ML20141N638

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Monthly Operating Rept for Feb 1986
ML20141N638
Person / Time
Site: Salem PSEG icon.png
Issue date: 02/28/1986
From: Ronafalvy J, White P, Zupko J
Public Service Enterprise Group
To:
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE)
References
NUDOCS 8603170430
Download: ML20141N638 (15)
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. AVERAGE DAILY UNIT POWER LEVEL ,

Docket No. 50-272-Unit Name Salem # 1-

Date March 10,1986 Ccmpleted.by "Pell White. Telephone 609-935-6000 Extension 4455 Month February 1986~

Day Average Daily' Power Level- Day Average Daily Power Level

- (MWe-NET). (MWe-NET)

1. 0 17 1063

.2 0 18 1068 3 856 19 '1079 14 726 -

20 42 5 216 21 90

~6 1009 22 956 .

7 1082 23 1040 ,

j 8 1074 24 961 9 1073 25 974 .[

10 1069 26 1035

'll 1068 27 1045 12 1077 28 1029 13' 1070 29 14 1080 30 15 1078 31 16 1079 r

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l OPERATING DATA REPORT

. D ckOt No.50-272 Date . March 10, 1986 Telephone 935-6000 Completed by Pell White Extension 4455 Operating Status

1. Unit Name Salem Mo. 1 Notes
2. Reporting Period February 1986
3. Licensed Thermal Power (MWt) 3338
4. Nameplate Rating (Gross MWe) 1170
5. Design Electrical Rating (Net MWe) 1333
6. Maximum Dependable Capacity (Gross MWe)TTYT
7. Maximum Dependable Capacity (Net MWe) 107F
8. If Changes Occur in Capacity Ratings (itemn 3 through 7) since:Last Report, Give Reason N/A l 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 672 1416 75985
12. No. of Hrs. Reactor was Critical 620.6 1331'.8 45517.2
13. Reactor Reserve Shutdown Hrs. 0.0 0.0 3088.4___
14. Hours Generator On-Line 574.4 1261.2 43766
15. Unit Reserve Shutdown Hours 0.0 0.0 ~~~~~

0.0'

16. Gross Thermal Energy Generated (MWH) 1816716 4079162 134563191
17. Gross Elec. Energy Generated I (MWH) 601380 1354500 44650510
18. Net Elec. Energy Generated (MWH) 573578 1295684 _

42401176 l

19. Unit Service Factor 85.5 89.1 57.6
20. Unit Availability Factor 85.5 G9.1 57.6
21. Unit Capacity Factor I (using MDC Net) 79.1 __84.8 51.7
22. Unit Capacity Factor (using DER Net) 78.3 83.9 51.2
23. Unit Forced Outage Rate 14.5 10.9 26.2 )
24. Shutdowns scheduled over next 6 months (type, date and duration of each)

Refueling, March 22, 1986, approximately 60 days

25. If shutdown at end of Report Period, Estimated Date of Startup:

N/A

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

Forecast

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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 8-1-7.R2 Page of 1

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Dockst1No;50-2Y2 ~

UNIT CHUTDOWN AND POWER REDUCTIONS REPORT MONTH Febru^ry 1986 Unit Name S'lem he.1 -

D2tg March 10,1986 ..

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Telephone 609-935-6000-Completed by Pell Whito ,

Extension 4455 -

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.- Method of ~~ .

Cause and Corrective:

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Duration . Shutting License Down Event! System?~, Component Action to;

.No . Date Type Hours Reason 1 2 Reactor Report Code 4' Code 5 Prevent' Recurrence

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A 3 - CH VALVEX, Feedwater' Regulating 144 0131 P 13.1 Boiler level control valves HA- VALVEX Lube Oil Systems 150 020 F 12.1 A 1 -

valves and piping, turbine 0224 F 3.4 B 5 - HC HTEXCH Condenser tube and 232 Water Box' cleaning 5 HC HTEXCH- Condenser tube fouling 240 0225 F 5.8 A -

