ML20080G232

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Monthly Operating Rept for Aug 1983
ML20080G232
Person / Time
Site: Salem PSEG icon.png
Issue date: 09/10/1983
From: Miller L, Zupko J
Public Service Enterprise Group
To:
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE)
References
NUDOCS 8309200165
Download: ML20080G232 (13)
v • d • e


Text

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+ . AVERAGE DAILY UNIT POWER LEVEL Docket No. 50-311 Unit Name Salem # 2 Date Sept. 10, 1983 Comple+.ed by L. K. Miller Telephone 609-935-6000 Extension 4455 Month August 1983 Day. Average Daily Power Level Day Average Daily Power Level (MWe-NET) (MWe-NET) 1 11 7 16 0 2 196 17 996 3 590- 18 1085 4 854 19 41 5 943 20 0 6 1044 21 0 7 1079 22 0 8 1083 23 0 9 1090 24 0 10 1085 25 0 11 358 26 0 12 0 27 0 13 0 28 0 14 0 29 0 15 0 30 0 31 0 Pg. 8,1-7 R1 Page 2 of 13 8309200165 830910 PDR ADOCK 05000311 R PDR

O PSEG Public Service Electric and Gas Company P.O. Box E Hancocks Bridge, New Jersey 08038 Salem Generating Station September 10, 1983 Director, Office of Inspection and Enforcement U.S. Nuclear. Regulatory Commission Washington, DC 20555

Dear Sir:

MONTHLY OPERATING REPORT SALEM NO. 2 DOCKET NO._50-311 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 1983 are being sent to you.

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

General Manager - Salem Operations LKM:sbh 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 Regulatory Commission Washington, DC 20555 Enclosures Page lof 13 8-1-7.R4

/l The Energy People ss mg, ,, g

  • 1* OPERATING DATA REPORT Docket No. 50-311 Date Sept.10, 1983 Telephone 935-6000 Completed by; L. K '. Miller Extension' 4455 Operating Status 1.' Unit Name Salem No. 2 Notes
2. Reporting Period August 1983
3. Licensed Thermal Power (MWt), 3411
4. Nameplate Rating (Gross MWe) 1162
5. Design Electrical Rating (Net MWe) 1115
6. . Maximum Dependable Capacity (Gross MWe) TIT 9

'7.- Maximum Dependable Capacity (Net MWe) 1106

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 16537
12. No. of Hrs. Reactor was Critical 306.9 932.3 11387.9

-13. Reactor Reserve Shutdown Hrs.- 0 3.3 38.9

.14.. Hours Generator On-Line 274.8 766.8 11104

'15. Unit Reserve Shutdown Hours 0 0 0 16.= Gross Thermal Energy Generated (BHm) 816136.8 1979184 32495733

'17. Gross Elec. Energy Generated (PHGI) 262300 528940 10545190

18. Net Elec. Energy Generated (MWH) 243959 457866 10031513
19. Unit Service Factor 36.9 13.2 67.1
20. Unit Availability Factor 36.9 13.2 -67.1 l
21. .

Unit Capacity Factor (using MDC Net) 29.6 7.1 54.8

22. Unit Capacity Factor (using DER Net)' 29.4 7.0 54.4
23. Unit Forced Outage Rate 63.0 49.0 8.9
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.~Dnits-in Test Status (Prior to Commercial Operation):

Forecast Achieved Initial Criticality 6/30/80 8/2/80 Initial Electricity 9/1/80 6/3/81 Commercial Operation 9/24/81 10/13/81 8-1-7.R2 Page 3 of 13

Dock 3t No..50-311

~

UNIT SHUTDOWN'AN'D POWER REDUCTIONS REPORT MONTH AUGUST 1983 Unit Name Salem No.2 Date. Sept. 10, 1983 Completed-by L.K. Miller . Telephone 609-935-6000

' Extension 4435

< r Method of.

Duration Shutting License Cause and Corrective-No. Date .Tygm Hours Reason. Down Event System Component Action to.

