ML18100A760

Monthly Operating Rept for Nov 1993 for Salem Unit 2.W/ 931210 Ltr

ML18100A760
Person / Time
Site:	Salem
Issue date:	11/30/1993
From:	Heller R, Shedlock M Public Service Enterprise Group
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 9312200006
Download: ML18100A760 (10)

Text

1-Public Service Electric and Gas Company P.O. Box 236 Hancocks Bridge, New Jersey 08038 Salem Generating Station December 10, 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 November 1993 are being 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 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 9312200006 931130 I 1' 95-2189 (10M) 12-89 PDR ADOCK 05000311 l_J)

R PDR

e AVERAGE DAILY UNIT POWE.VEL Docket No.: 50-311 Unit Name: Salem #2 Date: 12-10-93 Completed by: Mark Shedlock Telephone: 339-2122 Month NOVEMBER 1993 Day Average Daily Power Level Day Average Daily Power Level (MWe-NET) (MWe-NET) 1 1014 17 1127 2 1120 18 1134 3 1140 19 1130 4 1139 20 1131 5 1122 21 1131 6 1123 22 1115 7 1116 23 996 8 1114 24 860 9 1119 25 944 10 1120 26 1008 11 1120 27 1127 12 1132 28 1124 13 1135 29 1053 14 805 30 1023 15 1076 31 16 1133 P. 8.1-7 Rl

OPERATING DATA REP~

Docket No: 50-311 Date: 12/10/93 Completed by: Mark Shedlock Telephone: 339-2122 Operating Status

1. Unit Name Salem No. 2 Notes

2. Reporting Period November 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 NONE This Month Year to Date Cumulative

11. Hours in Reporting Period 720 8016 106369

12. No. of Hrs. Rx. was Critical 720 5442.11 69207.71

13. Reactor Reserve Shutdown Hrs. 0 0 0

14. Hours Generator On-Line 720 5259.21 66817.67

15. Unit Reserve Shutdown Hours 0 0 0

16. Gross Thermal Energy Generated (MWH) 2375899.2 17136708 162232397.8 Gross Elec. Energy Generated (MWH) 811230 5760570 *70468058

18. Net Elec. Energy Gen. (MWH) 778308 5478233 67064209

19. Unit Service Factor 100 65.6 62.8

20. Unit Availability Factor 100 65.6 62.8

21. Unit Capacity Factor (using MDC Net) 97.7 61.8 57

22. Unit Capacity Factor (using DER Net) 96.9 61.3 56.5

23. Unit Forced Outage Rate 0 11.6 22.1

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 NOVEMBER 1993 DOCKET NO.: ....:5::..:0:..,.*""27c.::2~--

UN IT NAME: _s'"-'a""'l""e"'m-'#"-"'2,___ _

DATE: _1"""2,._/""10=/+93"""'"'__,-

COMPLETED BY: Mark Shedloc~

TELEPHONE: ....:3=3-.9.....

-2""'1=22---._ _

METHOD OF SHUTTING LICENSE DURATION DOWN EVENT SYSTEM COMPONENT CAUSE AND CORRECTIVE ACTION 2

NO. DATE TYPE 1 (HOURS) REASON REACTOR REPORT # CODE 4 CODE 5 TO PREVENT RECURRENCE 044 11-14-93 F 5.9 A 5 ------- CH HTEXCH NUCLEAR STEAM GENERATOR INTERNAL PROBLEMS 045 11-23-93 F 25.38 A 5 ------- HF PUMPXX CIRCULATING WATER PUMPS 046 11-28-93 F 6.73 A 5 ------- EG RELAYX SWITCHYARD OR HIGH VOLTAGE SYSTEM PROBLEMS 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-Refueling 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)

SAFE~Y RELATED MAIN.ANCE DOC.T NO:

UNIT NAME:

50-311

• MONTH.: - NOVEMBER 1993 SALEM 2 DATE: DECEMBER 10, 1993 COMPLETED BY: R. HELLER TELEPHONE: (609)339-5162 WO NO UNIT EQUIPMENT IDENTIFICATION 931025097 2 VALVE 22SW4 FAILURE DESCRIPTION: SERVICE WATER LEAK ON THE PIPING AT THE WELD TO 22SW4 - REPAIR 931029130 2 VALVE 26SW3 FAILURE DESCRIPTION: HANDWHEEL BROKEN OFF DURING TAGGING - REPLACE

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931103095 2 VALVE 23SW58 FAILURE DESCRIPTION: 23SW58 HAS NO FLOW - OPEN AND INSPECT 931112110 2 2A DIESEL GENERATOR FAILURE DESCRIPTION: THE BRANCH PIPE TO HEADER JACKET WATER IS LEAKING - REWORK BY CHANGING OUT GASKETS

10CFRS0.59'EVALUATI. DO.T NO: 50-311

~MONTH.: - NOVEMBER 19 9 3 UNIT NAME: SALEM 2 DATE: DECEMBER 10, 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-3202 Pkg 1 "CW-0008 circulating Water Electrical Upgrade Unit 2 (Outage)" - This DCP performs the following work:

1.) This DCP completes the electrical tie-in of the new Unit 2 Circ. Water 460V substation and demolished the existing substation. The substation was installed previously on its foundation by DCP lSC-2298. A new splice/pull box is installed on the existing foundation to perform the cable splices.

The substation is tested and re-energized; 2.) The 230 VAC motor control center, transformer, control equipment and lighting panels are located in a metal building ("Control House"). This control house is dismantled and replaced. All existing electrical equipment is reused. New ventilation, sump pump and piping is provided for the cable manhole; 3.) This DCP refurbished panels 360-2 and TS-2. Panels 670-2A, 670-2B and 670-2C are replaced, and 4.)

