ML20082E510
| ML20082E510 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 11/10/1983 |
| From: | Miller L, Zupko J Public Service Enterprise Group |
| To: | NRC OFFICE OF INSPECTION & ENFORCEMENT (IE) |
| References | |
| NUDOCS 8311280222 | |
| Download: ML20082E510 (12) | |
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AVERAGE DAILY UNIT POWER LEVEL Docket No. 50-311 Unit Name Salem # 2 Date Nov 10, 1983 Completed by L. K. Miller Telephone 609-935-6000 Extension 4455 l
Month October 1983 Day Average Daily Power Level Day Average Daily Power Level-(MWe-NET) (MWe-NET) 1 1074 16 0 2 1109 17 0 3 1094 18 0 4 1076 19 0 5 1076 20 0 6 1016 21 0 7 611 22 0 8 0 23 0 9 0 24 0 10 0 25 0 11 0 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 12 mmamm, PDR
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OPERATING DATA REPORT Docket No. 50-311 -
Date Nov.10, 1983 Telephone 935-6000 Completed by L. K. Miller Extension 4455 Operating Status
- 1. Unit Name Salem No. 2 Notes
- 2. Reporting Period October 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)1149
- 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 745 7296 18002
- 12. No. of Hrs. Reactor was Critical 158.2 1252.9 11708.5
- 13. Reactor Reserve Shutdown Hrs. 586.8 590.1 626.6
- 14. Hours Generator On-Line 158.1 1080.1 11417.3
- 15. Unit Reserve Shutdown Hours 0 0 0
- 16. Gross Thermal Energy Generated (MWH) 527417 2954523 33471072
- 17. Gross Elec. Energy Generated (MWH) 176510 852040 10868290
- 18. Net Elec. Energy Generated (.MWH) 16404a 752263 10325910
- 19. Unit Service Factor 21.2 14.8 63.5
- 20. Unit Availability Factor 21.2 14.8 63.5
. 21. Unit Capacity Factor (using MDC Net) 19.9 9.3 51.9
- 22. Unit Capacity Factor (using DER Net) 19.7 9.2 51.5
- 23. Unit Forced Outage Rate 78.8 63.6 16.4
- 24. Shutdowns scheduled over next 6 months (type, date and duration of each)
N/A I 25. If shutdown at end of Report Period, Estimated Date of Startup:
11/27/83
- 26. Units 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 i Commercial Operation 9/24/81 10/13/81 8-1-7.R2 Page 3 of 12
UNIT SHUTDOWN AND POWER REDUCTIONS Docket No. 50-311 REPORT MONTH OCTOBER 1983 Unit Name Salcm No.2 Date Nov. 10, 1983 .
Completed by L.K. Miller 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 ctor Report Code 4 Code 5 Prevent Recurrence Traveling Screens /
Tra sh. Racks /
83-098 10/01 F 3.6 B 5 - HF FILTER Canal Screen 83-100 10/01 9.0 83-102 10/01 4.0 83-104 10/02 "
6.2 " HF Transmission System Problems Other than 83-106 10/03 "
12.6 H " "
EA ZZZZZZ Catastrophies Intake System Problems Other than 82-108 10/05 "
5.1 B HF HTEXCH Traveling Screens Transmission System Problems Other 83-110 10/06 "
9.6 H 5 -
EA ZZZZZZ than Catastrophies Traveling Screens /
Trash Racks /
" " Canal Screens83-112 10/06 "
6.8 B HF FILTER Other Hydrogen System Problems
" Generator 83-114 10/07 "
431.8 A 1 HA HTEXCH 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 fue ling 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)
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- DOCKET NO: 50-311 MAJOR PLANT MODIFICATIONS SALEM 2 UNIT NAME:
REPORT MONTH OCTOBER 1983 NOVEMBER 10, 198.3 DATE:
COMPLETED BY: L. K. MILLER TELEPHONE: (609) 339-4455 PRINCIPLE SYSTEM SUBJECT
- DCR NO.
2EC-1052 Various Solenoid Valves Replace selected sa[ety related solenoid valves located in Containment, Penetration Areas, and Auxiliary Building with Asco NP-1 series solenoid valves.