1 2 Reactor Report' Code'4 Code 5 Prevent Recurrence.

' Circulating Water '

HF PUMPXX Pumps83-057 7/28' F 248.5 B 1 ---

Nuclear Control Rod '

RB' CRDRVE Drive Power Supplies83-062 8/01 29.5 Traveling Screens /

Trash Racks /

" " -" " HF FILTER -Canal Screens 064 8/05 4.0 83-066' 8/06 5.0 83-068 8/06 2.7 Control Valves83-070 8/07 "

1.2 " "

", CCX MECFUN Turbine 83-072 8/07 3.0 1 2 Reason 3 Method 4 Exhibit G- 5 Exhibit 1 F: Forced A-Equipment Failure-explain 1-Manual Instructions Salem.as S: Scheduled B-Maintenance or Test 2-Manual Scram. for Prepara- Source C-Re fueling 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 l H-Other-explain- (NUREG 0161) t l

Page'4aof 13

~ MAJOR PLANT MODIFICATIONS DOCKET NO: 50-311 REPORT MONTH AUGUST 1983 DATE: SEPTEMBER 10, 1983, COMPLETED BY: L. K. MILLER I

TELEPHONE: (609) 935-6000 Ext. 4455 V

  • DCR NO. PRINCIPLE SYSTEM SUBJECT 2EC-1534 Building and Equipment Change nuclear classification of Drains, Flood and Sump Pumps containment sump pumps from Nuclear Class III to Non-Nuclear Safety.

2EC-1661 Safety Injection Replace valve 23SJ23 (Mark #FA-17) with a 1" Yarway valve (Mark #FA-130).

2SC-0800 Auxiliary Annunciator Provide a permanent fix to repair and replace existing obsolete equipment for the auxiliary annunciator.

2SC-0864 Steam Generator Blowdown Improve the durability of the short piping run between valves 23GB924 (typical) and the main condenser. Revise pipe configuration, schedule or material specification as required.

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  • DESIGN CHANGE REQUEST 8-1-7.R1 Page 5 of 13

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' MAJOR PLANT MODIFICATIONS DOCKET NO.: 50-311 REPORT MONTH AUGUST UNIT NAME: Salem 2 DATE: September 10, 1983 COMPLETED BY: L.K. Miller TELEPHONE: 609/935-6000 X4455

-plant. The DCR has-no effect on the plant discharge. No unreviewed safety or environmental questions are involved.

2EC-1661 This design change will replace an existing valve with a valve capable of maintaining a positive shutoff which is necessary to properly calibrate the transmitter. No i unreviewed safety or environmental questions are involved.

2SC-0800 This DCR will update the present system with a 4 ore

reliable configuration. No unreviewed safety c.

. environmental questions are. involved.

2SC-0864 This DCR will upgrade the piping with a more erosion-resistant material. No unreviewed safety or environmental questions are involved.

!

  • Design Change Request l

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1 Page 6 of 13 i

f

PSE&G SALEM GENERATING SIATION SAFEIT REIATED WOIE ORDER IOG SAIDI UNIT NO. 2

'l WO NO Drrr Uhrr Egu1H4ENE nnNnHCATIGI 922380 PD 2 INS OIANL BUS 2R41B j ' FAILURE DESGIPTIN: 2R41B IS FAIIED IOCALLY. 830517 C@RECTIVE ACTIW: CHANNEL BUS DifEBMITIANT FAIIURE. GIECKED OIANNEL SAT AND rem 3RNED 'IO l SERVICE. REPIACED TEST JACK Ato CLEARED RAMS OIAl@lEL. EUNCTINAL CCMPLETE 6/21/83. 830630 922412 PO 2 VALVOP, 2BH4 FAILURE DESCRIPTICN: HANDWHEEL WILL NOT ENGAGE EOR MANUAL TERATICN.

