ML18100A660

Monthly Operating Rept for Sept 1993 for Salem Unit 2. W/931008 Ltr

ML18100A660
Person / Time
Site:	Salem
Issue date:	09/30/1993
From:	Heller R, Shedlock M Public Service Enterprise Group
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 9310200209
Download: ML18100A660 (10)

Text

Public S*ervice Electric and Gas Company P.O. Box 236 Hancocks Bridge, New Jersey 08038 Salem Generating Station October 8, 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 September 1993 are be~ng sent to you.

Average Daily Unit Power Level Operating Data Report Unit Shutdowns and Power Reductions Safety Related Maintenance 10CFR50.59 Evaluations Operating Summary Refueling Information 8?tJZL General Manager -

Salem Operations RH:pc 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 .- . -

9310200209 930930 * -- r---- 95-2189 (10M) 12-89 PDR ADOCK osooo311 I **

R PDR /__,

~ERAGE DAILY UNIT POWER L~L Docket No.: 50-311 Unit Name: Salem #2 Date: 10-08-93 Completed by: Mark Shedlock Telephone: 339-2122 Month September 1993 Day Average Daily Power Level Day Average Daily Power Level (MWe-NET) (MWe-NET) 1 1081 17 1052 2 1048 18 949 3 865 19 1127 4 410 20 1100 5 480 21 1114 6 1057 22 1117 7 1115 23 1133 8 1088 24 1128 9 1120 25 1108 10 1113 26 1119 11 1116 27 1113 12 1108 28 1115 13 1114 29 1118 14 1091 30 1125 15 1095 31 16 1068 P. 8.1-7 Rl

OPERATING DATA REPORT~

Docket No: 50-311 Date: 10/08/93 Completed by: Mark Shedlock Telephone: 339-2122 Operating Status

1. Unit Name Salem No. 2 Notes

2. Reporting Period Se:gtember 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) 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~O~N~E=-~~~~~~~~~~~~~~

This Month Year to Date Cumulative

11. Hours in Reporting Period 720 6551 104904

12. No. of Hrs. Rx. was Critical 720 3977.1 67742.7

13. Reactor Reserve Shutdown Hrs. O 0 0

14. Hours Generator On-Line 720 3831.1 65389.6

15. Unit Reserve Shutdown Hours O 0 0

16. Gross Thermal Energy Generated (MWH) 2349696.0 12604588.8 157700278.6 Gross Elec. Energy Generated (MWH) 785910 4233530 68941018

18. Net Elec. Energy Gen. (MWH) 753235 4016932 65602908

19. Unit Service Factor 100 58.5 62.3

20. Unit Availability Factor 100 58.5 62.3

21. Unit Capacity Factor (using MDC Net) 94.6 55.4 56.5

22. Unit Capacity Factor (using DER Net) 93.8 55.0 56.1

23. Unit Forced Outage Rate O 14.6 22.4

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-l-7.R2

UNIT SHUTDOWN AND POWER REDUCTIONS REPORT MONTH SEPTEMBER 1993 DOCKET NO.: _,5:;.;:0'°"'"-=27:.. .:2""=-_ __,

UNIT NAME: Salem #2 DATE: 10/08/93 COMPLETED BY: .Mark Shedlock TELEPHONE: 339-2122 METHOD OF r -

SHUTTING LICENSE DURATION DOWN EVENT SYSTEM COMPONENT CAUSE AND CORRECTIVE ACTION NO. DATE TYPE 1 (HOURS) REASON 2 REACTOR REPORT # CODE 4 CODE 5 TO PREVENT RECURRENCE 0037 9-3-93 F 46.8 A 5 ---------- CH PIPEXX #21 S.G. FEED PUMP LEAK 0038 9-17-93 F 14.3 B 5 ----------- HF HT EX CH WATERBOX CLEANING 1 2 3 4 5 F: Forced Reason Method: Exhibit G - Instructions Exhibit 1 - Same S: Scheduled A-Equipment Failure (explain) 1-Manual for Preparation of Data Source B-Maintenance or Test 2-Manual Scram Entry Sheets for Licensee C-Refuel ing 3-Automatic Scram Event Report CLER) File D-Requlatory Restriction 4-Continuation of (NUREG-0161)

