ML18095A352

Monthly Operating Rept for June 1990 for Salem Generating Station Unit 1.W/900713 Ltr

ML18095A352
Person / Time
Site:	Salem
Issue date:	06/30/1990
From:	Miller L, Morroni M Public Service Enterprise Group
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 9007190271
Download: ML18095A352 (9)

Text

Public Service Electric and Gas Company P.O. Box E Hancocks Bridge, New Jersey 08038 Salem Generating Station July 13, 1990 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 che monthly operating reports for the month of June 1990 are being sent to you.

Average Daily Unit Power Level Operating Data Reporc Unit Shutdowns and Power Reductions Safety Related Maintenance Major Plant Modifications Operating Summary Refueling Information Sincerely yours,

¥~~ tf/~

L. K. Miller ~./r: *~"/~~

General Manager -

Salem Operations RH:pc cc: Mr. Thomas T. Martin Regional Administrator USNRC Region I 631 Park Avenue King of Prussia, PA 19046 Enclosures 8-1-7.R4 The Energy People 95-2189 (11 M) 12-84

AVERAGE DAILY UNIT POWER LEVEL Docket No. 50-272 Unit Name Salem # 1 Date 07-10-90 Completed by Art Orticelle Telephone 609-339-2122 Month JUNE, 1990 Day Average Daily Power Level Day Average Daily Power Level (MWe-NET) (MWe-NET) 1 0 17 1084 2 0 18 1104 3 0 19 1070 4 0 20 1093 5 0 21 1082 6 0 22 1099 7 244 23 1012 8 810 24 984 9 1003 25 1067 10 1055 26 1026 11 1061 27 912 12 1074 28 911 13 1077 29 1072 14 1111 30 598 15 1101 31 16 1094 P. 8.1-7 Rl

1 I

OPERATING DATA REPORT I

I Docket No: 50-272 Date:

Completed by: Art Orticelle Telephone:

Operating Status

1. Unit Name Salem No. 1 Notes

2. Reporting Period June 1990

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~/~AO--~~~~~~~~~~~~~~~~~~~~~~~~

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 113976

12. No. of Hrs. Reactor was Critical 614.4 2777 73685.6

13. Reactor Reserve Shutdown Hrs. 0 0 0

14. Hours Generator On-Line 570.2 2673 71368.8

15. Unit Reserve Shutdown Hours 0 0 0

16. Gross Thermal Energy G~nerated (MWH) 1831912.8 8724475.2 223825401.2

17. Gross Elec. Energy Generated (MWH) 596260 2887020 74348380

18. Net Elec. Energy Generated (MWH) 565595 2758769 70770479

19. Unit Service Factor 79.2 61.5 62.6

20. Unit Availability Factor 79.2 61.5 62.6

21. Unit Capacity Factor (using MDC Net) 71. 0 57.4 56.1

22. Unit Capacity Factor (using DER Net) 70.5 57.0 55.7

23. Unit Forced Outage Rate 20.8 38.5 22.3

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

Refueling Outage scheduled to start 10-20-90 and last 55 days.

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

N/A

UNIT SHUTDOWN AND POWER REDUCTIONS OOCKEr NO. : 272 REPORI' MONTH JUNE 1990 UNIT NAME: Salem #1 DA'IE: 07-10-90 mMPLEI'ED BY: Art Orticelle TELEPHONE: 339-2122 MEI'HOD OF SHUITING LICENSE DURATION OOWN EVENT SYSTEM rotPONENT CAUSE AND OORRECTIVE ACTION NO. DA'IE TYPE i (HOURS) REASON z REACIDR REPORI' # CDDE 4 CDDE ~ 'ID PREVENT RECURRENCE 0035 06-01-90 F 137.5 A 4 CH INSTRU #12 S.G. FEED PUMP 0036 06-06-90 F 12.3 A 4 CH MECFUN #12 S.G. FEED PUMP 0046 06-30-90 F 0 A 5 HF HTEXCH 13A WATERBOX CLEANING e 0045 06-30-90 F 0 A 5 HF HTEXCH 13A WATERBOX CLEANING 0048 06-30-90 F 0 A 5 HF PUMPXX 13A &B C.W. PUMPS 1 2 3 4 5

