ML18094A631

Monthly Operating Rept for Jul 1989 for Salem Generating Station,Unit 1

ML18094A631
Person / Time
Site:	Salem
Issue date:	07/31/1989
From:	Miller L, Orticelle A, White P Public Service Enterprise Group
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 8908230289
Download: ML18094A631 (9)

Text

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

Dear Sir:

MONTHLY OPERATING REPORT SALEM NO. 1 DOCKET NO. 50-272 August 11, 19 89 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 July 1989 are being sent to you.

RH:sl Average Daily Unit Power Level Operating Data Report Unit Shutdowns and Power Reductions Safety Related Maintenance Major Plant Modification Operating Summary Refueling Information Sincerely yours,

'It:~

L. K. Miller General Manager -

Salem Operations 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 r£2-'/-

g~l181,5M) 12-88

AVERAGE DAiLY UNIT POWER LEVEL Docket No. 50-272 Unit Name

~S-a~l-e_m_,,.#-=-1.....-.....---~

Date 8-10-89 Completed by Art Orticelle

....,_...,.._---=~----.....----

Telephone 609-935-6000 Extension 4722

~~--------.....----

Month JULY 1989 Day Average Daily Power Level Day Average Daily Power Level (MWe-NET)

(MWe-NET) 1 897 17 1085 2

974 18 1089 3

1092 19 1050 4

1057 20 1060 5

1070 21 110 0 6

1056 22 1077 7

1032 23 1106 8

947 24 1040 9

64 8 25 1037 10 1047 26 1110 11 1000 27 1075 12 1084 28 1039 13 1070 29 1100 14 1050 30 1118 15 1092 31 10 81 16 1086 P. 8.1-7 Rl

e OPERATING DATA REPORT Completed by Art Orticelle Operating Status Docket No.50-272 Date: ~8--~l~0~-~8~9=-~~~~

Telephone: 935-6000 Extension: _4_7_2_2~~~~~~-

1.

Unit Name Salem No. 1 Notes

2.

Reporting Period July 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)ll49

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

~~~~~~~~~~~~~~~~~~~~~

11. Hours in Reporting Period

12. No. of Hrs. Reactor was Critical

13. Reactor Reserve Shutdown Hrs.

14. Hours Generator On-Line

15. Unit Reserve Shutdown Hours

16. Gross Thermal Energy Generated (MWH)

17. Gross Elec. Energy Generated (MWH)

18. Net Elec. Energy Generated (MWH)

19. Unit Service Factor

20. Unit Availability Factor

21. Unit Capacity Factor (using MDC Net)

22. Unit Capacity Factor (using DER Net)

23. Unit Forced Outage Rate This Month 744 74 4 0

744 0

2482315 809980 776888 100 100 94.4 93.7 0

Year to Date 5087 28 29. 2 0

26 43. 8 0

8735206 2890270 2736886

51. 97

51. 97 48.6 48.3 15.1 Cumulative 105960 67 461. 4 0

65279. 7 0

204171998 67837450 64543001

61. 6

61. 6 55.1 54.6 22.1

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

NONE

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

N/A 8-l-7.R2

nNTT SHUTDOWN AND POWER REDUCTIONS REPORT MONTH JULY 1989 Docket No.50-272

~~~~~~~~~

Salem No.1 8-10-89 Completed by Art Orticelle Unit Name Date Telephone Extension 609-935-6000 No.

Date 0082 7-08-89 0085 7-11-89 1

F: Forced S: Scheduled Type 1

F F

Duration Hours 0

0 Reason 2

A A

Method of Shutting Down Reactor 5

5 License Event Rep art 2 Re;:i.son A-Equipment Failure-explain B-Maintenance or Test C-Refueling D-Regulatory Restriction E-Operator Training & Licensing Exam F-Administrative G-Operational Error-explain H-Other-explain System Code 4 ED HF 3 Method 1-Manual Component Code 5 TRAN SF xx xx xx 2-Manual Scram.

3-Automatic Scram.

4-Continuation of Previous Outage 5-Load Reduction 9-0ther 47 22 Cause and Corrective Action to Prevent Recurrence AUX. POWER TRANS.

