ML20127L454

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Monthly Operating Rept for Apr 1985
ML20127L454
Person / Time
Site: Salem PSEG icon.png
Issue date: 04/30/1985
From: Ronafalvy J, Zupka J
Public Service Enterprise Group
To:
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE)
References
NUDOCS 8505220347
Download: ML20127L454 (14)
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AVERAGE DAILY UNIT POWER LEVEL Docket No. 50-272 Unit Name Salem # 1 Date May 10,1985 Completed by. J. P. Ronafalvy Telephone 609-935-6000 Extension 4455

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Month April 1985 Day Average Daily Power Level- Day Average Daily Power Level (MWe-NET) (MWe-NET)

'1' 1077 17 1100

.2 -1107 18 1093

-3 1095 19 1102 4 1092 20- 986 5 1099 21 1099 6- 1095 22 1039' 7 1107 23 1079 8- 1114 24 1109 9- 1093 25 1100 10 1103 26 1096 11 1084 27 1107 12- 1113 28 1089 13 1095 29 -1109 14 1106 30- 1090 15 1100 31 16 1107 P. 8,1-7 R1 h

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- ' , . OPERATING. DATA REPORT-Docket No.50-272 as, ,

.Date May 10, 1985 y .

Telephone 935-6000 Completed by -J. P. Ronafalvy Extension ~4455 sOperating Status

1. Unit Name . .

' Salem No.'1' Notes

2.  ; Reporting Period  : April 1985
3. . Licensed Thermal Power (Mit)~ -3338 L4.. Nameplate Rating (Gross MWe) T176
5. . Design Electrical l Rating (Net MWe) T5T6
6. ' Maximum Dependable Capacity (Gross MWe)IT2T
17. ~ Maximum Dependable Capacity (Net MWe) T67T

'8. If. Changes Occur in Capacity Ratings (items 3 through 7) .since Last Report,.Give' Reason- N/A 9..LPower Level to which Restricted, if any (Net MWe) N/A

10. Reasons 1for Restrictions, if any N/A This Month Year to Date Cumulative

'11.LHours in Reporting Period 719 2879 68688 11:2. ENo. of. Hrs. Reactor was Critical 719 2861.6 38685.1 13.-Reactor Reserve' Shutdown Hrs. 0 3088.4 14-. Hours Generator >On-Line 719 2858.7 37017.3 L15. Unit Reserve Shutdown' Hours 0 0 0

16. Gross Thermal Energy Generated Dem) 2394694 9477598- 112245595
17. Gross Elec. Energy Generated _

100G1) 818610 3243750 37159800 18.LNet'Elec.-Energy Generated (MWH) 787467 3118672 35216654 ly 19. Unit ~ Service Factor 100 99.3 53.9

20. Unit.-Availability Factor 100 99.3 53.9
21. Unit Capacity Factor'

-(using MDC Net)- 101.5 100.4 47.5

22. Unit Capacity Factor

-(using DER Net) 100.5 99.4 47.0

23. Unit-Forced-Outage Rate 0 0.7 31.5
24. Shutdowns scheduled over next 6 months (type, date and duration of each)

N/A 2..-If 5 shutdown at end of Report Period, Estimated Date of Startup:

N/A

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

Forecast Achieved i Initial . Criticality 9/30/76 12/11/76 i 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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' UNIT' SHUTDOWN AND POWER REDUCTIONS Dockrit No.'50-272' ,

. REPORT MONTH April 1985 Unit'Name S'ilem No.1

Date .

May 10,1985 Completed.by -J.P.-Ronafalyy' . Telephone 609-935-6000 ExtensionL 44 55 '

Method of Duration , . Shutting -License Cause and Corrective No. Date Type- Hours Reason Down LEvent System . Component- - Action to 1- 2 Reactor Report Code 4 Code 5 Prevent Recurrence

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  • There were no outages in April-resulting-in load. reductions greater than 20%._

1 2 Reason 3 Method 4 Exhibit G 5 Exhibit 1 1-Manual Instructions Salem as

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F: Forced A-Equipment Failure-explain 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)-

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' MAJOR PLANT MODIFICATIONS -DOCKET NO.: 50-272 REPORT 1 MONTH' APRIL 1985 UNIT NAME: Salem-1 DATE: .May-10, 1985 COMPLETED BY: J. Ronafalvy TELEPHONE: 609/339-4455

  • DC R NO. - PRINCIPLE SYSTEM . SUBJE CT 1BC-0743A-. Security Erect a subcontractors' security gatehouse.

1ET-11657 #14 Fan Coil Unit- Add. temperature connections to

  1. 14 FCU motor housing.