' tube side dirty condenser 3 Method 4 Exhibit G 5 Exhibit 1 1 2 Reason F: Forced A-Equipment Failure-explain 1-Manual- Instructions . Salem as 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-l H-Other-explain- (NUREG 0161)

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g hP MAJOR. PLANT MODIFICATIONS . DOCKET NO.: 50-272 Y

' REPORT' MONTH FEBRUARY 1986 <> UNIT NAME:- Salem 1

  • DATE: March T0, 1986 COMPLETED BY:. J..Ronafalvy A TELEPHONE: 609/339-4455
  • DCR NO.- PRINCIPAL SYSTEM SUBJECT 1ET-1940 4KV Power System Test the 4KV UV Transfer Scheme on the IB Vital: Bus. '

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IEC-1990.

Aux Feedwater Change of the relay setting for Nos. 11 & 12 Aux. Feed Pump Motors -

s 1SC-0839 Steam Generators:- Modify design of Moisture Secondary Side Separator Drains ISC-0892 Test Air to Containment Install a mechanical stop Personnel Hatch valve at the hatch flow meter air-supply line s-1EC-1272 Service Water Install-a vortex eliminator for

  1. 11 S.W.' Pump (Bay #1)

'1EC-1619B ' Reactor Coolant System Replace c=isting recorders

  • Wide Range RTD Recorders

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with seismically qualified.onee-lEC-1837 Service Water Intake Raise the ventilation. intake Structure penthouse and add structural i steel barrier plates.to the ve:7tilation exhaust penthouse.

., is 1EC-1862 ' Safety Injection: Replace existing cooler,1s on Pump Lube Oil Coolers Nos. 11 & 12 S.I. Pumps with ones of upgraded materials of. t construction 1EC-1965 Structural Replace shield blocks in shielding wall for North Penetration El. 100' j

-1EC-2025 Fire Doors Add three (3) doors; two (2) in the I,x. Bldg. and one (1) in t0h % rvice Water Intake c tv ure DCR - Design Change Request

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3 MAJOR PLANT MODIFICATIONS (co'ntinued)

REPORT MONTH . FEBRUARY'1986' .

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  • DCR NO. PRINCIPLE SYSTEM SUBJECT

.1EC-1565- '

Chilled Water System . Install a 10 PSIG relief valve at the Expansion Tank-and repair w the nitrogen pressiire reducing .i valve

. . . . , , :lEC-1413- Reactor Coolant Replacement of Wide-Range-RTD's' A_ with environmental qualified elements s

-.lEC 0882. , Service -Watier System Add 3/4" pressure sensing lines

, off of the.S.W.~ Header at the.

  1. 12 CCHX ISC-1533- Change nuclear classification-

, Building and. Equipment

> Drains, Flood & Sump .of Containment ~ Sump Pumps.from Pumps; Nuclear Class III to Non-Nuclear-

, Safety ,

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  • DCR - Design Change Request t

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UNIT'1 MAJOR PLANT MODIFICATIONS-(continued)

. REPORT. MONTH - FEBRUARY 1986~

lEC-1837 This modification. raised the SW-Intake' Structure-s Ventilation Intake Penthouse flood and wave runup protection level. Structural barriers-were-

. installed on the' Ventilation Exhaust Penthouse to protect'the SW Intake Control. Rooms.from flooding and to inhibit water from running into the exhaust- -

chase down~into the pump rooms. No. plant process a or discharge is affected by this design change.

No unreviewed safety or environmental questions are involved.

1EC-1862 This, modification constituted an upgrading of the t SI Lube' Oil Coolers by installing coolers with titanium tubing._.The new coolers are seismically qualified to 1980 ASME Section III Class 3-1981 Summer Addenda for the tube side only. The shell side-is classified to the 1980 ASME Section VIII Code Division I. The original coolers'were.not seismically qualified.. The tubesheet material 3 (titanium) .is an upgrade from the previous

. materials which were susceptable to the corrosive action of the service-water. No plant process or discharge is affected by this design change. No '

unreviewed safety or environmenta) questions are <

involved.

