ML18096B142

Monthly Operating Rept for Nov 1992 for Salem Generating Station,Unit 2

ML18096B142
Person / Time
Site:	Salem
Issue date:	11/30/1992
From:	Fest J, Polizzi V, Shedlock M Public Service Enterprise Group
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 9212160057
Download: ML18096B142 (10)

Text

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Public Service Electric and Gas Company P.O. Box 236 Hancocks Bridge, New Jersey 08038 Salem Generating Station December 10, 1992 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 November 1992 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, fJ/a9o4.

General Mana~~~,,.._,

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 9212160057 921130 PDR ADOCK 05000311 R

PDR j01~

95-2189 (10M) 12-89

~ERAGE DAILY UNIT POWER Lta:L Docket No.:

50-311 Unit Name:

Salem #2 Date:

12/10/92 Completed by:

Mark Shedlock Telephone:

339-2122 Month November 1992 Day Average Daily Power Level Day Average Daily Power Level (MWe-NET)

(MWe-NET) 1 1118 17 1121 2

1125 18 1101 3

1122 19 1130 4

1130 20 1119 5

1105 21 1124 6

1113 22 1119 7

1118 23 1120 8

1126 24 1118 9

1119 25 1124 10 1117 26 1110 11 839 27 1123 12 184 28 1087 13 0

29 1125 14 0

30 1116 15 420 31 16 903 P. 8.1-7 Rl

tt OPERATING DATA REPORT--

Docket No:

50-311 Date:

12/10/92 Completed by:

Mark Shedlock Telephone:

339-2122 Operating Status

1.

Unit Name Salem No. 2 Notes

2.

Reporting Period November 1992

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 EleG. 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 720 720 0

658.9 0

2165481. 6 730750 699363

91. 5 91.5 87.8 87.1 8.5 Year to Date cumulative 8040 97609 4405.5 63021. 6 0

• o 3915.7 60814.5 0

0 12477038.4 142588760.2 4124260 63851308 3894189 60762474 48.7 62.3 48.7 62.3 43.8 56.3 43.4 55.8 19.4 23.1

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

Refueling outage scheduled to start 03/27/93 and last 55 days.

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

NA 8-1-7.R2

NO.

DATE D032 11/11/92 0033 11/12/92 1

2 F:

Forced S:

Scheduled DURATION TYPE1 (HOURS)

REASON 2 F

17.1 F

61.1 Reason A-Equipment Failure (explain)

B-Maintenance or Test C-Refuel ing D-Requlatory Restriction B

A UNIT SHUTDOWN AND POWER REDUCTIONS REPORT MONTH NOVEMBER 1992 METHOD OF SHUTTING DOWN REACTOR 5

1 3

LICENSE EVENT REPORT #

Method:

1-Manual 2-Manual Scram SYSTEM CODE4 CH HA 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)

COMPONENT CODE5 DOCKET NO.: _,5=-=0'"'"*=-31'-'1'---__ _

UN IT NAME:

_s~a~l'-"e~m_,#;..:;2=---

DA TE:

_1~2~/-f-10"'"/-"-9=-2..,..,.........,...-

COMPLETED BY:

Mark Shedloc~

TELEPHONE:

_,3~3~9_,*2~1=2=-2 __ _

CAUSE AND CORRECTIVE ACTION TO PREVENT RECURRENCE PUMPXX

1. 21 S.G.F. PUMP MAINTENANCE GENERA GENERATOR HYDROGEN LEAK 4

Exhibit G - Instructions for Preparation of Data Entry Sheets for Licensee Event Report CLER) File (NUREG-0161) 5 Exhibit 1 - Same Source

e SAFETY RELATED MAINTENANCE DOCKETtlto:

50-311 SALEM 2

-MONTH: -

NOVEMBER 1992 UNIT NAME:

WO NO UNIT 920821120 2

921023178 2

921103085 2

921103086 2

921106099 2

921113168 2

VALVE 22SW39 DATE:

COMPLETED BY:

TELEPHONE:

DECEMBER 10, 1992 J. FEST (609)339-2904 EQUIPMENT IDENTIFICATION FAILURE DESCRIPTION:

22SW39 FAILED STROKE TIME -

INVESTIGATE AND CORRECT VALVE 22SW305 FAILURE DESCRIPTION:

22SW305 DIAPHRAGM AIR LEAK -

INVESTIGATE AND REPAIR VALVE 24SW223 FAILURE DESCRIPTION:

24 CFCU INLET FLOW CONTROL FLOW IS HIGH -

INVESTIGATE AND CORRECT VALVE 22SW223 FAILURE DESCRIPTION:

24 CFCU INLET FLOW CONTROL FLOW IS HIGH -

INVESTIGATE AND CORRECT 2B DIESEL GENERATOR FAILURE DESCRIPTION:

2B D/G T.C COVERS LOOSE -

REWORK VALVE 21MS10 FAILURE DESCRIPTION:

21MS10 INDICATOR BEZEL DRIFTS IN AUTO -

INVESTIGATE I

10GFR50.59 EVALUATIONS e 4 MONTH: -

NOVEMBER 1992 DOCKETtlo:

UNIT NAME:

DATE:

COMPLETED BY:

TELEPHONE:

50-311 SALEM 2 DECEMBER 10, 1992 J. FEST (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 and concurs with these evaluations.

ITEM A.

Design Change Packages 2SC-2267 Pkg 2 2SC-2267 Pkg 3

SUMMARY

"Safeguards Equipment Controller -

ATI Restoration" The purpose of this change is to install new EPROMs in the ATis of the three SECs and spare chassis.