2EC-1151 ECCS Provide semi-automatic transfer of the ECCS from the injection phase -
to the recirculation phase of operation.
2EC-1715 Main Turbine Generator- Install a tee with a valve in the Hydrogen System piping to and from the turbine-generator hydrogen dryer.
Main Turbine High Delete the existing " knock" unions 2EC-1729 in the 1-1/4" cylinder heating Pressure Cylinder Heating piping adjacent to the high pressure turbine.
Penetration Area Provide low temperature alarm in 2SC-0160 north and south penetration.
Ventilation Emergency Diesel Relocate the generator field flashing 2SC-0825 resistors.
Generator Emergency Diesel Provide a means for testing the 2SC-0961 operability of the emergency diesel Generator generator back-up start solenoid, l
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- DESIGN CHANGE REQUEST 8-1-7.R1 Page 5 of 12 I
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MAJOR PLANT MODIFICATIONS DOCKET NO.: 50-311 REPORT MONTH October UNIT NAME: Salem 2 DATE: November 10, 1983 COMPLETED BY: L.K. Miller CELEPHONE: 609/339-4455 DCR NO. 10CFR 50.59 SAFETY EVALUATION 2EC-1052 The design of the systems affected will not be changed.
The result of this DCR will be improved system reliability. No unreviewed are involved.
2EC-1151 No unreviewed safety or environmental questions are involved.
2EC-1715 The installation of the tee and valves does not alter the original design concept of the system. No unreviewed safety or environmental questions are involved.
2EC-1729 This DCR does not alter the original design concept of the system but does eliminate known sources of steam leakage.
No unreviewed safety or environmental questions are involved.
2SC-0160 The thermostats being added were not used in any presently performed safety analysis. No unreviewed safety or environmental questions are involved.
2SC-0825 The resistors are being moved, however their function remains the same. No unreviewed safety or environmental questions are involved.
2SC-0961 Installation of this DCR improves the reliability of the diesel starting system by ensuring that all normal and redundant air starting and turbo boost solenoid valves are operable.
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PSE&G SALEM GENERATING STATION ~
SAFEIY REIATED WORK ORDER IOG ,
SAIIM UNIT NO.' 2 WO NO DEPT UNIT EQUIPMENE IDEdrIFICATICN i
I- 929870 PD 2 25 CNDMr ECU ,
i FAIIURE DESCRIPTIN: INVESTIGMPE MarOR 'IHEI@0 COUPLE PROBLEM, INBOAPD At0 OU'IBOMO. 830606 CORRECTIVE ETION: THRICPLS BROKEN AND BENT. REPI1CED 'INIOCPIS AND NIPPLES. VERIFIED 'IHRICPLS NORK TO CmPU'IER. MTR INBD BRG TA2639 (CmPTr1052A), 01BD BRG TA2640 (cmp-T1053A) l 929875 PD 2 2IE-412C RD INSREN l
l FAILURE DESCRIPTIN: GANNEL OUT T CALIBRATIN MIILE PERFORMING I/O-403545. 830613 i
CUKKtL'nVE ETION: RPLCD SLMRTOR 2DC-422C arxl 2DM-412. ADJSID 2DC-442C, 2DR-412 A&B,
! 2DC-422 A&B, & 2DC-442 A&B. 830618 i '
I 929895 PD 2 VTL Mr TRACE 2609A FAIIURE DESCRIPTIN: REPIACE 2609A PRDERY CCNTROLLER AIO 26097C to DCRIC. 830700 a
! CunxtI;nVE ETION: REPIACED 7EERICCOUPLES. DORIC READ 162, IOCAL 160. 830712 I
! 929920 PD 2 2Pr-545 24 S/G j FAILURE DESCRIPTION: GANNEL CUT T CALIBRATION. CNPARATOR PC-525 A&B CUT T SPEC. 830620 CORRBCTIVE ACTION: ISOIATOR 2PM525B SN-00409 NAS PUITING OUr SWE AC NOISE CAUSING PROBLEMS TO @PC-525A & B. ISOLATOR REPIACED BY SN-667. BENG CALIBRATED AND
! RETURNED TO SERVICE. 830624 j
929924 PD 2 21SW24 l
1 FAIIURE DESCRIPTIW: REPLACE SOLENOID DUE TO NATER DAMAGE. 830624
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830706
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CuuxtL'nVE ACTION: REPIACED CNPIEPE SOLENOID.
