ML18095A749

Monthly Operating Rept for Jan 1991 for Salem Unit 2.W/

ML18095A749
Person / Time
Site:	Salem
Issue date:	01/31/1991
From:	Labruna S, Orticelle A Public Service Enterprise Group
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 9102260079
Download: ML18095A749 (9)

Text

• OPS~G Public Service Electric and Gas Company P.O. Box 236 Hancocks Bridge, New Jersey 08038 Salem Generating Station February 15, 1991 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 January 1991 are being sent to you.

RH:pc Average Daily Unit Power Level Operating Data Report Unit Shutdowns and Power Reductions Safety Related Maintenance 10CFR50.59 Evaluations Operating Summary Refueling Information Sincerely yours, 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 95-2189 (10M) 12-89

.ERAGE DAILY UNIT POWER LE.L Completed by:

Art Orticelle Month January 1991 Day Average Daily Power Level (MWe-NET) 1 1097 2

1085 3

1095 4

1104 5

1054 6

1088 7

1092 8

1085 9

1072 10 1011 11 1094 12 1075 13 1077 14 1104 15 1078 16 1110 P. 8.1-7 Rl Day Docket No.:

Unit Name:

Date:

Telephone:

Average Daily Power (MWe-NET) 17 1069 18 1052 19 1084 20 1118 21 1084 22 1102 23 1088 24 1083 25 1119 26 1081 27 1075 28 1090 29 1104 30 1115 31 964 50-311 Salem #2 2/10/91 339-2122 Level

OPERATING DATA REPORT

• Docket No:

50-311 Date:

2/10/91 Completed by:

Art orticelle Telephone:

339-2122 Operating Status

1.

Unit Name Salem No. 2 Notes

2.

Reporting Period January 1991

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 (Ne~ MWe) 1106

8.

If Changes Occur in Capacity Ratings (items 3 through 7) since Last Report, Give Reason NA

9.

Power Level to Which Restricted, if any (Net MWe)

N/A

10. Reasons for Restrictions, if any ~~~~N.:...s...:.A~~~~~~~~~~~~~~~

11. Hours in Reporting Period

12. No. of Hrs. Rx. 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 Gen.

(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 744 744 0

744 0

2526556.8 853192 820496 100 100 99.7 98.9 0

Year to Date 744 744 0

744 0

2526556.8 853192 820496 100 100 99.7 98.9 0

Cumulative 81553 52100.2 0

50454.1 0

108520025.8 52585119 50028307 61.9 61.9 55.5 55.0 24.1

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

NA

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

NA 8-l-7.R2

NO.

DATE 0003 1/,9/91 1

2 F:

Forced S:

Scheduled DURATION TYPE1 (HOURS)

REASON2 F

8.7 Reason A-Equipment Failure (explain)

B-Maintenance or Test C-Refueling D-Requlatory Restriction A

UNIT SHUTDOYN AND POYER REDUCTIONS REPORT MONTH JANUARY 1991 METHOD OF SHUTTING DOYN REACTOR 5

3 LICENSE EVENT REPORT #

Method:

1-Manual 2-Manual Scram SYSTEM CODE4 CH E-Operator Training & License Examination F-Administrative 3-Automatic Scram 4-Continuation of Previous outage 5-Load Reduction 9-0ther G-Operational Error (Explain)

H-Other (Explain) 4 DOCKET NO.

UNIT NAME DATE COMPLETED BY TELEPHONE 50-311 Salem #2 2/10/91 Art Orti eel Le 339-2122 COMPONENT CAUSE AND CORRECTIVE ACTION CODE5 TO PREVENT RECURRENCE INSTRU

1. 22 S.G. FEED PUMP Exhibit G - Instructions for Preparation of Data Entry Sheets for Licensee Event Report (LER) File (NUREG-0161) 5 Exhibit 1 - Same Source

SAFETY RELATED MAINTENANCE MONTH: -

JANUARY 1991 DOCKET NO:

UNIT NAME:

50-311 SALEM 2 WO NO UNIT 890423076 2

901019072 2

901102157 2

901218105 2

910110163 2

910807003 2

23 CHILLER DATE:

COMPLETED BY:

TELEPHONE:

FEBRUARY 10, 1991 F. THOMSON (609)339-2904 EQUIPMENT IDENTIFICATION FAILURE DESCRIPTION:

