ML18095A689

Monthly Operating Rept for Dec 1990 for Salem Unit 2.W/

ML18095A689
Person / Time
Site:	Salem
Issue date:	12/31/1990
From:	Thomson F Public Service Enterprise Group
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 9101180297
Download: ML18095A689 (9)

Text

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. *o PS~G Public Service Electric and Gas Company P.O. Box 236 Hancocks Bridge, New Jersey 08038 Nuclear Department January 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 December 1990 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,

~,6'~

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 2 21J1(1 'tf~rgy People 95-2168 (1 QOM) 12-84

.ERAGE DAILY UNIT POWER LE..

Completed by:

Art Orticelle Month December 1990 Day Average Daily Power Level (MWe-NET) 1 1083 2

1103 3

1021 4

1042 5

1054 6

1086 7

1103 8

1073 9

1100 10 1101 11 1102 12 1088 13 1112 14 1089 15 981 16 1096 P. 8.1-7 Rl Day Docket No.:

50-311 Unit Name:

Salem #2 Date:

1/10/91 Telephone:

339-2122 Average Daily Power Level (MWe-NET) 17 1107 18 1103 19 1115 20 841 21 993 22 1071 23 987 24 1010 25 1079 26 1115 27 1079 28 1104 29 1083 30 1109 31 1091

e OPERATING DATA REPORT e Docket No:

50-311 Date:

1/10/91 Completed by:

Art Orticelle Telephone:

339-2122 Operating Status

1.

Unit Name Salem No. 2 Notes

2.

Reporting Period December 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 NA

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. 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

2485303.2 837864 805093 100 100 97.8 97.1 0

Year to Date 8760 5350.4 0

5164.9 0

16941729.6 5684875 5407905 59.0 59.0 55.8 55.4 6.1 Cumulative 80809 51356.2 0

49710.l 0

105993469.0 51731927 49207811

61. 5 61.5 55.1 54.6 24.3

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

None

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

NA 8-1-7.R2

NO.

DATE 0103 12/03/90 0109 12/20/90 1

2 F:

Forced S: Scheduled DURATION TYPE 1 (HOURS)

REASON2 F

7.5 F

3.0 Reason A-Equipment Failure (explain)

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

A UNIT SHUTDOWN AND POWER REDUCTIONS REPORT MONTH NOVEMBER 1990 METHOD OF SHUTTING DOWN REACTOR 5

5 3

LICENSE EVENT REPORT #

Method:

1-Manual 2-Manual Scram SYSTEM CODE4 HF WA 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 1/10/91 '

Art Orticel Le.~

339-2122 COMPONENT CAUSE AND CORRECTIVE ACTION CODE5 TO PREVENT RECURRENCE HTEXCH

1. 23A & 23B WATERBOX CLEAN PIPEXX SERVICE WATER PIPE LEAK Exhibit G - Instructions for Preparation of Data Entry Sheets for Licensee Event Report CLER) File CNUREG-0161) 5 Exhibit 1 - Same Source

SAFETY RELATED MAINTENANCE MONTH: -

DECEMBER 1990 DOCKET NO:

UNIT NAME:

50-311 SALEM 2 WO NO UNIT 890202110 2

900907124 2

901026070 2

901026074 2

901205116 2

901207149 2

901228095 2

DATE:

COMPLETED BY:

TELEPHONE:

JANUARY 10, 1991 F. THOMSON (609)339-2904 EQUIPMENT IDENTIFICATION 2A D/G OUTLET EXPANSION JOINT FAILURE DESCRIPTION:

REPLACE EXPANSION JOINT FC-2A-1 VALVE 22SW150 FAILURE DESCRIPTION:

CONTAINMENT SPRAY PUMP COOLER #22 OUTLET VALVE WILL NOT OPEN -

TROUBLESHOOT AND REPAIR 2S27C FAILURE DESCRIPTION:

REPLACE DIESEL SPOOL RD-2-SW-903 2S27C FAILURE DESCRIPTION:

REPLACE DIESEL SPOOL RD-2-SW-914 21 SW HEADER FAILURE DESCRIPTION:

