ML20155E313

Monthly Operating Rept for Mar 1986

ML20155E313
Person / Time
Site:	Salem
Issue date:	03/31/1986
From:	White P, Zupko J Public Service Enterprise Group
To:	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE)
References
NUDOCS 8604170561
Download: ML20155E313 (15)

Text

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AVERAGE DAILY UNIT POWER LEVEL Docket No. 50-311 Unit Name Salem # 2 Date April 10,1986 Completed by Pell White Telephone 609-935-6000 Extension 4455 Month March 1986 Day Average Daily Power Level Day Average Daily Power Level (MWe-NET) (MWe-NET) 1 1082 17 1056 2 1085 18 1077 3 1103 19 1087 1 1094 20 1094 5 1092 21 1077 6 1089 22 919 7 1089 23 707 8 1053 24 1057 9 1086 - 25' 1084 10 1083 26 1089 11 1091 27 1087 12 1075 28 1088 13 1002 29 1064 14 1030 30 1076 15 981 31 1092 16 1085 Pg. 8.1-7 R1 8604170561 86033131 DR ADOCK 0

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OPERATING DATA REPORT CORRECTFD COPY Docket No. 50-311 Date April 10,1986 Telephone 935-6000 Completed by Pell White Extension 4455 Operating Status

1. Unit Name Salem No. 2 Notes

2. Reporting Period March 1986

3. Licensed Thermal 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 744 2160 39145

12. No. of Hrs. Reactor was Critical 744 1715.4 22041.2

13. Reactor Reserve Shutdown Hrs. 0.0 0.0 3533.6

14. Hours Generator On-Line 744 1697.4 21234.2

15. Unit Reserve Shutdown Hours 0.0 0.0 0.0

16. Gross Thermal Energy Generated (MWH) 2477746 5652061 65397759

17. Gross Elec. Energy Generated (MWH) 819170 1873820 21450300

18. Net Elec. Energy Generated (.MWH ) 786620 1792687 20327531

19. Unit Service Factor 100 78.6 54.2

20. Unit Availability Factor 100 78.6 54.2

21. Unit Capacity Factor (using MDC Net) 95.6 75.0 47.0

22. Unit Capacity Factor (using DER Net) 94.8 74.4 46.6

23. Unit Forced Outage Rate 0 17.5 36.0

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. 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 Commercial Operation 9/24/80 10/13/81 l 8-1-7.R2 l

Docket No. 50-311 ITNIT SHUTDOWN AND POWER REDUCTIONS REPORT MONTH MARCH 1986 Unit Nam 3 Snlcm No.2

' Date April 10,1986 J.P. Ronafalvy Telephone 609-935-6000' .

Completed by Extension 4455 Method of Duration Shutting License Cause and Corrective Reason Down Event System Component Action to No. Date Type Hours 2 Reactor Report Code 4 Code 5 Prevent Recurrence 1

B 5 -

HC PUMPXX Condensate /

86-134 0315 0.4 S Hotwell Pumps A 5 -

HF PUMPXX Circulating 86-142 .0316 F 0.9 Water Pumps A 5 -

HH PUMPXX Feedwater Pump 86-160 0322 F 2.8 A- 5 -

HH PUMPXX Feedwater Pump 86-162 0322. F 15.4 3 Method' 4 Exhibit G 5 Exhibit 1.

1 2 Reason. Salem as A-Equipment Failure-explain 1-Man.ual Instructions F: Forced 2-Manual; Scram. .for Prepara- Source S: Scheduled B-Maintenance or Test 3-Automatic Scram. tion of Data C-Refueling 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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-MAJOR' PLANT MODIFICATIONS' DOCKET NO.: 50-311 REPORT MONTH MARCH 1986 UNIT NAME: Salem 2 DATE: April 10, 1986 ~~

COMPLETED BY: J. Ronafalvy TELEPHONE:. 609/339-4455

• DCR NO.. PRINCIPAL SYSTEM SUBJECT 2EC-1058' Hydrogen Recombiners The replacement of the existing containment

hydrogen monitoring system i with one that is qualified i foriuse in the containment 4

does no. alter the function of the' system.

