ML20128K305

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Monthly Operating Rept for June 1985
ML20128K305
Person / Time
Site: Salem PSEG icon.png
Issue date: 06/30/1985
From: Ronafalvy J, Zupko J
Public Service Enterprise Group
To:
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE)
References
NUDOCS 8507240089
Download: ML20128K305 (16)
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AVERAGE. DAILY UNIT POWER LEVEL Docket No. 50-311 Unit Name Salem # 2 Date July 10,1985 Completed by J. P. Ronafalvy Telephone 609-935-6000 e Extension 4455 Month June 1985 Day Average Daily Power Level Day Average Daily Power Level (MWe-NET) (MWe-NET) 1 1093^ 17 1091 2 1104 18 1105 3 1092 19 1098 4 1093 20 1107 -

l 5 1099 21 1105-6 1095 22 1110 7 1096 23 1111 8 1083 24 1101 9 1101 25 1092 10 1103 26 1108 11 1098 27 1095 12 1107 28- 584 13 606 29 0 14 908 30 0 15 1090 31 16 1100 Pg.'8.1-7 R1 4

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OPERATING DATA REPORT

-I Docket No. 50-311 Date July 10,1985 Telephone 935-6000 Completed by J. P. Ronafalvy Extension 4455 Operating Status l

1. Unit Name Salem No. 2 Notes
2. Reporting Period June 1985  !
3. Licensed Thermal Power (MWt) 3411
4. Nameplate Rating (Gross MWe) 1170
5. Design Electrical Rating (Net MWe) 1715
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 720 4343 32568
12. No. of Hrs. Reactor was Critical 665.1 1719.7 16814.3
13. Reactor Reserve Shutdown Hrs. 0 0 3533.6
14. Hours Generator On-Line 664.0 1491.2 16103.3
15. Unit Reserve Shutdown Hours 0 0 0
16. Gross Thermal Energy Generated (MWH) 2210338 4486057 48213093
17. Gross Elec. Energy Generated (MWH) 740060 1470200 15747850
18. Net.Elec. Energy Generated (MWH) 708944 1364471 14882307
19. Unit. Service Factor 92.2 34.3 49.4
20. Unit Availability Factor 92.2"- 34.3 49.4
21. Unit Capacity Factor (using MDC ' Net) 89.0 28.4 41.3
22. Unit Capacity Factor (using DER Net) 88.3 28.2 41.0
23. Unit Forced Outage Rate 7.8 62.7 40.9
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:

7-7-85

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 u

F UNIT SHUTDOWN AND POWER REDUCTIONS Dockst No.-50-311 REPORT MONTH June 1985 - Unit Nrme Salem No.2 Dato July 10,1985 .

Telephone 609-935-6000 Completed by J.P. Ronafalvy 4455 Extension Method of Duration Shutting License Cause and Corrective Hours Reason Down Event System Component Action to No. .Date Type 1 2- Reactor Report Code 4 Code 5 Prevent Recurrence Condenser Tube B 5 - HC HTEXCH Inspection 85-110 6-13 F 5.9 Nuclear.Nonpower F 56.0 A 1 - CJ VALVEX operated safety valves85-130 6-28 Reactor Coolant 3 Method 4 Exhibit G 5 Exhibit 1 1 2 Reason Salem as F: Forced A-Equipment Failure-explain 1-Manual Instructions 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)

s MAJOR PLANT MODIFICATIONS DOCKET NO. : 50-311 REPORT MONTH JUNE 1985 UNIT NAME: Salem 2 DATE: July 10, 1985 __

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

  • DC R NO . PRINCIPLE SYSTEM SUBJECT 2EC-1014 Component Cooling Provide motor operators for component cooling water pumps discharge header valves 21CC3 and 22CC3.

2EC-1225 Turbine Generator Install reflash annunciator interface locally for the isolated phase bus alarms so that multiple alarms for.the above system can be acknowledged at the Control Room with a local self test fea ture .

2EC-1406 28V D.C. Replace existing undervoltage relay with new type.

2 EC-1532 Waste Gas Install redundant waste gas oxygen analysis capability.

2EC-1559 Nuclear Instrumentation Addition of.a complete source

-range indication in order to provide source range flux indication.at the remote shutdown panel. The new channel is to be electrically  ;

isolated from the Control Room.