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1EC-1965 This modification repaired the masonary block wall radiation shield in the Unit 1, North Penetration-Area-(100' El.) in line with the Containment Airlocks. The modification was' analyzed'to ensure it would maintain integrity in the event of a seismic occurrence. No plant process or discharge is affected by ~this design change. No unreviewed safety or environmental questions are involved.

-* . Design. Change Request h

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'. h UNIT 1 MAJOR PLANT MODIFICATIONS (continued)

REPORT MONTH - FEBRUARY 1986

  • DCR SAFETY EVALUATION 10CFR 50.59 lEC-2025 The new doors are not required to be safety related. Their presence will not impact the operation of existing safety related equipment nor will they reduce the margin of safety for such equipment as outlined in the Technical Specifications. A failure' of the doors will not result in any damage or influence the operation of safety.related equipment. Functionally, the doors will reduce the risk of fire damage to safety related equipment. No plant process or. discharge is affected by this design change. No unroviewed safety or environmental questions are involved.

lEC-1413 This modification involved the direct replacement of existing equipment. The system was not-changed functionally. No plant process or discharge is affected by this design change. No unreviewed safety or environmental questions are involved.

lEC-0882 This design change involved the addition of pressure sensing lines to the Service Water lines of the #12 Component Cooling Heat Exchanger.

These lines will not increase the potential of any failures or malfunctions of the system, nor will they increase the potential effects of any adjacent system or structure. No plant process or discharge is affected by this design change. No unreviewed safety or environmenta) questions are involved.

1EC-1533 The Containment Sump Pumps are not part of a safety related system and do not affect the safe -

shutdown of the plant. They are not reguried.to mitigate consequences of an accident. No plant process or discharge is affected by this design change. No unreviewed safety or environmental questions are involved. For additional information refer to Salem Generating Station Safety Evaluation #S-C-M700-MSE-161.

  • Design Change Request

. ,L MAJOR PLANT MODIFICATIONS DOCKET NO.:' 50-272

. REPORT MONTH FEBRUARY 1986. UNIT NAME - Salem 1 DATE: March 10, 1986 COMPLETED BY: J. Ronafalvy TELEPHONE: 609/339-4455

.lET-1940- This test involved the testing of the 4160V Vital Bus UV. Transfer scheme. No' equipment modifications were required. No' plant process or' discharge is affected by this design change. No unreviewed safety or environmental questions are involved.

lEC-1990 The design change only modifies a relay set point change. No plant process or discharge is affected.

by this design change. No unreviewed safety or environmental questions are involved.

ISC-0839 This modification provides more effective drainage ~

of water, but will not effect steam generator nor.

system performance. No plant process or discharge is affected by this design ~ change. No unreviewed safety or environmental 1 questions are involved.

ISC-0892 The controls changes do not affect the operation of installed equipment and will not deduct from the margin of safety of persently installed equipment. No plant process or discharge is affected by this design change. No unreviewed safety or environmental questions are involved.

1EC-1272 The installation of the vortex breaker will not affect the safe shutdown of the reactor or the structural integrity.of the Service Water Intake Structure. No plant process or discharge is affected by this design change. No unreviewed safety or environmental questions are involved.

1EC-1619B This design change provides for the redesignation of existing "non-vital" associated cables to vital channels. No cable installation or rerouting was required. No functional or operational changes

, were made. No plant process or discharge is affected by this design change. No unreviewed safety or environmental questions are involved.

  • Design Change Request

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' UNIT 1 MAJORLPLANT MODIFICATIONS (continued)

REPORT MONTH - FEBRUARY'1986 m

~*DCR SAFETY EVALUATION 10CFR 50.59 1EC-1565 The' change does not jeopardize the pressure retaining boundary.nor impact'the operation / basic design criteria of the Chilled Water System. No plant process or discharge is.affected by this design change.; No unreviwed' safety or environmental questions are-involved. For additional information refer to Salem Generating Station Safety Evaluation #S-C-M700-MSE-161.