It assures the operator of continuous indication of hydrogen concentration in containment as required-by NUREG 0737, 2EC-1534 Bldg. & Equip. Drain; Change nuclear Flood & Sump Pumps classification'of 4

containment sump pumps j from Nuclear Class III.to Non-Nuclear Safety.

2EC-1682 Polar Containment Revise upper limit switch Gantry Crane protection arrangement as-necessary to follow the recommendations made by Westinghouse's Nuclear Division & contained in Technical Bulletin No.

' NSD-TB 75-9, dated 9/15/75.

2EC-1687 Service Water For 21,22,23,24,25 SW57 and SW223 vlaves,' remove cavitation control. tube t

bundles from all ten valves.

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• Design Change Request l

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UNIT 2 PLANT MODIFICATIONS. (continue'd)

REPORT MONTH MARCH 1986

• DCR NO.- PRINCIPAL SYSTEM SUBJECT 2EC-1724 Chem. & Volume Control Replace the 2CV45 &.2CV50 ~

Valves. Replace the pipingsdownstream of the CV45'& CV50 valves, located on the.No. 21 &

No. 22 C/SI pump casing drain ~line,.with piping in

.accordance with pipe spec.

49G and install a 1500#

blind flange at the end of.

these lines-in accordance-with pipe spec. 53D to be.

used during maint.non the' respective pumps.

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2EC-1772 RHR Sump Pump Level Install a new upper 3' of Indication probe'for the containme'nt sump indication.. The new probe should contain the same resistance per foct as the first 14' of probe.

2SC-0483 Chilled Water System Change shaft sleeve material from stainless' steel (316) to.monel.

2SC-0949 Waste Gas Add two' test conn'ections

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to the Waste Gas System.

-One between 2WG6 &--2WL99-on vent header.& the other 21 & 22 WG27 and 21,22,23, & 24'WG33 Valves on the H.P. header. Both test connections'should be located'inside, or as-closed as possible to the WG valve rooms as'possible.

2SC-1488 Service Water Provide permanent

. engineering design to

,/ satisfy operations 7

department ~ test-SP (O) 4.0.5V leak rate check for 21 &J22 SW51 and 21, & 22 SW79. Valves.

• Design Change Request l

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MAJOR PLANT MODIFICATIONS DOCKET NO: 50-311 REPORT MONTH - MARCH 1986 UNIT NAME: SALEM 2 DATE: APRIL 10, 1986 COMPLETED BY: J. RONAFALVY TELEPHONE: (609)339-4455

• DCR SAFETY EVALUATION 10 CFR 50.59 2EC-1058 The replacement of the existing Containment Hydrogen Monitoring System with one that is qualified for use in the containment does not alter the fuention of the system. This change assures the operator of a continuous indication of hydrogen concentration in the containment as requird by NUREG 0737. No unreviewed safety or environmental questions are involved.

2EC-1534 The Containment Sump Pumps themselves are,not part of a safety related system, and do not a ffect the safe - shutdown of the plant, accident mitigation or radioactivity release. The design change has no affect on plant discharge, therefore, no change is made in the' environmental impact. No unreviewed safety or environmental questions are involved.

2EC-1682 The crane performs no safety function in regard to the safe shutdown of the plant. This modification will not change any plant process or discharge and will not affect the existing environmental impact.- No unreviewed safety or environmental questions are involved.

2EC-1687 The removal of the Cavitrol tube bundles will enable the valves to function without interference from loosened tube bundles or reduced service water flow due to plugging of the tube bundles with the shells of miscellaneous mollusks and marine organisms. No plant process or-discharge is affected by this design change.

No unreviewed safety or environmental questions are involved.

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• Design Change Request

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I ' UNIT 2 MAJOR PLANT. MODIFICATIONS (contd)

REPORT MONTH - MARCH 1986 l

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• DCR SAFETY EVALUATION 10'CFR 50.59 -

! 2EC-1724 'The valves have been-replaced due to.the .