2ET-1685 Circulating Water Replace'23B circulating water traveling screen with a screen whose effective height is

changed from 40' to 20' - will be done by raising entire rotating assembly 20'.

Remaining traveling screen

, frame will be enclosed down to El. 50'.

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  • Design Change' Request ~

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  • DCR NO. -PRINCIPLE SYSTEM SUBJECT i

2EC-1699A Circulat!.ng Water - Install a 316 S.S. traveling

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Traveling Screen screen in place of 21A screen.

Install one set of 316 S.S.

baskets in 23A traveling

, screen. Install 316 S.S.

flexible hose on screen wash connections.

2EC-1767 Post Accident Sampling Design and install sample System lines from the discharge of the FHR pumps to the PASS Liquid Sampling Panel #813.

The modification shall be capable of sampling the ill, 12, 21 and 22 RHR trains.

Samples shall be conditioned / cooled prior to entering Panel 813.

2EC-1776 Circulating Water Replace the remaining inlet i

expansion joints of Unit No. 2 Main Condenser.

2F.C-1916 Reactor Coolant Replace RTD bypass loop valves 22RC16, 17, 24, 25 & 28 Mark No. FA-17 with Mark No.

FA-131.

2EC-1918 . Reactor Coolant Replace RTD bypass loop valves 24 RC 16 , 17, 24, 25 & 28 mark No. FA-17 with Mark No.

j FA-131.

2EC-1919 Reactor Coolant Replace RTD bypass loop valves 21RC16, 17, 24, 25 & 28 mark l

No. FA-17 with Mark No.

'FA-131.

2EC-2056 Steam Generator Feed' Replace 2BF75 socket welded and Condensate- relief valve Mark No. M206, 4

with a flanged relief valve Mark No. F77.

2EC-2101 Auxiliary Feedwater -Replace #21 Aux Feedwater Pump .

- motor (Allis-Chalmers)_with spare (Westinghouse) motor.-

2SC-1245 Pressurizer Change design of pressurizer Overpressurization system to one similar to Protection- Unit 1,. utilizing 2PR1 and 2PR2 as the " POPS" valves.

  • Design' Change Request v

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MAJOR PLANT MODIFICATIONS DOCKET NO.: 50-311

- REPORT MONTH' JUNE 1985 UNIT NAME: Salem 2 DATE: July 10, 1985 COMPLETED BY: J. Ronafalvy TELEPHONE: 609/339-4455

  • DC R NO. 10CFR 50.59 SAFETY EVALUATION 2EC-1014 The new motor operators will enable more rapid and remote operation of the valves. The handwheels will be retained.

The valves and their function do not change. The new

  • operators will be seismically (Class I) and '

environmentally qualified. The description as addressed in the FSAR will be. appropriately modified. No unreviewed safety or environmental questions are involved.

2EC-1225 The isolated phase bus and its alarms are not safety related nor do. they affect any safety related systems .

through this DCR. No unreviewed safety or environmental l questions are involved.

2EC-1406 This DCR installs an undervoltage relay with a higher setpoint than the currently installed relay. The relay is not safety related. No unreviewed safety or environmental questions are involved.

2EC-1532 -This DCR enhances the oxygen analysis of the Waste Gas System by providing redundancy. It-does not affect the function of any safety 'related system nor will it affect the safe shutdown of the plant. No unreviewed safety or environmental que'stions are involved.

2EC-1559 This DCR will meet the 10CFR 50, Appendix R and Regulatory Guide l.97 requirements for post accident monitoring.

Fire wrapping, cable routing and power sources have been considered for this installation. ~ No unreviewed safety -or environmental questions are involved.--

. 2 ET-16 8 5' This modification.will not reduce the present open area of the. screen. A velocity survey:will be performed in order to evaluate this proposed configuration prior to implementation of any further changes. This change does not affect the presently performed safety analysis nor; does.it create any new hazards. No unreviewed safety or .

environmental questions are-involved.

  • . Design Change _ Request' i L -~. 1 ___

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l 2EC-1699A This change does not affect the presently performed safety analysis nor does it create any new hazards. No unreviewed safety or environmental questions are involved.

2EC-1767 The installation is being performed in accordance with the design specifications for the presently installed sampling system sample lines. It does not affect the ability to safety shutdown the Unit and will enhance the available information for maintaining the plant at safe. shutdown after an accident. No unreviewed safety or environmental questions are involved.

