ML20106E513

Monthly Operating Rept for Sept 1984

ML20106E513
Person / Time
Site:	Salem
Issue date:	09/30/1984
From:	Ronafalvy J, Zupko J Public Service Enterprise Group
To:	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE)
References
NUDOCS 8410290259
Download: ML20106E513 (15)

Text

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-AVERAGE' DAILY UNIT POWER LEVEL Docket No.

50-272-

. Unit Name.

Salem #-1 Date Oct.- 10,1984 ~

Completed by J.~P.

Ronafalvy Telephone 609-935-6000

-Extension-4455-Month ~

September 1984 Day Average Daily Power Level Day: Average Daily Power Level (MWe-NET)

(MWe-NET)

~1 0

17 0

2 0

18-0 3-0 19 0

4

'0 20 0

5

-0 21 0

6 0

22 0

7 0

23 0

8 0

24 0

i

.9 0

25 0

10 0

26 0

11 0

27 0

'12 0

28 0

13 0

29 0

14 0

30 0

15 0

31 0

16 0

P.

8,1-7 R1 8410270259 840930 PDR ADOCK 05000272 R

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i OPERATING DATA REPORT Docket No.50-272 Date.

Oct. 10, 1984 Telephone 935-6000 Completed In(

J.

P.

Ronafalvy Extension 4455 Operating Status 1.

Unit Name Salem No. 1 Notes 2.

Reporting Period September 1984 3.

Licensed Thermal Power (MWt) 3338 4.

_ Nameplate Rating (Gross MWe)

IITY 5.

Design Electrical ~ Rating (Net MWe) 1090

-6.-

Maximum Dependable Capacity (Gross MWe)1124 7.

Maximum Dependable Capacity (Net.MWe) IbTF 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 6575 63600

12. No. of Hrs. Reactor was Critical 0

1237.6 34388.8

13. Reactor Reserve Shutdown Hrs.

0 54.5 3088.4

14. Hours Generator On-Line 0

1197.8 32975.7

15. Unit Reserve Shutdown Hours 0

0 0

16. Gross Thermal Energy Generated

(}Dm) 0 3800023 99619394

17. Gross Elec. Energy Generated (MWH) 0 1281380 32896480

18. Net Elec. Energy Generated (MWH) (10750) 1190286 31161598

19. Unit Service Factor 0

18.2 51.8

20. Unit Availability Factor 0

18.2 51.8

21. Unit Capacity Factor (using MDC Net) 0 16.8 45.4

22. Unit Capacity Factor (using DER Net) 0 16.6 45.0

23. Unit Forced Outage Rate 100 71.6 32.8

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:

10-13-84

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

l Forecast 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

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.,e.g UNIT SHUTDOWN AND POWER REDUCTIONS-Dock,t No.50-272-REPORT MONTH September 1984 Unit Ntme Salem No.l.

Date LOct. 10,1984 Completed by J.P.

Ronafalvy

_ Telephone 609-935-6000' Extension 4455

~ '

Method of Duration Shutting License Cause andLCorrectiver No.

Date Type Hours

-Reason Down Event System Component Action.to, 1

2 Reactor Report Code 4 Code 5 Prevent Recurrence ~

Generator Liquid HA GENERA Cooling System 84-176 7-9 F

720 A

4 Nuclear Service WA VALVEX Water Valves84-178 9-5 F

133.0 A

4 Nuclear Other Control-84-180 9-10 F

483.0 A

4 RB CRDRVE Rod Drive Problems.

1 2 Reason 3 Method 4 Exhibit G 5 Exhibit 1 F: Forced A-Equipment Failure-explain 1-Manual Instructions 1 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 Load Reduction Event Report.

G-Operational Error-explain 9-Other (LER) File H-Other-explain (NUREG.0161)

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t MAJOR PLANT MODIFICATIONS DOCKET'NO.:: 50-272 REPORT MONTH ~. September 1984-UNIT NAME:

Salem.1 DATE:

October 10, 1984 JCOMPLETED BY:-

J.

Ronafalvy

-TELEPHONE:

609/339-4455

• DCR NO.

. PRINCIPLE SYSTEM.

SUBJECT i

i

- 1BC-1413

' Reactor Coolant Replacement.of reactor coolant wide range RTD's with environmentally qualified elements..