1 CIANGED OPERATOR, TEST SAT.

CNRECTIVE ACTIQ 4: ,

922560 PD 2 VALVOP, 2PS1 & 2PS3' FAIIURE DESCRIPTICN: VALVES WILL NOT MAKE INCREASE LIMIT NOR WILL DECREASE LIMIT GO GTf. DEMAND INDICATIN CYCLES NOINALLY. 830508 1

l CORRECTIVE ACTICN: REELACED VALVOP DIAPHRAGM ABO 5-100 PSI RDGUIA'IGS CN 2PS1 Ato 2PS3.

REPIACED DEFECTIVE E/P TRANSDUCER m 2PS3. OfECKED OPERATICN FRCM CCNIBOL RO N SAT. 830511 922572 PO 2 VALVE 2PS2 FAILURE DESCRIFFICN: VALVE LEAKS. 830509 I

i CORRECTIVE ACTIGl: DISASSEIELED VALVE. REPLACED DIAPHRAW AND PACKING. 830525 I

922574 MD 2 . VALVE 22SW50 FAIIURE DESCRIPTICN: VALVE WILL NOT MOVE. HANDWHEEL 'IURNS BUT DOES NOT FEEL ENGAGED 'IO DISK.

I 830509 CORRECPIVE ACTIW: REPLACED BROKEN KEY IN GEARBOX MECHANISM. 830510 i

I i

Page 7 of 13 ,

PSE&G SALEM GENERMPING STATICN SAFETY RELP.TED NWK WDER IOG SAI2M UNIT NO. 2 WO NO DEPT UNIT EQUIPMENT IDENTIFICATIN 922719 PD 2 VALVE 2WL71 FAIIERE DESCRIPTICN: VALVE WILL NOP TERATE. 830602 CORRBCTIVE ACTICN: INCREASED AIR PRESSURE 'IO INPUP T ACITR'IOR T 2WL71 'IO APPROK 90 IBS.

AC'IVATCR 'IHEN BEGAN 'IO TERATE. STROKED VALVE TEN / CLOSED 5 TIMES. 830603 922787 m 2 .VALVOP, 2SJ4 '

F, 6 DESCRIPTIN: VALVE SEAT APPEARS 'IO BE LEAKING 'IHROUGH. 830321 CORRECTIVE ACTIN: RESET 'IORQUE SWITCH 'IO 2 AS PER ENG IEFIER. 830331 922793 10 2 21 CHARGING K MP FAIIURE DESCRIPTICN: PUMP MAY 1RVE RUN WITH AN EMP1Y OIL RESERVOIR. 830322 CORRECTIVE ACTIN: INBOARD AND OUFBOARD RADIAL BRGS OK. 'IERUST BRG DAMAGED BUT NOP WIPED.

CLEANED _ OIL LINES, HOUSING ABD SNP. INS'IALLED NEW 'IHRUST SHTS AND VERIFIED

'IERUST. 830322 922840 m 2 VALVE 2CV171 FAIIURE DESCRIPTIW: BCEY 'IO BCNNET IFAK. 8,30316 C@RECPIVE ACTICN: REPIJCED BONEff. 830418 922872 ND 2 21 CCMP COOLING REP FAIIURE DESCRIPTICE: OUTBQARD BEARING IEAKS EKGSSIVELY. 830326 CORRECTIVE ACTICE: INSTALLED NEW MECHANICAL SEAL AND CUrBQARD SEAL. 830424 Page 8 of 13-2

. . . . = . . - . --- .

.PSE&G SALEM GENERATING STATION 4

SAFETY REIATED WORK @ DER IOG ,

SALEM LNIT 2 r

WO NO DEPT WIT EUJIPMENT puwnrICATIN 922743 ND 2 26 SERVICE WIR RNP FAIIERE DESCRIPTIN: LINE DOWNSTREAM OF 26SW24 BAC NASH VALVE HAS " HOLE IN IT. 830609 CWarL'nVE N'fIW: DISASSDELED & REPAIRED 4" LINE W/ WEED AND PLASTIC ETAL FOR NEAR. ASSENRTE PIPING WITH NEW GASKETS. 830621 ,