  • Design-Change Request

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PSEEG SALEM GENERATING: STATION ' _

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SA?ETY.RELATED WORK ORDER' LOG-

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-SALEM UNITil

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.NO NO DEPT UNIT- EQUIrram.nr IDENTIFICATION -

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I 11 BA PUNP SEALS _

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FAILURE DESCRIPTION: -THE PUMP NEALS'ARE LEAKING EXCESSIVELY.

CORRECTIVE ACTION: REPLACEC WAP.IdGS, SHAFT, 0-RINGS, SEALS AND- -

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-MECHANICAL. SEAL.- -

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I 8602020058 1' 12 BAT PUMP- _

FAILURE DESCRIPTION: PUMP-IS SEIZED AND HAS A BAD SEAL-LEAK.

CORRECTIVE ACTION: REPLACED MECHANICAL SEAL.

8601280749 l 1 13BF19 i

i FAILURE DESCRIPTION:. PACKING-IS LEAKING.

CORRECTIVE ACTION: VALVE PACKING GLAND WAS FURMANITED.

8601140637 13 CHILLER 1 e THE CHILLER-IS TRIPPING ON-FREEZE PROTECTION,-11 AND

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FAILURE DESCRIPTION: '

12-CHILLERS.:ARE C/T.

CORRECTIVE ACTION: REPAIRED CRACKED:1/4 FLARE FITTING ON REFRIGERATION LIQUID LINE.

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WO NO DEPT UNIT EQUIPMENT IDENTIFICATION 8601140033 1 13 CHARGING PUMP FAILURE DESCRIPTION: Ti!E PUMP HAS A LEAK COMING FROM #1 PISTON HEAD.

THE LEAK WAS BLOWING WATER AGAINST THE SIDE WALL.

THE LEAK IS LOCATED ON THE BOTTOM RIGHT CORNER OF TIIE PISTON HEAD.

CORRECTIVE ACTION: REPLACED GASKET ON 1 & 3 DISCHARGE COVER AND 1 & 5 SUCTION COVER.

8512061189 1 13 S/G ATMOS RELIEF -

VALVE FAILURE DESCRIPTION: VALVE SEAT IS BLOWING BY.

CORRECTIVE ACTION: FOUND I/P TRANSDUCER OUT OF CALIBRATION, LIFTING VALVE OFF OF ITS SEAT. CALIBRATED I/P AND VERIFIED VALVE IS FULLY SEATED.

8512010053 1 1 AFWST HEATING CIRC PUMP FAILURE DESCRIPTION: THE PUMP HAS A SLIGHT MECHANICAL SEAL LEAK.

CORRECTIVE ACTION: INSTALLED NEW SEAL. _

0099182718 1 MAIN STEAM ISOLATION VALVE FAILURE DESCRIPTION: VALVE DOES NOT CLOSE FROM 90% OPEN IN LESS THAN 5 SECONDS.

CORRECTIVE ACTION: RECALIBRATED AND ADJUSTED BYPASS VALVE.

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SALEM UNIT 1-  ; -

DEPT. UNIT a

=~ WO-NO EQUIPMENT IDENTIFICATION

.0099168031

1. 13 S/G BYPASS VALVE-

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FAILURE DESCRIPTION:- 13BF40 . POSITIONER LEAKING AIR. :

-LORRECTIVE ACTION: REPLACED POSITIONER,-CALIBRATED SAME AND VERIFIED ~

OUTPUT OF POSITION TRANSMITTER,'HAD. OPERATIONS.~

VERIFY OPERATION OF' VALVE FROM CONTROL ROOM ,

8601240054 1 1A DIESEL FAILURE DESCRIPTION: AFTER A 'l HOUR: OPERABILITY RUN '(AFTER REPLACEMENT .j OP THE HFA RELAY), THE GENERATOR BREAKER-WAS OPENED AND WHEN THEfCNC-SWITCH (A" MICRO SWITCH) ,

WAS TURNED TO'OFF, THE DIESEL DID'NOT STOP.

CORRECTIVE ACTION: FOUND A LOOSE WIRE'ON THE REPLACED-HFA RELAY, '

TIGHTENED WIRE AND CHECKED REST OF CIRCUIT. -RAN' DIESEL AND SHUT DOWN BY CSING SWITCH.

