ML20215H143

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Monthly Operating Rept for Sept 1986
ML20215H143
Person / Time
Site: Salem PSEG icon.png
Issue date: 09/30/1986
From: Miller L, White P, Zupko J
Public Service Enterprise Group
To:
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE)
References
NUDOCS 8610210478
Download: ML20215H143 (16)
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Text

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AVERAGE DAILY UNIT POWER LEVEL Docket No. 50-311 Unit Name Salem # 2 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 0 17 0 2 534 18 0 3 712 19 0 4 702 20 0 5 660 21 0 6 700 22 0 7 713 23 0 8 712 24' 0 9 697 _ _ 25 0 10 695 26 0 11 573 27 0 12 0 28 505 13 0 29 545 14 0 30 933 15 0 31

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OPERATING DATA REPORT Docket No. 50-311 Date ' October 10,1986 Telephone- 935-6000 Completed by Pell-White Extension 4451 Onerating Status-

1. Unit Name Salem No. 2 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)lllT
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) 85%
10. Reasons for Restrictions, if any Due to power distribution on power transformers This Month Year to Date Cumulative
11. Hours in Reporting Period 720 6551 43536
12. No. of Hrs. Reactor was Critical 320.9 5275.6 25601.5
13. Reactor Reserve Shutdown Hrs. 0 0 0
14. Hours Generator On-Line 287.5 5175.2 247 L1. 0
15. Unit Reserve Shutdown Hours 0 0 0
16. Gross Thermal Energy Generated (MWH) 728568 5995328 25571809
17. Gross Elec. Energy Generated (MWH) 210920 5477680 25054160
18. Net Elec. Energy Generated (MWH) 193890 5223944 23758788
19. Unit Service Factor 39.9- 79.0 56.8 I 20. Unit Availability Factor 39.9 -79.0 56.8 l 21. Unit Capacity Factor l (using MDC Net) 24.3 72.1 49.3 i 22. Unit Capacity Factor I (using DER Net) 24.2 71.5 48.9 l
23. Unit Forced Outage Rate 38.6 19.8 35.2
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:

11/28/86

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

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Forecast Achieved 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

UNIT SHUTDOWN AND POWER REDUCTIONS Docket No. 50-311' REPORT MONTH SEPTEMBER 1986 Unit Name salem No.z Date October 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 1 2 Reactor Report Code 4 Code 5 Prevent Recurrence Reactor Trip 502 0826 F 157.6 G 3 ----

IA RELAYX System Nuc Reg. Proceedings 504 0902 F 3.5 D 5 ----

EG TRANSF and Hearings Moisture Separator 506 0902 F 21.7 A 5 ----

HH HTEXCH Reheater 508 0902 F 11.8 A 5 ----

CH PUMPXX Feedwater Pump Nuc Reg. Proceedings 510 0903 F 71.2 D 5 ----

EG TRANSF and Hearings Station Power Auxiliary Station 518 0906 F 585.6 A 5 ----

EG TRANSF Service Transformer Station Power Auxiliary Station 522 0911 F 410.4 A 3 ----

EG TRANSF Service Transformer Station Power Auxiliary Station 532 0930 F 10.4 B 5 ----

EG TRANSF Service Transformer 534 0930 F 5.8 B 5 ----

CH POMPXX Feedwater Pump 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-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)

MAJOR PLANT MODIFICATIONS DOCKET NO.: 50-311 REPORT MONTH SEPTEMBER 1986 UNIT NAME: Salem 2 DATE: October 10, 1986 COMPLETED BY: L. Miller TELEPHONE: 609/339-4497

  • DCR NO. PRINCIPAL SYSTEM SUBJECT 2EC-1305 Chem & Volume Control Buttwelding of the valves (associated with the test, vent and drain connections along the centrifugal and reciprocating charging pump suction and discharge lines &

CVC letdown line) to header making each of them a "one-piece connection". The second valve on all vent and drain connections shall be eliminated and replaced with a short nipple and screwed cap.

2EC-1564 Fire Protection Install smoke detectors in areas designated P2C-1, P2C-3, P2C-4, P2C-5, P2F-1 and P2G-1.

