ML18100A604

Monthly Operating Rept for Aug 1993 for Salem Generating Station Unit 2.W/930913 Ltr

ML18100A604
Person / Time
Site:	Salem
Issue date:	08/31/1993
From:	Heller R, Shedlock M, Vondra C Public Service Enterprise Group
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 9309150394
Download: ML18100A604 (11)

Text

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Public Service Electric and Gas Company P.O. Box 236 Hancocks Bridge, New Jersey 08038 Salem Generating Station September 13, 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 August 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 S~cerel y yours, Genl~

Salem Operations RH:pc cc: Mr. Thomas T. Martin Regional Administrator USNRC Region I 631 Park Avenue King of Prussia, PA 19046 Enclosures 8-l-7.R4 PDR R

_The En_ergy Peopie .

9309150394 930831 ADOCK 05000311 PDR D16 00 _0 1u 95-2189 (10M) 12-89

~RAGE DAILY UNIT POWER LE9i Docket No.: 50-311 Unit Name: Salem #2 Date: 9/10/93 Completed by: Mark Shedlock Telephone: 339-2122 Month August 1993 Day Average Daily Power Level Day Average Daily Power Level (MWe-NET) (MWe-NET) 1 1079 17 1098 2 1088 18 1115 3 1080 19 1124 4 1113 20 1124 5 1112 21 1076 6 1084 22 1104 7 1096 23 1090 8 1103 24 1109 9 1106 25 1100 10 1098 26 1042 11 1108 27 1106 12 1111 28 1103 13 1096 29 1082 14 1133 30 1110 15 1080 31 1087 16 1098 P. 8.1-7 Rl

.. OPERATING DATA REPORT ~

Docket No: 50-311 Date: 9/10/93 Completed by: Mark Shedlock Telephone: 339-2122 Operating Status

1. unit Name Salem No. 2 Notes

2. Reporting Period August 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 NA This Month Year to Date Cumulative

11. Hours in Re~orting Period 744 5831 104184

12. No. of Hrs. Rx. was Critical 744 3257.11 67022.71

13. Reactor Reserve Shutdown Hrs. 0 0 0

14. Hours Generator On-Line 744 3111.11 64669.57

15. Unit Reserve Shutdown Hours 0 0 0

16. Gross Thermal Energy Generated (MWH) 2534409.6 10254892.8 155350582.6 Gross Elec. Energy Generated (MWH) 851680 3447620 68155108

18. Net Elec. Energy Gen. (MWH). 817861 3263697 64849673

19. Unit Service Factor 100 53.4 62.1

20. Unit Availability Factor 100 53.4 62.1

21. Unit Capacity Factor (using MDC Net) 99.4 50.6 56.3

22. Unit Capacity Factor (using DER Net) 98.6 50.2 55.8

23. Unit Forced Outage Rate 0 17.4 22.6

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

NA

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

NA 8-1-7.R2

UNIT SHUTDOWN AND POWER REDUCTIONS REPORT MONTH AUGUST 1993 DOCKET NO.

UNIT NAME 50-272 Salem #1 DATE 09/10/93 COMPLETED BY Mark Shedlock TELEPHONE 339-2122 METHOD OF SHUTTING LICENSE DURATION DOWN EVENT SYSTEM COMPONENT CAUSE AND CORRECTIVE ACTION 1

NO. DATE TYPE (HOURS) REASON 2 REACTOR REPORT # CODE 4 CODE 6 TO PREVENT RECURRENCE 114 8-19-93 F 15.27 A 5 ----------- HF PUMPXX CIRCULATING WATER PUMPS 116 8-24-93 F 1.67 A 5 ----------- EC BATTRY DC POWER PROBLEMS DC INSTRUMENT POWER 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 CNUREG-0161)

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

e SAFETY\RELATED MAINTENANCE e

DOCKET NO: 50-311 MONTH: - AUGUST 1993 UNIT NAME: SALEM 2 DATE: SEPTEMBER 10, 1993 COMPLETED BY: R. HELLER TELEPHONE: (609)339-2212 WO NO UNIT EQUIPMENT IDENTIFICATION 920916233 2 21 EMERGENCY LIGHTING INVERTER FAILURE DESCRIPTION: 21 EMERGENCY LIGHTING INVERTER SWAPPED TO ITS EMERGENCY SOURCE UNEXPECTEDLY - INVESTIGATE 930119111 2 2A2 125V BATTERY CHARGER FAILURE DESCRIPTION: BATTERY CHARGER RIPPLE VOLTAGE HIGH - CORRECT