1EC-1264A Moisture Separator Modify existing HP-channels.to LReheater Steam ~and reflect.the design (that was performed,cnl the Unit 2'HP Drains channels. This includes the following: 1) Modify 4th pass drain connection to conform to the tube sheet ligament-configuration and seal using <

Kalrex "O" ring. 2) Modify the 3rd pass connection ~as in

-item (1)-above. 3) Modify channel cover to accept Kalrez "O" ring. 4) Re-route 4th pass drain and vent.

1EC-1611 Safety Injection Change valve packing for ~

valves 1SJ4, 5,:12 and 13

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(Valve Mark No. . FA-46) . from existing " John Crane 187-I" +

packing to new "Grafoil Halogenated Valve Stem Die '

Molded Ring Sets."

1EC-1810 Miscellaneous Change range of 1PL3325 and Condensate 1PL33 26 from 0-3004 to 0-6004.

11EC-1847' Generator Rewind of No. 1 Generator.

1EC-1929A Circulating Water Upgrade the material of construction of Circulating Water Pump 13A.

1EC-1948 Main Generator Replace existing hydrogen Hydrogen dryer with a larger capacity dual tower dryer..

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  • DCR NO. PRINCIPLE SYSTEM SUBJECT

-1MD-0091 Communications Implement Suggestion 77-159 to install interfacing relay _

between phone and P.A. system.

1SC-0159 Main Steam Provide low temperature alarm

-in north and south penetration.

1SC-0363 Condensate Modify condenser, heater drain and circulating water pump motors to allow filling of oil reservoirs.

1SC-0909. Circulating Water Provide.the following changes:

Traveling Screens 1) Stainless steel chain.

2) Fill in. unused fish trough.
3) Install trolley beam for basket removal. 4) Install access holes in head section.

1SC-0967 Potable Water . Install screening on potable water tank overflow line.

1SC-1272 Auxiliary Feedwater The.#13-Aux Feedwater Pump Trip Valve 1 MSS 2 presently ,

I does not provide indication'in the Control Room when it is reset and latched. Provide-indication-on the controls bezel to indicate when trip valve is reset and latched.

1SC-1305 Security (Barriers) Make additions and modifications to provide security barriers on outside air intake / exhaust openings on ventilation systems at 130' El. South Penetration.

1SC-1385 Heater Drain Pump Provide gland leak off' lines from all three heater drain pumps to the Turbine Building flood sumps.

1SC-1411A Annunciator System Delete-vacuum switch 1PD188.

Install an (actual trip) alarm actuated by vacuum trip solenoid.

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(( l MAJOR-PLANT MODIFICATIONS" DOCKET-NO.: 50-272 REPORT MONTH ~ APRIL 1985 UNIT NAME:  : Salem 1 DATE: May 10, 1985 COMPLETED BY: J .-- Ronafalvy TELEPHONE: 609/339-4455

- 1BC-0743A' 1The erection of a steel building will neither effect any previously performed safety analysis nor affect the safe operation of the plant. No unreviewed safety or environmental questions are involved.

1ET-1165 The addition of' thermometer connections to the Fan Coil housing'does not effect the safe shutdown of the plant.

No unreviewed safety or environmental questions are involved.

1BC-1264A .This change does not affect presently. performed safety

. analysis nor does it create any new hazards. The system involved is not safety related. No unreviewed safety or

-environmental questions are involved.

'1BC-1611 The replacement of the existing valve packing will

' increase the reliability of the affected valves. No

- unreviewed safety or environmental questions are involved.

R, 1EC-1810 :This change does not affect the intended function of the system. It will not change the plant process or discharge

-and will not affect the' existing plant impact. No unreviewed safety or environmental questions are involved.

1EC-1847 This change is a conventional installation which does not interface or alter any safety related equipment. No unreviewed safety or environmental questions are involved.

1EC-1929A This part changeout of Circulating Water Pump Nos. 13A, 11B, 12A and 13B.does not affect the present safety analysis nor does-itLcreate any new hazards. The basis for.the Tech.~ Specs. remains unchanged. No unreviewed

, safety or environmental questions are involved.

1EC-1948. This change is a conventional installation which does not interface or alter any safety related equipment. No unreviewed safety or environmental questions are involved.-

  • DCR - Design Change Request

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1MD-0091 i

This is a non-safety related change which ties together

=the N.J. Bell Telephone-system with the Station PA System.

No unreviewed safety or~ environmental questions are-involved.

's 19C-0159 The thermostats being added were-not used in the

, calculation for 'any presently performed safety. analysis.

