ML18094A577

Monthly Operating Rept for June 1989 for Salem Unit 1. W/890712 Ltr

ML18094A577
Person / Time
Site:	Salem
Issue date:	06/30/1989
From:	Miller L, White P Public Service Enterprise Group
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 8907200308
Download: ML18094A577 (10)

Text

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Public Service Electric and Gas Company P.O. Box 236 Hancocks Bridge, New Jersey 08038 Salem Generating Station July 12, 1989 U.S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555

Dear Sir:

MONTHLY OPERATING REPORT SALEM NO. 1 DOCKET NO. 50-272 In compliance with Section 6.9.1.6, Reporting Requirements for the Salem Technical Specifications, the original copy of the monthly operating reports for the month of June 1989 are being sent to you.

Average Daily Unit Power Level Operating Data Report Unit Shutdowns and Power Reductions Safety Related Maintenance Major Plant Modification Operating Summary Refueling Information Since~ely yours,

_;¢UJg<t, L. K. Miller General Manager -

Salem Operations RH:sl cc: Mr. William T. Russell Regional Administrator USNRC Region I 631 Park Avenue King of Prussia, PA 19406 Enclosures 8-l-7.R4 The Energy People 95-2189 (SM) 12-88

e e AVERAGE DAILY UNIT POWER LEVEL Docket No. 50-272 Unit Name ~S-a~l-e_m_,,.#~1------~

Date 7-10-89 Completed by Art Orticelle Telephone 609-935-6000 Extension 4451 Month JUNE 1989 Day Average Daily Power Level Day Average Daily Power Level (MWe-NET) (MWe-NET) 1 0 17 0 2 0 18 23 3 0 19 111 4 0 20 0 5 0 21 0 6 0 22 0 7 0 23 0 8 0 24 0 9 0 25 0 10 0 26 0 11 0 27 0 12 0 28 181 13 0 29 466 14 0 30 777 15 0 16 0 P. 8.1-7 Rl