932832 m 2 2B DIESEL JKP WrR IK FAILURE DESCRIPTICN: SMALL JM5TP NATER LEAK CN EXPANSIN TANK VENT LINE WIERE IT ENTERS BY

'IURB0 CHARGER. LEAK IS ON 'IHREADED SECTICN CF PIPE. 830625 CORRF'PIVE ACTIW: REPLACED BROlGN PIPE WITH A UNIN AND NIPPLE AND NEW GASKEP. 830809 4

932871 m 2 25 SW PMP STRNR IK j FAIIURE DESCRIPTIW: 25 SW RNP STRAINER BACNASH LINE IS LEAKING BETWEEN 25SW24 AND STRAINER.

1 830624 CORRECTIVE ACTICN: RENOVED LINE FOR WEIDING & BELZWA REPAIRS, 'IHEN REINSTATTm. 830627 933763 m 2 23FE68 l FAILURE DESCRIPTIW : 23MS68 HAS A PIDG MISSING BEEDRE PACKING GLAND. REPIACE PIIG. 830808 CORMtL'nVE ACTIN: USING MAGELOCK FITIING PUf A VLV IN PIDG HOLE, CIOSED VLV AND CAPPED 'IHE IND.

830808 J

i A

Page 9 of 13 7

PSE&G SALEM GENERATING SDG'ICN SAFELY REIATED WWK CEIDER IOG SALEM INIT 2 WO NO Drrr WIT EQUIINENT IDENTIFICATICN 933897 bD 2- 23 SW PLMP FAIIURE DESCRIPTIW: DO NOT HAVE OFFRL IWR CN INP. DID N0f GET START LIGHT & COUID N0f STOP INP FRCN CCNTROL ROCN. 830729.

CWRECTIVE ACTIN: FEMALE 125VDC CNTRL BIOCK COCKED NOT AUINING GOOD (XNr7CF & CAUSING TEN CIRCUIT. ADJSID BIOCK AND RAISED CUBICLE ELEVA'ITR SW TO ALIIN GOCD CCNDCf.'

830730 900545 PD 2 24 ACCLMJIA'IOR FAIIURE DESCRIPTICN: EXCESSIVE DEVIA;fIm BE'INEEN GANNELS. 820511 CORRECTIVE ACTICN: TRANSMITTER ROOT VALVES IEAKING 'IHROUGH. CAWOf CALIBRATE TRANS AT POWER.

TRANSMITTERS CALIBRATED CN 830423 907421 2 2 21 CECU M71DR COGER FAIIURE DESCRIPTICN: IEAK IN MOIOR COOLER. 820908 CCRRECTIVE ACTICN: INSTALLED NEN COGER. 820908 908662 bD 2 23 S WrR STRAINER ,

FAIIURE DESCRIPTICN:  : TEN AND INSPECT. 820910 CCERECTIVE ACTICN: INSPECTED, CLEANED & REPIACED WWN PAIUS. 830521 910013 PD 2 VALVE, 22MS168 FAIIURE DESCRIPTICN: REPAIR S'IEAM IEAK. 820728 CORRECTIVE ACTICN: WEIDED STEAM CUTS IN BCDY GASKET SFATING SURFACE. IAPPED ARFA AND REGASKEFED. .

830314' i

+

! Page 10 of 13 i

PSE&G SALEM GENERATING SFIATION SAFETfY RELATED WORK ORDER ILG SALEM UNIT 2 WO NO DEPT UNIT EQUIINENT niFwne'1CATIN 919902 PD 2 2IC-732A1B FAIIEEE DESCRIPTIW: OCNPAPA'IOR TRIP FOINT QJT T SPEC. 830208 CUtetix1VE ACTIW: REPIACED 'INO CAP 1CITWS IN 2IC-732A/B. 830208 922127 PD 2 VALVOP, 2CV7 FAIIBRE DESCRIPTICN: VALVE WILL Nor CPEN. 830123 CustLnVE JCfIW: FOUND IEAKING SOLENOID VALVE SV425 AND FEED WIRES 15 AND 16 IN 'IP22-2 CABINET REVERSED. REPLACED SOLENOID VALVE AND REVERSED FEED WIRES. 830124 922206 PD 2 NIS PR CH 2N41 FAILURE DESCRIPTI W: WANNEL READS 18% IN PANEL; CWSOLE INDICATIW FAILED HIGH AT 120%. 830209 CutmEL'nVE ACTIW: REPIACED utm;nVE POWER SUPPLY NO-302. TEST SAT. 830209 Page 11 of 13

