ML20141N930

Monthly Operating Rept for Feb 1986

ML20141N930
Person / Time
Site:	Salem
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 8603180288
Download: ML20141N930 (13)

Text

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AVERAGE DAILY UNIT POWER LEVEL Docket No. 50-311 Unit Name Salem # 2 Date March 10,1986 Completed 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 1079 2 0 18 1096 3 317 19 1105 4 1006 20 1101 5 1088 21 1093 6 1087 22 1036 7 1093 23 1086 8 1093 24 1091 9 1115 25 1091 10 1078 26 1089 11 1094 27 1056 12 1105 28 1080 13 1090 29 14 1109 30 15 1097 31 16 1086 Pg. 8.1-7 R1 l

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

1. Unit Name Salem No. 2 Notes

2. Reporting Period February 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 4 10. Reasons for Restrictions, if any N/A This Month Year to Date Cumulative 11._ Hours in Reporting Period 672 1416 38401

12. No. of Hrs. Reactor was Critical 629.7 971.7 21297.2

13. Reactor Reserve Shutdown Hrs. 0.0 0.0 3533.6

14. Hours Generator On-Line 618.9 953.4 20490.2

15. Unit Reserve Shutdown Hours 0.0 0.0 0.0- '

16. Gross Thermal Energy Generated (MWH) 2066002 3174315 62920013

17. Gross Elec. Energy Generated (MWH) 686220 1054650 20631130

18. Net Elec. Energy Generated (MWH) 657468 1006067 19540911

19. Unit Service Factor 92.1 67.3 53.4

20. Unit Availability Factor 92.1 67.3 53.4

21. Unit Capacity Factor (using MDC Net) 88.5 64.2 46.0

22. Unit Capacity Factor (using DER Net) 87.7 63.7 45.6

23. Unit Forced Outage Rate 7.9 27.5 36.9

24. Shutdowns scheduled over next 6 months (type, date and duration of each)

N/A 3

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

N/A

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

4 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 4

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.._.e UNIT SHUTDOWN AND POWER REDUCTIONS Dock 3t No. 50-311 ,i

' REPORT MONTH Fcbruary'1986 Unit Name Salem No.2

. #', 5 Dato- -March'10,1986 J.P. Ronafalvy Telephone. 609-935-6000 .

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

5 - CH INSTRU .Feedwater Pump.

042 0203 F. 11.7 A.

Local controls Intake system A 5 - HF' PUMPXX problems other.than 068 0222 F 1.3 traveling screens Traveling Screen /

A 5 - HF FILTER Trash Rack /

086 0227 F 1.1 Canal Screen-l 3

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t 3 Method 4 Exhibit G 5 Exhibit 1 -!

1 2 Reason Instructions Salem as A-Equipment Failure-explain 1-Manual F: Forced 2-Manual Scram. for.Prepara- Source S: Scheduled B-Maintenance or Test 3-Automatic Scram. tion of Data C-Refueling '

4-Continuation of Entry Sheets D-Regulatory Restriction Previous Outage for Licensee E-Operator Training & Licensing Exam l-F-Administrative 5-Load Reduction Event Report G-Operational' Error-explain 9-Other (LER) File-H-Other-explain (NUREG 0161) l i

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

DATE: March 10, 1986 l COMPLETED BY: J. Ronafalvy  !

TELEPHONE: 609/339-4455  ;

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• DCR NO.. PRINCIPAL SYSTEM SUBJECT f 2EX-1651 Service Water Modification of cards in the ,

2A Safeguard Emergency l Controller (SEC) in order to eliminate spurious actuations '

2ET-1876- Generator Test of Vital Bus "2B" 4.16KV Diesel Generator Supply Breaker (2BBD) Anti-Pumping '

1 Circuit and Strip chart monitoring of Vital Bus "2B" Bus Differential Control

, Circuit i' 2SC-0420 Service Water Modify the S.W. Cooling piping to the SW Pump motor coolers to allow quick removal and restoration of piping hangers and associated piping during motor change

.out

. 2EC-1894 Main Steam Add a "Y" type strainer downstream of valve 2MS55 2EC-1957' Pressurizer System Modify control circuit to 2PR6 and 2PR7 valves to prevent immediate direction

! reversal of valve 1

2EC-2003 E220, DC Power Replace existing 2C Battery System and replace with equivalent replacement (C & D Datteries Model LC-33 and Rack No. .

1 RD-659)

2EC-2026 Fire Doors Add two (2) doors in the Aux.

Bldg. and Mechanical ,

Penetration Areas.  !

