ML18096B044

Monthly Operating Rept for Sept 1992 for Salem Unit 1.W/ 921013 Ltr

ML18096B044
Person / Time
Site:	Salem
Issue date:	09/30/1992
From:	Fest J, Shedlock M, Vondra C Public Service Enterprise Group
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 9210190196
Download: ML18096B044 (12)

Text

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Public Service Electric and Gas Company P.O. Box 236 Hancocks Bridge, New Jersey 08038 Salem Generating Station October 13, 1992 U.S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555

Dear Sir:

MONTHLY OPERATING REPORT SALEM NO. 1 DOCKET NO. 50-272 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 1992 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-l-7.R4 95-2189 ( 1OM) 12-89

AVERAGE DAILY UNIT POWER LEVEL

/

Docket No.: 50-272 Unit Name: Salem #1 Date: 10/10/92 Completed by: Mark Shedlock Telephone: 339-2122 Month SEPTEMBER 1992 Day Average Daily Power Level Day Average Daily Power Level (MWe-NET) (MWe-NET) 1 1088 17 1084 2 1091 18 1070 3 1096 19 1068 4 1098 20 1090 5 1092 21 1094 6 1116 22 1078 7 1075 23 1102 8 1114 24 1037 9 1077 25 315 10 1103 26 314 11 1098 27 802 12 1087 28 1096 13 1089 29 1079 14 1078 30 1017 15 1082 31 16 1078 P. 8.1-7 Rl

OPERATING DATA REPORT Docket No: 50-272 Date: 10/10/92 Completed by: Mark Shedlock Telephone: 339-2122 Operating Status

1. Unit Name Salem No. 1 Notes

2. Reporting Period September 1992

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 Reporting Period 720 6575 133728

12. No. of Hrs. Rx. was Critical 720 3472.7 87073.0

13. Reactor Reserve Shutdown Hrs. 0 0 0

14. Hours Generator on-Line 720 3184.0 84232.0

15. Unit Reserve Shutdown Hours 0 0 0

16. Gross Thermal Energy Generated (MWH) 2328307.2 10413806.4 265910951. 6

17. Gross Elec. Energy Generated (MWH) 769480 3452800 88257430

18. Net Elec. Energy Gen. (MWH) 737072 3274671 84051244

19. Unit Service Factor 100 48.4 63.0

20. Unit Availability Factor 100 48.4 63.0

21. Unit Capacity Factor (using MDC Net) 92.6 45.0 56.8

22. Unit Capacity Factor (using DER Net) 91.8 44.7 56.4

23. Unit Forced Outage Rate 0 29.4 21. 6 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 8-1-7.R2

I I

UNIT SHUTDOiN AND POWER REDUCTIONS REPORT. MONTH SEPTEMBER 1992 DOCKET NO. 50-272 UNIT NAME Salem #1 DATE 10/10/92 COMPLETED BY Mark Shedlock TELEPHONE 339-2122 METHOO OF SHUTTING LICENSE DURATION DOWN EVENT SYSTEM COMPONENT CAUSE AND CORRECTIVE ACTION NO. DATE TYPE 1 (HOURS) REASON 2 REACTOR REPORT # COOE 4 COOE 6 TO PREVENT RECURRENCE 0029 09/25/92 F 6.0 A 5 ------------ IF INSTRU #12 LOOP R. T.D.

0030 09/25/92 F 20.6 A 5 ------------ IF INSTRU #12 LOOP R. T.D.

0031 09/26/92 F 6.5 A 5 ------------ IF INSTRU #12 LOOP R.T.D.