REBUILD TEMPERATURE CONTROLLER 2A DIESEL FAILURE DESCRIPTION:

SHAFT DRIVEN FUEL OIL PUMP LEAKS REPLACE VALVE 2AF63 FAILURE DESCRIPTION:

VALVE LEAKS THROUGH -

REPLACE DIAPHRAGM 26 SW PUMP FAILURE DESCRIPTION:

PUMP FAILED ITS 4.0.5 P SURVEILLANCE -

REPLACE PUMP VALVE 2SW185 FAILURE DESCRIPTION:

PIPING HAS A THROUGH WALL LEAK -

REPAIR VALVE 21WR8 FAILURE DESCRIPTION:

REPLACE DIAPHRAGM

10CF.R50. 59 EVALUATIONS

• MONTH: -

JANUARY 1991 DOCKET NO:

UNIT NAME:

50-311 SALEM 2 DATE:

FEBRUARY 10, 1991 COMPLETED BY:

F. THOMSON TELEPHONE:

( 609) 339-2904 The following items were evaluated in accordance with the provisions of the Code of Federal Regulations 10CFR50.59.

The Station Operations Review Committee has reviewed these evaluations and agrees with their conclusions that these items do not present Unreviewed Safety Questions (USQs).

ITEM A.

Design Change Packages 2SC-2034 Pkg 1 B.

Procedures and Revisions S2.0P-PT.SW-0002(Q)

SUMMARY

"Series 240 Controlatron Flowmeter" -

This Design Change Package implements a functional 1 for 1 replacement of instrumentation.

The functionally replaced instrumentation is being relocated from the 90' El. of the Service Water Intake Structure to the relatively benign environment of the 112' El.

Local indication at the 90' El. is beinq added for test convenience.

No safety systems are impacted and no functions are altered.

(SORC 91-006)

"Flush of Emergency SW Supply and Return for the Emergency Air Compressors" Rev. 0 -

This procedure provides the instructions necessary to flush the Emergency Service Water supply and return piping for the Emergen6y Control Air Compressor for Unit 2.

(SORC 91-007)

C.

Temporary Modifications (TMODS)

TMR 91-005 The purpose of this modification is to install a Leak Repair enclosure to stop a line leak which occurred just upstream of the 24TD3 valve.

The line cannot be isolated at power and a permanent repair will be made during the next outage of sufficient duration.

( SORC 91-004)

10CFR50.59 EVALUATIONS MONTH: -

JANUARY 1991 (Cont'd)

ITEM D.

Safety Evaluations (S/E)

SMD 91-073 DOCKET NO:

50-311 UNIT NAME:

SALEM 2 DATE:

COMPLETED BY:

TELEPHONE:

SUMMARY

FEBRUARY 10, 1991 F. THOMSON (609)339-2904 "Application of Freeze Plugs" -

The subject of this evaluation is the application of temporary freeze plugs to the 1 1/2" cement lined carbon steel Service Water piping to the inlet and outlet of 21 RHR Pump Room Coo*ler and the outlet of 22 RHR Pump Room Cooler during normal plant operation.

Considerations such as brittle fracture, nozzle jet effect, spray down of components and flooding were addressed.

No concerns were identified for any of the areas addressed.

(SORC 91-007)

r I

I L

SALEM GENERATING STATION MONTHLY OPERATING

SUMMARY

UNIT 2 JANUARY 1991 SALEM UNIT NO. 2 The Unit began the period operating at 100% power.

On January 9, 1991, power was briefly reduced to approximately 80% to investigate problems with 22 Steam Generator Feedwater Pump governor control.

The troubleshooting was completed and the Unit restored to full power on January 10, 1991.

The Unit continued to operate at essentially full power throughout the remainder of the period.

REFUELING INFORMATION MONTH: -

JANUARY 1991 MONTH JANUARY 1991 DOCKET NO:

UNIT NAME:

DATE:

COMPLETED BY:

TELEPHONE:

1.

Refueling information has changed from last month:

YES NO

~---"-"X~~

50-311 SALEM 2 FEBRUARY 10, 1991 F. THOMSON (609)339-2904

2.

Scheduled date for next refueling:

November 30, 1991

3.

Scheduled date for restart following refueling:

February 9, 1992

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?:

October 1991

5.

Scheduled date(s) for submitting proposed licensing action:

N/A

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-l-7.R4