E-Operator Training & License Examination Previous Outage F-Administrative 5-Load Reduction G-Operational Error (Explain) 9-0ther H-Other (Explain)

SAFET¥ RELATE~ MAI~TEN,CE MONTH: - SEPTEMBER 1993 DOCKE~O:

UNIT NAME:

50-311 SALEM 2 DATE: OCTOBER 8, 1993 COMPLETED BY: R. HELLER TELEPHONE: (609)339-5162 WO NO UNIT EQUIPMENT IDENTIFICATION 930818218 2 2R46A MAIN STEAMLINE RADIATION MONITOR FAILURE DESCRIPTION: CHECK SOURCE WEAK - INVESTIGATE 930920109 2 21 STEAM GENERATOR LEVEL INDICATION FAILURE DESCRIPTION: 2LI1640 >3.3% DIFFERENCE WITH 2LI518 - TROUBLESHOOT 930920112 2 24 STEAM GENERATOR LEVEL INDICATION FAILURE DESCRIPTION: 2LI1643.>3.3% DIFFERENCE WITH 2LI548 - TROUBLESHOOT 930922069 2 24 CONTAINMENT FAN COIL UNIT FAILURE DESCRIPTION: SW FLOW LOW IN LOW SPEED -

INVESTIGATE AND CORRECT 930927150 2 PRESSURIZER LEVEL INDICATION FAILURE DESCRIPTION: 2LT459 CLOSE TO 3% DIFFERENCE WITH OTHER CHANNEL - INVESTIGATE

10CFR50.59 EV~LUAT~ONS~

• ONTH: - SEPTEMBER 1993 DOCKE~O:

UNIT NAME:

50-311 SALEM 2 DATE: OCTOBER 8, 1993 COMPLETED BY: R. HELLER TELEPHONE: (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-3200 Pkg 1 "Fuel Transfer Tube Blind Flange Replacement/Bolt Reduction" - The proposed modification will replace the existing 20 11 fuel transfer blind flange at Salem Unit 2. The existing flange which uses two (2) flexitallic gaskets and requires twenty bolts to obtain a proper seal, will be replaced with a new blind flange utilizing a new seal design which only requires four bolts to obtain a proper seal. The new blind flange utilizes a Westinghouse design ,

which replaces the flexitallic gaskets with a rubber Quad ring seal design. Design calculations performed by Westinghouse show that a minimum of four (4) bolts can be used with the quad ring seals while still generating sufficient preload to compress the seals and resist hydraulic and seismic forces. The proposed changes to the fuel transfer tube blind flange is being implemented as a maintenance/ radiation dose reduction enhancement (ALARA). The margin of safety of the fuel transfer tube blind flange and bolting is defined, in part, by the requirements imposed by the ASME code. The design requirements have been shown to be met. The containment isolation function is maintained. The margin of safety is therefore, unaffected.

(SORC 93-082) 2EC-3078 Pkg 1 "Rosemount 1153 Upgrade/Replacement with 1154 11 Rev.

7 - The purpose of this revision is to revise the 10CFR50.59 evaluation to reflect the instrument accuracies as calculated by the setpoint/accuracy calculations. Although some of these changes are in the less-conservative direction, the analysis performed on the EOP basis and proposed EOP revisions has been found to be acceptable. This modification replaced 27 Rosemount electronic transmitters with new transmitters having improved performance under harsh environmental conditions.

