ML18096B280

Monthly Operating Rept for Jan 1993 for Salem,Unit 2.W/

ML18096B280
Person / Time
Site:	Salem
Issue date:	01/31/1993
From:	Fest J, Shedlock M PACIFIC GAS & ELECTRIC CO., Public Service Enterprise Group
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 9302220409
Download: ML18096B280 (10)

Text

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• ps~G Public Service Electric and Gas Company P.O. Box 236 Hancocks Bridge, New Jersey 08038 Salem Generating Station February 12, 1993 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 1993 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,

/J/!JV4~

~Iteral 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 9302220409 930131 PDR ADOCK 05000311 R

PDR 95-2189 (10M) 12-89

8-1-7.R2 AVERAGE DAILY UNIT POWER LEVEL Docket No.:

50-311 Unit Name:

Salem #2 Date:

2/10/93 Completed by:

Mark Shedlock Telephone:

339-2122 Month January 1993 Day Average Daily Power Level Day Average Daily Power Level (MWe-NET)

(MWe-NET) 1 1130 17 1116 2

1120 18 1109 3

1119 19 1110 4

1083 20 1127 5

1083 21 1104 6

1127 22 1128 7

1131 23 1127 8

1131 24 1110 9

1137 25 1115 10 1121 26 1107 11 1121 27 1115 12 1122 28 631 13 1131 29 0

14 1131 30 0

15 1130 31 0

16 1116 P. 8.1-7 Rl

P.. B

• 1-7'. Rl OPERATING DATA REPORT Docket No:

Date:

Completed by:

Mark Shedlock Telephone:

Operating Status

1.

Unit Name Salem No. 2 Notes

2.

Reporting Period January 1993

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)

Report, Give Reason NA

9.

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

10. Reasons for Restrictions, if any

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)

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 NA This Month Year to Date 744 744 673.6 673.6 0

0 661.8 661.8 0

0 2239932.0 2239932.0 769090 769090 737365 737365 88.9 88.9 88.9 88.9 89.6 89.6 88.9 88.9 11.1 11.1 50-311 2/10/93 339-2122 since Last NIA Cumulative 99097 64439.2 0

62220.4 0

147335621.8 65476578 62323341 62.8 62.8 56.9 56.4 22.7

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

Refueling outage scheduled to start 3-20-93 and last 74 days.

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

NA

NO.

DATE 0009 01/28/93 1

2 F:

Forced S:

Scheduled DURATION TYPE1 (HOURS)

REASON2 F

82.2 A

Reason A-Equipment Failure (explain)

B-Maintenance or Test C-Refueling D-Requlatory Restriction UNIT SHUTDOWN AND POWER REDUCTIONS REPORT MONTH JANUARY 1993 METHOD OF SHUTTING DOWN REACTOR 2

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)

DOCKET NO.: -'5""'0'"'"-=-31"'""1'"""'" __ _

UNIT NAME:

Salem #2 COMPONENT CODE 5 DATE:

02/10/93 COMPLETED BY:

Mark Shedlock TELEPHONE:

339-2122 CAUSE AND CORRECTIVE ACTION TO PREVENT RECURRENCE PUMP XX LOSS OF MAIN FEED PUMPS 4

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

SAFETY RELATED MAINTENAIE MONTH: -

JANUARY 1993 e

DOCKET NO:

UNIT NAME:

50-311 SALEM 2 WO NO UNIT 920715093 2

920916239 2

921215103 2

921227084 2

930115097 2

930120079 2

930128135 2

930128157 2

930129076 2

DATE:

COMPLETED BY:

TELEPHONE:

FEBRUARY 10, 1993 J. FEST (609)339-2904 EQUIPMENT IDENTIFICATION AUXILIARY FEEDWATER STORAGE TANK FAILURE DESCRIPTION:

LEVEL SWITCH IMPROPER SETPOINT -

INVESTIGATE RADIATION MONITOR 2R46E FAILURE DESCRIPTION:

NO RESPONSE TO CHECK SOURCE -

INVESTIGATE 22 SERVICE WATER PUMP FAILURE DESCRIPTION:

REPLACE WITH SPARE PUMP 24 STEAM GENERATOR RECORDER FAILURE DESCRIPTION:

WR LEVEL RECORDER PEN ERRATIC -

INVESTIGATE PLANT VENT FLOW RECORDER FAILURE DESCRIPTION:

FLOW RECORDER FAILED HIGH -

INVESTIGATE RADIATION MONITOR 2R41A FAILURE DESCRIPTION:

SAMPLE FLOW FAILED -

INVESTIGATE NUCLEAR INSTRUMENT 2N35 FAILURE DESCRIPTION:

CHANNEL I IR POWER SUPPLY DRIFTING -

REPLACE VALVE 2WG41 FAILURE DESCRIPTION:

VALVE TO PLANT VENT WILL NOT STAY OPEN -

INVESTIGATE VALVE 2WG38 FAILURE DESCRIPTION:

NOT CONTROLLING PRESSURE PROPERLY INVESTIGATE

e 10CFR50.59 EVALUATIONS MONTH: -

JANUARY 1993 e

DOCKET NO:

UNIT NAME:

DATE:

COMPLETED BY:

TELEPHONE:

50-311 SALEM 2 FEBRUARY 10, 1993 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 2EC-3175 Pkgs. 1 & 2 2EC-3181 Pkg. 1

SUMMARY

"22W & 23E MSR HP Tube Bundle Replacement" -

The purpose of this design change is to replace the high pressure tube bundle of MSR 22W with tube bundles of an improved and proved design.