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930503035 2 EXPANSION JOINT 2SWE51 FAILURE DESCRIPTION: INSPECT/REPAIR/REPLACE AS REQUIRED 930724080 2 VALVE 24SW20 FAILURE DESCRIPTION: 24SW20 HAS NO CLOSED INDICATION ON CONSOLE - INVESTIGATE 930808060 2 SERVICE WATER SPOOL RD-2-SW-740 FAILURE DESCRIPTION: SPOOL HAS A THOUGH WALL LEAK -

REPAIR 930821091 2 22 SERVICE WATER PUMP STRAINER FAILURE DESCRIPTION: 22 SW PUMP STRAINER SEIZED -

TROUBLESHOOT AND REPAIR 930824076 2 RADIATION MONITOR 2R46D FAILURE DESCRIPTION: 24 SG MAIN STEAMLINE RADIATION MONITOR FAILED - INVESTIGATE 930825098 2 VALVE 22RH8 FAILURE DESCRIPTION: 22RH8 DISCHARGE CHECK VALVE DID NOT CLOSE IAW PROCEDURE -

INVESTIGATE

1QCFR50. 59 EVALUATIONS MONTH: - AUGUST 1993 e DOCKET'°:

UNIT NAME:

50-311 SALEM 2 DATE: SEPTEMBER 10, 1993 COMPLETED BY: R. HELLER TELEPHONE: (609)339-2212 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 2SC-2293 Pkg 1 "Circulating Water Air Ingress Monitor, Loop Seal and Vacuum Pumps" - The engineering change to the Condenser Air Removal and Priming System replace the

1. 23 condenser vacuum pump with a single stage pump which does not require an air ejector stage; adds a heat traced loop seal to the system to replace the (12) float valves; replaces extraneous boundary valves with blind flanges; changes the control on

1. 22 vacuum pump and separating tank vent valves; changes the control room bezel nameplates; removes part control devices and installs air ingress monitors on the pystem. The Salem Technical Specifications do not address the Condenser Air Removal and Priming System. Therefore, the proposed modifications do not reduce the margin of safety as defined in the basis for any Technical Specification. {SORC 93-073) 2EC-3223 Pkg 1 "Restoration of Upfront Chlorination" - The upfront chlorination system is presently configured to permit.the upfront chlorination valves {SW32s) to remain in the open position during strainer backwash, thus allowing chlorinated water to be discharged into the river, which was viewed as an "Unpermitted Discharge". This resulted in the upfront chlorination system being taken out of service. This design change will restore the upfront chlorination system to a configuration that will prevent chlorinated water from being discharged into the river during strainer backwash. This modification does not affect the function of the Service Water System, only the upfront chlorination system which is not addressed in the Technical Specifications. Therefore, this modification does not reduce the margin of safety as defined in the Technical Specifications. {SORC 93-075)

19CFR50.59 EVALUATIONS MQNTH: - AUGUST 1993 e DOCKET':

UNIT NAME:

50-311 SALEM 2 DATE: SEPTEMBER 10, 1993 COMPLETED BY: R. HELLER TELEPHONE: (609)339-2212 (cont'd)

ITEM

SUMMARY

2EE-0020 Pkg 1 "Steam Quality Sample Pipe Removal" - This design change entails the removal of two {2) steam quality sample lines on the main steam system at the following locations: 21MS122 {1 11 Steam quality sample line), and 22MS122 {1 Steam quality sample 11 line). Chemical injection/steam quality sample lines similar to the subject lines have a history of failure (Reference PSE&G Research and Testing Laboratory Report No. 74151) which could affect the operations/ function of equipment and components downstream of these connections. Recently, failure of 2BF10 sample line on the Salem Unit 2 resulted in the loss of feedwater isolation on the 24BF19 valve during a plant trip due .to the sample pipe lodging in the valve seat area. The subject lines have been identified by the Salem Technical Departments as not functional and not required. In addition, similar connections have already been removed on the condensate and fe*edwater systems under DCP 2EE-0013, during 2R7. DCP lEE-0028 will remove the chemical feed, chemistry/steam quality sample lines {lBFlO, 11, 12, and 13CF19 and 11 and 12MS122) on Salem Unit 1 during the upcoming refueling outage. There is no reduction in the margin of safety as defined in the basis for any Technical Specification. {SORC 93-076) 2EC-3248 Pkg 1 "SW Auto-Start Setpoint" - The purpose of this design change is to reconstitute design basis for low SW Header Press Alarm and auto/ start setpoints, recalibrate instrumentation to reflect new setpoint and recalibrate SW Header Pretransmitter and local gauge to reflect new scaling valves. The reason for this change is discrepancies in several documents and settings for the auto/start setpoints. The proposed change does not reduce the margin of safety as defined in the basis for any Technical Specification. Service Water System setpoints and operating pressure band are not specifically listed in basis Section 2.0 or in the RPS or ESFAS Section 3/4/3/1 and 3/4.3.2, therefore they do not have an analytical limit. The function of the setpoints is equipment protection while maintaining minimum

lpCFRSp.59 EVALUATIONStt DOCKET.O: 50-311 MQNTH: - AUGUST 1993 UNIT NAME: SALEM 2 DATE: SEPTEMBER 10, 1993 COMPLETED BY: R. HELLER TELEPHONE: (609)339-2212 (cont'd)

