ML18095A353

Monthly Operating Rept for June 1990 for Salem Generating Station,Unit 2

ML18095A353
Person / Time
Site:	Salem
Issue date:	06/30/1990
From:	Miller L, Orticelle A Public Service Enterprise Group
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 9007190274
Download: ML18095A353 (9)

Text

OPS~G 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. 2 DOCKET NO. 50-311 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 1990 are being sent to you.

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

General Manager -

Salem Operations 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 (11M)12-84

AVERAGE DAILY UNIT POWER LEVEL Docket No.

=5~0_-=3=1=1~~~~~-

Unit Name Salem # 2 Date

=0~7_-=1=0_-~9=0~~~~-

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 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 73 9

0 25 325 10 0

26 298 11 0

27 317 12 0

28 0

13 0

29 0

14 0

30 0

15 0

31 16 0

P. 8.1-7 Rl

CORRECTED OPERATING DATA REPORT Docket No:

Date:

Completed by:

Art Orticelle Telephone:

Operating Status

1.

Unit Name Salem No. 2

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 Report, Give Reason N/A 50-311 07-10-90 609-339-2122 Notes through 7) since Last

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 76392

12. No. of Hrs. Reactor was Critical 145.3 2139.1 48145

13. Reactor Reserve Shutdown Hrs.

0 0

0

14. Hours Generator On-Line 82.2 2056.3 46601.5

15. Unit Reserve Shutdown Hours 0

0 0

16. Gross Thermal Energy Generated (MWH) 125880 6681681.6 95733421.0

17. Gross Elec. Energy Generated (MWH) 28390 2266270 48313322

18. Net Elec. Energy Generated (MWH) 11491 2151984 45951890

19. Unit Service Factor

11. 4 47.3 61

20. Unit Availability Factor 11.4 47.3 61

21. Unit Capacity Factor (using MDC Net) 1.4 44.8 54.4

22. Unit Capacity Factor (using DER Net) 1.4 44.4 53.9

23. Unit Forced Outage Rate 45.0 10.0 25.4

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:

7/24/90 8-l-7.R2

ID.

DATE 0050 06/01/90 0051 06/24/90 0052 06/26/90 0053 06/28/90 0054 06/30/90 1

F: Forced S: Scheduled DURATIOO

'IYPE 1 (IDURS)

REASON 2 FO 558.3 c

ftl)

.6 B

Ul 7.5 A

Ul 59.8 A

MO 11.6 A

2 Reason:

A-FquiIJient Failure (Explain)

B-Ma:intenance or Test C-Refueling D-Regulatory Restriction UNIT SHlJl'rom AND ~

REIXJCI'IOOS REroRI' mN'IH JUNE 1990 IXn\\EI' ID.: 50-311 UNIT NAME: Salem #2 MEIIDD OF SHUI'I'ING ram REACTOR 4

1 1

3 4.*

LICENSE EVF.NT SYSTEM REPORI' #

CDDE 4 RC cc cc EB CD 3

Method:

1-Manual 2-Manual Scram 3-Autanatic Scram 4--COntinuation of cntroNEN'I' CDDE !I FUEi.XX

'IURBIN VALVEX TRAN SF INSTRU 4

DATE: 07-10-90 CXMPI.EI'ED BY: Art Orticelle

• 'I'El.EP~: 339-2122 CAUSE AND CDRRECTIVE ACI'IOO

'ID PREVENT REOJRRENCE RmJELING

'IURBINE TRIP TEm'

1. 24 OOV. VALVE 2F 460/230V TRANSFORMER 21, 22, 23, & 24 MS167 CDNTOOlS 5

Exhibit G - Instructions for Preparation of Data Entry Sheets for Licensee Event Report (IBR) File (NURID--0161)

Exhibit 1 - sane Source E--Operator Training & License Examination Previous O.ltage F-Administrative G-Operational Error (Explain)

H--Other (Explain) 5-I..oad Reduction 9--0ther

L SAFETY RELATED MAINTENANCE MONTH: -

JUNE 1990 DOCKET NO:

50-311 UNIT NAME:

SALEM 2 WO NO UNIT 890104136 2

890104158 2

890728121 2

900206243 2

900318010 2

900422071 2

900430099 2

DATE:

JULY 10, 1990 COMPLETED BY:

M. MORRON!

TELEPHONE:

(609) 339-2068 EQUIPMENT IDENTIFICATION PNL 689-2C MN STM 23MS169 FAILURE DESCRIPTION:

REDUNDANT AIR LEAKS -

REPAIR PNL 689-2A MN STM 21MS169 FAILURE DESCRIPTION:

SWITCHING VALVE AIR LEAK -

REPAIR CONTROL ROOM MODS FAILURE DESCRIPTION:

INSTALL DCP 2SC-2154 -

CONTROL ROOM MODIFICATIONS VALVE 21SJ43 FAILURE DESCRIPTION:

VALVE LEAKS THROUGH -

OPEN &

INSPECT 24BF19-24 SG FD CONTROL VLV PNL REGULATOR 702D FAILURE DESCRIPTION:

REPLACE REGULATOR IN PANEL LETDOWN FLOW INDICATION FAILURE DESCRIPTION:

INDICATION FAILED LOW -

TROUBLESHOOT & REWORK 2B DIESEL GENERATOR INDICATION FAILURE DESCRIPTION:

FREQUENCY INDICATION SHOWING 60HZ WITH NO CHANGE DURING LOADED RUN INVESTIGATE

SAFETY RELATED MAINTENANCE (cont'd)

MONTH: -

JUNE 1990 DOCKET NO:

50-311 UNIT NAME:

SALEM 2 WO NO UNIT 900504123 2

900507095 2

900515134 2

900515209 2

900501052 2

900619176 2

910318017 2

22 CHARGING PUMP DATE:

JULY 10, 1990 COMPLETED BY:

M. MORRONI TELEPHONE:

(609) 339-2068 EQUIPMENT IDENTIFICATION FAILURE DESCRIPTION:

REWELD ALIGNMENT PIN AND CENTERING PIN BLOCK VALVE 2VC5 FAILURE DESCRIPTION:

VALVE LEAKS PAST SEAT AND PINS -

REMOVE AND REPAIR VALVE 2CV11 FAILURE DESCRIPTION:

VALVE LEAKS THROUGH -

REPLACE INTERNALS 2LT504/24 SG LEVEL SENSING LINE FAILURE DESCRIPTION:

SG LEVEL SENSING LINE 2LT504 BENT REPAIR TUBING AT ROOT VALVE CABLE SEPARATION CRITERIA FAILURE DESCRIPTION:

CORRECT CABLE SEPARATION CRITERIA DISCREPANCIES 28VDC FIRE PROTECTION CIRCUIT FAILURE DESCRIPTION:

28VDC GROUND ON FIRE PROTECTION CIRCUIT -

INVESTIGATE & REPAIR 2RC40 RX HEAD VENT VALVE FAILURE DESCRIPTION:

REPLACE RELAYS AND 11 0 11 RING

MAJOR PLANT MODIFICATIONS MONTH: -

JUNE 1990

• DOCKET NO:

UNIT NAME:

DATE:

COMPLETED BY:

'I'ELEPHONE:

50-311 SALEM 2 J"ULY 10, 1990 M. MORRONI (609) 339-2068

• DCR PRINCIPAL SYSTEM DESCRIPTION None for the period.

~

DCR -

Design Change Request

SALEM UNIT NO. 2 SALEM GENERATING STATION MONTHLY OPERATING

SUMMARY

UNIT 2 JUNE 1990 The Unit entered the period shutdown for a refueling outage.

Following completion of maintenance and testing activities, the Unit was synchronized to the grid on June 24, 1990.

During the power ascension, a leak developed on the Turbine/Generator Electro-Hydraulic Control (EHC) system.

The Turbine/Generator was briefly removed from service on June 26, 1990 to repair the leak.

The Unit was returned to service on June 27, 1990, and a power escalation commenced.

The Unit experienced a Reactor Trip on June 28, 1990, due to the failure of 2F 460V transformer.

The Unit remained shutdown through the rest of the period for replacement of the transformer and Main Steam Isolation Valve testing and control circuit modifications.

r -

f REFUELING INFORMATION MONTH: -

JUNE 1990 MONTH J"UNE 19 9 0 DOCKET* NO:

UNIT NAME:

DATE:

COMPLETED BY:

TELEPHONE:

1.

Refueling information has changed from last month:

YES x

NO 50-311 SALEN 2 JULY 10, 1990 M. MORRONI (609) 339-2068

2.

Scheduled date for next refueling:

October 12, 1991

3.

Scheduled date for restart following refueling:

December 15, 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 1991

5.

Scheduled date(s) for submitting proposed licensing action:

NIP.

6.

Important licensing considerations associated with refueling:

7.

Number of Fuel Assemblies:

a.

Incore 193

b.

In Spent Fuel Storage 316

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:

March 2003 8-1-7.R4