ML18100B204

Monthly Operating Rept for June 1994 for Salem Generating Station Unit 2

ML18100B204
Person / Time
Site:	Salem
Issue date:	06/30/1994
From:	Hagan J, Morroni M Public Service Enterprise Group
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 9407180207
Download: ML18100B204 (8)

Text

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Public' Service Electric and Gas Company P.O. Box 236 Hancocks Bridge, New Jersey 08038 Salem Generating Station July 14, 1994 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 1994 are being sent to you.

RH:pc Average Daily Unit Power Level Operating Data Report Unit Shutdowns and Power Reductions 10CFR50.59 Evaluations Operating summary Refueling Information Sincerely yours, ger -

cc:

Mr. Thomas T. Martin Regional Administrator USNRC Region I 631 Park Avenue King of Prussia, PA 19046 Enclosures 8-1-7.R4 The Enerav Peoole 9407180207 940630 PDR ADDCK 05000311 R

PDR 95-2189 (10M) 12-8

.ERAGE DAILY UNIT POWER LE~

Docket No.:

50-311 Unit Name:

Salem #2 Date:

07-10-94 Completed by:

Mike Morroni Telephone:

339-2122 Month June 1994 Day Average Daily Power Level Day Average Daily Power Level (MWe-NET)

(MWe-NET) 1 1039 17 1075 2

1028 18 886 3

1062 19 1039 4

1058 20 1053 5

1046 21 1001 6

1046 22 878 7

1037 23 504 8

1057 24 308 9

1044 25 0

10 1023 26 0

11 975 27 0

12 1037 28 0

13 1049 29 0

14 892 30 0

15 1026 31 16 1043 P. 8.1-7 Rl

~ OPERATING DATA REPORT ~

Docket No:

50-311 Date:

07/10/94 Completed by:

Mike Morroni Telephone:

339-2122 Operating Status

1.

Unit Name Salem No. 2 Notes

2.

Reporting Period June 1994

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)

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 720 652.65 0

577.05 0

1846245.6 582860 551889 80.1 80.1 69.3 68.7 6.9 Year to Date Cumulative 4343 111456 4198.68 73478.24 0

0 4039.3 70928.82 0

0 12013790.1 174476729.5 3837320 74383838 3650335 70777612 93 63.6 93 63.6 76 57.4 75.4 57 4.8 21.8

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

Refueling outage scheduled to start October 15, 1994 and last 60 da s.

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

NA 8-l-7.R2

NO.

DATE 1212 6/22/94 1251 6/24/94 1252 6/24/94 1265 6/25/94 1

F:

Forced S: Scheduled UNIT SHUTDOWN AND POWER REDUCTIONS REPORT MONTH JUNE 1994 METHOD OF SHUTTING LICENSE DURATION DOWN EVENT SYSTEM TYPE1 (HOURS)

REASON 2 REACTOR REPORT #

CODE4 F

51.07 A

5 HF F

14.74 B

5 cc F

13.67 A

5 HA s

100.26 B

1 HF 2

3 Reason A-Equipment Failure (explain)

B-Maintenance or Test C-Refueling D-Requlatory Restriction E-Operator Training & License Examination F-Administrative G-Operational Error (Explain)

H-Other (Explain)

Method:

1-Manual 2-Manual Scram 3-Automatic Scram 4-Continuation of Previous Outage 5-Load Reduction 9-0ther COMPONENT CODE5 PUMPXX VAL VEX VAL VEX PUMPXX 4

DOCKET NO.

50-272 UNIT NAME Salem #2 DATE 07-10-94 COMPLETED BY Mi<<e Morroni TELEPHONE:

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

CAUSE AND CORRECTIVE ACTION TO PREVENT RECURRENCE CIRCULATING WATER PUMPS MAIN SAFETY/RELIEF VALVE TEST GOV. CONTROLS VALVE TURBINE INTAKE GRATING FOULING 5

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

J

l-OCFR50.59 EVALUATIONS MONTH: -

JUNE 1994 DOCKET

• UNIT NAME:

DATE:

COMPLETED BY:

TELEPHONE:

50-311 SALEM 2 JULY 10, 1994 R. HELLER (609)339-5162 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

SUMMARY

A.

Design Change Packages 2EC-3178 Pkg 2 2EC-3228 Pkg 1 "Digital Feedwater/ RG 1.97 Isolators" - This DCP will install new signal isolation devices in class lE instrument loops within instrument racks which contain various monitoring and protection channels.