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• Design Change Request ,

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UNIT 2 PLANT MODIFICATIONS (continued)

REPORT MONTH FEBRUAPY 1986

• DCR NO. PRINCIPAL SYSTEM SUBJECT 2SC-1093 Boric Acid System Construct a permanent platform around BA Batching Tank 2SC-1580 Main Steam Safety Remove lever #17, forked Valves lever #22, and spindle nut #12 on all 20 valves 2EC-1534 Building & Equipment Change nuclear Floor Drains, Flood classification of

& Sump Pumps Containment Sump Pumps from Nuclear Class III to Non-Nuclear Safety 2EC-0677 Switchgear & Revise dampers CAV12, Penetration Areas CAV13, and CAV33 to Ventilation System fail open. Also, add damper position indication to read out on the Aux.

Annunciator System Design Change Request l

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MAJOR PLANT MODIFICATIONS DOCKET NO.: 50-311 REPORT MONTH FEBRUARY 1986 UNIT NAME: Salem 2 DATE: March 10, 1986 COMPLETED BY: J. Ronafalvy TELEPIIONE: 609/339-4455

• DCR SAFETY EVALUATION 10CFR 50.59

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2EX-1651 The additional electronic components being added to the printed circuit cards in the 2A SEC are CCI items equivalent to many of the items already present in the SEC card files. They will not affect the seismic qualification of the SEC nor will they malfunction in any way which is inconsistent with the present design of the SEC.

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

2ET-1876 This design change does not change or add to plant systems or equipment. The test will not affect

-the function of the circuits being tested. No

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

2SC-0420 This modification changed the carbon steel cement  !

lined piping to the service water pump motor bearing coolers with 316 stainless steel and flex hose at the inlet and outlet connections. The

! system function was not changed and no new equipment was added. This change will prevent corrosion of the pipe thereby increasing the reliability of the system. No plant process or discharge is affected by this design change. No unreviewed safety or environmental questions are involved.

2EC-1894 The installation of the strainer does not create a new safety hazard. The strainer will provide protection to the restricting orifice by reducing the possibility of a " clogging" condition. The functioning of the system does not change with the installation of the strainer. A separate Safety Evaluation (#S-C-0210-MSE-277) which addresses the l strainers seismic qualification in accordance with '

10CFR Part 50 Section 50.55a has been completed.

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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UNIT 2 MAJOR PLANT MODIFICATIONS (continued)

REPORT MONTH - FEBRUARY 1966

• DCR SAFETY EVALUATION 10CFR 50.59 2EC-1957 The valve operation has been enchanced by the completion of this design chang 9 (rewiring) in accordance with manufacturer's recommendations.

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

2EC-2003 The existing 2C Battery arrangement was replaced I with an equivalent safety related Class lE Battery and Battery Rack. The replacement was required due to visible evidence that put the long-term life of the battery in doubt. No plant process or discharge is affected bythis design change. No unreviewed safety or environmental questions are involved.

2EC-2026 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 unreviewed safety or environmental questions are involved.

2SC-1093 The elimination of the need to erect temporary scaffolding removes a severe safety hazard. The new platform is seismically qualified. No plant process or discharge is affected by this design change. No unreviewed safety or environmental questions are involved.

• Denign Change Request

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UNIT 2 MAJOR PLANT MODIFICATIONS (continued)

REPORT MONTH - FEBRUARY 1986 i

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• DCR SAFETY EVALUATION 10CFR 50.59 1

2SC-1580 The removal of the lever, the forked lever, and

the spindle nut from the affected valves will not affect the operation of the valves. The pressure set points will also not be affected. The lifting levers were removed from the ASME code since 1977.

Also, the environment of a Nuc1 car Power Plant is l' much cleaner than a Fossil Plant which therefore

, precludes oxidation of the nozzle / disc area i preventing sticking or galling. Therefore, the

need for manual lifting levers is obviated. No i plant process or discharge is affected by this design change. No unreviewed safety or L environmental questions are involved.

l 2EC-1534 The Containment Sump Pumps are not part of a i safety related system and do not affect the safe L shutdown of the plant. They are not required to j mitigate consequences of an accident. No plant l process or discharge is affected by this design j change. No unreviewed safety or environmental '

questions ara involved. For additional ,

information refer to Salem Generating Station l Safety Evaluation #S-C-M700-MSE-161.

2EC-0677 The damper positions being modified were not used  !

i in the calculations for any presently performed safety analysis. Their failure does not i

constitute a new hazard not previously analyzer.

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

• Design Change Request l

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PSE&G SALEM GENERATING STATION $

SAFETY RELATED WORK ORDER LOG SALEM UNIT 2 -

WO NO DEPT UNIT EOUIPMENT IDENTIFICATION 8602090072 2 POWER RANGE CliANNEL 1 FAILURE DESCRIPTION: THE POWER RANGE CHANNEL NI-41 HAS FAILED LOW AND THE LOSS OF HIGH VOLTAGE ANNUNCIATOR CAME UP.