2 EC-1776 The replacement of the Main. Condenser Inlet Expansion Joints does not affect any presently performed safety analysis nor does it create any new hazards. No unreviewed safety or environmental questions are involved.

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2EC-1916 The replacement of the valves does not alter the. ability of the piping system to perform as designed. The:new valve has been evaluated as an acceptable substitute. The valve meets or exceeds seismic, nuclear, and pressure class of the existing valves. The flowmeter in the loop will ensure that the required flow is not affected. No unreviewed safety or environmental questions are involved.

2EC-1918 The replacement of the valves does not' alter the ability of the piping system.to perform as designed. The new valve has been evaluated as an- acceptable substitute. The valve meets or exceeds' seismic, nuclear, and pressure class of the existing valves. The flowmeter in the loop will~ ensure that the required-flow is not affected.- No unreviewed safety or environmental questions are involved.

2EC-1919 The replacement of the valves does not alter the ability of the piping system to perform as designed. -The new valve has been evaluated as an acceptable substitute. The valve meets cn: exceeds seismic, nuclear, and pressure

. class of the existing valves.- eThe flowmeter in the loop

-will ensure-that the required flow is not affected. No unreviewed safety cn: environmental questions are. involved..  ;

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* - Design Change Request ~ j I

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  • DCR No. 10CFR 50.59 SAFETY EVALUATION 2EC-2056 The replacement of relief valve 2BF75 (welded in place)
with' a relief valve with break flanges will not change the i function of.the system and will ensure its integrity. The 4 modification does not affect any safety related system and will not affect plant shutdown. The valve is not safety related and will not affect any safety related

-installation. No unreviewed-safety or environmental

, questions are involved.

2EC-2101 The replacement motor is a Westinghouse safety related

motor of equ'ivalent size,-horse power, RPM,'and mourti_ng configuration. The replacement will not alter the

. -operation or reliability of the system and will not adversely affect the safe shutdown of'the plant. No i unreviewed safety or environmental questions are involved.

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2SC-1245 The original' design function of the system remains unchanged. The design change addressed itself to new

, plant protection criteria. 'No unreviewed safety or i- environmental questions are involved.

  • Design. Change Request'

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r PSE&G SALEM GENERATING STATION SAFETY RELATED WORK ORDER LOG SALEM UNIT 2

-WO NO' DEPT UNIT EQUIPMENT IDENTIFICATION.

I850623019"~

SIC- 2 2CV179 AUTO CONTROLLER ,

FAILURE DESCRIPTION: -2CV179, PRIMARY WATER MAKEUP AUTO CONTROLLER, INTERMITTENTLY GOES FROM AUTO TO MANUAL CONTROL WHILE' ADJUSTING THE INCREASE / DECREASE SETPOINT PUSHBUTTONS. ALSO THE SETPOINT FAILS TO ZERO WHEN THIS OCCURS. PLEASE INVESTIGATE AND REPAIR.  ;

CORRECTIVE ACTION: REPLACED CAPACITOR ACROSS AUTO / MAN. RELAYS IN

  • SERVO-SETPOINT STATION lHC-lllC. ' OPERATOR VERIFIED SETPOINT.

J 8506181364 SMD 2- 21 SW PUMP STRAINER

. FAILURE DESCRIPTION: #21 SW PUMP HAS A PACKING LEAK. (STILL LEAKING).  ;

.THIS W.O. WAS WRITTEN TO COVER THE FAILED RETEST

-OF W.O. #8506143004.

CORRECTIVE ACTION:' ADD ONE RING OF PACKING.

8506141354-SIC 2 DRIVE MOTOR FAILURE DESCRIPTION: THE DRIVE FOR THE PSAT-TSAT RECORDER IS NOT WORKING.

PLEASE REPAIR.

' CORRECTIVE ACTION: FOUND CHART NOT ADVANCING. CHECKED FUSE FOR CHART MOTOR. REPLACED CHART DRIVE MOTOR.

SALEM UNIT 2 WO NO DEPT UNIT EQUIPMENT IDENTIFICATION 8506111790 SMD 2 21 B.A.T. P.

FAILURE DESCRIPTION: LEAK AT.' SHAFT SEAL. PLEASE REPAIR, BORON.

CRYSTALIZATION.

CORRECTIVE ACTION: ' CLEANED'UP BORON, REMOVED PLUGS IN MECH. SEAL.

REINSTALLED PLUGS WITH TEFLON TAPE.