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e SALEM GENERATING STATION MONTHLY OPERATING

SUMMARY

- UNIT NO. 1 FEBRUARY 1986

. SALEM NO. l'

.The Unit began the period in Mode 3 (Hot Standby) as investigations

, and repairs were being completed due to the reactor trip on January

- 31,'1986. The Unit was returned to service on February'2, 1986 at 2157 hours0.025 days <br />0.599 hours <br />0.00357 weeks <br />8.207385e-4 months <br />. On February 4, 1986 at 1454 hours0.0168 days <br />0.404 hours <br />0.0024 weeks <br />5.53247e-4 months <br />, a Unit shutdown was commenced due'to an oil-leak from the #4 Turbine bearing. The Unit was returned to service on February 5, 1986 at 0828 hours0.00958 days <br />0.23 hours <br />0.00137 weeks <br />3.15054e-4 months <br />. On February 20, 1986 at 0142 hours0.00164 days <br />0.0394 hours <br />2.347884e-4 weeks <br />5.4031e-5 months <br />, the Unit tripped due-to Steam LFlow/ Feed Flow mismatch coincident with low level in #14 Steam Generator (i.e., Low Steam Generator Level with Low Feed Flow) as a result of closure of valve 14BF19 (Steam Generator Feed Water Control

, Valve). 'The valve closure was caused by a broken wire connector associated with the Train "A" Feedwater. Isolation Solenold. The Unit was returned to service on February.21, 1986 at 1718 hours0.0199 days <br />0.477 hours <br />0.00284 weeks <br />6.53699e-4 months <br />. Reactor power was limited to 95% due to No. 13 Turbine stop valve inoperability. On February 24, 1986 at 1500 hours0.0174 days <br />0.417 hours <br />0.00248 weeks <br />5.7075e-4 months <br /> power was reduced to.72% due to Circulating Water System traveling screens problems caused by large amounts'of river grasses. The Unit was returned to 96% power on the same day at 2230 hours0.0258 days <br />0.619 hours <br />0.00369 weeks <br />8.48515e-4 months <br />. On February 25, 1986 at 1545 hours0.0179 days <br />0.429 hours <br />0.00255 weeks <br />5.878725e-4 months <br />, power was reduced to 83% in order to repair 13A Circulator traveling screen as well as to clean the 13B Circulator tube sheet of river grasses. The Unit was returned to 96% power the same day where it' remained for the rest of the period.

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REFUELING INFORMATION DOCKET NO.: 50-272 COMPLETED BY: J. Ronafalvy UNIT NAME: Salem 1 DATE: March 10, 1986 TELEPHONE: 609/935-6000 EXTENSION: 4455 Month Februarv 1986

1. Refueling information has changed from last month:

YES X NO

2. Scheduled date for next refueling: March 22, 1986
3. Scheduled date for restart following refueling: May 20, 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 X NO If no, when is it scheduled?

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

N/A

6. Important licensing considerations associated with refueling:

NONE

7. Number of 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 to opent fuel pool assuming the present licensed capacity: September 2001 8-1-7.P4

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Public Service Electric and Gas Cornpany P.O. Box E Hancocks Bridge. New Jersey 08038 Salem Generating Station Pa d 10, 1986 Director, Office of Inspection and Enforcement U.S. Nuclear Regulatory Commission Washington, DC 20555 Dear Sirs 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 February 1986 are being sent to you.

Average Daily Unit Power Level Operating Data Report Unit Shutdowns and Power Reductions Major Plant Modificction Safety Related Work Orders Operating Summary Refueling Information Sincerely yours, g/ * [- ,-

J, M. Zupko, Jr.

General Manager - Salem Operations JR:kcb cc Dr. Thomas E. Murley Regional Administrator LJNRC Region I 631 Park Avenue King of Prussia, PA 19406 Director, Of fice of Management Information and Program Control U.S. Nuclear Regulatory Commission Washington, DC 20555 Enclosures 8-1-7.R4

.y The Energy Peoph)

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