2EC-1660 Chilled Water Install a 4" isolation gate System valve in the chilled water supply header immediately upstream of the 4" C.W. supply line to 2CH-62 and a 4" isolation ball valve in the chilled water return header downstream of the 4" C.W.

return from 2CH-76. This will assure uninterrupted C.W.

supply from Unit 1 to the counting room in event of Unit 2 C.W. pump shut down or securing the C.W. system for other DCR implementation 2EC-1677A Reactor Coolant Replace Reactor Coolant System narrow range resistance temperature detectors with environmentally qualified elements.

  • Design Change Request

MAJOR PLANT MODIFICATIONS REPORT MONTH SEPTEMBER 1986

  • DCR NO. PRINCIPAL SYSTEM SUBJECT i

2EC-2071 Aux Feedwater System Provide low suction pressure trip for each AFW pump in order to preclude inadvertent actuation additional circuitry will be required. This additional circuitry will allow actuation only during periods when a " tornado warning" is in effect.

2SC-0796 Containment Area. Design and locate 4 tool boxes needed to store tools to be used in case of an airlock malfunction. Two tool boxes must be located in the airlocks, 1 in the 130' El.

airlock, the other 2 must be located in the containment near the airlocks. List of tools to'be stored in~ tool box is attached.

Design Change Request

MAJOR PLANT MODIFICATIONS DOCKET NO: 50-311 REPORT MONTH - SEPTEMBER 1986 UNIT NAME: SALEM 2 DATE: October 10,1986 COMPLETED BY: L. Miller TELEPHONE: (609)339-4497

  • DCR SAFETY EVALUATION 10 CFR 50.59 2EC-1305 This modification increased the conservatism of the design by reducing the possibility of future occurrences of cracks and breaks at the test, vent, and drain connections. The resistance to unexpected shock load has also been increased.

This modification does not alter any plant process or discharge or affect the existing plant impact. No unreviewed safety or environmental questions are involved.

2EC-1564 This modification expanded the' existing fire detection system to cover additional areas of the plant. The design is consistent with the previously existing fire detection system and does not affect any' safety related systems or equipment or affect the safe shutdown of the plant. This modification does not alter any plant process or discharge or affect the environmental impact of the plant. No unreviewed safety or environmental questions are involved.

2EC-1660 The new isolation valves used in the chilled water supply and return headers were safety related, nuclear grade, hydrostatically tested, and leakage tested prior to installation. This modification does not alter any plant process or discharge or affect the environmental impact of the plant. 'No unreviewed safety or environmental questions are involved.

2EC-1677A This design change enhances plant safety by reducing the closing response time 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 plant process or discharge and does not affect the existing plant impact. No unreviewed safety or environmental questions are involved.

Design Change Request

MAJOR-PLANT MODIFICATIONS- DOCKET NO: 50-311 REPORT MONTH - SEPTEMBER 1986 UNIT NAME: SALEM 2 DATE: October 10,1986

-COMPLETED BY: L. Miller TELEPHONE: (609)339-4497 i

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  • DCR SAFETY EVALUATION 10 CFR 50.59 2EC-2071 This design change provides separate low suction pressure trip functions for each of the auxiliary feedwater pumps, thereby assuring the required separation between the redundant pump control circuits. This modification does not alter any 4 plant process or discharge and it does not affect ~

the existing plant impact. No unreviewed safety or environmental questions are involved.

2SC-0796 This modification allows someone trapped inside the containment or the airlock itself to free a i

{ jammed airlock door. This could not be done from outside the airlock. If the tools were used to defeat the airlock door interlock system, the i control room would automatically receive a j

signal. The Technical Specifications address such a scenario. This modification does not alter any plant process or discharge and does not i affect the existing plant impact. No unreviewed j safety or environmental questions are involved, t

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  • Design Change Request i

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PSE&G SALEM GENERATING STATION -

SAFETY RELATED WORK ORDER LOG SALEM UNIT 2 WO NG UNIT EQUIPMENT IDENTIFICATION 8609220516 2 21/22 SG WIDE RANGE RECORDER FAILURE DESCRIPTION: THE CHART'S DRIVE MOTOR DOES NOT MOVE THE PAPER.

PLEASE REPAIR.