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PSE&G SALEM GENERATING SIATION
- $AFETY REIMED WORK WDER IOG- ,
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i SALEM UNIT NO. 2 1
i WO NO DEPP UNIT EQUIPMENT IDDrraICATIN d
4 929926 PD 2 23SW24 FAILURE DESCRIPTIW: REPLACE SOLENOID DUE 'IO WATER DAMAGE. 830624 i
CUKMBL'nVE ACTICN: REPIACED CWPLETE SOLENOID. 830706 i 929959 PD 2 22AC CABINET s
i FAILURE DESCRIPTIN: 22AC CABINET URGENT FAILURE ALARM AND VERIFY ALL IGS WIII STEP IN AND OUT.
830530 L
i CORRECTIVE ACTIm: REPRD AND REPIfD FIRING CIRCUIT CARDS A2 and D2 VERIFIED PROPR OPS. CLEANED i DIRTY CNNCINS AT HEAD ON INSI MVBL GRIPPR. VERIFIED RW STEP IN AND Off.
l REPLACED 11 BIDWN EUSES 830700 l
929963 PD 2 23 BCL FILW CHNL II d
- FAILURE DESCRIPTIW
- FLOE INDICATING IIM. 830704 i
i CuMMtL'nVE ACTION: REPLACED TRANSMITTER FORCED MTR, DETECIDR COIL ASSY, TRANSEURMER.
4 PERFORMED CALTRRATIm 2PD-2.5.011 & TIME RESP WSE AS PER 2PD-2.8.011. 830719 1
I 929966 PD 2 RWST LEVEL CHANNELS PERFORM GANNEL CAL CHECKS 'IO SATISFY 'IHII SPEC EUCTICNAL RErJfrS. 830706
! FAILURE DESCRIPTIm:
j CORRECTIVE ACTION: PERFORMED CALS-ALL CHNLS EXCEPT III. DUEL CWPARATOR 2CB-926B 'OUT T SPEC.
1 REPLACED WITH NEW BOARD. RECALIBRATED AIO VERIFIED OPERATIN. 830715 i
i 929967 PD 2 RCL 21 & 24 RID'S FAILURE DESCRIPTIW: REPLACE ILOP 21 & 24 NARROW RANGE RID'S - COLD LEGS. REPIACE IOOP 21 WIDE I RANGE RID - COLD LEG. 830705 I
REPLACED RID'S AND PERFOFMED RID TIME RSPNSE TEST PD-14.3.009. PERFORMED 21 l CORRECTIVE ACTIm:
' WIDE RANGE CHANNEL CAL 2PD 2.10.055. 830711 '
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PSE&G SALEM GENERATING STATION SAFEl"I REIATED NORK CEDER I4G ,
SALEM UNIT 2 WO NO DEPT UNIT EQUIPMENT IDENnFICATIN 929969 PD 2 RX 'IRIP BKR B FAIIURE DESCRIPTIW: PERFORM UV COIL TEST CN RX 'IRIP BREAKER B. 830706 CORRECTIVE ICTION: PERFORMED PRnrmURE 2IC-18.1.0ll - 1CIUAL TIME 6 CYCLES. 830706 929704 PD 2 2R41'S APD FAIIURE DESCRIPTICN: PERFORM IEAK TESTS W ALL APD TUBING AND SAMPLER ASSEMBLIES PRIOR TO IVITING IN SERVICE. 830400 CORRCPIVE JCTIm: REPIKED APD FILTER ENCIOSURE S/N-262 WITH S/N-280. 830601 929728 PD 2 NARRON RNG RID IOOP 2 FAIIURE DESCRIPTIW: REPIEE HOT AND COLD LEG RID'S IN ICOP 2 (NARROW) . RECALIBRATE CHANNEL AS REQD' FCR NEW RID'S. PERFORM PIUNGER TEST ON NEW RID BEFORE INSTALIATION.