The new isolators will be manufactured by NUS and will comprise two types: a) direct replacements for Hagan isolators currently in use within the protection racks, and b) stand alone encapsulated isolators for use within the process and protection racks.

Each of the selected isolators has been fully tested by NUS for seismic and performance requirements (including surge withstand and fault testing) to ensure its acceptability for use in class lE applications at Salem Generating station.

This DCP will make no changes to the functional.

operational, or design requirements of any of the affected instrument loops, including instrument

• ranges, setpoints, and protection channel response times as noted in the Salem Generating station Technical Specifications.

No changes will be made to any Limiting Conditions for Operation nor to any surveillance.

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

(SORC 94-047)

"Waste Gas Compressor Modifications" - This DCP involves modifications on the Waste Gas Compressor Header and Waste Gas Compressor skids.

The replacement of valves and some piping segments on the compressor skids with stainless steel equivalent components and addition of vent header drain assembly will eliminate the system malfunctions due to water intrusion and rusting.

The addition of isolation valves will allow maintenance to be performed on one compressor without shutdown of the other.

The addition of bypass valves around the water inlet valve WG13, will allow the separator

+ocFR50.59 EVALUATIONS MONTH: -

JUNE 1994 (cont'd)

ITEM 2EC-3285 Pkg 1 DOCKET..

UNIT NAME:

DATE:

COMPLETED BY:

TELEPHONE:

SUMMARY

50-311 SALEM 2 JULY 10, 1994 R. HELLER (609)339-5162 tanks to be filled with water without running the compressor dry.

The replacement of the existing leaking valves should eliminate oxygen incursion in

• the waste gas decay tanks and provide the capability for maintaining an inventory of spare parts for easy maintenance of the valves and skid in the future.

The addition of pressure gages will add diagnostic capabilities for troubleshooting the compressors.

The proposed changes do not reduce the margin of safety as defined in the basis for any Technical Specification.

(SORC 94-049)

"Condensate & Feedwater Systems Overpressurization Protection Installation" -

The purpose of this change is as follows: 1.) To install 3/4" x 1 11 flanged safety relief valves (21 & 22BF82) on the valve bonnet of check valves 21 and 22BF2.

This will involve drilling the flat plate valve bonnets and welding on a flanged pipet connection to mount the relief valves.

Route the 1 11 relief valve outlet piping from relief valves 21 & 22BF82 (Elv. 105'-6")

to down to Elv. 100 1 -6 11

• Two (2) pipe supports will be required for these piping runs; 2.) To install 3/4" x 1 11 flanges safety relief valves (21, 22 &

23CN141 & 142) on the 18 11 90 degree elbows on the outlet of 22/25A, B and C low pressure feedwater heaters between valves 21, 22 & 23CN24/25 and 29/30.

This will involve drilling the 18 11 elbows and welding on a flanged pipet connection to mount the relief valves.

The outlet piping on relief valves 21, 22 and 23CN141 & 142 will not require any pipe supports.

These modifications address concerns identified in INPO Operations and Maintenance Reminder (O&MR-302) and INPO Significant Event Report (SER) 02-92.

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

(SORC 94-051)

SALEM UNIT NO. 2 SALEM GENERATING STATION MONTHLY OPERATING

SUMMARY

UNIT 2 JUNE 1994 The Unit began the period operating at full power and, with the exception of minor load reductions to clean condenser waterboxes and circulating water screens, and a scheduled load reduction to repair a turbine auxiliaries cooling heat exchanger leak, continued to operate at full power until June 23, 1994.

Power was reduced to 55% on June 23, 1994, and the Unit was taken off line on June 24, 1994, for circulating water inlet area dredging.

The reactor remained critical during dredging operations; however, a reactor trip occurred on June 29, 1994, during power escalation, due to a low low steam generator level signal.

The Unit remain shutdown throughout the remainder of the period as investigations into the event continued.

~EFUELING INFORMATION MONTH: -

JUNE 1994 MONTH JUNE 1994 DOCKET

• UNIT NAME:

DATE:

COMPLETED BY:

TELEPHONE:

1.

Refueling information has changed from last month:

YES NO ~~X~~

2.

Scheduled date for next refueling:

OCTOBER 15, 1994 50-311 SALEM 2 JULY 10, 1994 R. HELLER (609)339-5162

3.

Scheduled date for restart following refueling: DECEMBER 13, 1994

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 94

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 492

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