0032 09/30/92 F 3.0 A 5 ------------ HF MOTORX CIRCULATING WATER PUMPS 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-Adninistrative 5-Load Reduction G-Operational Error (Explain) 9-0ther H-Other (Explain)

SAFETY RELATED MAINTENANCE DOCKET NO: 50-272 MONTH: - SEPTEMBER 1992 UNIT NAME: SALEM 1 DATE: OCTOBER 10, 1992 COMPLETED BY: J. FEST TELEPHONE: (609)339-2904 WO NO UNIT EQUIPMENT IDENTIFICATION 910222073 1 1SWE29 FAILURE DESCRIPTION: CLEAN/INSPECT MOTOR COOLER BASE AND PLENUM. BASE AND PLENUM ARE CORRODED 911125115 1 12 SERVICE WATER PUMP FAILURE DESCRIPTION: 12 SW PUMP TRIPPING - INVESTIGATE AND REWORK 920908024 1 13 CONTAINMENT FAN COIL UNIT FAILURE DESCRIPTION: CALIBRATE 13 CFCU SERVICE WATER INLET FLOW TRANSMITTER

10CFR50.'59 EVALUATIONS DOCKET NO: 50-272 MONTH: - SEPTEMBER 1992 UNIT NAME: SALEM 1 DATE: OCTOBER 10, 1992 COMPLETED BY: J. FEST TELEPHONE: (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

SUMMARY

A. Design Change Packages (DCPs) lEC-3157 Pkg 1 "Condensate Polisher System and Demineralized Plant Water system - Acid/Caustic Tanks - Unit 1 11

- The purpose of this change is as follows: 1)

Remove all existing acid bricks, asphalt coating and deteriorated concrete from inside and outside the tank basin area for the damage. Replace this area with protective liner and coating; 2}

Evaluate and repair/modify as necessary the damaged structural steel and concrete components; 3). Improve the operation of the Chemical Waste pumps by providing a self contained seal water system; 4) Add new external level gages with remote volume indication to the Acid and Caustic storage tanks to help eliminate overflow problems;

5) Provide a ventilation system to the high conductivity sump; 6} Reroute existing backwash drain piping from tie-in to Condensate Polishing Building floor drain system to a direct discharge to the low conductivity sump; 7) Install new permanent Condensate Polishing Building pipe tunnel sump pumps and reroute existing. discharge line to the High Conductivity Sump; 8) Provide heat tracing for the Caustic Storage Tanks Nos. 1

& 2 and the associated piping from the tanks to the Caustic Metering Pumps and from the metering pumps to the dilution water mixing tees, including the level transmitter; 9) Install additional lighting for the Acid, Caustic and Chemical Waste Tanks area, and 10} Remove eve caustic Metering Pump 1DME32 and its associated piping, valves and supports. There is no reduction in the margin of safety as defined in the basis for any Technical Specification. (SORC 92-101}

lEC-3176 Pkg 1 "Control Air Dryer Replacement" - The purpose of this design change is to replace the existing Unit 1 and Unit 2 Control Air Dryers (1CAE25, E26, E27

& E28 and 2CAE25, E26, E27 and E28} in the Turbine Generator A~ea (El. 100 1 -0 11 , near Col. M-13 and M-15 respectively} with new model T750DHA4-CSP-PM-F01 air dryers manufactured by

10CFR50.'59 EVALUATIONS DOCKET NO: 50-272 MONrH: - SEPTEMBER 1992 UNIT NAME: SALEM 1 DATE: OCTOBER 10, 1992 COMPLETED BY: J. FEST TELEPHONE: (609)339-2904 (cont'd)

ITEM

SUMMARY

Pneumatic Products Corporation. This design change will also modify the existing control air piping as necessary to facilitate installation of the new dryers and install new drain lines for each new Control Air Dryer. The new drain lines will be routed to existing floor drains in the vicinity of the dryers. A spare air dryer will be installed (TMOD 92-057) to allow continued full operation of the Control Air System while each existing dryer is removed and replaced. Each new dryer will be turned over to Operations prior to the replacement of the next dryer. Following replacement of the final dryer, the spare dryer will be removed. The operation of the Control Air System and/or the Control Air Dryers and the operation of a third (spare) dryer and unit cross-tie are not addressed in the Technical Specifications. Therefore, there is no reduction in the margin of safety as defined in the basis for any Technical Specification. (SORC 92-105)

B. Procedures and Revisions EPlan Section 17 E Plan Section 17 and EPIP 1003 have been revised EPIP 1003 to only require SORC approval of future revisions of the Emergency Plan and Implementing procedures if a 10CFR50.59 Safety Evaluation is required or if the revision involves a potential decrease in the effectiveness of the Emergency Plan per 10CFR50.54(Q). All E Plan and Implementing Procedure revisions (other than editorial) will continue to require review and approval of the designated department manager and the General Manager Hope Creek/Salem Operations.

