ML20112H019

Monthly Operating Rept for Dec 1984

ML20112H019
Person / Time
Site:	Salem
Issue date:	12/31/1984
From:	Ronafalvy J, Zupko J Public Service Enterprise Group
To:	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE)
References
NUDOCS 8501160600
Download: ML20112H019 (13)

Text

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AVERAGE DAILY UNIT POWER LEVEL Docket No. 50-272 Unit Name Salem # 1 Date J an . 10,1985 Completed by J. P. Ronafalvy Telephone 609-935-6000 Extension 4455 Month December 1984 Day Average Daily Power Level Day Average Daily Power Level (MWe-NET) (MWe-NET) 1 773 17 1078 2 873 18 1081 3- 945 19 1098 4 993 20 1082 5 1044 21 627 6 1033 22 1032 7 1081 23 1067 8 1073 24 0 9 1090 25 0

'10 1076 26 0 11 865 27 0

.12 1048 28 0 13 1075 29 168 14 1101___ 30 445 15 1081 31 623 16 1081 P.-8,1-7 R1 6

$6 \

i ii 8501160600 841231 PDR ADOCK 05000272 R PDR

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OPERATING DATA REPORT  ;

Docket No.50-272 L Date Jan. 10, 1985 Telephone 935-6000 t Completed by J. P. Ronafalvy Extension 4455 Operating Status

1. Unit Name Salem No. 1 Notes

'2. Reporting Period December 1984

3. Licensed Thermal Power (MWt) 3338

4. Nameplate Rating (Gross MWe) 1135

5. Design. Electrical _ Rating (Net MWe) 16F6

6. Maximum Dependable Capacity (Gross MWe)1124

7. Maximum Dependable Capacity (Net MWe) 1079

8. If Changes Occur.in Capacity Ratings (items 3 through 7) since Last t

Report, Give Reason N/A N/A

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9.

1 Power Level to Which Restricted, if any (Net MWe)

10. Reasons for Restrictions, if any N/A This Month Year to Date Cumulative

11. Hours-in Reporting Period 744 8784 65809  ;

12.lNo. of Mrs. Reactor was Critical 627.6 2672.3 35823.5

'13. Reactor Reserve Shutdown Hrs. 0 54.5 3088.4 34158.6

14. Hours Generator On-Line 610.6- 2380.7

• L15'- Unit Reserve' Shutdown Hours

. 0 0 0

16. Gross Thermal Energy Generated (Bom) _ 1855997 6948626' 102767997

17. Gross.Elec. Energy Generated

. (POm) .

626960- 2300950 -33916050

, 18.< Net:Elec. Energy Generated (MWH) 596998 2126670 32097982 1- 19. Unit Service Factor -82.1 27.1 51.9

20. Unit:Ava'ilability Factor-82.1 27.1 51.9-

.:21. Unit' Capacity Factor _

(using MDC Net) 74.4 22.4 45.2

22. Unit Capacity Factor-(uaing DER . Net) 73.6 22.2- 44.7 23.-Unit Forced Outage Rate' 4.5 62.4 33.2

- 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:

a 1-1-85

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 ,

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im UNIThSHUTDOWN AND POWER REDUCTIONS- Dock 3t No.50L272' REPORT MONTH Dactmber 1984 Unit Nam 3 Solen No.1 Date Jan. 10,1985 Completed bys 'J.P. Ronafalvy Telephone' 609-935-6000 s Extension 4455 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 EH System Turbine 84-242 12-01 F' '8.0 A 5 -

HA INSTRU Governing Main. Bus Cooling '84-274 12-11 F 5.7 -A 5 -

EB BLOWER Fan Bearing 84-294 12-23 F 26.0' G 3 -

ZZ ZZZZZZ Maintenance Error 1 84-296 12-25'- F -104.7 B 4- -

HA ZZZZZZ Generator Inspection Nuclear Core 84-298 12-29 F 6.5' B 5 - RC ZZZZZZ Physics Test Nuclear Core 84-300' 12 F' 127.3 B 5 - RC- ZZZZZZ Physics Test Feedwater Regulating 84-302- 12-31 F 2.6 A 3 - HH VALVEX Valve 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.: 50-272 REPORT MONTH December 1984 UNIT NAME: Salem 1 DATE: January 10, 1984 COMPLETED BY: J. Ronafalvy TELEPHONE: 609/339-4455

• DC R N O . PRINCIPLE SYSTEM SUBJECT lEC-1074 Main Feedwater Pumps Add an additional control for and Turbines individual steam generator feed pumps which will have a setpoint of 190 psig, with no time suppression.

