ML20211P958
| ML20211P958 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 11/30/1986 |
| From: | White P, Zupko J Public Service Enterprise Group |
| To: | NRC OFFICE OF INSPECTION & ENFORCEMENT (IE) |
| References | |
| NUDOCS 8612190168 | |
| Download: ML20211P958 (15) | |
Text
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AVERAGE DAILY UNIT POWER LEVEL Docket No.
50-311 Unit Name Salem # 2 Date Dec ember 10,1986 Completed by Pell White Telephone 609-935-6000 Extension 4451 Month November 1986 Day Average Daily Power Level Day Average Daily Power' Level (MWe-NET)
(MWe-NET) 1 0
17 0
2 0
18 0
3 0
19 0
4 0
20 0
5 0
21 0
6 0
22 0
7 0
23 0
8 0
24 0
9 0
25 0
10 0
26 0
11 0
27 0
12 0
28 0
13 0
29 0
14 0
30 0
15 0
31 0
16 0
Pg. 8.1-7 R1 N<
8612190168 861130 PDR ADOCK 05000311 R
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OPERATING DATA REPORT Docket No. 50-311 Date December 10,1986 Telephone 935-6000 Completed by Pell White Extension 4451 Ope ra t ing Status 1.
Unit Name Salem No. 2 Notes 2.
Reporting Period November 1986 3.
Licensed The rmal Power (MWt) 3411 4.
Nameplate Rating (Gross MWe) 1170 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 720 8016 45001
- 12. No. of Hrs. Reactor was Critical 0
5323.5 25649.4
- 13. Reactor Reserve Shutdown Hrs.
0 0
0
- 14. Hours Generator On-Line 0
5247.5 24783.9
- 15. Unit Reserve Shutdown Hours 0
0 0
- 16. Gross Thermal Energy Generated (MWH) 0 6105990 23682470
- 17. Gross Elec. Energy Generated (MWil) 0 5510130 25086610
- 18. Net Elec. Energy Generated (MWH)
-5160 5242616 23777460
- 19. Unit Service Factor 0
65.5 55.1
- 20. Unit Availability Factor 0
65.5 55.1
- 21. Unit Capacity Factor (using MDC Net) 0 59.1 47.8
- 22. Unit Capacity Factor (using DER Net) 0 58.7 47.4
- 23. Unit Forced Outage Rate 0
19.2 35.0
- 24. Shutdowns scheduled over next 6 months (type, date and duration of each)
N/A
- 25. If shutdown at end ot Report Period. Estimated Date of Startup:
12/14/86
- 26. Units in Test Status (Prior to Commercial Operation):
Forecast A ch ie ve d Initial Criticality 6/30/80 8/2/80 Initial Electricity 9/1/80 6/3/81 Commercial Operation 9/24/80 10/13/81 8-1-7.R2 l
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UNIT SHUTDOWN AND POWER REDUCTIONS Docket No, 50-311' REPORT MONTH NOVEMBER 1986 Unit Nane Snlan Ns.2-Date December 10,1986 Completed by Pell White Telephone 609-935-6000 Extension 4451 Method of Duration Shutting License Cause and Corrective No.
Date Type Hours Reason Down Event System Component Action to i
2 R ea ct o r Rep ort Code 4 Code 5 Prevent Recurrence Nuclear Refueling 546 10-02 S
1417.1 C
1 ZZ ZZZZZ Refueling i
2 Reason 3 Method 4 Exhibit G S 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-Refueling 3-Automatic Scram. tion of Data D-Regulatory Restriction 4-Continuation of Entry Sheets E-Ope rator 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.:
50-311-REPORT MONTH NOVEMBER 1986 UNIT NAME:
Salem 2 DATE:
December 10, 1986 COMPLETED BY:
L. Miller TELEPHONE:
609/339-4497
- DCR NO.
PRINCIPAL SYSTEM SUBJECT None Design Change Request
PSE&G SALEM GENERATING STATION SAFETY RELATED WORK ORDER LOG SALEM UNIT 2 WO NO UNIT EQUIPMENT IDENTIFICATION 8606041619 2
UNIT #2 REACTOR FAILURE DESCRIPTION:
DISASSEMBLE THE UNIT 2 REACTOR IN SUPPORT OF FUEL SHUFFLE AND REASSEMBLE UPON COMPLETION OF FUEL SHUFFLE IN SUPPORT OF THE 3RD REFUELING OF SALEM 2.