CORRECTIVE ACTION: REPLACED HIGH VOLTAGE POWER SUPPLY AND PERFORMED FUNCTIONAL TEST (SAT).

8602100027 2 23 SERVICE WATER PUMP FAILURE DESCRIPTION: THE STUFFING BOX BELOW THE PACKING GLAND HAS A SEVERE LEAK. IT LOOKS LIKE THE PACKING IS BLOWN.

CORRECTIVE ACTION: REPLACED GASKET MATERIAL UNDER THE TUBE TENSIONER LOCK NUT.

8602010117 2 22 REACTOR COOLANT PUMP FAILURE DESCRIPTION: THE SEAL INLET TEMPERATURE ON 22 RCP IS READING LOW.

t (65 DEGRESS). THE DORIC AND COMPUTER READ APPROX.

! 110 DEGREES.

CORRECTIVE ACTION: FOUND TE-154A&B LEADS LOOSE, TIGHTENED LOOSE LEADS TIGHTENED LEADS IN THERMOCOUPLE HEAD.

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SALEM UNIT 2 ,

WO NO DEPT UNIT EQUIPMENT IDENTIFICATION 8601070426 2 21 S/G STEAM RELIEF VALVE FAILURE DESCRIPTION: VALVE BLOWS BY.

CORRECTIVE ACTION: REMOUNTED LIMIT SWITCH PLATE TO VALVE; SET LIMIT SWITCHES BY CYCLING VALVE; REPAIRED BROKEN SECTION OF TUBING AND REPLACED STRIPPED FITTING WFICH WAS LEAKING.

8601060439 2 RCDT LEVEL INDICATION FAILURE DESCRIPTION: GAUGE INDICATES 3% WHILE CONTROL ROOM INDICATES 2%, ALSO VERIFY PUMP CUTOFF SETPOINT.

CORRECTIVE ACTION: INSTALLED AND CALIBRATED NEW METER BREAKER.

I SALEM GENERATING STATION MONTHLY OPERATING

SUMMARY

- UNIT NO. 2 FEBRUARY 1986 SALEM UNIT NO. 2 The Unit began the period in Mode 4 as the seal replacement for Nos.

22 and 24 Reactor Coolant Pumps was completed. It was returned to service on February 3, 1986 at 0505 hours0.00584 days <br />0.14 hours <br />8.349868e-4 weeks <br />1.921525e-4 months <br />. On February 22, 1986 at 0446 hours0.00516 days <br />0.124 hours <br />7.374339e-4 weeks <br />1.69703e-4 months <br />, the Unit was reduced in power. (to 66%) due to the loss of four (4) Circulating Water Pumps. The pumps had tripped due to high differential pressure across the strainers due to river grasses. The  :

Unit was returned to full power the same day at 0600 hours0.00694 days <br />0.167 hours <br />9.920635e-4 weeks <br />2.283e-4 months <br /> where it remained for the rest of the period.

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l REFUELING INFORMATION DOCKET NO.: 50-311

[ COMPLETED BY: J. Ronafalvy UNIT NAME: Salem 2 I DATE: March 10, 1986  :

TELEPHONE: 609/935-6000 I

EXTENSION: 4455 Month February 1986 i

! 1. Refueling information has changed from last month:

YES NO X l l

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

h YES NO X  !

If no, when is it scheduled? August 1986 r

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

August 1986 if required .

6. Important licensing considerations associated with refueling:

NONE I

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7. Number of Fuel Assemblies: [

A) .Incore 193 i B) In Spent Fuel Storage __140 T

8. Present licensed spent fuel storage capacity: 1170  !

Future spent fuel storage capacity: 1170

, 9. Date of last refueling that can be discharged l to spent fuel pool assuming the present licensed capacity: March 2003

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• i Public Service E'?ctric and Gas Company P.O. Box E Hancocks Bridge, New Jersey 08038 Salem Generating Station March 10, 1986 Director, Office of-Inspection and Enforcement

.U.S. Nuclear Regulatory Commission Washington, DC 20555

Dear Sir:

MONTELY OPERATING REPORT SALEM NO. 2 /

DOOKET 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 1986 are being sent to you.

Average Daily Unit Power Level Operating Data Report i Unit Shutdowns and Power Reductions Major Plant Modification Safety Related Work Orderc Operating Summary Refueling Information l

Sincerely yours, v4 b J. M. Zupko, Jr.

General Manager - Salem Operations JRakcb 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 l

'The Ener0y People '

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