1EC-1565 Chilled Water Install a 10 PSIG relief valve at the chilled water expansion tank. Inspect and repair nitrogen pressure reducing valve (lCH-147) by removing the bonnet.

lEC-1600 Circulating Water Material upgrade the No. 11A and 12B Circulating Water Pumps internal assembly to Ni resist to improve pump reliability.

lEC-1847 Generator Rewind of No. 1 Generator.

1EC-1901 Reactor Coolant Provide break flanges to the leak off line from valve 1PS 28.

ISC-0799- Auxiliary Annunciator Provide a permanent fix to repair and replace existing obsolete equipment for the auxiliary annunciator.

1SC-0844A Aux. Turbine Gantry Provide instrumentation to Cranes measure wind speed and direction, in the immediate vicinity of the turbine crane.

Transmitter mounted atop crane, with indication local in operator cab.

MAJOR PLANT MODIFICATIONS DOCKET NO.: 50-272 REPORT MONTH December 1984 UNIT NAME: Salem 1 DATE: January 10, 1984 COMPLETED BY: J. Ronafalvy TELEPHONE: 609/339-4455

• DCR NO. PRINCIPLE SYSTEM SUBJECT ISC-0875 Turbine Area Crane Provide instrumentation to measure wind speed and direction in the immediate vicinity of the turbine crane.

Transmitter mounted atop crane with local indication in operators cab.

1SC-0948 Waste Gas Add two test connections to the waste gas system. One test connection between 1WG6 and 1WL99 on vent header and one test connection between 11 and 12WG27 and 11, 12, 13, 14WG33 valves on the HP header.

ISC-1161 Reactor Coolant Pump Replace 11, 12, 13 and 14 RCP Motors motor resistance rings with new improved design.

1SC-1163 Reactor Coolant Pump Replace copper tubing to 11, Motors 12, 13, and 14 RCP motor thrust bearing shoes.with stainless steel tubing.

1SC-ll65 Reactor Coolant Pump Modify 11, 12, 13 and 14 RCP Motors motor thrust runner pumping ring to new Westinghouse design - (retrofit) .

MAJOR PLANT MODIFICATIONS DOCKET NO.: 50-272 REPORT MONTH DECEMBER 1984 UNIT NAME: Salem 1 DATE: January 10, 1985 COMPLETED BY: J.-Ronafalvy TELEPHONE: 609/339-4455

• DCR NO. SAFETY EVALUATION 10 CFR 50.59 1EC-1074 This DCR adds an additional trip for the SGFP's. It does not affect existing circuitry. No unreviewed safety or environmental questions are involved.

1EC-1565 This change does not jeopardize the pressure retaining boundary nor does it impact the operation / basic design criteria of the Chilled Water System. No unreviewed safety or environmental questions are involved.

1EC-1600 This partial change-out of the Circulating Water Pumps 11A and 12B does not affect the present safety analysis nor does it create any new hazards. The basis for the Technical Specifications remains unchanged. No unreviewed safety or environmental questions are involved.

.1EC-1847 This change does not affect any safety related equipment.

- .The material change will prevent hydrogen embrittlement cracking. No unreviewed safety or environmental questions are involved.

1EC-1901 The addit' ion of break flanges does not alter-the original design concept of the leak off system. Also, page 53F of

-Piping Specification 1553, 61-6200 states, "the piping connections are welded except where flanged connections are necessary at equipment to facilitate maintenance". No unreviewed safety or. environmental questions are involved.