~

F: Forced Reason: Method: Exhibit G - Instructions Exhibit 1 - Same S: Scheduled A-Equipnent Failure (Explain) 1-Manual for Preparation of Data Source B-Maintenance or Test 2-Manual Scram Entry Sheets for Licensee C-Refueling 3-Autanatic Scram Event Report (LER) File D-Regulatory Restriction 4--continuation of (NUREG-0161)

E--Operator Training &License Exarrri.nation Previous Outage F-Adrninistrative 5-1.Dad Reduction G--Operational Error (Explain) 9-0ther H-Other (Explain)

SAFETY RELATED MAINTENANCE DOCKET NO: 50-272 MONTH: - JUNE 1990 UNIT NAME: SALEM 1 Dli.TE: J"ULY 10, 1990 COMPLETED BY: M. MORRONI

• TELEPHONE: (609) 339-2068 WO NO UNIT EQUIPMENT IDENTIFICATION 890619099 1 14GB3 BODY TO BONNET LEAK FAILURE DESCRIPTION: BODY TO BONNET LEAK - PERFORM LEAK REPAIR 891128117 1 1VC6 STROKE TIME FAILURE DESCRIPTION: FAILED STROKE TIME TEST - REPAIR 900501084 1 1CH168 POSITIONER FAILURE DESCRIPTION: Ul CONTROL ROOM EMERGENCY AIR CONDITIONER OUTLET - REBUILD POSITIONER 900605066 1 2PR3, 4, 5 AL}1.RM FAILURE DESCRIPTION: VALVE OPEN ALARM IN - INVESTIGATE AND REPAIR 900621154 1 lH 230V GROUP BUS TEST FAILURE DESCRIPTION: PERFORM TRANSFORMER DOBLE TEST 900625112 1 AXIAL FLUX RECORDER FAILURE DESCRIPTION: RECORDER FAILED LOW - INVESTIGATE AND REPP.IR

MAJOR PLANT MODIFICATIONS DOCKET NO: 50-272 MONTH: - JUNE 1990 UNIT NAME: S.P.LEM 1 DATE: JULY 10, 1990 COMPLETED BY: M. MORRONI TELEPHONE; (609) 339-2068

• DCR PRINCIPAL SYSTEM DESCRIPTION 1SM-0369A Motor Operated This design change modified the closed indication to provide the Operator with more accurate indication of an actual closed condition. Additionally, the open torque switch bypasses were increased to 25% of the open stroke.

• DCR - Design Change Request

MAJOR PLANT MODIFICATIONS DOCKET NO: 50-272 MONTH: - JUNE 1990 UNIT NAME: SALEM 1 DATE: JULY 10, 1990 COMPLE'I'ED BY: M. MORRON!

TELEPHONE: (609) 339-2068

• DCR SAFETY EVALUATION 10 CFR 50.59 1SM-0369A This design change modified the closed indication to provide the Operator with more accurate indication of an actual closed condition. Additionally, the open torque switch bypasses were increased to 25% of the open stroke, thus reducing the possibility of the valve de-energizing at high unseating loads. This design change did not alter the original operational design, thus it does not introduce possible accident scenarios not previously analyzed. There is 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 I

SALEM GENERATING STATION MONTHLY OPERATING

SUMMARY

- UNIT 1 JUNE 1990 SALEM UNIT NO. 1 The Unit began the period shutdown for resolution of Residual Heat Removal (RHR) problems. The RHR problems were satisfactorily resolved and star~up operations commenced. The Unit was returned ~o service on June 7, 1990 and reached 100% power on June 10, 1990. The Unit continued to operate at essentially full power until June 23, 1990, when load was briefly reduced to approximately 74% power ~o maintain condenser vacuum following the loss of a vacuum pump, which resulted from a transformer failure. During the period between June 26-30, 1990, the Unit experienced several load reductions due to Circulating Water System (CWS) problems.

REFUELING INFORMATION DOCKET l\TO: 50-272 MONTH: - JUNE 1990 UNIT NAME: SALEM 1 DATE: JULY 10, 1990 COMPLETED BY: M. MORRONI TELEPHONE: (609) 339-2068 MONTH JUNE 1990

1. Refueling information has changed from lasL month:

YES NO x

2. Scheduled date for next refueling: October 20, 1990

3. Scheduled date for restart following refueling: December 13, 1990

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 NO x If no, when is it scheduled?: September 1990

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

N/A

6. Important licensing considerations associated with refueling:

7. Number of 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 the spent fuel pool assuming the present licensed capacity: September 2001 8-1-7.R4