BATTERY FAILURE DESCRIPTION: WHILE PERFORMING M10 SST 009-1 ON #1 DIESEL FIRE PUMP THE BATTERY BLEW UP. PLEASE REPLACE THE BATTERY BANK AND INVESTIGATE CAUSE.

CORRECTIVE ACTION: REPLACED BATTERY BANK.4 BATTERIES. BAD CELL HAD INTERNAL FAILURE.

] SALEM UNIT 1 .

WO NO UNIT EQUIPMENT IDENTIFICATION 0099170213 1 11 CFCU SW INLET FAILURE DESCRIPTION: IT APPEARS THAT THE VANE HAS BROKEN LOOSE FROM THE VANE ARM. WHEN SCORE ON VANE ARM INDICATES CLOSED THERE IS 400 GPM; WHEN INDICATING OPEN THERE IS ZERO FLOW.

I CORRECTIVE ACTION: CHECKED VALVE. REPLACED LINER, SHAFT PINS, PUT i VALVE BACK IN PIPING.

0099182025 1 ICU55 CHG CONTROL FAILURE DESCRIPTION: PLEASE REMOVE THE MINIMUM STOP ON CV55 TO ALLOW BETTER CONTROL AT REDUCED RCS PRESS.

j CORRECTIVE ACTION: ADJUSTED ICU55 STEM FOR MIN FLOW OF 30 GPM AS PER 4 OPERATIONS. ADJUSTED 1CV55 STEM FOR MIN FLOW OF j 7 GPM.

i j 0099182319 l OHA FAILURE DESCRIPTION: ALARM WAS NOT RECEIVED FOR "14 RCP BRG COOLING

WATER FLOW LOW" AFTER CHARGING WAS ISOLATED. PLEASE l INVESTIGATE AND REPAIR.

I CORRECTIVE ACTION: FOUND ALAPM SWITCH STICKING, FIXED SAME.

PERFORMED CAL ON IFIC-622 VERIFIED OHA C/29.

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SALEM UNIT 1 .

WO NO UNIT EQUIPMENT IDENTIFICATION 8512180781 1 RX TRIP BREAKER FAILURE DESCRIPTION: PERFORM CONTROLS VERIFICATION ON RX TRIP BREAKER 1ASTR-B IN ACCORDANCE WITH TEST PACKAGE FOR 1EC-1365. REFER TO PROCEDURE lIC-18.1.011.

CORRECTIVE ACTION: CONNECTED LEADS FOR SPDS 1ASTR B TO TB518-1,2.

ALSO CONNECTED GROUND WIRE TB-518-3 TO CHASSIS GROUND. VERIFIED OPERATION AS PER IO 400026.

8604021124 1 SFP SKIMMER RAD.

MONITOR FAILURE DESCRIPTION: INVESTIGATE IRREGULAR READINGS FROM U/l SPENT FUEL SKIMMER FILTER RAD. MONITOR. HP SURVEYS INDICATE READINGS CONSIDERABLY LESS THAN THAT ON MONITOR. SEE ATTACHED WORK ORDER COPY.

CORRECTIVE ACTION: FOUND METER READING LOW. REPLACED WITH NEW METER AND MADE LOOP CHECK ON NEW METER AND DRAWER.

8606160075 1 4KV CKT BREAKER VALVE FAILURE DESCRIPTION: TROUBLESHOOT AND REPAIR G.E. 4KV CKT BREAKER NO.

0224A6260-006. THIS BREAKER FAILED TO CLOSE UPON RECEIVING A START SIGNAL FOR 12 AUX FEED PUMP.

FOUND ANTI-PUMP RELAY HUNG UP. BREAKER HAD 5 YEAR OVERHAUL ON 3/86.

CORRECTIVE ACTION: BREAKER WAS RETURNED TO G.E. FOR REPAIR IAW DR SMD-IE-86-187. BREAKER RETESTED UNDER WORK ORDER 86-08-21-053-3.

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SALEM UNIT 1 ,

WO NO UNIT EQUIPMENT IDENTIFICATION 8607031988 1 RMS SPENT FUEL FILTER FAILURE DESCRIPTION: THE POWER SUPPLY FOR 1R28 APPEARS TO HAVE BURNED UP AND THE FUSES ARE BLOWN. PLEASE INVESTIGATE AND REPAIR.