8506031362 SMD 2 2SJ67, SI PUMP RECIRC FAILURE DESCRIPTION: 2SJ67 (SI PUMP MTR. OP. RECIRC VALVE) HAS A PACKING "

LEAK. PLEASE INVESTIGATE AND' REPAIR.

CORRECTIVE ACTION: TIGHTENED DOWN PACKING. LEAK STOPPED. ,

8506020093 SMD 2 22SW144 FAILURE DESCRIPTION: VALVE LEAKING FROM UNDER INSULATION. PLEASE INVESTIGATE AND REPAIR.

CORRECTIVE ACTION: FLANGE LEAKING. CUT OLD BOLTS OUT. ADDED NEW STUDS AND TIGHTENED SAME.

8505300149 SMD 2 21' CHARGING PUMP

FAILURE' DESCRIPTION
THE ' SUCTION AND DISCHARGE FLANGES ON 21 CHARGING PUMP HAVE DAMP BORON BUILD-UP.

CORRECTIVE ACTION: -REPLACED SUCTION GASKETS. CLEANED SUCTION SPOOL FLANGES. CLEANED DISCHARGE FLANGES.

SALEM UNIT 2 WO NO DEPT UNIT EQUIPMENT IDENTIFICATION 8505300211 SMD 2 22 CONT. SPRAY PUMP FAJLURE DESCRIPTION: #22 CONTAINMENT SPRAY PUMP HAS DAMP BORON BUILD-UP ON THE SUCTION FLANGE.  ;

CORRECTIVE ACTION: TIGHTENED FLANGE STUDS. ,

8505311221 SMD 2 22 SI PUMP FAILURE DESCRIPTION: THERE IS A SEAL LINE LEAKING WHERE IT ATTACHES TO THE HEAT EXCHANGER ON THE MOTOR END OF THE PUMP. ,

CORRECTIVE ACTION: FOUND LINE LOOSE, TIGHTENED.

8505312970 SIC 2 SSPS INTERFACE FAILURE DESCRIPTION: WHEN THIS VALVE WAS STROKED OPEN AND THE OPEN LIMIT WAS MADE UP, THE STATUS LIGHTS ON 2RP4 ILLUMINATED FOR 4

CONT. VENT & PHASE B ISOLATION, PLEASE INVESTIGATE.

CORRECTIVE ACTION: CHECKED OUT CIRCUIT AND FOUND BAD LIGHT ASSEMBLY ON LIGHT f338. DIODE SHORTED. REPLACED BLOCK ASSEMBLY AND HAD CONTROL OPERATOR OPEN 24AF21 AND VERIFIED THAT ONLY'THE STATUS LIGHT FOR 24AF21 WAS LIT.

8505260023

, SIC 2 PZ R. LEVEL CH. 1 FAILURE DESCRIPTION: PZR. LEVEL CH. 1 FAILED HIGH. PLEASE INVESTIGATE AND REPAIR.

CORRECTIVE ACTION: FOUND S/G ISOLATOR 2LM-459A HAD DRIFTED 1 VOLT HIGH.

REPLACED S/N QO-518 WITH 409.

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SALEM UNIT 2

- WO NO DEPT UNIT EQUIPMENT IDENTIFICATION 8505171314 SMD 2 23MD6, STEAM TRAP ISOLATION FAILURE DESCRIPTION: 23MS6, STEAM TRAP ISOLATION (MS167 DRAIN) IS BLOWING STEAM. PLEASE INVESTIGATE AND REPAIR.

CORRECTIVE ACTION: #

TEMP. REPAIRS MADE BY FURMANITING PACKING GLAND. t 8503260336 j SMD 2 AUX FEEDWATER SYSTEM FAILURE DESCRIPTION: PRESENT B-J AUX FEED PUMP NO. 22 IS DAMAGED. REPLACEMENT WITH AN EQUIVALENT PUMP FROM INGERSOLL RAND IS REQUIRED.,

CORRECTIVE ACTION: COMPLETED WORK ORDER AS PER 2EC2081. REPLACED AT PUMP WITH IR PUMP.

,0099158418 SMD 2 21 SW PUMP STRAINER FAILURE DESCRIPTION: 21 SW PUMP STRAINER HAS A PACKING LEAK.

' CORRECTIVE ACTION: REPLACED SHAFT THAT HAS BEEN REWORKED WITH BELZONI A, 4 NEW SHOES AND REPACKED STRAINER.