Their failure does not constitute a new hazard not- .

previously analyzed.. The thermostats do not'enterLinto the logic for the basis of any of the Technical Specifications. No unreviewed safety or. environmental:

questions are involved.

1SC-0363: The change in the upper and. lower bearing oil fill piping will Lnot affect' the operation of the motors. No unreviewed. safety or environmental questions are involved.

I 1SC-0909- This system is not safety.related. No unreviewed safety or environmental questions are involved.

1SC-0967 The addition of screening material within the overflow of the Portable Water Tank does not affect'any previously performed = safety analysis.- No unreviewed safety or

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-environmental questions are involved.

1SC-1272~ This' change enhances the operators control Room indication for the 13 Aux Feedwater status. The change does not alter any automatic control system or' adversely affect the capability 1to safely shut /down the plant. No unreviewed safety-or environmental questions'are involved.

ISC-13 05 .This change provides a more adequate security system by.

bringing a vent opening into compliance with,10CFR73.55.

No unreviewed safety or environmental questions are

, involved.

1SC-1385 This change does not affect any previously performed safety analysis nor does it create any new hazards. The E basis for the Tech. Specs.' remains unchanged. No unreviewed safety or environmental questions are' involved.

'1SC-1411A The moving of an annunciator window to a new location does not affect any safety functions or safety related equipment. No unreviewed safety or environmental questions are involved.

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  • DCR - Design Change Request i

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PSEEG SALEM-GENERATING STATION SAFETY RELATED WORK ORDER LOG .

SALEM UNIT 1 WO NO- DEPT UNIT EQUIPMENT. IDENTIFICATION

.8504240860 SMD 1' 14MS131, PRESS TAP -ISOL. -

FAILURE DESCRIPTION: 14MS131, (l" PRESS. TAP ISOLATION VALVE) ~ HAS A BAD

. PACKING-LEAK. PLEASE INVESTIGATE AND REPAIR.

CORRECTIVE ACTION: FURMANITED GLAND PER PROCEDURE T-161.

8504230678 SIC 1 13 C .F .C .U . . FLOW TRANS .

FAILURE DESCRIPTION: PLEASE BLOWDOWN'#13 C.F.C.U. FLOW TRANSMITTER.

CORRECTIVE ACTION: FOUND FLOW TRANSMITTER PLUGGED. CLEARED BLOCKAGE.

8504230562 SMD 1 1CV268 POSITION IND FAILURE DESCRIPTION: THERE IS A SCREW MISSING FROM THE POSITION IND ON THE REACH ROD AND WE ARE UNABLE TO DETERMINE THE VALVE POSITION.

CORRECTIVE ACTION: DRILLED AND TAPPED HOLE INSERTED SCREWS.

t 8504161200 SMD 1 llSW303 FAILURE DESCRIPTION: HEAT TRACE ON LINE FROM 11SW303 TO LOCAL GAUGE IS COLD. PLEASE REPAIR. ,

CORRECTIVE ACTION: HEAT TRACE WAS CUT - SPLICED NEW LENGTH OF HEAT TRACE.

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t SALEM UNIT 1-WO NO DEPT UNIT EQUIPMENT IDENTIFICATION 8504081443 ..

SIC 1 12 S/G STM PRESS CH 1 FAILURE DESCRIPTION: COMPARATOR TRIPPING OUT OF SPEC. RECAL AS'NECESSARY.

CORRECTIVE ACTION: REPLACED CAPACITORS IN 1PM-514B AND CALIBRATED.

8504050092 SMD 1 CVCS BORIC ACID FAILURE DESCRIPTION: SHAFT SEAL APPEARS TO BE LEAKING. PLEASE REPAIR.

CORRECTIVE ACTION: REPLACED SEAL.

8504010741 SMD 1 13 GB4 FAILURE DESCRIPTION: VALVE HAS A BODY TO BONNET LEAK. MAINT DEPT PLEASE INVESTIGATE AND REPAIR.

CORRECTIVE ACTION: FURMANITE VALVE PER - T16 0 PROCEDURE.

8502140922 SMD 1 13 ' CFCU FAN FAILURE DESCRIPTION: I/O #251580: REPACK AND REGREASE PILLOW BLOCK BEARINGS AND LABYRINTH SEALS DURING MOTOR BEARING INSPECTION.

CORRECTIVE ACTION: REPACKED AND REGREASED PILLOW BLOCK BEARING.

PERFORMED VIBRATION - OK 8502210084 SMD 1 1 CC 364

-FAILURE DESCRIPTION: REPACK VALVE AND PUT ON NEW GLAND NUTS. COULD NOT TAKE UP ANY MORE ON PACKING.