It will activate the ATis for the first time.

Output alarm relays will be installed in existing XK-9 and XK-91 sockets.

Wires will be terminated, as required to allow annunciation at the Aux and Overhead Annunciator Systems.

The main advantage of the ATI is that it will help maintenance personnel to locate system faults quickly.

If an alarm occurs, the ATI will stop at that location, however, the mode-op function will remain operable.

The ATI provides a self checking function for the SEC.

replacement EPROMS are qualified to the original specifications, and the modification will be thoroughly tested prior to declaring the SEC operable.

There is no reduction in the margin of safety as defined in the basis for any Technical Specification.

(SORC 92-115)

"SEC Circuit -

Service Water Pump Start Test Switch Installation" Rev. 1 -

The purpose of this change is to provide a permanently mounted key lock test switch in the 24 service water pump circuit breaker cubicle.

The switch will be installed in the service water pump SEC circuitry, and when placed in the "Test" position, will ensure that two service water pumps are available to provide flow to the plant (Minimum Safeguards Requirement) powered from different vital busses during performance of SP(0)4.0.5-P-SW (24-26), Full Flow Test Surveillance, with an SEC Mode Operation.

This modification will also eliminate the current practice of lifting a lead in the SEC cabinet during performance of SP(0)4.0.5-P-SW (24-26),

and provide an added degree of personnel safety.

Since the installation of a key lock test switch does not affect the subject

e 10GFR50.59 EVALUATIONS

,MONTH: -

NOVEMBER 1992 (cont'd)

ITEM 2EC-3105, Pkg.1 B.

Procedures and Revisions S2.0P-SO.BR-0001(Z) e DOCKET NO:

UNIT NAME:

DATE:

COMPLETED BY:

TELEPHONE:

SUMMARY

50-311 SALEM 2 DECEMBER 10, 1992 J. FEST (609)339-2904 Technical Specification Requirement, the margin of safety as defined in the Basis of the Technical Specifications is not reduced.

(SORC 92-115)

"Rad Waste Panel 104 Modifications" Rev.1 -

The purpose of this change is to modify Rad Waste Panel 104 and associated instruments and equipment.

Work will include upgrading of instrument loops with new components, physical repair of Panel 104, removal of equipment no longer needed, and a functional verification of each instrument loop.

The instruments being replaced include indicating switches which are used to monitor administratively controlled evolutions within the Liquid Radwaste, Gaseous Waste, and eves Systems. The replacement components are similar in fit and function to the existing instruments except that the Helicoid indicating switches do not permit indication beyond the setpoint values. The switches have "control tabs" on the setpoint indicators which lock in the alarm value but prevent the indicating needle from passing the setpoint indicator. Process values beyond the setpoint will not be shown to the operator.

The purpose of this revision of the DeP is to authorize revision of OD-36 to ensure that daily checks of instrument setpoint locations will occur. The new method of indication has been.

analyzed and no unresolved safety question is involved.

(SORe 92-116)

"Boric Acid Evaporator Operations" Rev. o - The purpose of this procedure is to provide direction for the operation of the Boric Acid Evaporator. This new procedure allows for transfer of the Boric Acid Evaporator bottom to the eves Holdup Tank or the Boric Acid Tank.

The intent of the UFSAR was to ensure that the evaporator bottoms were sampled prior to discharge to the eves HUT or the Boric Acid Tank. The UFSAR implies allowance for sampling

==================-------------- -

e lOCF'.R.50.59 EVALUATIONS

• MONTH:.- NOVEMBER 19 9 2 (cont'd)

ITEM e

DOCKET NO:

UNIT NAME:

DATE:

COMPLETED BY:

TELEPHONE:

SUMMARY

50-311 SALEM 2 DECEMBER 10, 1992 J. FEST (609) 33.9-2904 without transfer to the concentrates holding tank because it mentions the existence of a sample connection at the discharge of the boric acid concentrates' pump.

This procedure places procedural controls on boron concentration of the bottom concentrates that are discharged to the CVCS HUT and/or the Boric Acid Tanks.

The boron recovery system is not used for accident mitigation, therefore, this procedure does not reduce the margin of safety as defined in the basis for any Technical Specification.

( SORC 92-116)

i--

1 I

I SALEM UNIT NO. 2 SALEM GENERATING STATION MONTHLY OPERATING

SUMMARY

UNIT 2 NOVEMBER 1992 The Unit began the period operating at full power.

Power was reduced to 45% on November 11, 1992 to perform maintenance on 21 and 22 Steam Generator Feedpumps.

The Unit was subsequently taken off line to repair a stator cooling water leak in the neutral bushing lead box and to determine the source of H2 in the stator cooling system.

Repairs were completed and the Unit was resynchronized on November 15, 1992.

The Unit was restored to full power on November 16, 1992, and continued to operate at full power throughout the remainder of the period.

R~RU~L~NG INFORMATION ~

,,l-10NTH: -

NOVEMBER 1992 e

DOCKET NO:

UNIT NAME:

50-311 SALEM 2 DATE:

COMPLETED BY:

TELEPHONE:

DECEMBER 10, 1992 J. FEST (609)339-2904 MONTH NOVEMBER 1992

1.

Refueling information has changed from last month:

YES NO X

2.

Scheduled date for next refueling:

MARCH 27, 1993

3.

Scheduled date for restart following refueling:

MAY 21. 1993

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?: FEBRUARY 1993

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

b.

In Spent Fuel storage

8.

Present licensed spent fuel storage capacity:

Future spent fuel storage capacity:

193 408 1170 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