1EC-1514 Incore Thermocouples Change method of~ connecting field. cable to incore.

thermocouples.

Also cable itself will be replaced.

1EC-1622 Station Air Assign a new number to 1SA323 (A-3) valve.

This valve is located on the 4" line to the Condensate Polishing System demineralizer.

1EC-1628 Reactor Protection Rewire shunt trip coil of "A",

(B) reactor trip breakers to open breakers upon a SSPS "A" ~

and/or SSPS "B" train trip signal.

1EC-1652 Safety Injection Replace the existing 2" accumulator level tap isolation valves with two 1" Yarway valves.

1EC-1762

- Miscellaneous Upgrade the condenser spray Condensate Condenser headers in the~1ower exhaust Sprays necks of condenser shells #11, 12, 13._. Modify'hange'rs to prevent pipe breakage due to high thermal stress loading.

1EC-1860 Charging / Safety Replace the existing lube oil Injection Pumps Lube coolers on the Nos. 11 s.12 Oil Coolers C/SI~ pumps with coolers of.

similar design characteristics but upgraded materials ~of constructions.

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-MAJOR-PLANT l MODIFICATIONS DOCKET NO.: 150-272 REPORT MONTH September 1984 UNIT NAME:- Salem 1 DATE:: October 10, 1984 COMPLETED BY:

J.

Ronafalvy TELEPHONE: -609/339-4455

• DCR NO.

PRINCIPLE SYSTEM -

SUBJECT.

1EC-1945 Containment.

Install spring assembly in the Ventilation backdraft-damper mechanism of the Containment Fan Coil Units

~ 11, 12, 13, 14 and 15.

'1SC-0025A

Fuel Transfer Modify Fuel Transfer. System-

~

System (WRAPS.13) to improve the operation of original WRAPS la modification.

1SC-1043 Circulating Water Change anchor bolts'on the following equipment:

11, 12, 13 and 14 Screen Wash Pumps and their associated automatic strainers.

Also change anchor bolts on #1 and #3 Circulator Bearing Lube Pumps and their associated automatic strainers.

1SC-1287A Containment Sump Modify control circuit to Pumps prevent both pumps from running prior to reaching Hi-Hi level due to logic error in pump alternating circuit.

ISC-1357 Containment Replace containment fan coil ventilation unit suction expansion joints with ones of improved design.

1SC-1449 Reactor Coolant Provide an alternate oil lift Pump Motor Oil Lift pump for the reactor coolant Pump pump oil lift pump.

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=-

8

' e' MAJOR PLANT MODIFICATIONS DOCKET NO.:

50-272

. REPORT MONTH SEPTEMBER 1984 UNIT NAME:

Salem 1 DATE:

October 10, 1984 COMPLETED BY:

J.

Ronafalvy TELEPHONE:

609/339-4455

• DC R NO.

SAFETY EVALUATION 10 CFR 50.59 1EC-1413 This change involves a direct replacement of existing equipment.

The system will not change functionally.

No unreviewed safety or environmental questions are involved.

1EC-1514 This modification does not alter reliability of safety related systems.

This change introduces e superior method of connecting cables as well as introducing a cable that has been environmentally qualified.

The cable function remains unchanged.

No unreviewed safety or environmental questions are involved.

1EC-1622 This change only specifies the correct identification of a valve.

No unreviewed safety or environmental questions are involved.

l 1EC-1628 This change does not alter any plant process or discharge.

No unreviewed safety or environmental questions are involved.

l 1EC-16 52 This change is a mechanical change that does not alter the l

installed controls equipment function.

No unreviewed safety or en',1ronmental questions are involved.

l 1EC-1762 This change in the condenser spray header hangers will not l

affect station operations or plant effluent.

No I

unreviewed safety or environmental questions are involved.

l 1EC-1860 This change involves the inst.allation of lube oil coolers with upgraded materials but with the same design specifications.

These new coolers are designed to the 1980 Edition of the ASME Code - Section III, Class 3 1981 on the Service Water side and designed to Division I of Section VIII of the 1980 Edition of the ASME Code on the lube oil side.

No unreviewed safety or environmental questions are involved.

'*DCR - Design Change Request

e

~ *DCR NO.

SAFE 1Y EVALUATION 10 CFR 50.59 1EC-1945 The new spring assembly does not prevent opening of the damper blades when the fan operates.