CORRECTIVE ACTION: REPLACED BAD CHART DRIVE FROM RECORDER S/N C705247434 WITH CHART DRIVE FROM RECORDER S/N C205247413.

VERIFIED PROPER OPERATION.

8609120082 2 SHUNT RELAY B FAILURE DESCRIPTION: PLEASE VERIFY SHUNT RELAY B TRIP-TRIP RESPONSE TIME ON 23 RCL LO FLOW; P-8 RX TRIP. NEEDED FOR ADl6 CLOSE OUT.

CORRECTIVE ACTION: COMPLETED 2IC-18.1.011 SAT. SHUNT RELAY B TRIP =

6 CYCLES.

8609100596 2 S/W PIPING FAILURE DESCRIPTION: PLEASE APPLY TEMP. PATCH TO S/W PIPING DOWN STREAM OF 22 SW 122 AND PERMANENTLY REPAIR DURING OUTAGE.

CORRECTIVE ACTION: REMOVED DEFECTIVE SECTION OF 20" SW PIPE. FABRICATED NEW SPOOL IAW DR ALL WELD NDE BY BRANCH SAT,

. -HYDRO SAT.

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1 SALEM UNIT 2 UO NO UNIT EQUIPMFNT IDENTIFICATION 8609030849 j 2 23 CHARGING PUMP ROOM COOLER INLET

' FAILURE DESCRIPTION: INLET VALVE TO 23 CHARGING PUMP ROOM COOLER HAS BEEN DISCONNECTED RENDERING THE ROOM COOLER INOPERABLE.

1 IT APPEARS THAT WORK WAS STARTED BUT STOPPED. THIS

! IS A SEVEN DAY ACTION STATEMENT THEN 23 CHARGING PUMP IS INOPERABLE. PLEASE REPAIR.

CORRECTIVE ACTION: NONE COVERED BY PRIOR DR AND ENGINEERING EVALUATION.

REPAIRS COVERED BY MAINTENANCE WO PENDING PARTS.

8609030415 3

2 22 SG LEVEL CHANNEL l

1 FAILURE DESCRIPTION: 22 SG LEVEL CHANNEL I INDICATING DIFFERENTLY THAN OTHER CHANNELS. PLEASE INVESTIGATE AND REPAIR.

CORRECTIVE ACTION: SETPOINT FOR 2LC-529A/B OUTPUT CHANGE ROM 67% TO 61% AS PER DR SMD 86-267 SAFETY EXHAUSTION LETTER S-2-R100 TSE. QA VERIFIED SAT.

J 8608251604 2 21 SW HEADER OVERPRESS CONTROLLER

! FAILURE DESCRIPTION: WHEN THE SW49 GOES OPEN THE SW305 SEES A 105#

l DELTA P AND THEN GOES FULLY OPEN. THIS DELTA P IS 1 TOO HIGH FOR BOTH VALVES BEING FULLY OPEN. PLEASE j INVESTIGATE THE CONTROLLERS FOR BOTH VALVES.

] CORRECTIVE ACTION: AFTER INSPECTION, FOUND LINKAGES ON 21SW305 RUSTED l

AWAY. REPLACED BROKEN LINKAGE WITH NEW SPARE PARTS l LISTED. ALSO FOUND 2PA-9222 21 SW BYPASS PRESS I

TRANSMITTER OUT OF CAL. TRANS CAL COVERED UNDER WORK ORDER 86-09-09-057-4.

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SALEM UNIT 2 WO NO UNIT EQUIPMENT IDENTIFICATION 8608230127 2 PRI WATER FLOW CONTROL FAILURE DESCRIPTION: VALVE EXCEEDED PREVIOUS STROKE TIME BY GREATER THAN 25% DURING STROKE TIME TEST. PLEASE INVESTIGATE AND REPAIR.

CORRECTIVE ACTION: RE: SP (O) 4. 0. 5-V-CV COS 1-2 STROKED VALVE AND CHECKED LIMIT SWITCH.

8608210401 2 SUCTION FLANGE FAILURE DESCRIPTION: THERE IS A LEAK ON THE SUCTION FLANGE OF THE CHARGING PUMP. PLEASE REPAIR DURING OUTAGE.

CORRECTIVE ACTION: REPLACED GASKET, CLEANED FLANGE AREA.