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

(SORC 93-002)

"AFW Flow Reduction - AFll Modifications" - This design change is proposed to reduce the maximum auxiliary feedwater (AFW) flow rates, under certain plant conditions, delivered by the turbine-driven pump, by modifying flow control valves 21 to 24AF11.

The proposed design change essentially consists of limiting the upward stem travel using the side-mounted handwheel, and then locking the handwheel in the "new full open" position.

The valve stroke will be reduced form 1 1/2 inches to 29/32 inches on 21AF11 and 23AF11, and 1.0 inch on 22AF11 and 24AF11.

The existing design is suitable for a pad lock to prevent inadvertent operation.

The proposed design change will be implemented as an interim modification and will be replaced by a permanent design change (reduced capacity trim on AFlls and AF12s) during 2R8.

Prior to reducing the stroke on AFll valves, a full flow AFW test is proposed to obtain the system flow and pressure data.

This baseline test data will be used to benchmark the Salem RETRAN model and accurately specify the reduced capacity trim for AFlls and AF12s.

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

(SORC 93-002)

10CfR50.59 EVALUATIONS MONTH: -

JANUARY 1993 (cont'd)

ITEM 2EC-3127 Pkg. 1 2EC-3170 Pkg. 1 e

DOCKET NO:

UNIT NAME:

DATE:

COMPLETED BY:

TELEPHONE:

SUMMARY

50-311 SALEM 2 FEBRUARY 10, 1993 J. FEST

( 6 o 9 ) 3 3 9 - 2 9 *o 4 "Service Water Pipe Diesel Generator Piping" -

The purpose of this change is to remove a section of compressed air pipe (feeding service air drop 23SA137) during service water pipe installation under DCP 2EC-3127, and temporarily place the rest of the service air drops on elev.

84' back in service.

The system will be restored to original condition upon DCP completion.

The interim installation and test conditions do not impact the ability of the Service Water system to perform its intended safety function and will be in full compliance with the Technical Specifications.

A stress analysis has been performed to assure that the temporary configuration is acceptable and can be declared operable to meet the Technical Specification requirements for two diesels to be operable during refueling.

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

{SORC 93-007)

"Steam Generator Feed Pump Independent Control*

Oil System" -

The purpose of this change is to install two (2) Woodward High Pressure Hydraulic Power Units {21PLE40, 22PLE40) to provide an independent supply of control oil to the SGFP&T governor hydraulic actuators.

In order to provide an emergency source of oil to the new

units, connections will be made between the existing low pressure lube oil system and the new reservoirs to the SGFP&T lube oil storage tank.

Control of the new HPU's will be from control switches located inside of the new HPU auxiliary equipment cabinets which will be mounted to the end of the respective SGFP local panels (362, 363) and a normal hinged door with a handle will provide quick access to the switches.

By mounting these switches inside the panels, they are made less visible and less prone to inadvertent operation.

Abnormal HPU operation will be alarmed on the overhead annunciator (SGFP trouble) and similarly at the local SGFP panels 362 (363).

At a pressure of

e 10CFR50.59 EVALUATIONS MONTH: -

JANUARY 1993 (cont'd)

ITEM e

DOCKET NO:

UNIT NAME:

DATE:

COMPLETED BY:

TELEPHONE:

SUMMARY

50-311 SALEM 2 FEBRUARY 10, 1993 J. FEST (609)339-2904 350 PSI decreasing, the standby pump will start.

At a pressure of 300 PSI decreasing, the HPU will trip the SGFP.

During the installation of a cable through penetration seal, flood protection will be compromised.

If at anytime during this installation, the Delaware River water level, as monitored by Operations, rises above 99.5 feet, the work will be stopped and a temporary barrier will be installed.

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

(SORC 93-008)

SALEM GENERATING STATION MONTHLY OPERATING

SUMMARY

UNIT 2 JANUARY 1993 SALEM UNIT NO. 2 The Unit began the period operating at full power and continued to operate at full power until January 28, 1993, when the Reactor was manually tripped due to loss of both Steam Generator Feed Pumps.

The Reactor remained shutdown throughout the rest of the period.

L

~

REFUELING INFORMATION DOCKET NO:

MONTH: -

JANUARY 1993 UNIT NAME:

DATE:

COMPLETED BY:

TELEPHONE:

MONTH JANUARY 1993

1.

Refueling information has changed from last month:

YES X

NO ~~~~

2.

Scheduled date for next refueling:

MARCH 20, 1993 50-311 SALEM 2 FEBRUARY 10, 1993 J. FEST (609)339-2904

3.

Scheduled date for restart following refueling:

JUNE 2. 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 193

b.

In Spent Fuel storage 408

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