Three of the four screen wash pump motors (No. 21, 23, 24) have been replaced over time as the old motors failed. When the motors were replaced, they were upgraded from 125 horsepower to 150 horsepower. The remaining 125 HP motor (No. 22) is replaced by this DCP. Cabling to all four screen wash pumps is replaced to accommodate the increased motor size. This DCP 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. This modification increases the circulating water system reliability and availability. (SORC 93-101) 2EC-3081 Pkg 1 "Penetration Area Welding Receptacles" Rev. 1 - This DCP provides three new 460V welding receptacles, one in the Chilled Water Pump Area, El. 100, at column lines BC-16.2, one in the Main Steam Penetration

10CFR50.59"EVALUATI. DO.T NO: 50-311

• MONTH; - NOVEMBER 1993 UNIT NAME: SALEM 2 DATE: DECEMBER 10, 1993 COMPLETED BY: R. HELLER TELEPHONE: (609)339-5162 (cont'd)

ITEM

SUMMARY

Area, El. 100, near column lines FF-16.8, and one in Personnel Hatch Area, 'El. 100, near column lines GG-16.8. These receptacles are in a common circuit fed from a new circuit breaker, I2118-21X, in the 2El 460-230 Volt Control Center. With this installation, welding receptacles will be available to power welding machines in these areas with no need to breach wall penetrations for power cables.

This will provide the capability for TIG welding, as well as SMAW welding, in each of these areas without the need to breach wall penetrations. This DCP will not reduce the margin of safety as defined in the basis for any Technical Specification because the new welding machine receptacles will be on a circuit powered from a non-vital bus, the 2EL 460-230V Control Center. The control center has the spare capacity to take the additional circuit and there -1 I

will be no effect on any other part of the power distribution system, vital or non-vital. There is no increase in load on the control center or the group bus as far as the Load Management Study is _

concerned because the welding receptacles are intermittent loads. Activities pertaining to the affected penetrations will be conducted in accordance with approved procedures. (SORC 93-103)

B. Safety Evaluations (S/E)

CN 93-24 "SGS-UFSAR Section 3.6.5.12.5 Revisions" - DEF

1. DES-93-00660 identified that SGS-UFSAR Section 3.6.5.12.5 which applies only to Unit 2 does not address moderate energy pipe failure in the 10 Ton C02 Room and the Diesel Fuel Storage Tank areas.

SGS-UFSAR Section 3.1.3 identifies that the NRC required that a Moderate - Energy Break Analysis (MEBA) be performed for Unit 2. The proposal revises SGS-UFSAR Section 3.6.5.12.5 to address the 10 Ton C02 room, the Diesel Fuel storage Tank areas, and the entrance to these areas on the basis of a revised MEBA (Design Calculation S-C-ZZ-SDC-1203} as follows: "The 10 Ton C02 Room, the Diesel Fuel Storage Tank areas, and the entrance to these areas contain service water, fuel oil, and carbon dioxide

10CFRS0.59"EVALUATI. DO.T NO: 50-311

'MONTH~ - NOVEMBER 1993 UNIT NAME: SALEM 2 DATE: DECEMBER 10, 1993 COMPLETED BY: R. HELLER TELEPHONE: {609)339-5162 (cont'd)

ITEM

SUMMARY

fire protection MEL piping in addition to diesel fuel oil storage and transfer system equipment. The areas do not contain floor drainage, hence service water or fuel oil piping failure could cause flooding of the areas and the adjoining fuel transfer pump rooms. therefore, flooding of diesel fuel oil storage and transfer system equipment can occur. Spray damage can also occur. However, because blackout coincident with service water or fuel oil piping failure is not a design basis condition at Salem Generating Station, diesel fuel oil storage and transfer equipment are not required to function to mitigate the consequences of such piping failure. Protection against the effects of service water or fuel oil piping failure is not required for diesel fuel oil storage and transfer system equipment. No changes are being made to any component, system or structure. There is no effect on plant operation. The only change is the addition of a description of the facility in SGS-UFSAR Section 3.6.5.12.5, which is changed on the basis o'f a revised MEBA {Design Calculation S-C-ZZ-SDC-1203). There is no reduction in the margin of safety as defined in the basis for any Technical Specification. {SORC 93-101)

SALEM GENERATING STATION MONTHLY OPERATING

SUMMARY

- UNIT 2 NOVEMBER 1993 SALEM UNIT NO. 2 The Unit began the period operating at full power and continued to operate at essentially full power until November 14, 1993, when load was reduced to 50% for repairs to repair #21 steam generator feed pump. The Unit was restored to full power on November 15, 1993, and continued to operate at that level until November 23, 1993, when power was reduced to 79% due to jamming of the travelling screen for 23A circulator. The repairs were completed and a power escalation commenced later the same day. Power was held at 86% due to governor swings on #21 steam generator feed pump. Power was increased to 100%

on November 26, 1993. A load reduction to 80% was required on November 29, 1993 due to forced cooling problems on the main transformer. The cooling was restored and power increased to 100%

later in the day. The Unit continued to operate at 100% power through the remainder of the period.

REFUELING. INFORMATII DO.T NO: 50-311 "MONTH-:: -'NOVEMBER 1993 UNIT NAME: SALEM 2 DATE: DECEMBER 10, 1993 COMPLETED BY: R. HELLER TELEPHONE: (609)339-5162 MONTH NOVEMBER 1993

1. Refueling information has changed from last month:

YES NO X

2. Scheduled date for next refueling: SEPTEMBER 24, 1994

3. Scheduled date for restart following refueling: NOVEMBER 22, 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 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