Failure of the spring does not jeopardize the operation of the backdraft damper.

Also, it does not affect any presently performed Safety Analysis nor does it create any new safety hazards.

No unreviewed safety or environmental questions are involved.

ISC-0025A This change does not affect any performed safety analysis nor does it create any new safety hazards.

No unreviewed safety or environmental questions are involved.

ISC-1043 This change is a replacement in kind except that the anchor is made of an upgraded material designed to resist chloride corrosion.

No unreviewed safety or environmental questions are involved.

1SC-1287A This change has been reviewed for all realistic failure modes and it has been determined that no unreviewed safety or environmental questions are involved.

1SC-1357 This change involves the replacement of an expansion joint in the CFCU's.

The replacement is of an improved design.

It does not change the original function of the expansion joint.

No unreviewed safety or environmental questions are involved.

1SC-1449 This modification is non-safety related.

No unreviewed safety or environmental questions are involved.

• DCR - Design Change Request

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.j PSE&G SALEM GENERATING STATION SAFETY RELATED WORK ORDER LOG i

SALEM UNIT 1 l

WO NO DEPT UNIT EQUIPMENT IDENTIFICATION 0099103915 SMD 1

10 0' ELEVATION AIRLOCK FAIURE DESCRIPTION:

EXTERIOR DOOR WILL NOT OPEN

,3 CORRECTIVE ACTION:

READJUSTED INTERLOCK ROD l

0099099233 SMD 1

VALVE 12MS167 FAILURE DESCRIPTION:

ALL THE OIL IN THE HYDRAULIC SYSTEM OF VALVE BLEW OUT 1

~

CORRECTIVE ACTION:

BLED AND REFILLED RESERVOIR 939520-7 OD 1

NO. 13 REACTOR COOLANT PUMP - SEAL LEAKOFF I

FAILURE DESCRIPTION: -LOW FLOW INDICATED AS COMPARED WITH OTHER PUMPS CORRECTIVE ACTION:

NO. 13 RCP SEALS REPLACED l

0099026066 l

SMD 1

OHA C-28 SPENT FUEL PIT LOW ALARM l

I FAILURE DESCRIPTION:

AL uM DOES NOT COME IN WITH ACTUAL LOW LEVEL l

CORRECTIVE ACTION:

REPLACED ALARM DEVICE t

0099103354 SMD 1

1RC43 - REACTOR HEAD VENT l

FAILURE DESCRIPTION:

VALVE IS LEAKING THROUGH l

l CORRECTIVE ACTION:

CLEANED INTERNAL PARTS l

UNIT 1 WO NO DEPT UNIT EQUIPMENT IDENTIFICATION 0099103346 SMD 1

1RC41 - REACTOR HEAD VENT FAILURE DESCRIPTION:

VALVE LEAKS THROUGH CORRECTIVE ACTION:

CLEANED INTERNAL PARTS 94170 PD 1

1PS1 FAILURE DESCRIPTION:

VALVE DOES NOT OPEN FROM CONTROL ROOM

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CORRECTIVE ACTION:

REPLACED DIAPHRAGM ON VALVE; REPLACED MAN / AUTO I

STATION IHC455 936925 PD 1

IPS3 FAILURE DESCRIPTION:

WITH A 60% DEMAND SIGNAL THE CLOSE LITE DOES' NOT EXTINGUISH AND THE VALVE DOES NOT APPEAR TO OPEN.

CORRECTIVE ACTION:

REPLACED DIAPHRAGM; REPLACED POSITIONER RELAYS; REPLACED AIR REGULATOR; REPLACED LEAKING CONOFLOW REGULATOR TO TRANSDUCER-943632 SMD 1

13GB3 FAILURE DESCRIPTION:

VALVE FAILED LEAK RATE TEST CORRECTIVE ACTION:

CLEANED STEM; REPLACED GASKET.

84-09-24-052-1 SMD 1

1C DIESEL FAILURE DESCRIPTION:

SWITCH ON THE 125V DC CONTROL POWER FOR THE 4KV DIESEL GEN OUTPUT BROKE OFF i

CORRECTIVE ACTION:

REPLACED SWITCH

?