NUETRAL GROUND TRAVELING SCREENS 4 Exhibit G Instructions for Prepara-tion of Data Entry Sheets for Licensee Event Report (LER) File (NUREG 0161) 5 Exhibie Salem as Source

WO NO 870901364 880712166 880712170 890620132 890623115 PSE&G SALEM GENERATING STATION SAFETY RELATED WORK ORDER LOG SALEM UNIT 1 UNIT EQUIP:MENT IDENTIFICATION 1

1SW163 FAILORE DESCRIPTION:

1SW163 12 SJ PMP OIL CLR INLET/REBUILD ACTUATOR MK#AA-98 1

13 INNER PEN AREX EX FAN FAILURE DESCRIPTION:

REPLACE PER lSM-00672.

1 14 INNER PEN AREA EX FAN FAILURE DESCRIPTION:

REPLACE PER lSM-00672.

1 P25 0 FAILURE DESCRIPTION:

INCORE TC'S IND/TC'S INDICATING LOW/INVES~ &

REPAIR.

1 11-14MS167 FAILURE DESCRIPTION:

11-14MS167 WIRING MODIFICATION AS PER DCR lEC-3008.

M...l\\,JOR PLANT MODIFICATIONS REPORT MONTH JULY 1989

• DCR NO.

PRINCIPAL SYSTEM lSC-00 537A Boric Acid lSM-00610.

Safety Injection

• DCR -

Design Change Request DOCKET NO.:

50-27 2 UNIT NAME:

Salem 1 DATE:

August 10, 1989 COMPLETED BY:

P. White TELEPHONE:

609/339-4455 DESCRIPTION This design change replaced Nos. 11 and 12 Boric Acid Evaporator Concentrates Pumps with Goulds Model 3196 pumps.

The suction piping and valves for the pumps were replaced with larger diameter piping and valves.

This design change drilled weep holes in the disks of the 11SJ50 and 12SJ40 valves on the upstream side of the valve disks.

e MA.JOR PLANT MODIFICATIONS DOCKET NO.:

50-272 REPORT MONTH JULY 1989 UNIT NAME:

Salem 1

• DCR 1SC-00537A lSM-00610 DATE:

August 10, 19 89 COMPLETED BY:

P. White TELEPHONE:

609/339-4455 SAFETY EVALUATION 10 CFR 50.59 This design change replaced the existing Boric acid Evaporator Concentrates Pumps with Goulds Model 3196 pumps.

The suction piping and valves were also replaced with larger piping and valves.

Installation of the replacement pumps, piping and valves enhances the reliability and operability of the system.

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.

This design change installed weep holes in the upstream side of the disks for the 11SJ50 and 12SJ40 Valves.

Drilling of the weep holes provides a thermal expansion path for fluid trapped between the two disks and helps to prevent valve binding.

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 UNIT NO. 1 SAJ_,EM GENERATING STATION MONTHLY OPERATING

SUMMARY

UNIT NO. 1 JULY 1989 The Unit began the period in a post outage power ascension and achieved full power on July 1, 1989.

The Unit continued to operate at essentially full power until July 8, 1989, when power was reduced to 25% as a precautionary measure during a swap of auxiliary loads from the No. 1 Auxiliary Power Transformer to the Station Power Transformers.

The load swap was required to reconnect the No. 1 Auxiliary Power Transformer neutral ground.

The Unit was restored to full power on July 10., 1989, and, with the exception of several minor load reductions, continued to operate at essentially full power through the remainder of the period.

~,,.....

REFUELING INFORMATION DOCKET NO.:

50-272 COMPLETED BY:

P. White UNIT NAME:

Salem 1 DATE:

August 10, 1989 TELEPHONE:

609/935-6000 EXTENSION:

4497 Month JULY 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

~D~A=T=E-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:

7.

8.

9.

NONE Number of Fuel Assemblies:

A)

Inc ore B)

In Spent Fuel Storage Present licensed spent fuel storage capacity:

Future spent fuel storage capacity:

Date of last refueling that can be discharged to spent fuel pool assuming the present licensed capacity:

8-l-7.R4 193 540 1170 1170 September 2001 J