CORRECTIVE ACTION:
REACTOR DISASSEMBLED, FUEL TRANSFERRED, REACTOR REASSEMBLED IN ACCORDANCE WITH PROCEDURE #FP-PNJ-R3.
8509250120 2
21 AUX FEED PUMP FAILURE DESCRIPTION:
OUTBOARD SEAL LEAKS SINCE PUMPS WERE RUN 9-22-85.
CORRECTIVE ACTION:
REPLACED OUTBOARD SEAL AND THRUST BEARINGS, RESET THRUST, REALIGNED MOTOR AND PUMP.
8601080162 2
INCORE FLUX THIMBLES FAILURE DESCRIPTION:
EDDY CURRENT TEST THE SALEM UNIT 2 FLUX THIMBLES DURING THE 3RD REFUELING OUTAGE AFTER MAINTENANCE HAS CLEANED THE THIMBLE TUBE PER WORK ORDER # 8601080138.
VISUALLY INSPECT THIMBLE AT N-08 FOR KINK 10 FEET BELOW SEAL TABLE.
CORRECTIVE ACTION:
EDDY CURRENT EXAM OF UNIT 2 FLUX THIMBLES COMPLETED.
KINK INSPECTED AT N-08.
SALEM UNIT 2 WO NO UNIT EQUIPMENT IDENTIFICATION 8608260034 2
EHC RUNBACK FAILURE DESCRIPTION:
EHC RUNBACK FOR NO REASON.
SWAPPED FROM " HOLD" TO "GO" ON EHC CONTROLS.
PLEASE INVESTIGATE AND REPAIR.
CORRECTIVE ACTION:
REPLACEO GO SWITCH. INSTALLED.01 MF/200V CAP
,BETWEEN PINS 21 AND 29 ON 1AO4E.
8609210120
~
,7 2
24SW58 FAILURE DESCRIPTION:' IIAVE OPEN ANC CLOSE LIMITS SHOWING.
VALVE IIAS
/
~
BEEN VERIFIED 50% OPEN AND IT WILL-NOT MOVE.
IT APPEARS TO BE FROZEN IN POSITION.
PLEASE INVESTIGATE AND REPAIR.
v-
,,/
j i
CORRECTIVE ACTION:
CLEANED, LUBRICATED; INSTALLED NEW BOOT & O RING.
INSTALLED NEW PINS.
8610160041 f'
2 24 RCP MOTOR FAILURE DESCRIPTION:
INVESTIGATE FAILURE OF OIL LIFT SYSTEM FOR 24 RCP MOTOR.
CORRECTIVE ACTION:
DISASSEMBLED 24 MOTOR, FOUND CAUSE OF LIFT DEFICIENCY TO BE LOOSE INTERNAL OIL LIFT LINES, 1 BROKEN 3
COPPER INTERNAL OIL LIFT LINE TO UPPER TIIRUST SHOES CLOGGED. CHECK VALVES TO LOWER THRUST SHOES, SLIGHTLY WIPED BABBIT ON LOWER THRUST SHOESg
/
^
SALEM UNIT-2 WO NO UNIT EQUIPMENT IDENTIFICATION 8611080122 2
2CV35 FAILURE DESCRIPTION:
VALVE DRIFTS FROM ONE POSITION TO THE OTHER WITHOUT OPERATOR ACTION AND DOES NOT MATTER IF THE VALVE IS IN AUTO OR MANUAL CONTROL.
PLEASE REPAIR.
CORRECTIVE ACTION:
REPLACED MAN / AUTO CONTROLLER SN KO100 WITH SN 178 AND RETURNED CHANNEL TO NORMAL.
VERIFIED 2CV35 DIREVTS TO HUT AT PROPER VCT LEVEL AND MOVES BACK TO VCT UPON NORMAL LEVEL.
