ML20207S562

Monthly Operating Rept for Feb 1987

ML20207S562
Person / Time
Site:	Salem
Issue date:	02/28/1987
From:	Miller L, White P, Zupko J Public Service Enterprise Group
To:	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE)
References
NUDOCS 8703200037
Download: ML20207S562 (11)

Text

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AVERAGE DAILY UNIT POWER LEVEL Docket-No. 50-311 Unit Name Salem # 2 Date March 10,1987 Completed by_ Pell White Telephone 609-935-6000 Extension 4451

' Month- February 1987 Day Average Daily Power Level Day Average Daily Power. Level

.(MWe-NET) (MWe-NET) 1 1040 17 1110' 4 2 1112 .18 1116 3 1102 19 1107 4

4 1110 20 1108

.5 _

1016 21 1093 6 1116 22 ~1112 7 1100 23 1116 8 -1084 24 1114 9 1105 25 1113 10 1104 26 1106 11- 1102 27 1114 12 1100 28 1124 13 1105 29 14 1083 30

-15 -1104 31 16 1097 Pg. 8.1-7 R1 8703200037 B70228 PDR ADOCK 05000311 R PDR 1 fEQ4 ili

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OPERATING DATA REPORT Docket No. ^ 5 0-311' Date- March 10,1987

. Telephone. 935-6000

. Completed by; Pell White Extension 4451 Operating Status 61'. Unit Name- Salem No. 2 Notes

2. Reporting Period. . -February 1987 13.- Licensed Thermal ~ Power (MWt) 3411

4. Nameplate Rating (Gross MWe) IIT6

5. .. . Design .' Electrical: Rating (Net MWe) ITTE

6. Maximum Dependable Capacity (Gross MWe)1149 7.. Maximum Dependable' Capacity (Net MWe) IIDT

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

Repert, Give Reason -N/A

9. Power Level to Which Restricted, if any (Net MWe) NA

10. Reasons for Rectrictions, if any 7

This-Month Year to Date Cumulative til. Hours in Reporting Period 672- ~1416 47161

12. No. of Hrs. Reactor was Critical 672 1400.8 27340.7 13.: Reactor Reserve Shutdown Hrs. 0 0 0

14. Hours Generator On-Line 672 1397.7 26336.1

15.. Unit Reserve Shutdown Hours 0 0 0 i 116.' Gross Thermal Energy Generated (MWH) 22884121 4630654 30639126

17. Gross'Elec. Energy Generated .

(MWH) 767290 1534820 26711960 p 18. Net Elec. Energy Generated (MWH) 739871 1477596 25325001 L 19. Unit Service' Factor 100 98.7 55.8 20.. Unit' Availability Factor -100- 98.7 55.8

21. Unit. Capacity Factor

[ .

.(using MDC Net) 99.5 94.1 48.6 l 22. Unit-Capacity Factor (using DER Net) 98.7 93.6 48.1

..23. Unit Forced Outage Rate 0 0 26.0

-24. Shutdowns scheduled over next 6 months (type, date and duratIbn 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 8-1-7.R2

,- . _ . = -

UNIT SHUTDOWN:AND' POWER' REDUCTIONS. Dock 3t No. 50-311-REPORT MONTH FEBRUARY 1987 Unit N; met salem No.z. g Date, March'-10,1987., a 1 Completed by- Pell i 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 1 2 Reactor' Report Code 4- Code 5 Prevent Recurrence LOAD CondenserrTube &

0078 02-01-87 F 1.67 B REDUCTION- ----

HC' 'HTEXCH Water Box:Claning-Condesate/

0080 02-05-87 F- 3.53 B "- ----

HH PUMPXX Hotwell~ Pumps 1 2 Reason 3 Method- 4 Exhibit-G 5' Exhibit'l-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) l

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MAJOR PLANT MODIFICATIONS- DOCKET NO.:- 5'0-311 -

REPORT MONTH FEBRUARY 1987- UNIT NAME: Salem 2 DATE: . March.12, 1987 COMPLETED BY: L.-Miller-TELEPHONE: 609/339-4497

• DCR NO. PRINCIPAL SYSTEM SUBJECT

- 2EC-1014 Component Cooling Provide motor operators for

- Water component cooling water pumps discharge header valves No.

21CC2 and 22CC3.

t 2EC-1573 Hoists & Cranes Derate " Overhead-Load Handling System" capacity to 2,000 pounds.(1.1 tons) or less by.

changing the "name/ capacity plate" marking and adding appropriate notes to design, maintenance, operating, and-other documents.

-2EC-1574 Hoists & Cranes 'Derate Fuel Handling Crane capacity to 2,000 pounds (1.1 tons) by changing

" nameplate / capacity plate"

-marking and adding appropriate-notes to design, maintenance,

, and other documents.