SW HEADER INDICATION ERRATIC -

TROUBLESHOOT AND REPAIR 2B DIESEL FAILURE DESCRIPTION:

SL CYLINDER HEAD JACKET WATER LEAK -

REWORK PZR LEVEL INDICATION FAILURE DESCRIPTION:

PZR LEVEL IND. OUT OF SPEC HIGH -

TROUBLESHOOT

~------- -

10CFR50.59 EVALUATIONS MONTH: -

DECEMBER 1990 DOCKET NO:

UNIT NAME:

DATE:

COMPLETED BY:

TELEPHONE:

50-311 SALEM 2 JANUARY 10, 1991 F. THOMSON (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 2EC-3047 Pkg 1 2SC-2291 Pkg 1 B.

Procedures and Revisions S2.RE-ST.ZZ-0002(Q)

SUMMARY

"Polar Crane Upgrade" -

The purpose of this design change is to strengthen three trolley beam connections on the polar gantry cranes.

A325 high strength bolts will replace A307 bolts on the top flange plates and stiffeners will be welded to the bottom flanges.

(SORC 90-160)

"Primary Sample Lab" -

The purpose of this design change is to modify the gas stripping rig located in the Primary Sample Lab to allow for sample recirculation between the sample vessel and the glass sample tube.

This modification will provide a more reliable method of obtaining gas samples which are representative of actual RCS condi tiond.

( SORC 90-161)

"Shutdown Margin Calculation" Rev. 0 -

The purpose of this revision is to convert the Reactor Engineering Manual Procedures to the AP numbering system, and revise the procedures to add in the worth from a stuck rod.

Other changes include revising the procedures such that initial xenon reactivity is that reactivity relating to the reference critical conditions and not the shutdown conditions.

The change ensures that the reactivity balance is calculated correctly and consistently.

(SORC 90-160)

r 10CFR50.59 EVALUATIONS MONTH: -

DECEMBER 1990 (Cont'd)

ITEM DOCKET NO:

50-311 UNIT NAME:

SALEM 2 DATE:

COMPLETED BY:

TELEPHONE:

SUMMARY

JANUARY 10, 1991 F. THOMSON (609)339-2904

c.

Temporary Modifications (TMODS)

STD 90-130 E.

Safety Evaluations (S/E)

SMD 90-321 The purpose of this modification is to install a leak repair enclosure to stop a leak from a line break downstream of the 2RD102 valve.

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

The modification is bounded by the worst case analysis.

(SORC 90-160)

The subject of this evaluation is the application, in Salem Unit 2, of a temporary freeze plug to the common 2" lined carbon steel Service Water supply pipe to No. 21 Component Cooling and No. 2 Auxiliary Feed Pump room coolers, during normal plant operations.

The freeze plug will be used to isolate the supply piping to the No. 21 Component Cooling room cooler during replacement of the flanged piping spools in accordance with the disposition of Deficiency Report SMD 90-321.

(SORC 90-164)

I I

SALEM UNIT NO. 2 SALEM GENERATING STATION MONTHLY OPERATING

SUMMARY

UNIT 2 DECEMBER 1990 The Unit began the period operating at 100% power.

On December 3, 1990, power was briefly reduced to approximately 75% for condenser water box cleaning.

The Unit was restored to full power on December 4, 1990, and continued to operate at essentially full power until December 20, 1990, when load was reduced to repair a service water leak pipe leak.

The leak was repaired and the Unit returned to 100%

power the following day.

On December 24, 1990, the Load Dispatcher declared a minimum generation condition and power was reduced to 65%

to support system operations.

The Unit returned to 100% power on December 25, 1990, and continued to operate at essentially full power throughout the remainder of the period.

.* '. ' *., t REFUELING INFORMATION MONTH: -

DECEMBER 1990 MONTH DECEMBER 1990 DOCKET NO:

UNIT NAME:

DATE:

COMPLETED BY:

TELEPHONE:

1.

Refueling information has changed from last month:

YES NO

~----"-X"--~-

50-311 SALEM 2 JANUARY 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 8-1-7.R4