.1SC-0799 .The' annunciator equipment being modified.was not-used in the calculations for any presently performed safety analysis. -Its failure does not constitute a new hazard:

not previously analyzed. :The equipment does not enter into the logic for 'the basis of any of- the Technical Specifications. No unreviewed safety.or environmental questions are involved.

• DCR: - Design > Change -Request u .:

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• DCR NO. SAFETY EVALUATION 10 CFR 50.59 ISC-0844A Installation of the wind speed indicator and other instrumentation in the Auxiliary Turbine Gantry Crane will not affect the safe shutdown of the reactor nor will it create a new fire hazard. Implementation of this device will comply with OSHA standards for cranes (OSHA Art. No.

1910.179). No unreviewed safety or environmental questions are involved.

1SC-0875 Installation of the wind speed indicator and other

, instrumentation in the Turbine (Dresser) Gantry Crane will

+-

not affect the safe shutdown of the reactor nor will it ,

create a new fire hazard. Implementation of this device will comply with OSHA standards for cranes (OSHA Art. No.

. 1910.179). No unreviewed safety or environmental questions are involved.

1SC-0948 The Controls Division changes are drawing changes only.

This installation does not modify any control logic of affect any safety related equipment.- No unreviewed safety-

, o or environmental questions are involved.

ISC-1161 Implementation of this DCR does not affect, add, delete,

!. or_ alter any safety related system. The modification will not change the plant process or discharge-and will not

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

1SC-1163 Implementation of this DCR does not add, delete, or alter any safety related system. The modification will not change the plant process or discharge and will not . affect.

the: existing plant impact. tk) unreviewed safety or environmental questions are involved.

i-

l. 1SC-1165 Implementation of this DCR does not add, delete, or alter i: any safety related system. The modification will not change the plant process or discharge and will not affect the existing plant' impact. No unreviewed-safety or environmental questions are involved.

• DCR - Design Change Request

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r PSE&G SALEM GENERATING STATION SAFETY RELATED WORK ORDER LOG .

SALEM UNIT l'-

. WO NO DEPT UNIT EQUIPMENT IDENTIFICATION 11-24-007-0

• SMD 1 NO. 12 SW PUMP STRAINER-FAILURE DESCRIPTION:- SHAFT IS NOT ROTATING IN MANUAL OR AUTOMATIC- ,

CORRECTIVE ACTION: REPLACED SHEAR KEY AND BOTTOMS SHOES 0099121638 SMD 1 11SW236 - LINE; LOCATED:BY 11 CFCU FAILURE DESCRIPTION: THE LINE IS SPRAYING CORRECTIVE ACTION: NEW PIPE FLANGE AND VALVE GASKET INSTALLED 0099121671-SMD 'l #13 SERVICE WATER PUMP STRAINER FAILURE DESCRIPTION:. DIAPHRAGM LEAK-CORRECTIVE ACTION: DIAPHRAGM REPLACED 0099128420 SIC' 1 (12 S/G FEEDWATER FLOW CHANNELS FAILURE: DESCRIPTION: CHANNELS ARE PEGGED HIGH CORRECTIVE ACTIVE: REPLACED 1FM520D ISOLATOR 0099119838 SIC 1 $12 S/G FEEDFLOW CHANNEL' II FAILURE DESCRIPTION: ' CHANNEL STEPPED OUT APPROXIMATELY 20% HIGHER THAN STEAM FLOW CORRECTIVE-ACTION: REPAIRED 1 SIGNAL ISOLATOR (FAILED HIGH)

SALEM UNIT l-

WO NO DEPT UNIT EQUIPMENT IDENTIFICATION .

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i 0099119781 SIC 1 VALVE 13MS10 l

FAILURE DESCRIPTION: VALVE BLOWING STEAM .