CORRECTIVE ACTION: REPLACED TRANSFORMER AND TRANSISTOR Q2, REPAIRED BROKEN WIRE AT FIELD CONNECTOR. CALIBRATED CHANNEL AND DETECTOR.

8607240145 1 RX TRIP BREAKER 02YN201-1 FAILURE DESCRIPTION: REACTOR TRIP BREAKER 02YN201-1 / PERFORM SEMI-ANNUAL INSPECTION. NOTE DURING REFUELING PERIODS PERFORM IN CONJUNCTION WITH IO 252135 AND IO 201908.

CORRECTIVE ACTION: PERFORMED SEMI-ANNUAL INSPECTION IAW M30-2 ON THIS REACTOR TRIP BREAKER. SER #02YN201-1.

8607241613 1 S/G 14 SNUBBER (12A)

FAILURE DESCRIPTION: HYDRAULIC SNUBBER SER #12A, LOCATED IN 14 S/G SE POSITION HAS A LEAK ON THE 90 DEGREE FITTING GOING INTO THE VALVE BLOCK ALSO RESERVOIR IS LOW.

TIGHTEN LEAKING FITTING AND FILL RESERVOIR.

CORRECTIVE ACTION: TIGHTENED FITTING AND REPLACED OIL.

SALEM UNIT 1 ,

WO NO UNIT EQUIPMENT IDENTIFICATION 8608012022 1 RWST LOCAL LEVEL INDICATION FAILURE DESCRIPTION: LOCAL INDICATION READS 42.5' CONTROL BEZEL CHANNEL D& B ARE READING 41.9' IWH OHA D-35 IN SOLID.

PLEASE INVESTIGATE AND REPAIR.

CORRECTIVE ACTION: CALIBRATED LOCAL INDICATOR AND ALARM SWITCHES.

RETURNED TO SERVICE READING 41' COMPARED TO BEZEL CHANNELS B & D READING 41'.

8608201003 1 MASTER PRESS. CONTROL FAILURE DESCRIPTION: THE RCS PRESSURE MASTER CONTROLLER WAS INDICATING 85% SPRAY DEMAND (68% ON THE MASTER DEMAND) BEFORE THE ACTUAL SPRAY VALVE DEMAND MOVED FROM THE 0%

POSITION. ACTUAL RCS PRESSURE WAS AT 2262#. PLEASE INVESTIGATE AND REPAIR.

CORRECTIVE ACTION: REMOVED CONTROLLER SN E0123 FROM 1PC-455F INSTALLED CONTROLLER FROM IPC-556. REMOVED MAN / AUTO STATION ON SN 102 FRM IHC 455A INSTALLED SN 20141 IN lHC 455B AND SN EO128 IN IPC-455G. PERFORMED CAL ON IPC-455F.

8609040046 1 RCP THERM. BARR.

DISCHARGE FAILURE DESCRIPTION: THE HIGH FLOW ALARM (175 GPM) IS COMING IN AND OUT WITH NO OTHER INDICATION OF A HIGH FLOW CONDITION.

THIS ALARM SHUTS THE 1CC131 WHICH ISOLATES CC FROM THE RCP'S. INVESTIGATE AND REPAIR.

CORRECTIVE ACTION: CHECKED CAL ON IF12625 FOUND IN SPEC. ADJUSTED CLOSER TO REQUIRED.

.- _____. _- . . - _ - . . =_ .- _ - _ - _ -. - . . ~ _ . . _ _ _

SALEM UNIT 1 ,

WO NO UNIT EQUIPMENT IDENTIFICATION l 8609050238

} 1 IN36 NIS 7 DAY FUNCTION FAILURE DESCRIPTION: NUCLEAR INSTRUMENTATION SYSTEM / PERFORM CHANNEL I

FUNCTIONAL TEST OF INTERMEDIATE RANGE CHANNEL N-36 i MUST BE PERFORMED WITHIN SEVEN DAYS OF STARTUP.

l CORRECTIVE ACTION: FUNCTION SATISFACTORY.

j j 8609050661

! 1 BEZEL ALARM VCT l HI/LO PRE l

{

FAILURE DESCRIPTION: THE COMPARATOR IS TRIPPED AND THE FUSE IS BLOWN FOR THIS BEZEL ALARM. PLEASE INVESTIGATE AND REPAIR.