8608181746 2 N44 FLUX RECORDER FAILURE DESCRIPTION: CHART DRIVE BROKE.

CORRECTIVE ACTION: REPLACED CHART DRIVE MOTOR. RECORDER PLACED INSERVICE AND OPERATING. SAT.

8607252534 2 CRANE HOOKS NDE FAILURE DESCRIPTION: ARRANGE FOR A MAGNETIC PARTICLE EXAMINATION OF ALL UNIT 2 CRANE HOOKS.

CORRECTIVE ACTION: PERFORMED NDE OF U/2 CASK HANDLING, POLAR MAIN AND AUX HOOKS, FUEL HANDLING AND CHERRY PICKER HOOKS BY BRANCH.

SALEM UNIT 2 WO NO UNIT EQUIPMENT IDENTIFICATION 8607212591 2 22SW42 FAILURE DESCRIPTION: PERFORM AN INSPECTION OF THE CAVITROL BUNDLE IN VALVE 22SW42 IAW FIELD DIRECTIVE S-C-M600-MFD-218 REV. O.

CORRECTIVE ACTION: REMOVED AND INSPECTED VALVE. PUT BELZONA ON DAMAGED PIPE LINING. REINSTALLED VALVE.

8607170031 2 DIESEL FAILURE DESCRIPTION: RUBBER GASKET ON #8 CYCLINDER INJECTION COVER ON LEFT SIDE IS BROKEN AND HANGING OUT. PLEASE REPAIR.

CORRECTIVE ACTION: REPLACED GASKET.

8607160095 2 AUX FEED FLOW FAILURE DESCRIPTION: CONSOLE INDICATION INDICATES 1.5E4 LBS/HR FLOW WITH NO PUMPS IN SERVICE. PLEASE REPAIR.

CORRECTIVE ACTION: EQUALIZED 2FA-1087Z. WHEN RETURNED TO NORMAL STILL READING HIGH. RECALIBRATED 2FA-3969-2 ADJUSTED DROP OUT RELAY. CHECKED INDICATOR FOR 2 DAYS SAT.

8607010867 2 EXHAUST LEAK FAILURE DESCRIPTION: EXHAUST LEAK BEHIND 3 & 4RCYL. EXHAUST LEAK BEHIND TURBOCHARGER.

CORRECTIVE ACTION: REPLACED GASKETS AND FAN BELLOWS ON TURBO CHARGER AND GASKETS ON 3 & 4 CYL EXHAUST.

SALEM UNIT 2 -

WO NO UNIT EQUIPMENT IDENTIFICATION 8606170062 2 2B DIESEL GENERATOR FAILURE DESCRIPTION: THE 4-L CYLINDER HAS A CHROMATED WATER LEAK. PLEASS REPAIR. LEAK IS IN THE JACKET WATER HEATER.

CORRECTIVE ACTION: REMOVED, CLEANED AND INSPECTED, REPLACED JACKET WATER HEATER BY CYLINDER. INSTALLED NEW JACKET WATER HEATER.

8606060283 2 2F GROUP BUS FAILURE DESCRIPTION: RELAY DEPT. TO MAINTAIN 2F GROUP BUS BREAKER FAILURE RELAYS 22FSD, 2BFGD, 2R14.

CORRECTIVE ACTION: REF: TECH SPEC 3.8.3.1 TESTING DONE IAW CORP RELAY MANUAL AND ATTACHED TEST SHEET.

8605220406 2 CASK HANDLING CRANE UNIT 2 FAILURE DESCRIPTION: PERFORM AND DOCUMENT THE FREQUENT CRANE INSPECTION IAW M2. OHSA AND NML INSPECTION REQUIREMENT.

CORRECTIVE ACTION: NON OUTAGE INSPECTED CRANE AS PER MAINT PROCEDURE M-2.

8605190671 2 21CV159 FAILURE DESCRIPTION: REPLACE DIAPHRAGM, 0-RINGS DWG 205328 SH 1 G-1,2 CORRECTIVE ACTION: DISASSEMBLED VALVE REPLACED WITH NEW BONNETT AND DIAPHRAGM.