.. e 10CFR50.59 EVALUATIONS DOCKEAo: 50-311

~ONTH: - SEPTEMBER 1993 UNIT NAME: SALEM 2 DATE: OCTOBER 8, 1993 COMPLETED BY: R. HELLER TELEPHONE: {609)339-5162 (cont.'d)

ITEM

SUMMARY

The new transmitters are seismically and environmentally qualified for the installed locations. There is no change to instrument process variable spans. The new transmitters are equal to or better than the previous instruments under all conditions. Verification of the P-11 allowable value, consistent with the setpoint calculation, will continue to assure that manual block of safety injection is defeated well above the SI actuation allowable value of ~ 1775 psi. There is no impact on the margin of safety as defined in the basis for any Technical Specification. {SORC 93-085) 2EC-3211 Pkg 1 "SGFP/Condensate Pump/Feedwater Heaters: System Design Press Modifications" Rev. 3 - The purpose of this revision is to revise the 10CFR50.59 evaluation to address a change to UFSAR Table 10.4-1. This change will provide setpoint corrections for the 21, 22 and 23 condensate pump recirculation flow control loops to ensure a maximum sustained nominal pressure of 625 psig during cold startup. This change will also provide setpoint corrections for the f eedwater heaters 26A, 26B and 26C thermal relief valves 21, 22 and 23HV22. This change will develop a two-out-of-two high pressure trip signal by installing redundant transmitters on the discharge piping of each f eedwater pump to provide the required protection while minimizing the potential for a spurious trip. The existing feed pump trip circuitry will be modified to allow the feed pump to trip on a high feed pump discharge pressure at all power levels. The existing L&N power supply, bistable and transmitter from each of the #21 and

1. 22 SGFP analog discharge pressure transmitter-circuits, as well as the existing Keylock override switches will be deleted to implement the new single channel instrument loop trip circuitry noted above. The only Technical Specification which involves SGFP circuitry is Technical Specification 3/4.3.2.b {Table 3.3-3, 5.a

& 8.f), feedwater isolation and a trip of main feedwater pumps starting the motor driven Auxiliary

- . e 10CFR50.59 EVALUATIONS DOCKE.O: 50-311 MONTH: - SEPTEMBER 1993 UNIT NAME: SALEM 2 DATE: OCTOBER 8, 1993 COMPLETED BY: R. HELLER TELEPHONE: (609)339-5162 (cont'1 d)

ITEM

SUMMARY

Feedwater pump. This modification does not alter this function in any way. There is no reduction in the margin of safety as defined in the basis for any Technical Specification. (SORC 93-085)

B. Temporary Modifications TMOD 93-031 "Temporary Operation and Control of CW Systems" -

The purpose of this modification is to provide temporary connections for continued operation of Unit 2 CW equipment (circulating water pumps, circulator bearing lube pumps, screen wash pumps, and traveling screens) during performance of DCP lSC-2297 when old Panel 371 will be replaced by new Panel 371. This design change does not reduce the margin of safety as defined in the basis for any Technical Specification. There are no requirements directly specified for the operation or performance of any circulating water system equipment in the Technical Specifications. The TMOD allows the.

operator to manually start the circulating water pumps when adequate circulator bearing lube header pressure is available and to maintain circulator bearing lube pressure and travelling screen wash header pressure manually from Panel 360-2 during the installation of Panel 371 by DCP lSC-2297.

(SORC 93-083)

SALEM GENERATING STATION MONTHLY OPERATING

SUMMARY

- UNIT 2 SEPTEMBER 1993 SALEM UNIT NO. 2 The Unit began the period operating at full power and continued to operate at full power until September 3, 1993, when power was reduced to 90% to repair a leaking turbine auxiliaries cooling system heat exchanger drain valve. On September 4, 1993, power was further reduced to 48% to repair a leaking drain valve on #21 steam generator feedwater pump. The Unit was returned to full power on September 6, 1993, and continued to operate at full power until September 28, 1993, when power was reduced to 80% to replace 22B circulating water pump and clean condenser water boxes. The Unit was returned to full power later, the same day, and continued to operate at full power throughout the remainder of the period.

REFUELING INFORMATION e

DOCKET NO: 50-311 MONTH: - SEPTEMBER 1993 UNIT NAME: SALEM 2

.- DATE: OCTOBER 8, 1993 COMPLETED BY: R. HELLER TELEPHONE: (609)339-5162 MONTH SEPTEMBER 1993

1. Refueling information has changed from last month:

YES NO X

2. Scheduled date for next refueling: SEPTEMBER 17, 1994

3. Scheduled date for restart following refueling: NOVEMBER 6, 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?:

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 464

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