CORRECTIVE ACTION: FOUND CONNECTOR ON IPC-139A/B LOOSE. REPLACED CONNECTOR AND CHECKED TRIP SETPOINT IIC-2.10.024.

i 8609110532 1 16SW15

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FAILURE DESCRIPTION: PLEASE REMOVE ACTUATOR. MAINTENANCE HAS TO OPEN,

! INSPECT AND REPAIR VALVE AS NECESSARY.

i CORRECTIVE ACTION: INSTALLED HANDSENDER ON VALVE. CHECKED STROKE, ADJUSTED LIFT OFF SPRING TENSION, INSTALLED NEW GAUGE ON REGULATOR, REMOVED HANDSENDER. CALIBRATED AND RETURNED TO SERVICE.

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SALEM UNIT 1 .

WO NO UNIT EQUIPMENT IDENTIFICATION 8609151271 1 EXCORE NIS SYSTEM FAILURE DESCRIPTION: CALIBRATE THE TARGET DELTA-I TO A VALUE OF -4.0%

(100% RTP VALUE). SEE SPECIAL INSTRUCTIONS FOR IMPLEMENTATION TIMING.

CORRECTIVE ACTION: RECALIBRATED AXIAL FLUX DIFFERENCE TARGET BAND TO 4% AS PER IIC-16.1.008. ADJUSTED 10M200M XA-8440 RB GREEN PEN AND XA-8740RB RED PEN.

8609210031 1 12 WASTE GAS COMPRESSOR FAILURE DESCRIPTION: INVESTIGATE AND REPAIR COMPRESSOR. WILL NOT TURN.

CORRECTIVE ACTION: REPLACED SEAL COVER ROTOR. INSPECTED INTERNAL SURFACES AND FOUND TO BE ERODED BADLY.

. - _ . _ _ _ = _ _ _ - _ . . _ _ _ _ _ . . - . _

SALEM GENERATING STATION MONTHLY OPERATING

SUMMARY

- UNIT NO. 1 SEPTEMBER 1986 SALEM NO. 1 On September 1, 1986, power was reduced to approximately eighty percent (80%) due to problems associated with the loading of the station power transformers. This problem is addressed in the summary for Unit No. 2. On September 16, 1986 load, was increased to 98%

power based on the availability of electrical power from Unit 2 to operate No. 11 Condensate Pump. At 2115 hours0.0245 days <br />0.588 hours <br />0.0035 weeks <br />8.047575e-4 months <br />, the same day, the Unit was taken off line due to a steam leak at the weld joint between a bleed steam pipe and the high pressure turbine exhaust line. The leak was caused by steam erosion. The pipe replacement was completed on September 22, 1986. On September 24, 1986, following the correction of problems with No. 13 Auxiliary Feed Pump steam supply check valves, the Unit was returned to service. The unit operated at approximately eight three percent (83%) power for the remainder of the period.

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REFUELING INFORMATION DOCKET NO.: 50-272 COMPLETED BY: L.K. Miller UNIT NAME: Salem 1 DATE: October 10, 1986 TELEPHONE: 609/935-6000 EXTENSION: 4497 Month September 1986

1. Refueling information has changed from last month:

YES NO X

2. Scheduled date for next refueling: September 12, 1987
3. Scheduled date for restart following refueling: November 26, 1987
4. A) Will Technical Specification changes or other license amendments be required?

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

YES NO X If no, when is it scheduled? August 1987

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

August 1987 if required

6. Important licensing considerations associated with refueling:

NONE

7. Number of Fuel Assemblies:

A) Incore 193 D) In Spent Fuel Storage 380

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

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O PSEG:

Pubhc Service Electnc and Gas Company P.O Box E Hancock s Bridge, New Jersey 08038 Salem Generating Station October 10,.1986 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 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 September 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, k o, Jr.

J. F Z Gen tal Manager - Salem Operations JR:sl cc: Dr. Thomas E. Murley

. Regional Administrator USNRC Region I 631 Park Avenue King of Prussia, PA 19406 Director, Office of Management U.S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 Enclosures 8-1-7.R4 kf 8

i The Energy People

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