830413 I CORRECTIVE JCTICN: CAL 'IM421A(110) l & 2IM42B (111) - NEW RID VLUS. ADJ LEAD-LAG 2TM422D I (FD115), 2TM422Z (80299) & 2TM422T (80292) . REPL 2'IM421G (QO389)W/SN # 577.
j PEPL DAILY DD MOD IN 2T1422. 830622 929736 PD 2 21S/G FDWrR CCNrROL FAILURE DESCRIPTIm: CALIBRATE CHANNEL. 820502 CORKtLnVE ACTION: REMOVED MOORE SIGNAL COUNTER lEM-510D SN-85759. INSTAT.im KORE SCT SN-65759 IN IFM-5100. 830518 i
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PSE&G SALEM GENERMPING STATICN ,
i 3 SAFE 1Y REIATED WORK CEDER IOG ,
SALEM UNIT 2 .i
. WO NO DEPT UNIT EQUIPMENP IDENPIFICATIN i ,
929355 PD 2 RX 'IRIP BKR A&P EUNC
! FAILURE DESCRIPTIW: PERFOR4 IN EINCTIO3AIS IC-18.1.010 AND 18.1.011 'IO VERIFY RX 'IRIP BREAKER TRIPPED TIMING. 830702 PERFORMED IN FUNCTIWAIS 2IC-18.1.010 & 18.1.011. RX BKR A-SCYC, RX BKR
? CORRECTIVE ACPIW:
! B-6CYC. PEREDRMED 2IC18.0.011 AS PER SPECIAL INSTRUCTIN S. BKR B-6CYC.
i 830705
I FAIIURE DESCRIPTIN: VLV LEAKING PAST SEAT. 821213 l
CORRECTIVE ACTION: REPIACED VLV. 830309 f
I
- 930649 PD 2 24 S/G t
j FAILURE DESCRIPTIN: PRESSURE WANNEL 1 READING 40 'IO 60# ICW. 821208 i
t Cunnex;nVE ACT. TON: 2PM-544A ISOIATOR E00ND CAPS C3&C4 BICWN. REPIACED CAPS C3, C4, C2, C6,
& C7. USED PROCEDURE 2PD-2.6.050 'IO REMOE & REIURN 'IO SERVICE. 830121 i
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SALEM UNIT 2 OPERATIONS
SUMMARY
REPORT OCTOBER 1983 Unit No. 2 began the month at full power following the initial repair of leaks in the Generator Stator Water Cooling System. During subsecuent testing, additional leaks were discovered in the Generator Cooling Water System and Unit 2 was again shutdown on October 7, 1983.
The decision was made to modify the cooling water headers to eliminate the Tee connections, and provide for direct connection of the Teflon _
cooling water hoses to eliminate the problem of vibrational fatigue.
The cooling water headers were shipped to East Pittsburgh, where they were remachined to accept the Teflon hoses. Unit No. 2 remained shutdown for the rest of the month as repairs to the generator continued. Unit No. 2 is scheduled to return to service on November 28, 1983.
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REFUELING INFORMATION Docket No. 50-311 Unit Name Salem #2 Date November 10, 1983 Completed by L. K. Mille Telephone 609-935-6000 Extension 4455 Month October 1983
- 1. Refueling information has changed from last month:
YES X NO
- 2. Scheduled date of next refueling: September 29, 1984
- 3. Scheduled 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 _ 11/1/83 B. Has the reload fuel design been reveiwed 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
- 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 12 of 12
O PSEG Public Service Electric and Gas Company P.O. Box E Hancocks Bridge, New Jersey 08038 Salem Generating Station November 10, 1983 Director, Office of-Inspection and Enforcement U.S. Nuclear Regulatory Commission Washington, DC 20555
Dear Sir:
MONTHLY OPERATIN': 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 October 1983 are being sent to you.
Average Daily Unit 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 1 of 12 8-1-7.R4 [/[gg l i
4 The Energy People 95 21M (20W 11-81 i