(SORC 92-100)

NC.NA-AP.ZZ-0050(Q) "Station Testing Program" Rev. 1 - This general revision: 1.) Contains editorial and format changes to the test and Attachments; 2.) Adds clarification of Special Tests and Infrequently Performed Tests or Evolutions to Scope; 3.)

Deletes "Hope Creek only" and "Salem only" (Sections 3.4, 3.8 and 5.2.1); 4.) Incorporates Testing Considerations (formerly Attachment 1) into general guidelines (Section 5.1.5); 5.) Adds the requirement to test major components after

10CFR50.'59 EVALUATIONS DOCKET NO: 50-272 MONTH: - SEPTEMBER 1992 UNIT NAME: SALEM 1 DATE: OCTOBER 10, 1992 COMPLETED BY: J. FEST TELEPHONE: (609)339-2904 (cont'd)

ITEM

SUMMARY

painting of movable parts, such linkage, shafts, springs, etc. (Section 5.1.6). Ref., INPO Good Practice, Post Maintenance Testing MA-305 INPO 87-028; 6.) Deletes retest requirements for routine service activities for pumps such as changing the oil, flushing the cooling system and mechanical seal maintenance; 7.) Deletes CD-147Y and CD-409D. These CDs are generic and their deletion does not adversely affect any commitments; 8.) Moves previous Attachment 2, Component Definitions /Service Applications, to Attachment 5; 9.) Adds Battery, Battery Charger and Inverter to new Attachment 1; 10.) Divides Testing Guidelines (formerly Attachment 4) into separate attachments for testing by maintenance topic, and 11.) Relocates Testing Definitions (formerly Attachment 3) to the specific maintenance testing attachment. The revision to the procedure does not change any previously analyzed testing requirement. The overall program has been enhanced by including guidance for testing of major components after painting of movable parts, linkages, shafts, springs, etc. to address operability concerns. There is no reduction in the margin of safety as defined in the basis for any Technical Specification.

(SORC 92-102)

C. Temporary Modifications (TMODs)92-060, 92-061 "Temporary Chemical Waste Tank and Associated 92-063,92-064 Piping" - In order to install those portions of DCP lEC-3157 affecting the chemical waste tanks and pumps, four (4) TMODs will be required. These TMODs will permit the continued operation of the chemical waste system portion of the demineralized water make-up system and allow other plant systems to function normally during these modifications.

The impact of the rupture of the sulfuric acid tank on Control Room habitability was addressed in Engineering Evaluation A-O-ZZ-NEE-0735, which concluded that the margin of safety as defined in the basis of the Technical Specifications is not reduced. (SORC 92-101)

.1,0CFR50.'59 EVALUATIONS DOCKET NO: 50-272 MONTH: - SEPTEMBER 1992 UNIT NAME: SALEM 1 DATE: OCTOBER 10, 1992 COMPLETED BY: J. FEST TELEPHONE: (609)339-2904 (cont'd)

ITEM

SUMMARY

92-057 "Installation of Temporary Air Dryer" - A spare air dryer will be installed to allow continued full operation of the Control Air System while each existing dryer is removed and replaced under DCP 1EC-3176. Each new dryer will be turned over to Operations prior to the replacement of the next dryer. Following replacement of the final dryer, the spare dryer will be removed. The operation of the Control Air System and/or the Control Air Dryers and the operation of a third (spare) dryer and unit cross-tie are not addressed in the Technical Specifications. Therefore, there is no reduction in the margin of safety as defined in the basis for any Technical Specification.