8611120787 2
CONTAINMENT SPRAY VALVE s
~.p FAILURE DESCRIPTION:
DURING THE CONTAINMENT SPRAY FULL FLOW TEST VISUAL
~
s EXAMINATION REVEALED A SMALL LEAK AT THE DISCHARGE
.. ~,
OF VALVE 22CS41 WAS NOTED.
PLEASE REPAIR VALVE OR CAP VENT CONNECTION.
VALVE LOCATED NEAR 22 CONTAINMENT SPRAY PUMP.
CORRECTIVE ACTION:
REPAIRED CAP VENT CONNECTION.
8611130294 2
REACTOR TRIP BREAKER FAILURE DESCRIPTION:
LUBRICATE THE MECHANIS!! FO THE "A" REACTOR TRIP BREAKER SERIAL NO. 02YN219-1 PER ATTACHED INTERNAL MEMORANDUM.
CORRECTIVE ACTION:
LUBRICATED MECHANISM AND USED M3Q-2 STEP 9.14.2 TRIP BAR FOURCE MEAS, WT CAME TO IST STEP 540 GR 2ND TEST 540 GPM, 3RD TEST 580 GR.
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SALEM UNIT 2 WO NO UNIT EQUIPMENT IDENTIFICATION 8610310477 2
REACTOR COOLANT DRAIN TANK FAILURE DESCRIPTION:
REMOVE R.C.D.T.
MANWAY COVER FOR INSPECTION AND POSSIBLE CLEANING, THEN REPLACE MANWAY COVER.
CORRECTIVE ACTION:
REMOVED MANWAY COVER, INSPECTED FOR RESINS (NONE FOUND) REPLACED GASKET, N U'2 S, STUDS, REINSTALLED.
8611031211 2
23 MS VALVE CONTROL FAILURE DESCRIPTION:
PLEASE REPAIR LEAKING LUNKENHEIMER PHEUMATIC ACTUATOR LOCATED ABOVE PANEL 683-2C.
CORRECTIVE ACTION:
DISASSEMBLED AND REBUILT ACTUATOR AND BALL VALVE, REINSTALLED, OPER SAT.
8611050061 2
2C DIESEL GEN.
FAILURE DESCRIPTION:
FUEL OIL LEAK AT HEADER TO INJECTOR PUMP FLANGE GASKET ON 2L AND 9R CYLINDERS.
CORRECTIVE ACTION:
REPLACED GASKETS IN 26 AND 9R HEADER.
8611060121 2
2C DIESEL GENERATOR FAILURE DESCRIPTION:
EXHAUST LEAK AT 3L CYLINDER.
CORRECTIVE ACTION:
REPLACED EXHAUST MANIFOLD & EXHAUST FLANGE GASKETS.
SALEM UNIT 2 WO NO UNIT EQUIPMENT IDENTIFICATION 8610200019 2
RAD MONITORING FAILURE DESCRIPTION:
PLEASE REPAIR 2R13A. IT IS IN NO SCAN.
CORRECTIVE ACTION:
REMOVED CONTROLLER S/N 230 FROM SERVICE.
PLACED CDC TAG ON MODULE.
INSTALLED S/N 240.
PERFORMED FUNCTIONAL-2IC-4.2.018.
8610201023 2
LETDOWN DIVERT VALVE FAILURE DESCRIPTION:
VALVE CONTROLLER SWAPS ITSELF FROM AUTO TO MANUAL AND DRIFTS OPEN CAUSING LOSS OF CAVITY LEVEL.
CORRECTIVE ACTION:
CONTROLLER FEED FROM B VITAL SUPSECT THE SWAP FROM B VITAL CAUSED THE CONTROLLER TRANSFER FROM AUTO TO MANUAL.
ON LOSS OF POWER CONTROLLER WILL SWAP FROM AUTO TO MANUAL.
REPLACED MANUAL / AUTO CONTROLLER.
8610290271 2
23 CFCU DAMPER FAILURE DESCRIPTION:
INSPECT AND REPAIR AIR OPERATORS AS PER DR
- SMD-M-86-0479.
CORRECTIVE ACTION:
FOUND 2 OF THE 4 AIR ACTUATOR FROZEN.
- REMOVED, DISASSEMBLED AND RELUILT WITH NEW KITS.