C1 PERAT::";:NG DATA REPORT Docket No .50-272 Date: 7~ 1~0~-~8~9,,.-~~~~

7 Telephone: 935-6000 Completed by Pell White Extension: 4451

~~~~~~~~~

Operating Status

1. Unit Name Salem No. 1 Notes

2. Reporting Period June 1989

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. It 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 105216

12. No. of Hrs. Reactor was Critical 22 2. 9 20 85. 23 66717.43

13. Reactor Reserve Shutdown Hrs. 0 0 0

14. Hours Generator On-Line 88.01 1899.76 64535. 66

15. Unit Reserve Shutdown Hours 0 0 0

16. Gross Thermal Energy Generated (MWH) 146042.4 6252890.4 201689682.8

17. Gross Elec. Energy Generated (MWH) 41090 2080290 67027470

18. Net Elec. Energy Generated (MWH) 18625 1959998 63766113

19. Unit Service Factor 12.2 43.7 61. 3

20. Unit Availability Factor 12.2 43.7 61. 3

21. Unit Capacity Factor (using MDC Net) 2.3 40.8 54.8

22. Unit Capacity Factor (using DER Net) 2.3 40.5 54.4

23. Unit Forced Outage Rate 71.1 19.8 22.3

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

NONE

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

N/A 8-l-7.R2

UNIT SHUTDOWN AND POWER REDUCTIONS Docket No.50-272 REPORT MONTH JUNE 1989 Unit Name Salem No.1 Date 7-10-89 Completed by Art Orticelle Telephone 609-935-6000 Extension 44 51 Method of Duration Shutting License Cause and Corrective No. Date Type Hours Reason Down Event System Component Action to 1 2 Reactor Report Code 4 Code 5 Prevent Recurrence SCHEDULED OUTAGE 0072 6-01-89 s 413.58 F 4 ------ zz zzzzzz EXTENSION TURBINE OVERS PEED 0074 6-18-89 s 1. 97 B 4 ------ HA TURBIN TRIP TEST TSAS lA SEC e

0075 6-18-89 F 15. 12 A 1 ------ SH INSTRU INOPERABLE TSAS lA SEC 0073 6-19-89 F 0 A 4 ------ SH INSTRU INOPERABLE 0076 6-19-89 F 20 1. 33 A 2 ------ HE VAL VEX MS 167 VALVES REACTIVITY TESTING 0077 6-28-89 s 0 B 9 ------ RB INSTRU FLUX MAPPING 1 2 Reason 3 Method 4 Exhibit G 5 Exhibit 1 F: Forced A-Equipment Failure-explain I-Manual Instructions Salem as S: Scheduled B-Maintenance or Test 2-Manual Ser am. 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 -Adm in i s t r a t iv e 5-Load Reduction Event Report G-Operational Error-explain 9-0ther (LER) File H-Other-explain (NUREG 0161)

PSE&G SALEM GENERATING STATION SAFETY RELATED WORK ORDER LOG SALEM UNIT 1 WO NO UNIT EQUIPMENT IDENTIFICATION 870601209 1 15 S.W.PUMP INSP.

FAILURE DESCRIPTION: PULL 15 SERVICE WTR. PUMP AND INSTALL REBUILT PUMP lAW M6L-2.

880517119 1 lFITlll PRI WTR FLOW XMTR FAILURE DESCRIPTION: lFITlll PRI WTR FLOW XMTR/MISMATCH W/P250/

TROUBLESHOOT.

880830093 1 100' AIRLOCK FAILURE DESCRIPTION: 100' AIRLOCK/HIGH LEAK RATE/REPACK DOOR SHAFTS.

881011128 1 1FA3407 FAILURE DESCRIPTION: 1FA3407 12 S/G STM FLOW IND/SPIKING DOWN/CORRECT.

890520096 1 RING DUCT FAILURE DESCRIPTION: RING DUCT/ 3" RIP IN EXPANSION JOINT. REPLACE IAW A.R.

890606175 1 1N32-SOURCE RANGE- CLIMBING.- REPAIR FAILURE DESCRIPTION: 1N32 - WHILE PERFORMING ROD DROPS, 1N32 STARTED CLIMBING.

SALEM UNIT 1 ' ..

WO NO UNIT EQUIPMENT IDENTIFICATION 890610083 1 "B" RX TRIP BKR SHUNT COIL FAILURE DESCRIPTION: "B" RX TRIP BKR SHUNT COIL/DID NOT REGISTER ON P250 COMPUTER.

890617053 1 12BF4 0 FAILURE DESCRIPTION: SEEMS TO BE LEAKING BY. PLEASE TROUBLE SHOOT AND REPAIR.

890617063 1 1-A S.E.C FAILURE DESCRIPTION: 1-A S.E.C FALIED TEST/TROUBLESHOOT & REPAIR.

FAILED WHILE DOING THE M3T PROCEDURE.

e

. MAJOR PLANT MODIFICATIONS e

DOCKET NO.: 50-272 REPORT MONTH JUNE 1989 UNIT NAME: Salem 1 DATE: July 10, 1989 COMPLETED BY: P. White TELEPHONE: 609/339-4455

• DCR NO. PRINCIPAL SYSTEM DESCRIPTION lEC-02163 Caustic Control This design change added secondary containment facilities at the caustic loading area as required by NJAC 7:1E-4.7.

lSM-00231 Waste Collection This design change installed a new waste line connecting the Waste Collector Tank and the High Conductivity Pit.

• DCR - Design Change Request

e

. MAJOR PLANT MODIFICATIONS e

DOCKET NO.: 50- 27 2 REPORT MONTH JUNE 1989 UNIT NAME: Salem 1 DATE: July 10, 19 89 COMPLETED BY: P. White TELEPHONE: 609/339-4455

• DCR SAFETY EVALUATION 10 CFR 50.59 lEC-02163 This design change installed secondary containment facilities at the NRLWDS caustic loading area to prevent spilled hazardous substances from reaching the waters of the State. There was no change to any plant process or discharge or to the environmental impact of the plant. No unreviewed safety or environmental questions are involved.

lSM-00231 This design change installed a new, properly sized waste line connecting the Waste Collector Tank and

.the High Conductivity Pit. This improves the operation of the system and reduces the possibility of spilling waste material. There was no change to any plant process or discharge or to the environmental impact of the plant. No unreviewed safety or environmental questions are involved.

• DCR - Design Change Request

SALEM GENERATING STATION MONTHLY OPERATING

SUMMARY

- UNIT NO. 1 JUNE 1989 SALEM UNIT NO. 1 The Unit began the period shutdown for a refueling outage. Major work accomplished during the period included the following:

1. Steam Generator and Feed Pump turbine overspeea tests;

2. RTD cross calibrations;

3. Establishing condenser vacuum,

4. Individual Rod Position Indication (IRPI) calibrations

5. Testing of all safety valves

6. Main Turbine Overspeed Test On June 9, 1989, an automatic safety injection occurred as a result of the premature opening of a main steam safety valve. A startup was commenced on June 14, 1989, and the Unit was synchronized on June 18, 1989, following completion of repairs to a main steam isolation valve and feedwater regulating valves. Subsequently, the Unit was shutdown due to problems encountered with lA SEC. The Unit was resynchronized on June 19, 1989, and a power escalation commenced. The Unit tripped later, the same day, while Operators were performing a surveillance test on the main steam isolation valves. The test circuitry was subsequently modified to prevent possible trips during future surveillance testing. A Safety Injection check valve bonnet leak was identified in the Containment and a cooldown and depressurization was performed to effect repairs. Following repairs to the check valve, technicians discovered the presence of sodium in the Reactor Coolant System during routine chemistry sampling. Investigations revealed that improper boric acid had been inadvertently used in the batching process and subsequently injected into the system. A thorough analysis of the event demonstrated that there were no adverse affects to the primary system. The sodium was subsequently removed from the system by use of demineralizers. The Unit was returned to service on June 28, 1989, and a power ascension was performed throughout the remainder of the period.

REFUELING INFORMATION DOCKET NO.~ 50-272 COMPLETED BY: P. White UNIT NAME: Salem 1 DATE: July 10, 1989 TELEPHONE: 609/935-6000 EXTENSION: 44 97 Month JUNE 1989

1. Refueling information has changed from last month:

YES NO X

2. Scheduled date for next refueling: March 28, 1989

3. Scheduled date for restart following refueling: May 24, 1989

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

YES NO NOT DETERMINED TO DATE X B) Has the reload fuel design been reviewed by the Station Operating Review Committee?

YES X NO If no, when is it scheduled?

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

N/A

6. Important licensing considerations associated with refueling:

NONE

7. Number ot Fuel Assemblies:

A) Inc ore 193 B) In Spent Fuel Storage 540

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