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SALEM UNIT 2 OPERATIONS

SUMMARY

REPORT AUGUST 1983 Unit'No. 2 began'the month ~in a power escalation following a trip of the reactor which occurred on July 29, 1983. . On August 1, during the power escalation, No. 2 Reactor tripped due to a spurious actuation of 2A Safeguards -Equipment Controller - (SEC) .' The SEC actuation caused a loss of-the equipment associated with the 2A Vital Bus. The-rod control system alternate power-supply failed to supply control power to.two control rod banks following swap-over from the deenergized 2A Vital Bus. This caused the control banks to fall into the core,

- tripping the reactor on a nuclear instrument negative rate trip.

A reactor startup was commenced on August 2, and-the unit was operating at-full-power on August 6. The majority of reactor zero power. physics and power escalation testing was completed.between

August 1 and August 11. Unit No. 2 continued to operate at full power 1

until the trip.of Unit No. 1 on August 11, due to the accumulation of excessive grass on the Circulator Water Screens. Following.the trip j of Unit No. 1, grass-began building up on the Unit No. 2 Circulating i Water Screens, causing a loss of five of the six circulators. Unit 4

-load was rapidly reduced, the generator was unloaded, and the

generator breakers were opened. The turbine wasJtripped'while reactor power was above the P-7 permissive setpoint resulting in an automatic

~ reactor trip.

Following the reactor trip of August 11, the decision was made to cool

.down to facilitate the replacement of the failed Intermediate Range

-Channel N35 Detector.

During the cooldown for repairs to Intermediate Range N35, the master controller for. pressurizer pressure failed high. .This caused both pressurizer? spray valves to fully open, resulting-in a rapid decrease of pressurizer pressure, which initiated a ' safety injection on low pressurizer pressure.

The reactor was again critical on August 16, and operating at full

,  : power on August 17. Unit'No. 2 continued to operate at full power until August 19 when the discovery of a hydrogen leak into the generator istator cooling water system forced a shutdown of the unit.-

Subsequent investigation revealed that there were six leaks on the general internal "T" connections where cooling water lines from the stator tie into the header. The cause of the leaks appears to be due

.to vibration fatigue caused by a' resonance frequency problem.

Additional' resonance-frequency. testing disclosed several loosened phase leads on the exciter end of the generator. Unit No. 2 remained shutdown through the end of August,.as repairs to the generator

. continued. Unit No. 2 is currently scheduled to return to power on September' 26,.1983.

Page 12 of 13

..o .

l REFUELING INFORMATION DOCKET NO.: 50-311 COMPLETED BY: L.K. Miller UNIT NAME: Salem 2 DATE: September 10, 1983 TELEPHONE: 609/935-6000 EXTENSION: 4455 Month -August 1983

1. Refueling information has changed from last month:

YES- X NO

2. Scheduled date for next refueling: September 28, 1984
3. Schedu, led date for restart following refueling: December 8, 1984
4. A) Will Technical Specification changes or other license amendments be required?

YES NO NOT DETERMINED TO DATE 9/1/83 B) Has the reload fuel design been reviewed by the Station Operating Review Committee?-

YES NO X If no, when is it scheduled? August 1984

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

August 1984 (if required)

6. Important licensing considerations associated with refueling:

NONE' 8

7. Number-of Fuel Assemblies: -

A) Incore 193 B)- In Spent Fuel _ Storage 72

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: March 2000 8-1-7.R4 Page 13 of 13
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