4 maintenance problem imposed by the welded bonnet-

design of the. original valves.- The-new valves are designed.to system temperature and pressure

. and are classified as. Seismic.I and Nuclear I.

l Installation of, the blind . flange eliminated -two potential sources of. unidentified leakage-from:  :

the Reactor Coolant System. . No unreviewed safety. ,

! or environmental questions are involved.

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I 2EC-1772 Installation of the design change', enhanced the

! operators ability to determine actual sump level.

1 This modification does not alter any plant I process or discharge.- Therefore, no unreviewed safety or environmetnal questions are involved.

2SC-0483 Corrosion, pitting and wearing of the stainless

steel shaft sleeve required a replacement sleeve  ;

of a better quality and grade material. The new

1. pump shaft sleeve is designed to thelsame . .  ;

i specifications as the originals. Changing the

shaft sleeve material from stainless steel to i monel-does not affect any presently performed safety analysis nor does it create any new' safety hazards. No plant process or_ discharge

is affected by this design change. No unreviewed~

, safety or environmental questions are' involved.

.; 2SC-0949 The new connections 1are only to.be used for j testing and will be blind. flanged during system

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i operation. No plant process or discharge is~ ,

affected by this design change. No unreviewed 3 safety or environmental' questions are-involved.

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UNIT 2 MAJOR PLANT MODIFICATIONS (contd)

REPORT MONTH - MARCH 1986

• DCR SAFETY EVALUATION 10 CFR 50.59 2 SC-14 88 This DCR provides a more dependable means of leak rate testing of service water check valves 21 &

22 SW51 and 21.& 22 SW79. This new design will ensure the integrity of the valves.and that they function as designed. A vent valve allows pressure to be relieved before the blind flange is removed for inspection. This ensures the safety of the inspector. No plant process or discharge is affected by this design change. No unreviewed safety or environmental questions are involved.

• Design Change Request i

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PSE&G SALEM GENERATING STATION SAFETY RELATED WORK ORDER LOG SALEM UNIT 2 WO NO UNIT EQUIPMENT IDENTIFICATION 8508060581 2 26SW19 FAILURE DESCRIPTION: VALVE STEM IS SEPERATED FROM VALVE SEAT.

CORRECTIVE ACTION: REPAIRED & REPLACED BACK INTO SYS.

86022890025 2 2MS132 FAILURE DESCRIPTION: PLEASE CHECK STROKE ON 2MS132 BECAUSE WE WERE UNABLE TO RELATCH TRIP VALVE WITH OUT ROLLING THE TURBINE. AFTER MANY ATTEMPTS TURBINE WAS FINALLY LATCHED.

CORRECTIVE ACTION: FOUND 2MS132 NOT TO BE LEAKING BY. RPM IND 0 @

23 AUX FD PMP PNL. VERIFIED PROPER AIR SUPPLY 8602220073 2 PRESSURIZER PRESSURE

. CHART FAILURE DESCRIPTION: PRESSURIZER PRESSURE CHART IS NOT FUNCTIONING.

CORRECTIVE ACTION: REPLACED FAULTY RIBBON CONNECTOR AND VERIFIED CALIBRATION. PLACED INSERVICE.

SALEM UNIT 2 ,

WO NO UNIT EQUIPMENT IDENTIFICATION 8602261012 2 CHILLER ISOL VALVE t FAILURE DESCRIPTION: VALVE INDICATION SPINDLE IS LOOSE CAUSING FAILED CONTROL ROOM INDICATION.

CORRECTIVE ACTION: FOUND ABM THAT CONTACTS LIMIT SWITCH OPEN AND CLOSED ARMS LOOSE. TIGilTED AND VERIFIED OPEN AND CLOSE LIMIT IN CONTROL ROOM BY HAVING NCO CYCLE VALVE 8512240130 2 2A DIESEL TURBO BOOST FAILURE DESCRIPTION: TURBO BOOST LINE THAT RUNC ALONG THE DIESEL IS 1

DAMAGED.

CORRECTIVE ACTION: REPAIRED AS PER DR SMD-M86-0039.