2EC-1650 Heating Steam Installation-of encapsulations

& Cond. and whip restraints to insure that a pipe rupture will not result in adverse conditions which-could preclude ~ safe shutdown of the plant.

2SC-1194 Containment Control circuit for Ventilation containment fan coil units should provide for a trip.of the high speed breaker should

,. the ty breaker fail to stay in the closed position. Also red start light should not come on without both breakers closed.

I i

• ' Design Change Request i

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MAJOR PLANT' MODIFICATIONS DOCKET NO: 50-311 REPORT MONTH - FEBRUARY 1986 UNIT NAME:. SALEM 2

.DATE: March 12,1987 COMPLETED BY: L. Miller TELEPHONE: (609)339-4497

• DCR SAFETY EVALUATION 10 CFR 50.59 2EC-1014l Existing manually operated valves will have. motor operators added to enable more rapid and remote operation. Handwheels will be retained to allow manual option. The valves themselves and their function remain the same. Added motor operatord

.will be fully seismically' (Class I)_and environmentally qualified. Therefore,'while the description in the FSAR must be modified to include the wording " Motor Operated" vs. " Manual" valves, there is no change involved to the Technical Specifications and no unreviewed safety question. The component cooling system is a closed. loop system. Thee are no environmental releases under normal conditions. Therefore, no unreviewed safety or environmental questions are involved.

2EC-1573 This DCR provides for the.implementaiton of a color coding to derate the manipulator crane from its present 3,000 pounds to 2,200 pounds lifting capacity, for Unit #2. This painting job will not create a new fire safety hazard to-the plant, nor affect the safe shutdown of the reactor.

Implementation of this lower capacity marking is-done to comply with a commitment made to the NRC and with Section 5.1.1(4) of NUREG-0612. There j are no unreviewed safety questions. This DCR L will not change the plants effluent releases I hence will not alter the existing environmental L impact. No unreviewed safety or environmental

! questions are involved.

L I

• DCR - Design Change Request l-

MAJOR PLANT MODIFICATIONS DOCKET NO: 50-311 REPORT MONTH - FEBRUARY 1986 UNIT NAME: SALEM 2 DATE: March 12,1987 COMPLETED BY: L. Miller TELEPHONE: (609)339-4497

• DCR SAFETY EVALUATION 10 CFR 50.59 2EC-1574 This DCR provides for the implementation of a color coding to derate the fuel handling crane from its present 10,000 pounds to 2,200 pounds lifting capacity, for Unit #2. This painting job will not create a new fire safety hazard to the plant, nor affect the safe shutdown of the reactor. Implementation of this lower capacity marking is done to comply with a commitment made to the NRC and with Secitan 5.1.1(4) of NUREG-0612. This DCR will not change plant effluent releases hence will'not alter the existing environmental impact. No unreviewed safety or environmental questions are involved.

2EC-1650- There is no unreviewed safety questions involved because the addition of encapsulations and pipe whip restraints enhance the safe shutdown capability of the plant in general. This change will-restrict heating water / heating steam escape flow rate providing adequate protection against environmental effects, therefore, no unreviewed environmental questions are involved either.

, This modification will not alter any plant process or discharge and will not affect the existing plant impact.

2SC-1194 -All potential, realistic failure modes have been considered but are not applicable. There are no applicable regulatory requirements. This modification will not alter any plant process or discharge and will not affect the existing plant impact. No unreviewed safety or environmental questions are involved.

• DCR - Design Change Request

, 1.,

PSE&G' SALEM GENERATING STATION  :*

SAFETY RELATED WORK ORDER LOG SALEM UNIT.2 WO NO UNIT EQUIPMENT IDENTIFICATION 8702050048 2 22SW23 SW CROSSTIE FAILURE DESCRIPTION: VALVE 22SW23 DOES NOT CLOSE ON CLOSE SIGNAL. CONTROL ROOM LOOSES OPEN INDICATION.'THERE IS:NO TRIP INDICATION. REFERENCE WORK REQUEST WR #000643.

CORRECTIVE ACTION: PERFORMED;M3Z AND TROUBLE SHOT THIS' VALVE, SAT.

TARNISHED CONTACTS ON TORQUE SWITCH WAS.THE ONLY' POSSIBLE FAILURE. RAN VALVE SAT, APPROXIMATELY 6-8 TIMES.

8610280349 2 4KV BREAKER FAILURE DESCRIPTION: PERFORM 4KV BREAKER MAINTENANCE ON S/N 0224A6266-007' I/O # 250550 CORRECTIVE ACTION:- A.O. WILL NOT ADJUST REPLACED PUSH ROD. ' INSTALLED NEW CHARGING MOTOR. PERFORMED M3J. PERFORMED M3J COUNTER NO. 951. INSTALLED IN 1BlOD - 12 COMPONENT COOLING.