CORRECTIVE ACTION: PILOT RELAY IN POSITIONER STICKING IN "OPEN" -

POSITION, EXERCISED RELAY ,

l. 84-10-12-003-8 t SIC- 1 11MS10 FAILURE ' DESCRIPTION : SETPOINT DRIFTS MAKING VALVE UNUSABLE CORRECTIVE ACTION: REPLACED. SERVO AMPLIFIER, CLEANED POTS, ALIGNED

' SHAFTS ON POTS TO SERVO MOTOR-t 0099099331~

SCH. 1 VALVE'14SS93 l FAILURE DESCRIPTION: VALVE DOES NOT MOVE OFF OF CLOSE-LIMIT h . I CORRECTIVE ACTION: REPLACED LIMIT SWITCH i  !

0099028824 SIC' 1" RMS CHANNEL 1R35 i FAILURE DESCRIPTION: CHANNEL INDICATES OFFSCALE LOW 2

CORRECTIVE ACTION: REPLACED.01 ON MBl;' REPLACED PB2 .

i- 04-11-21-020-1 S. V. 181 SUPPLY FOR 14SW15

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SIC- 1 a FAILURE DESCRIPTION: SOLENOID VALVE IS. BLOWING i

] CORRECTIVE ACTION: REBUILT SOLENOID VALVE AND REPLACED COIL ,

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SALEM UNIT.1.

WO NO DEPT UNIT EQUIPMENT IDENTIFICATION-0099119820 SIC 1 SSPS TRAIN B FAILURE DESCRIPTION: PROBLEM WHEN TESTING JA60 2 (ASSOCIATED WITH SEC 1A) ,

CORRECTIVE ACTION: RESET K602; MOVED CONTACT ASSEMBLY 0099021889 SMD. 1 #15 CONTAINMENT FAN COIL UNIT FAILURE DESCRIPTION: WATER DRAIN FLOW ALARM IS ANNUNCIATED (UNIT OUT OF SERVICE)

CORRECTIVE-ACTION: REPLACED DEFECTIVE RELAY (2-3) 84-12-05-087-8 SMD 1 #13 CHARGING PUMP

. FAILURE DESCRIPTION: SEAL TANK OVERFLOWING CORRICTIVE ACTION: REPAIRED VALVE ICV 59 (DIAPHRAGM REPLACED) 0099026236 SIC 1 1R29.

FAILURE DESCRIPTION: CHANNEL EXPERIENCING ELECTRICAL SPIKING CORRECTIVE ACTION: REPLACED DETECTOR 84-l'0-09-043-1 SMD 1 CONTROL AREA ELEVATOR EXHAUST FAN BREAKER 1EY3AX5D FAILURE DESCRIPTION: TRIPPING OUT CORRECTIVE ACTION: -REPLACED DEFECTIVE MOTOR 84-12-12-025-6 SMD 1 14 SERVICE WATER PUMP CLOSING COIL FAILURE DESCRIPTION: BURNED COIL CORRECTIVE ACTION:- REPLACED BREAKER AND CLOSING COIL

[ .

. SALEM GENERATING STATION MONTHLY OPERATING

SUMMARY

- UNIT NO. 1 DECEMBER 1984 ,

4 SALEM NO. 1 4

The period began with the Unit at 85% power. Monitoring of the Electro-Hydraulic Control (EHC) System and evaluation of the Generator

, Stator Water Coil delta T readings continues. On 12/01/84, at 1350 hours0.0156 days <br />0.375 hours <br />0.00223 weeks <br />5.13675e-4 months <br />.the Unit experienced a load reduction to 55% due to No. 13 i Governor Valve closing. The valve closed due to a broken wire in the

, linear voltage differential transformer (LVDT). After repairing the

wire, Unit power was returned to 85% power late on 12/01/84. On

! '12/03/84 at 1600 hours0.0185 days <br />0.444 hours <br />0.00265 weeks <br />6.088e-4 months <br />, Unit power was increased to.95% as a result of additional guidance received from Westinghouse regarding Stator Water Coil differential temperature readings. On 12/04/84 at 1533 hours0.0177 days <br />0.426 hours <br />0.00253 weeks <br />5.833065e-4 months <br />,

-power was reduced to 82% due to No. 11 Governor valve closure. The 4 valve closed due to a defective card (Mixing Amp) in the test circuit