8602120095 2 CONTAINMENT DIFF PRESSURE FAILURE DESCRIPTION: AFTER A PRESSURE RELIEF OF 1.5 HRS TIIE CONTROL ROOM METER INDICATES A POSITIVE PRESSURE.

CORRECTIVE ACTION: FOUND TRANSMITTER OUT OF SPEC. DURING CALIBRATION, FOUND IT TO DRIFT. REPLACED WITH NEW TRANSMITTER.

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WO NO UNIT EQUIPMENT IDENTIFICATION 8603050937 2 24 SG STEAM PRESSURE FAILURE DESCRIPTION: 2BS-5468 TRIP POINT OUT OF SPEC. REQUIRED TO TRIP "OFF" ON A DECREASING INPUT SIGNAL AT 3.167 VDC

+30, -20 MV. AS FOUND VALUE WAS 3.203 VDC.

PROBLEM IDENTIFIED DURING CHANNEL FUNCTIONAL TEST, (PROCEDURE 2PD-2.6.062)

CORRECTIVE ACTION: REPLACED CAPS C2,3 IN 2PC-546A/B. RE" LACED CAPS C23,24 IN 2PM546 BLEAD LAG AMP. COMPLETED FUNCTIONAL, SAT.

8603070091 2 24 CFCU INLET FAILURE DESCRIPTION: 24 SW 58 WILL NOT OPEN FROM CONTROL ROOM.

CORRECTIVE ACTION: FOUND VALVE JAMMED IN. SEAT. OPENED VLV BY ENGAGING HANDWHEEL. ADJ OPEN LIMIT SW. NCO CYCLED VALVE.

8603070652 2 STRAINER DELTA P FAILURE DESCRIPTION: DELTA P ACROSS STRAINER IS APPROX. 30 LBS.

STRAINER SHEAR KEY APPEARS TO BE BROKEN.' SHEAR KEY WAS ROTATING BUT PRESSURE DID NOT GO DOWN.

CORRECTIVE ACTION: REPLACED SHEAR KEY & ADJUSTED PACKING 416 DELTA.

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SALEM UNIT 2 ,

WO NO UNIT EQUIPMENT IDENTIFICATION 8603100021 2 22 SW PUMP STRAINER FAILURE DESCRIPTION: SHEAR KEY IS BROKEN.

CORRECTIVE ACTION: CHECKED STRAINER FOR FREE MOVEMENT. REPLACED SHEAR KEY.

0099168782 2 RC FLOW LOOP 3 CH III FAILURE DESCRIPTION: CHANNEL FOUND OUT OF SPEC.

CORRECTIVE ACTION: ADJUSTED SETPOINT OF COMPARATION 2FC-436.

COMPLETED PROCEDURE 2PD-2.2.012.

0099168791 2 #22 SG STEAM PRESS CH III FAILURE' DESCRIPTION: CHANNEL FOUND OUT OF SPEC WHILE PERFORMING CHANNEL CAL 2PD-2.2.042.,

CORRECTIVE ACTION: ADJUSTED LEAD / LAG MODULE TO. CORRECT OUT OF SPEC READING AND COMPLETED CHANNEL CAL 0099183510 2 2C DIESEL. GEN THE' JACKET WATER E:NPW AT #5 CYLINDER ON RIGHT (

FAILURE DESCRIPTION:

SIDE OF DIESEL GEN. IT-IS RUPTURED.

CORRECTIVE ACTION: REPLACED HOSE & GASKET ON JACKET WTR TO #5 CYLINDER-HEAD.

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SALEM UNIT.2

'a t WO NO ' UNIT EQUIPMENT IDENTIFICATION ,

8512240130 2 2A DIESEL TURBO BOOST FAILURE DESCRIPTION: TURBO BOOST LINE THT RUNS ALONG THE DIESEL IS DAMAGED.

CORRECTIVE ACTION: REPAIRED AS PER DR SMD-M86-0039.

8602220073 2 PRESSURIZE PRESSURE CHART FAILURE DESCRIPTION: PRESSURIZER PRESSURE CHART IS NOT FUNCTIONING.