ITEM

SUMMARY

flow. Calculations S-C-M600-MCD-1289 and s-c-swoo1-01 demonstrated that the setpoints adequately perform their function. (SORC 93-076) 2EC-3216 Pkg 1 "Piping Replacement" - Various pipe fittings and pipe segments must be replaced due to normal wear, resulting in pipe wall approaching code minimum thickness values. This DCP replaces existing carbon steel fittings and pipe with 2 1/4%Cr-1%Mo materials and in some cases heavier wall material. The design requirements of the replaced piping material are not changed and the replacement piping material meets or exceeds the design requirements of the original material specifications. This DCP also replaces a 26" diameter condensate system piping elbow with heavier wall and upgraded 2 1/4%Cr-1% Mo material.

Calculation S-C-BE-MDC-1153 and Engineering Evaluation S-C-CN-MEE-0774 established a reconstituted condensate system design pressure for which only the 26" diameter condensate piping required reassessment. Laboratory analysis performed on piping adjacent to the replaced elbow demonstrated that the 26 11 piping is seamless piping. As such, the existing pipe wall thickness is acceptable. The design requirements of the replaced piping material are changed by the above mentioned calculation and engineering evaluation.

The replacement piping material meets or exceeds the design requirements of the original and reconstituted material specifications. The replacement of worn fittings and pipe segments will restore the plant to its analyzed configuration.

There is no reduction in the margin of safety as defined in the bases for any Technical Specification. (SORC 93-081) 2EC-3179 Pkg 8 "Salem Fire Damper Upgrade" - The design scope for this package includes the replacement of two fire dampers and an existing fire door/damper in the Battery Room Exhaust System, a subsystem of the Control Area Ventilation (CAV) System. The function, basic configuration and operation of the system will not be altered and the codes, standards,

19CFRS0.59 EVALUATIONS4t DOCKET.O: 50-311 MONTH: - AUGUST 1993 UNIT NAME: SALEM 2 DATE: SEPTEMBER 10, 1993 COMPLETED BY: R. HELLER TELEPHONE: (609)339-2212 (cont'd)

ITEM

SUMMARY

qualification and design criteria of the original system will apply. This modification is intended to meet PSE&G's commitment to the NRC and comply with the requirements of 10CFR50, Appendix R. The basis for the Technical Specifications does not address the fire protection features or the Battery Room Exhaust System. Since replaced fire dampers and louvre associated with the system perform no safety related functions and are equivalent to or better than existing components, these modifications do not affect the system. Therefore, there is no reduction in the margin of safety as defined in the basis for the Technical Specifications. (SORC 93-081}

B. Technical Specification Interpretations (TSI}

TSI # LCO 3.3.2.1 "Semi-Automatic Swapover" - T/S Interpretation LCO 3.3.2.1 Tbl 3.303 Item 9 clarifies Amendment 69. In order to achieve an uninterrupted flow of ECCS water to the core, certain valves need to be placed in their armed condition prior to entering Mode 3.

These valves are 21SJ113, 22SJ113, 21CC16 and 22CC16. The SJ44 and RH4 valves will not be armed until called for in EOP-LOCA-3, Transfer to Cold Leg Recirculation. The clarification of the requirements of LCO 3.3.2.1, Tbl 3.3-3 Item 9 is consistent with the requirements of the NRC's safety evaluation supporting Technical Specification Amendment # 69 and Amendment # 21. There is no reduction in the margin of safety as defined in the basis for any Technical Specification. (SORC 93-081}

SALEM GENERATING STATION MONTHLY OPERATING

SUMMARY

- UNIT 2 AUGUST 1993 SALEM UNIT NO. 2 The Unit began the period operating at full power and continued to operate at essentially full power throughout remainder of the period.

REFU~bING INFORMATION DOCKET NO: 50-311 MONTH: - AUGUST 1993 UNIT NAME: SALEM 2 DATE: SEPTEMBER 10, 1993 COMPLETED BY: R. HELLER TELEPHONE: (609)339-2212 MONTH AUGUST 1993

1. Refueling information has changed from last month:

YES X NO ~~~~

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