WO NO DEPT UNIT EQUIPMENT IDENTIFICATION 84-08-30-001-6 SMD 1

IB DIESEL GENERATOR FAILURE DESCRIPTION:

D/G AIR STARTING VALVES FAILED TO ATTAIN THE REQUIRED 50 RPM DURING SURVEILLANCE TESTING CORRECTIVE ACTION:

REPLACED STARTING MOTOR AIR SOLENOID VALVE PILOT AIR START VALVES POSITIONS 1 AND 4 0099128578 SMD 1

VITAL HEAT TPACING FAILURE DESCRIPTION:

FIRE IN BIT HEAT TRACE; DE-ENERGIZED AT OPENING BREAKER IN HEAT TRACE PANELS 1A2 AND 1B2 CORRECTIVE ACTION:

HT622 PRIMARY AND SECONDARY FOUND SHORTED TO THE PIPE; REPLACED BURNT ENDS 84-07-04-340-1 SMD 1

llCFCU FAILURE DESCRIPTION:

FAN TRIPPED ON OVERLOAD OF LOWER SPEED BREAKER WHEN ATTEMPTING TO START IN HIGH SPEED CORRECTIVE ACTION:

REPLACED STARTING RELAY FOR HIGH SPEED BREAKER 0099103940 SMD 1

NO. 12 CFCU MOTOR FAILURE DESCRIPTION:

HIGH WINDING AND BEARING TEMPERATURES CORRECTIVE ACTION:

REPLACED MOTOR 0099104768 SMD 1

NO. 12 CFCU FAILURE DESCRIPTION:

SERVICE WATER LEAK DOWNSTREAM OF 12SW71 MOTOR COOLER SW OUTLET VALVE CORRECTIVE ACTION:

INSTALLED NEW SPOOL PIECE AND FLANGE D

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jeA WO NO DEPT UNIT EQUIPMENT IDENTIFICATION

.84-09-03-033 ;

SMD 1

NO. 12-CONTAINMENT SUMP PUMP

. FAILURE DESCRIPTION:

PUMP. RUNS CONTINUOUSLY WHEN THE-BREAKER IS CLOSED CORRECTIVE ACTION:

NOS. 11 AND 12 SUMP PUMP STRAINERS WERu FOUND CLOGGED-AND SUBSEQUENTLY WERE CLEARED; REPAIRED BROKEN LUG ON INDICATION LEAD 84-07-30-042-1 SMD

-1 NO. 11 CHILLED WATER PUMP FAILURE DESCRIPTION:

PUMP TRIPS AFTER ONE HOUR RUN CORRECTIVE ACTION:

CLEANED PUMP AND INSTALLED NEW SEALS 84-09-08-017-6 SMD 1

14MS17 8 (CHECK VALVE)

I FAILURE DESCRIPTION:

VALVE HAS BONNET LEAK i

CORRECTIVE ACTION:

REPLACED BONNET GASKET AND USED FURMANITE COMPOUND s

l 84-09-13-020-3 SMD 1

ISJ79 I

FAILURE DESCRIPTION:

BODY TO BONNET LEAK 4

CORRECTIVE ACTION:

REMOVED EXTRA GASKET AND REPLACED CORRODED STUD 951382 OD 1

VALVE ISJ222 - ISJ223 FAILURE DESCRIPTION:

VALVE LEAKS BY ITS SEAT i

CORRECTIVE ACTION:

CUT OUT VALVES AND WELDED IN NEW VALVES AS PER-DCR LED-0351 i

p-UNIT 1 WO NO DEPT UNIT EQUIPMENT IDENTIFICATION 84-08-25-017 SPD 1

ISJ4 FAILURE DESCRIPTION:

NO CLOSED INDICATION IN THE CONTROL ROOM CORRECTIVE ACTION:

CLEANED CONTACTS 0099026058 SMD 1

NO. 12 BORIC ACID TRANSFER PUMP FAILURE DESCRIPTION:

SEAL LEAK CORRECTIVE ACTION:

REPAIRED PUMP 84-09-04-090-5 SMD 1

NO. 16 SERVICE WATER STRAINER FAILURE DESCRIPTION:

SHEAR PIN ON STRAINER SHEARED CORRECTIVE ACTION:

PEPLACED BOTTOM SHOES AND SHEAR KEY 0099101696 SMD 1

llSW20 FAILURE DESCRIPTION:' VALVE INOPERABLE CORRECTIVE ACTION:

CHANGED TORQUE SWITCH SETTING 84-09-08-043-5 SMD 1

llSW23 FAILURE DESCRIPTION:

CLOSED INDICATION DOES NOT CHANGE WHEN CYCLING THE VALVE CORRECTIVE ACTION:

REPLACED AUXILIARY RELAY

f SALEM GENERATING STATION MONTHLY OPERATING

SUMMARY

September 1984 SALEM UNIS NO. 1 Unit No.1 remained shutdown as the fif th refueling outage continues.