REINSTALLED AND TESTED FROM LOCAL PANEL.
l I
1 m_
SALEM UNIT 2 WO NO UNIT EQUIPMENT IDENTIFICATION 8611060130 2
2C DIESEL GENERATOR FAILURE DESCRIPTION:
REPLACE O-RING GASKET ON TOP OF FUEL PUMP.
PUMP IS LEAKING.
CORRECTIVE ACTION:
REPLACED O RING IN 86 FUEL PUMP.
8611060610 2
2B DIESEL GENERATOR FAILURE DESCRIPTION:
FLEX HOSE FROM GOVERNOR TO FUEL RACK HAS A HOLE IN IT.
PLEASE REPAIR.
CORRECTIVE ACTION:
REPLACED HOSE.
8611060709 2
2B DIESEL GENERATOR FAILURE DESCRIPTION:
CRANKCASE EXHAUSTER BASE SUPPORT IS CRACKED AT WELDS.
CORRECTIVE ACTION:
WELDED BRT:0KET SUPPORT TO EXHAUSTER SUPPORT, USE WELD PASSES, BOLTED PANEL, INSTALLED ALL SCREWS, SECURITY PANLE, CLEANED AREA.
8611070593 2
2RS FAILURE DESCRIPTION:
THE RAD HI ALARM GOES OFF ALONG WITH VENTILATION SWAPPING DUE TO A RELAY PROBLEM IN 2R5 CIRCUITRY.
PLEASE REPAIR.
CORRECTIVE ACTION:
REMOVED SHORTED CAPACITOR FROM ACROSS THE N.O. ALARM CONTACTS, TESTED CH ALARM, SAT.
i SALEM UNIT 2
(
WO NO UNIT EQUIPMENT IDENTIFICATION 8611130308 2
REACTOR TRIP BREAKER 4
l FAILURE DESCRIPTION:
PERFORM INSPECTION AND TESTING.OF RL2CTOR TRIP "B" BREAKER IN ACCORDANCE WITH ATTACHED MEMORANDUM.
CORRECTIVE ACTION:
PERFORMED INSPECTION AND TE' TING OF "B" BREAKER S
8611140869
]
2 2SJ13 MOTOR OPERATOR l
FAILURE DESCRIPTION:
REWORK 2SJ13 LIMITORQUE OPERATOR IN ACCORDANCE WITH DEFICIENCY REPORT SMD IE-86-309.
CORRECTIVE ACTION:
REPLACED SPRING PACK AND TESTED VALVE AGAIN, l
EVERYTHING SAT.
i 8611150279 2
BAT TO BIT i
FAILURE DESCRIPTION:
VALVE WILL NOT. STROKE, VERIFIED AIR SIGNAL FROM j
PLEASE REPAIR.
CORRECTIVE ACTION:
REPLACED AIR REGULATOR.
8611150325 2
PRT LEVEL INDICATION FAILURE DESCRIPTION:
FAILED HIGH.
CORRECTIVE ACTION:
PERFORMED CH CAL 2IC-2.10.097.
PERFORMED SENSOR CAL 2IC-2.9.097.
FOUND BAD CARD.
- REPLACED, ADJUSTED TO SPEC.
SALEM UNIT 2 WO NO UNIT EQUIPMENT IDENTIFICATION 8611170636 2
HEAD VENT VALVE FAILURE DESCRIPTION:
NO CLOSED LIMIT INDICATION, PLEASE REPAIR.
CORRECTIVE ACTION:
FOUND CLOSED LIMIT SWITCH RELAY BAD.
INSTALLED NEW ELECTRICAL RELAY ASSEMBLY, SET LIMIT SWITCHES AND HAD VALVE CYCLED FROM CONTROL TO. VERIFY PROPER OPERATION.
i 8611190033 2
21 BAST TEMP INDICATION FAILURE DESCRIPTION:
BEZEL FAILED.
INDICATION CORRECT WHEN BEZEL SWAPPED.
CORRECTIVE ACTION:
REPLACED DEFECTIVE OP AMPL 12 AND PERFORMED CAL.