CORRECTIVE ACTION: ' REPLACED FAULTY RIBBON CONNECTOR AND VERIFIED CALIBRATION. PLACED INSERVICE.

8603090017 2- IR NEUTRON LEVEL CH. III

-FAILURE. DESCRIPTION: IR NEUTRON LEVEL CH.II CONSOLE INDICATION POINTER IS EROKEN OFF.ALSO CONSOLE INDICATION APPEARS TO BE READING. LOW, BUT IS READING CORRECTLY IN BACK N.I. RACK.

CORRECTIVE ACTION: REPAIRED BROKEN POINTER-AND CALIBRATED METER AS PER ICD CARD.

L 8603241171 2 22 BAT. PUMP l

FAILURE DESCRIPTION: PUMP HAS A BAD' SEAL LEAK.

CORRECTIVE ACTION:- REPLACED CASING GASKET.

i SALEM GENERATING STATION MONTHLY OPERATING

SUMMARY

- UNIT NO. 2 MARCH 1986 SALEM UNIT NO. 2 The Unit began the period operating at full power. On 3/07/86 at 0459 hours0.00531 days <br />0.128 hours <br />7.589286e-4 weeks <br />1.746495e-4 months <br />, power was reduced to 95% due to Circulating Water Screen problems caused by river grasses. The Unit was returned to full power operation at 0520 hours0.00602 days <br />0.144 hours <br />8.597884e-4 weeks <br />1.9786e-4 months <br /> the same day' . On 3/12/86, a hydrogen leak was discovered on No. 2 Main Generator. Subsequent investigations revealed the hydrogen leak was associated with the No. 10 Bearing seal. Hydrogen pressure was reduced to 55# where the leakage was within normal operating limits. Operating at the reduced hydrogen pressure required a slight load reduction to.99% to maintain generator operations within the stability curve limits. On 3/17/86 at 2251 hours0.0261 days <br />0.625 hours <br />0.00372 weeks <br />8.565055e-4 months <br />, power was reduced to 80% due to 23A, 22A and 22B Circulator Screens being out of service due to large quantities of river grasses, i

The Unit was returned to 99%. power operation at 2335 hours0.027 days <br />0.649 hours <br />0.00386 weeks <br />8.884675e-4 months <br /> the same day. On 3/22/86 at 1755 hours0.0203 days <br />0.488 hours <br />0.0029 weeks <br />6.677775e-4 months <br /> power was reduced to 60% as a result of a suspected oil leak at the inboard of the #22 Steam Generator Feed Pump (SGFP) Turbine. While power was reduced, the mechanical seal for

1. 22 Condensate Pump was replaced. Following repairs to the SGFP turbine and Condensate Seal the Unit.was returned to 99% power at 2320 hours0.0269 days <br />0.644 hours <br />0.00384 weeks <br />8.8276e-4 months <br /> on 3/23/86. On 3/24/86, slight load reductions were performed due to river grasses and debris causing circulating water problems.

The circulating water problems were corrected the same day and the Unit operated at essentially full power through-the remainder of the period.

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REFUELING INFORMTION DOCKET NO : 50-311 COMPLETED BY: J. Ronafalvy UNIT NAME: Salem 2 DATE: April 10, 1986 TELEPHONE: 609/935-6000 EXTENSION: 4455 Month March 1986

1. Refueling information has changed from last month:

YES NO X

2. Scheduled date for next refueling: September 20, 1986

3. Scheduled date for restart following refueling: November 19, 1986

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

YES NO Not determined to date B) Has the reload fuel design been reviewed by the Station Operating Review Committee?

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

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

August 1986 if required

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 l

• . o O PSEG

- Public Service Electric and Gas Company P.O. Box E Hancocks Bridge, New Jersey 08038 1 . Salem Generating Station -

April 10, 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 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 March 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 Sin cerely ' yours ,

J. . Zupko, Jr.

General Manager - Salem Operations JR:kcb 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 8-1-7.R4 The Energy People ' l 93-2189 tt 1 M) 12 84

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