CORRECTIVE ACTION: REPLACED GLAND NUT AND PACKING.-

SALEM UNIT 1 WO NO DEPT UNIT EQUIPMENT IDENTIFICATION -

0099161125 SIC 1 15' CFCU FAILURE-DESCRIPTION: 15 CFCU - NO FAST' SPEED SW FLOW INDICATION-IN CONTROL ROOM - PLEASE REPAIR.

CORRECTIVE ACTION: CLEARED CLOGGED SENSING LINE TO FLOW TRANSMITTER.

0099005603 SMD 1 12 BAT PMP FAILURE DESCRIPTION: INSUFFICIENT FLOW AND DISCHARGE PRESS FROM PUMP.

CORRECTIVE ACTION: READJUSTED IMPELLER CLEARANCE TO .008.

0099014505 SMD 1 11SW303 FAILURE DESCRIPTION: GAUGE LINE DOWNSTREAM OF 11SW303 BROKEN. REPAIR.

0099015021 SMD 1 VITAL HEAT TRACE FAILURE DESCRIPTION: HEAT TRACE CIRCUIT 701 AND 704 ON BORIC ACID EVAP SKID REQUIRES INSULATION TO MAINTAIN PROPER

-TEMPERATURE.

CORRECTIVE ACTION: BOTH 701 AND 704 SATISFACTORY. FOUND THERMOCOUPLE IN WRONG LOCATION. MOVED TO PROPER LOCATION.

0099018659 SIC 1 11 RX COOL LOOP DELTA T FAILURE DESCRIPTION: 1BS-411D TRIPPING OUT OF SPEC. RECAL AS NECESSARY.

CORRECTIVE ACTION:. FUNCTION GENERATOR 10M-411A OUT OF SPEC. ADJUSTED TO SPEC. RETURNED TO SERVICE.

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. SALEM UNIT 1 .

. WO NO DEPT UNIT EQUIPnt;nT IDENTIFICATION

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~0099157519 SIC 1 1B DIESEL SPEED IND.-

= FAILURE DESCRIPTION: PAINTER STEPPED.ON PICK-UP, PLEASE INVESTIGATE AND

-REPAIR AS NEEDED. ,

CORRECTIVE ACTION: REPLACED BROKEN SPEED PICKUP. REPAIRED BROKEN FLEX.

SALEM GENERATING STATION MONTHLY OPERATING

SUMMARY

- UNIT-NO. 1 APRIL 1985 SALEM NO. 1 The Unit began the' period operating at full power. On 4/20/85 at 0230 hours0.00266 days <br />0.0639 hours <br />3.80291e-4 weeks <br />8.7515e-5 months <br />, load was reduced to 80% to support Turbine / Generator vibration testing. The Unit was returned to full power operation by 1900 hours0.022 days <br />0.528 hours <br />0.00314 weeks <br />7.2295e-4 months <br /> on 4/20/85 and continued to operate at full power for the remainder of the period.

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REFUELING INFORMATION DOCKET NO. : 50-272-  !

[ COMPLETED BY: J. Ronafalvy UNIT NAME: Salem 1  ;

DATE: May 10, 1985 ,

TELEPHONES :609/935-6000 EXTENSION: 4455 t t

. Month April 1985 t

1. Refueling' information has changed from last month:

YES NO X

~ 2.. - Scheduled date for next~ refueling: February 22, 1986 ,

'3. Scheduled date for restart following refueling: May 4,1986

4. A) 'WilliTechnical Specification changes or other license  !

amendments be required?

YES. NO NOT NRMINED TO DATE B)~ Has the reload fuel design been reviewed by the Station ,

Operating Review Committee?

YES- - NO X If no, when is it scheduled? January 1986

5. Scheduled date(s) for submitting proposed licensing action:
  • January 1986 if required
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 spent fuel pool assuming the present '

- licensed capacity: September 2001 8-1-7.R4

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i O PSEG Public Service Electric and Gas Company P.O. Box E Hancocks Bridge, New Jersey 08038 Salem Generating Station .

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g,y 10,'1985 Director, Office-of Inspection and. Enforcement U.S.'. Nuclear Regulatory Commission washington', DC 20555

Dear Sir:

MONTNLYLOPERATING REPORT S ALEN ' 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 April 1985.are being sent to you.

s 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, 44 n f s4 #

J. M. Zupko, Jr.

General Manager - Salem Operations JR sbh

- cc t - Dr. Thomas E. Murley LRegional 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 i

< Enclosures

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