SALEM UNIT 2

  • WO NO UNIT EQUIPMENT IDENTIFICATION 8603031223 2 2CV272 CHG LINE BYPASS FAILURE DESCRIPTION: PLEASE INSTALL NEW PACKING GLAND FLANGE IN ACCORDANCE WITH DR SMD 85-3836. REPACK DWG 205328 SH2 D-10 CORRECTIVE ACTION: THE TEMP FIX OF THE PACKING GLAND FOLLOWER WILL BE CONSIDERED A PERMANENT FIX IAW DR 85-3836.

0099185008 2 2R19B FAILURE DESCRIPTION: RAD MONITOR NOT SCANNING. PLEASE REPAIR.

CORRECTIVE ACTION: CHANNEL WAS FOUND LOCKED HIGH. POWERED DOWN CHANNEL AND WIPED RAMS. POWERED UP AND VERIFIED SETPOINTS AS PER PAGE 16 OF CHANNEL CAL PROCEDURE 2IC-4.1.030 CHANNEL SAT.

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l SALEM GENERATING STATION i MONTHLY OPERATING

SUMMARY

- UNIT NO. 2 l SEPTEMBER 1986 SALEM UNIT NO. 2 l The Unit began the period in startup following investigation of the events that led to the blackout loading of the diesel generators. The investigation revealed that a transient stability analysis of the plant electrical loads has not been performed since June 1981. ,

Subsequently, plant loads have been modified on the basis of a static loading analysis only. Both Salem Units will remain at reduced power levels until a comprehensive design analysis of the electrical distribution system is performed. On September 1, 1986 the Unit returned to service. On September 2, 1986, No. 21 Steam Generator Feed Pump tripped on overspeed due to a failed diode in the governor control circuit. The circuit was repaired and the Unit brought to seventy four percent (74%) power. On September 5, 1986, power was reduced to sixty eight percent (68%) due to a bearing problem on #22 Heater Drain Pump. The problem was corrected and the Unit returned to seventy five percent (75%) power the same day. On September 11, 1986 at 1858 hours0.0215 days <br />0.516 hours <br />0.00307 weeks <br />7.06969e-4 months <br />, the Unit tripped due to a loss of power to the "F" and "G" 4KV group busses which supply power to Nos. 23 and 24 Reactor Coolant Pumps. Investigation revealed a failure of #22 Station Power Transformer and a fault on the 2F 230 volt transformer. Both the 230 volt-and No. 22 Station Power Transformers have been replaced.

Following installation and testing, the Unit was returned to service on September 27, 1986, with power limited to sixty five percent (65%)

due to steam generator feed pump problems. The Unit continued to operate at sixty five percent (65%) power for the remainder of the period.

REFUELING INFORMATION DOCKET NO.: 50-311 COMPLETED BY: L.K. Miller UNIT NAME: Salem 2 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: October 3, 1986
3. Scheduled date for restart following refueling: November 26, 1986
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 Operating Review Committee?

YES NO X If no, when is it scheduled? October 1986

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

None required i

6. Important licensing considerations associated with refueling:

NONE

7. Number of Fuel Assemblies:

A) Incore 193 B) In Spent Fuel Storage 140

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 2003 8-1-7.R4 L-

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4 0 PSEG Public Service Electnc and Gas Company P.O. Box E Hancocks Bridge, New Jersey 08038 Salem Generating Station October 10, 1986 j Director, Office of Inspection a'nd Enforcement U.S. Nuclear Regulatory Commission Washington, DC 20555

Dear Sir:

MONTiiLY OPERATING REPORT SALEM NO. 2 DOCKET NO. 50-311 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 September 1986 are being sent to you.

Average Daily Unit Power Level 1

Operating Data Report.

Unit Shutdowns and Power Reductions i Major Plant Modification Safety Related Work Orders l Operating Summary

, Refueling Information i

Sincerely yours, J. . o, Jr.

G era Manager - Salem Operations JR:sl

cc
Dr. Thomas E. Murley i Regional Administrator USNRC
Region I 631 Park Avenue King of Prussia, PA 19406

.l Director, Office of Management U.S. Nuclear Regulatory Commission Document Control Desk i Washington, DC 20555 i Enclosures 8-1-7.R4 i

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' l The Energy People l l

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