-for the valve. The card was replaced and the Unit returned to 95%

power. The Unit reached 100% indicated power operation on 12/5/84 at

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2130 hours0.0247 days <br />0.592 hours <br />0.00352 weeks <br />8.10465e-4 months <br />. On 12/6/84 power was reduced due to an excessive packing leak on No. 11 Heater Drain Pump. The leak was repaired and the Unit

- returned _to full power at 2045 hours0.0237 days <br />0.568 hours <br />0.00338 weeks <br />7.781225e-4 months <br />. On 12/11/84 at 0850 hours0.00984 days <br />0.236 hours <br />0.00141 weeks <br />3.23425e-4 months <br /> the

, Unit decreased power to.59% due to repairs required on one of two Generator Bus Duct Cooling fans. With completion of repairs (replaced '

. motor bearings), the Unit was returned to full power on 12/12/84 at

! 0614 hours0.00711 days <br />0.171 hours <br />0.00102 weeks <br />2.33627e-4 months <br />. . On 12/18/84, the Overspeed Protection Controller- (OPC)

System was returned to normal operation. On 12/23/84 at 1900. hours,

! . power was reduced to .75% because the flux map - (required- for the

! Quadrant Power Tilt Ratio (QPTR) calculation) .could not be. completed

- within'the required tim 9 interval due.to malfunctions in the Incore

) . Instrumentation. The Unit tripped at 2158 hours0.025 days <br />0.599 hours <br />0.00357 weeks <br />8.21119e-4 months <br /> on 12/23/84 due to

~

- indicated Over Temperature Delta T. The cause of the trip was due to

- a technician error while adjusting Nuclear Instrumentation required by-Technical Specifications as a result of_the Incore Instrumentation

!  : problems.- The Unit remained in hot standby (Mode 3) in ' order tcr perform a crawl-through of the Main Generator and completion of j  ; repairs to No. 12 Steam Generator Feed Pump Turbine 1 Steam Chest. The

-Unit was' brought critical (Mode II operation) on 12/28/84 at 1543

j. hours and synchronized on 12/29/84'at 0844 hours0.00977 days <br />0.234 hours <br />0.0014 weeks <br />3.21142e-4 months <br />.- On 12/31/84 at 2123 hours0.0246 days <br />0.59 hours <br />0.00351 weeks <br />8.078015e-4 months <br />, the Unit tripped due to.No.11 Steam Generator Steam Flow / Feed Flow mismatch combined with Steam Generator Low Level. This mismatch k

was a result of partial closure-of No. 11. Steam Generator Feedwater Control valve 11BF19 caused by a malfunctioning solenoid. Following replacement of the solenoid the Unit was returned- to service on 1/1/85 atz2017 hours.with full power operation expected on 1/2/85.

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REFUELING INFORMATION DOCKET NO.: 50-272 COMPLETED BY: J. Ronafalvy _

UNIT NAME: Salem 1 DATE: January 10, 1985 TELEPHONE: 609/935-6000 EXTENSION: 4455 Month December 1984

1. Refueling information has changed from last month:

YES NO X

2. Scheduled date for next refueling: February 22, 1986

3. Scheduled date for restart following refueling: May 4,1986

4. A) Will Technical Specification changes or other license amendments be required?

YES NO NOT DETERMINED TO DATE 10/1/84 B) Has the reload fuel design been reviewed by the Station Operating Review Committee?

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

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

January 1986 if required

6. Important licensing considerations associated with refueling:

NONE

7. Number ot Fuel Assemblies:

A) Incore '193 B) In Spent Fuel Storage 296

'8. 'Present licensed spent fuel storage capacity: 1170 Future spent. fuel storage capacity: 1170

.9.. -Date of last refueling that can be discharged toispent fuel pool assuming the_present licensed capacity: September 2001 8-1-7.R4

O PSEG Public Service Electric and Gas Company P.O. Box E Hancocks Bridge, New Jersey 08038 Salem Generating Station January 10, 1985 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 December 1984 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: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 of 8-1-7.R4

' I The Energy People 05 2189 (20W l191