PUMP.

8702110113 2 23 CFCU BACK PRESSURE FAILURE DESCRIPTION: REPAIR OR REPLACE VALVE.

CORRECTIVE ACTION: . REPLACED ACTUATOR, LINKAGE AND POSITIONER WITH NEW PARTS FROM SR, STROKED VALVE, SET UP POSITIONER AND SET LIMIT'SWS, STROKED FROM LOCAL CONTROL PANEL TO VERIFY PROPER OPERATION.

l l

SALEM UNIT 2

• WO NO UNIT EQUIPMENT IDENTIFICATION 8702181371 2 21 RC LOOP WR T COLD FAILURE DESCRIPTION: FAILED LOW, PLEASE FIX.

CORRECTIVE ACTION: PERFORMED CHANNEL CALIBRATION PROCEDURE:2.10.054 FOR RED PE

N. PROCEDURE

SAT. PERFORMED PROCEDURE

'2.10.055 FOR BLUE PEN, FOUND LOW LEVEL ANP 2IN-413B DEFECTIVE. REPLACED WITH NEW MODULE. CHANNEL JuqD -

RECORDER SAT.

8702120038 2 22 SW BACKWASH STRAINER VALVE FAILURE DESCRIPTION: VALVE.WILL NOT OPEN STRAINER-D/P. SV-0206 IS NOT WORKING PROPERLY. SOLENOID CYCLES IF CONDUIT IS SHAKEN. STRAINER IS NOW IN CONTINUOUS BACKWASH BY FAILING A IR SUPPLY. PLEASE. REPAIR..

CORRECTIVE ACTION: REPLACED SOLENOID VALVE COIL AND REINSTALLED SOLENOID VALVE COVER REQ.NON IN STOCK VALVE TESTED SAT, REPLACED COVER._

s'

-y SALEM' GENERATING STATION MONTHLY OPERATING

SUMMARY

'- UNIT NO. 2-FEBRUARY 1987 The Unit began 1the period by: reducing from: 100%, 1,150?KW gross for a short'periodion Sunday, February._l, 1987,.because of grass; fouling.the circulating. water screens. The unit returned to 100% power at 3:00 p.m. the same day: and continued at that level ~until early Thursday,.

February 5, when power was reduced to 85%.to clea No.'23 Condensate Pump: suction strainer. Power was increased to 100% following. return of the ' condensate pump.: -The. unit operated at 100%, 1,'150 MW-gross for

'the rest of~the month, except for a few brief-power reductions on February.14,.21-and:28 to perform turbine valve. tests.-

.The temporary; power feed from Hope Creek to: Salem: Unit No. 2's third circulating water- puap. was -completed int Wednesday, February 3, 1987.

Salem Unit 2 experienced apparent fuel failures in the February 4th to-February Sth? time. period. Dose Equivalent --I-131 values were

' detected to be: increasing on.the morning of February 5th and continued to increase until the' afternoon of February 7th. The DEI-activityL increased.from a nominal value of 2.3E-3 uCi/g to:a: peak value of:

4. 3E-2 uCi/g '. (an increase . of almost 19 times - the nominal) . The-activity _ increase throughout the weekend was the result of the. initial release of activity from the failed l fuel and.not a-continuing fuel failure event. . After.the peak on February'7th, the DEI activity started a slow decrease which is expected to continue until a'new

- primary ' system equilibrium is reached' (approximately one month) . The actual number'of fuel rods and/or type of failure cannot be predicted with any' confidence until a new primary system equilibrium is obtained.

1

j y- REFUELING INFORMATION DOCKET NO.: 50-311 COMPLETED BY: L.K. Miller UNIT NAME: Salem 2 DATE: March 12, 1987 TELEPHONE: 609/935-6000 EXTENSION:- 4497 Month February 1987

1. Refueling information has changed from last month:

YES NO X

2. Scheduled date for next refueling: April 9, 1988

3. Scheduled date for restart following refueling:

June 8, 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 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 refueling:

NONE

7. Number of. Fuel Assemblies:

A) Incore 193 B) In Spent Fuel Storage 224

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

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O PSIEG Public Service Electric and Gas Cornpany P.O. Box E Hancocks Bridge, New Jersey 08038 Salem Generating Station March 12, 1987 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 February 1987 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, k

J. . Z ko, Jr.

General Manager - Salem Operations JR:sl cc: Dr. Thomas E. Murley Regional Administrator USNRC Region I 631 Park Avenue King of Prussia, PA 19406 Director, Office of Management U.S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 Enclosures 8-1-7.R4 The Energy People

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