(SORC 92-105)

D. Safety Evaluations (S/E)

S-O-AF-MSE-0812 "Potential Cavitation of the Auxiliary Feedwater Pumps" - This document evaluates the impact of potential cavitation of the Auxiliary Feedwater Pumps, under cert~in secondary side depressurization scenarios, on the licensing basis of the plant. During the development of the Auxiliary Feedwater System CBD, DEF DES-88-00759 was written to document lack of calculations to support the basis for the Auxiliary Feedwater flow rates assumed in the UFSAR Chapter 15 accident analysis. Later Calculations S-C-AF-MDC-0445 and S-C-F400-MDC-0225 were performed, based upon the as built piping configuration, to show that the AF flow to a postulated line break will not exceed the values assumed in the UFSAR Chapter 15 analysis. These and other calculations were performed to resolve the above DEF, show that under certain worst case accident scenarios, one pump (either turbine driven or motor driven pump) will cavitate for ten minutes or less at one time; and in only one worst case accident scenario, the turbine driven Auxiliary Feedwater Pump and one motor driven Auxiliary Feedwater Pump will both cavitate for four minutes. The acceptance criteria for postulated steam line and feedwater line break transients affected by Auxiliary Feedwater define the acceptable margin of safety.

10CFR50:59 EVALUATIONS DOCKET NO: 50-272 MONTH: - SEPTEMBER 1992 UNIT NAME: SALEM 1 DATE: OCTOBER 10, 1992 COMPLETED BY: J .* FEST TELEPHONE: (609)339-2904 (cont'd)

ITEM

SUMMARY

The design limits of the systems or components affected by auxiliary feedwater are not exceeded.

There is no reduction in the margin of safety as defined in the basis for any Technical Specification. {SORC 92-102)

E.. Deficiency Reports. - "Use-As-Is" SMD-92-735 11 12 Service Water Return From 12 CCHX Wall Thinning" - The purpose of this evaluation is to assess the wall thinning of the Service Water {SW) return from 12 Component Cooling Heat Exchanger

{CCHX) and the ability of the system to maintain structural integrity at normal operating pressures. During the 1R10 refueling outage the pipe spool was inspected for deterioration. The pipe lining was missing in various areas and the piping showed signs of erosion. Subsequent U.T.

exams revealed that this pipe spool has sustained erosion/corrosion damage, however, its minimum measured wall thickness (.197") was sufficient to meet its design wall thickness. The pipe was cleaned and relined to inhibit any further deterioration. A work order was initiated to replace the pipe during 1R11. The first quarterly U.T. exam presented a minimum measured wall thickness of .135 11

• Due to the apparently high rate of degradation the U.T. was repeated the next week on the 12 lowest readings. The lowest measured wall thickness reading was .128", which is below the ASME code required minimum thickness at the design pressure. The Stress Group was requested to evaluate the pipe spool using alternate methods provided under Generic Letter 90-05 to determine the structural integrity of the spool. It was determined that the spool had maintained its integrity utilizing the G.L.

acceptance criteria. Due to the small margin and concern with the high erosion rate, subsequent U.T. exams were maintained on a weekly basis. As demonstrated in Study Calculation No. 267722B-SC1 Rev. 1, the thin area of spool 1-SW-P-1108 is within the ASME code allowable thickness at the new design pressure and the margin of safety as defined in the Technical Specifications is not reduced. {SORC 92-104)

SALEM GENERATING STATION MONTHLY OPERATING

SUMMARY

- UNIT 1 SEPTEMBER 1992 SALEM UNIT NO. 1 The Unit began the period operating at full power and continued to operate at essentially full power until September 24, 1992, when power was decreased to 25% to replace a Reactor Coolant System loop 12 Cold Leg resistance temperature detector. The Unit returned to full power on September 28, 1992. On September 30, 1992, power was reduced due to tripping of the circulators which are powered from the Hope Creek Switchyard.

REFUELING INFORMATION DOCKET NO: 50-272 MONTH: - SEPTEMBER 1992 UNIT NAME: SALEM 1 DATE: OCTOBER 10, 1992 COMPLETED BY: J. FEST TELEPHONE: (609)339-2904 MONTH SEPTEMBER 1992

1. Refueling information has changed from last month:

YES NO X

2. Scheduled date for next refueling: OCTOBER 2, 1993

3. Scheduled date for restart following refueling: DECEMBER 13, 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?:

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 656

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: September 2001 8-1-7.R4