8611190777 2
INVERTER FAILURE DESCRIPTION:
THE ALTERNATE SHUTDOWN INVERTER WILL NOT POWER UP.
THERE IS POWER UP TO THE INVERTER THROUGH THE POWER SUPPLY BUT THE INVERTER SHOWS NO VOLTAGE.
PLEASE INVESTIGATE AND REPAIR.
CORRECTIVE ACTION:
REPLACED OSCILLATOR COVER AND DK RELAY 8611260503 2
22 FUEL TRANS. PUMP FAILURE DESCRIPTION:
PLEASE INVESTIGATE AND REPAIR CAUSE OF 22 FUEL TRANSFER PUMP CONTROL NOT SWITCHING TO NORMAL MODE ON LOSS OF POWER TO 21 FUEL TRANSFER PUMP.
CORRECTIVE ACTION:
REPLACED 22 FTR OPER RESET RELAY. 'THE RESET COIL WAS OPEN, LOSS OF POWER ON 21 FUEL TRANSFER PUMP.
SALEM GENERATING STATION MONTHLY OPERATING
SUMMARY
- UNIT NO. 2 NOVEMBER 1986 The Unit remained shutdown throughout the period as the refueling outage continued.
Resin removal from the reactor cavity and from the fuel element guide tubes caused a delay in the start of core reload.
The source of the resin found in the reactor cavity and the reactor vessel appears to be the spent fuel demineralizer.
It has been concluded that reverse flow through the demineralizer washed resin into the refueling water storage tank and from there into the reactor cavity and vessel.
Design modifications will be initiated to prevent recurrence.
The Core reload was performed, the head set in place, and stud tensioning was completed, allowing entry into Cold Shutdown (Mode
- 5) on November 14, 1986.
The retubing of 21 Component Cooling Heat Exchanger (<CCHX) has been completed.
In addition to the 996 cracked tubes discovered, the remaining 2400 tubes were replaced due to cracking in the tube sheet area.
A pin hole leak was discovered during the hydro following service water piping inspection in the containment.
The leak was in a three inch schedule 40 stainless steel pipe which was not part of the inspection.
It has been determined that the leak was caused by a localized internal corrosion mechanism at the weld area.
A decision was made to x-ray all service water piping to the containment fan coil units and repair or replace as the results are evaluated.
In addition to refueling, repairs, and modifications a number of eighteen month surveillance tests were completed.
These surveillances included; Manual Safety Injection, ESF Containment Isolation Phase "A",
Leak Rate Testing of Type "C" Valves,.
and the Containment Type "A"
It is currently expected that synchronization will take place December 19, 1986.
.c
^
REFUELING INFORMATION i
DOCKET NO.:
50-311 COMPLETED ~BY:
L.K.
Miller UNIT NAME:
Salem 2 DATE:
December 10, 1986 TELEPHONE:
609/935-6000 EXTENSION:
4497 Month.
November 1986 1.
Refueling information has changed from last month:
YES X
NO 2.
Scheduled date for next refueling:
March 19, 1988 3.
Scheduled date for restart following refueling:
4 May 18, 1988 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 j
Operating Review Committee?
YES NO X
If no, when is it scheduled?
February, 1988 5.
Scheduled date (s) for submitting proposed licensing action:
February 1988 if required 6.
Important licensing-considerations associated with rsfueling:
NONE 7.
Number of Fuel Assemblies:
A)
Incore 193 B)
In Spent Fuel Storage 224 8.
Present licensed spent fuel storage capacity:
1170 l
Future spent fuel storage capacity:
1170 1
9.
Date of last refueling that can be discharged to spent fuel pool assuming the present licensed chpacity:
March 2003 i'
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- en O PSEG Public Service Electric and Gas Company P.O. Box E Hancocks Bridge, New Jersey 08038 Salem Generating Station December 12, 1986 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 1
In compliance with Section 6.9, Reporting Requirements for the Salem Technical Specification, 10 copies of the following monthly operating reports for the month of November 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:sl l
cc:
Dr. Thomas E. Murley Regional Administrator USNRC Region I i
631 Park Avenue King of Prussia, PA 19406 l[
Director, Office of Management U.S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 l
Enclosures 8-1-7.R4 l
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