'0099158515 SMD 2 22.SW PUMP I FAILURE DESCRIPTION: PUMP HAS A SEVERE PACKING LEAK. PLEASE REPAIR.

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CORRECTIVE ACTION : REPACKED STRAINER, REPLACED SEALS PLATES IN STRAINER.

I REPLACED HEADSHAFT, SLEEVE FROM 25 SW PUMP INTO 22.

REPACKED PUMP.

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4 SALEM UNIT 2 WO NO - DEPT- UNIT EQUIPMENT IDENTIFICATION 0099160277 SMD 2 22 AUX FEED PUMP FAILURE DESCRIPTION: THE MOTOR INBOARD BEARING WENT INTO ALARM. THE OIL WAS CHANGED BUT THE TEMPS DID NOT STABILIZE PRIOR TO REACHING 185 DEGREES.

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' CORRECTIVE ACTION: MOTOR SENT TO KEYSTONE FOR ARG. REPLACEMENT AND FAN REVERSAL FOR NEW INGERSOLL RAND PUMP.

0099164213 SMD 2 AFD RECORDER FAILURE DESCRIPTION: THE RECORDER SPIKED HIGH. I&C PLEASE INVESTIGATE AND REPAIR.

- CORRECTIVE ACTION: FOUND 20M-202B FAILED HIGH. REMOVED SN-693 AND INSTALLEN SN-691. CALIBRATED TO SPEC.

.'0099164337 <r

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SIC 2 BOD POSITION IND '

) - FAILURE DESCRIPTION: ROD 1D2 IS READING 240 STEPS WHICH IS 12 STEPS ABOVE

- BANK DEMAND. PLEASE CHECK CAL.

CORRECTIVE ACTION: RECALIBRATED SIGNAL CONDITIONERS MODULE. OUT OF SPEC.

GRID BIO FINAL INDICATION 235 STEPS.

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SALEM GENERATING STATION MONTHLY OPERATING ~

SUMMARY

- UNIT NO. 2 JUNE 1985

, SALEM UNIT NO. 2 The period began with the Unit operating at full power. On 6/13/85 at N 1410 = hours, power was reduced to 25% due to a condenser tube leak in

'23B' Condenser Waterbox. Investigations revealed that a tube plug had dislodged. Full. power was-restored on C/14/85 at 1232 hours0.0143 days <br />0.342 hours <br />0.00204 weeks <br />4.68776e-4 months <br />. On f- 6/28/85 at 1600 hours0.0185 days <br />0.444 hours <br />0.00265 weeks <br />6.088e-4 months <br />, the Unit was taken off the line and brought to Mode 5 (Cold Shutdown) to support repair of Pressurizer Safety Valve 2PR4 which was leaking. Additional work to be done during this

" forced outage" includes repacking - various - secondary valves ,

replacement of. valve.22MS14 (Main Steam Safety Valve) , and investigation of hydrogen leakage from the Generator.

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REFUELING INFORMATION DOCKET NO. : 50-311 COMPLETED BY: J. Ronafalvy UNIT NAME: Salem 2 DATE: July 10 , 1985 TELEPHONE: 609/935-6000 EXTENSION: 4455 I

Month June 1985

1. Refueling information has changed from last month:

YES NO X

2. Scheduled date for next refueling: September 6, 1986

( 3. Scheduled date for restart following refueling: November 16, 1986

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

YES NO.

Not determined to date l

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 ccasiderations associated with refueling:

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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

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O PSEG -

Public Service Electric and Gas Company P.O. Box E Hancocks Bridge, New Jersey 08038 Salem Generating Station July 10, 1985 Director, Office of Inspection and Enforcement U.S. Nuclear Regulatory Commission Washington, DC 20555

Dear Sir:

MONTHLY OPERATING REPORT S ALEM NO. 2 DOCKET NO. 50-311 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 June 1985 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 Q 1

Jj . %d ko, Jr.

G neral Manager -

Salem Operations JR:sbh cc: Dr. Thomas E. Murley Regional Administrator USNRC Region I 631 Park Avenue King of Prussia, PA 19406 Director, Of fice of Management Information and Program Control U.S. N,,71 ear Regulatory Commission Washington, DC 20555 Enclosure 8-1-7.R4 The Energy People ] fl 95 2169 (20M) 1181 L

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