The Unit began the month in Mode 5.

Preparations were completed for Unit. operational Mode changes f rom Mode 5 to Mode 4 and from Mode 4 to Mode 3.

The Unit entered Mode 4 on I

9/02/84 and on 9/07/84 entered Mode 3.

Limitorque valve i

modifications were completed on 9/02/84.

A total of thirty-eight (38) valves were inspected of which thirteen (13) required modification.

No.12 CFCU motor has been replaced.

No. 13 Service Water Strainer has been repaired.

Valve 13SN20 was i

reinstalled af ter repairs.

During Rod Drop Tests, Control Rod i

62B1 could not be raised past indicated position of 187 steps.

On 9/12/84 at 2311 hours0.0267 days <br />0.642 hours <br />0.00382 weeks <br />8.793355e-4 months <br /> a Unit cooldown was commenced to j

investigate and effect repairs for the problem with Control Rod j

1. 2Bl.

The Unit entered Mode 6 on 9/17/84.

Investigation of the problem wigh Control Rod 42B1 revealed that its tophat was rotated 90 out of position.

In addition to correcting this problem, the remaining sixty (60) tophats were also checked.

Control Rod #2D2's tophat was also found rotated.

During the Split Pin Replacement work perf ormed by Westinghouse, the tophats were removed for each control rod guide tube in the upper internals to facilitate replacement of the split pins.

Apparently, during the process, the two top hats in question were inadvertently repositioned.

Following discovery, the tophats were positioned correctly.

In the process of replacing the Reactor Vessel Head, the thermocouple column in core location L-1 was slightly bent.

Following repairs to the thermocouple column the Reactor Vessel Head was installed on 9/23/84.

On 9/27/84 the Unit entered Mode 5.

During the week of 9/24/84, a CVCS outage was initiated and completed.

As of 9/30/84, the conoseals were installed and the thermocouple connections were being secured.

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REFUELING INFORMATION DOCKET NO.:

50-272 COMPLETED BY:

J. Ronafalvy UNIT NAME:

Salem 1 DATE:

October 10, 1984 TELEPHONE:

609/935-6000 l

EXTENSION:

4455 Month September 1984 1.

Refueling information has changed from last month:

YES NO X

+

2.

Scheduled date for next refueling:

February 22, 1986 l

3.'

Scheduled date for restart following refueling:

May 4,1986

{

4.

A)

Will Technical Specification changes'or other license amendments be required?

l YES NO NOT BETETtMINED TO N 10/1/84 B)

Has the reload fuel design been reviewed by the Station Operating Review Committee?

I YES NO X

If no, when is it scheduled?

January 1986' l

L 5.

Scheduled date (s) for submitting proposed licensing action l

January 1986 if required 6.

Important licensing considerations associated with refueling:

I NONE l

7.

Number of Fuel Assemblies:

i A)

Incore 193 l

B)

In' Spent Fuel Storage 296

~~~

8.

Present licensed spent fuel storage capacity:

1170 Future spent fuel storage capacity:

1170 l

l 9.

Date of last refueling that can be discharged l

to spent fuel pool assuming the present i

l licensed capacityt September 2001 8-1-7.R4 i

i i

1

,i c) 0 PSEG Public Service Electric and Gas Company P.O. Box E Hancocks Bridge, New Jersey 08038 Salem Generating Station October 10, 1984 Director, Office of Inspection and Enforcement U.S. Nuclear Regulatory Commission Washington, DC 20555 Dear Sir 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 September 1984 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. M.

Zupko, Jr.

General Manager - Salem Operations JR sbh cc Dr. Thomas E. Murley Regional Administrator USNRC Region I 631 Park Avenuo King of Prussia, PA 19406 Director, Office of Management Information and Program Control U.S. Nuclear Regulatory Commission Washington, DC 20555 Enclosures Page of 8-1-7.R4 rat 4 The Ener0Y POOPIO 8/g wa wmwi ii si