ML18095A418

Monthly Operating Rept for Jul 1990 for Salem 1.W/900815 Ltr

ML18095A418
Person / Time
Site:	Salem
Issue date:	07/31/1990
From:	Miller L, Morroni M Public Service Enterprise Group
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 9008210129
Download: ML18095A418 (10)

Text

- ..0 *- PS~G Public Service Electric and Gas Company P.O. Box E Hancocks Bridge, New Jersey 08038 Salem Generating Station August 15, 1990 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 July 1990 are being sent to you.

Average Daily Unit Power Level Operating Data Report Unit Shutdowns and Power Reductions Safety Related Maintenance Major Plant Modifications Operating Summary Refueling Information Challenges to PORV or Safety Valves Sincerely yours, 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 Pe_ople ________ ----------------..._ :i:t:~'f

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~ 9008210129 900731 PDF;: 101DOCK O~'.i000272

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AVERAGE DAILY UNIT POWER LEVEL Docket No. 50-272~----

Unit Name Salem # 1 - - - -

Date 08-10-90 _ _ _ __

Completed by Art Orticelle Telephone 609-339-2122 _ __

Month JULY, 1990 Day Average Daily Power Level Day Average Daily Power Level (MWe-NET) (MWe-NET) 1 700 17 1088 2 753 18 1083 3 766 19 1076 4 751 20 1066 5 802 21 1064 6 845 22 591 7 826 23 0 8 821 24 0 9 1034 25 0 10 1061 26 0 11 1079 27 0 12 1055 28 0 13 1070 29 0 14 1073 30 0 15 1059 31 0 16 1000 P. 8.1-7 Rl

OPERATING DATA REPORT Docket No: 50-272 Date: 08-10-90 Completed by: Art Orticelle Telephone: 609-339-2122 Operating Status

1. Unit Name Salem No. 1 Notes

2. Reporting Period July 1990

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~--=-N~/~A-=---~~~~~~~~~~~~~~~~~~~~~~~~~

9. Power Level to Which Restricted, if any (Net MWe) ~~--=N~/~A=-=---~~~~~~-

10. Reasons for Restrictions, if any ~=N~/~A=--~~~~~~~~~~~~~~~~~-

This Month Year to Date Cumulative

11. Hours in Reporting Period 744 5087 114720

12. No. of Hrs. Reactor was Critical 524.5 3301.6 74210.1

13. Reactor Reserve Shutdown Hrs. 0 0 0

14. Hours Generator On-Line 523.9 3196.9 71892.7

15. Unit Reserve Shutdown Hours 0 0 0

16. Gross Thermal Energy Generated (MWH) 1619841.6 10344316.8 225445242.8

17. Gross Elec. Energy Generated (MWH) 518910 3405930 74868290

18. Net Elec. Energy Generated (MWH) 492834 3251603 71263313

19. Unit Service Factor 70.4 62.8 62.7

20. Unit Availability Factor 70.4 62.8 62.7

21. Unit Capacity Factor (using MDC Net) 59.9 57.8 56.2

22. Unit Capacity Factor (using DER Net) 59.4 57.3 55.7

23. Unit Forced Outage Rate 29.6 37.2 22.3

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

Refueling Outage scheduled to start 02-09-91 and 04-10-91.

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

8 15 90 8-1-7.R2

UNIT SHUTOOWN AND rowER REDUCTIONS OOCKEl' NO.: ~5~0-~2'"-'-72~~-

REroRI' IDNTH JULY 1990 UNIT NAME: Salem -#1 DATE: 08-10-90 rotPIBI'ED BY: Art Orticelle TELEPHONE: 339-2122' .

MEI'HOD OF SHUTl'JNG LICENSE DURATION OOWN EVENT SYSTEM <rnroNENT CAUSE AND CDRRFCTIVE ACTION NO. DATE TYPE 1 (HOORS} REASCN 2 REACIDR REroRI' # CDDE 4 CDDEll 'ID PREVENT RECURRENCE 0048 07-01-90 F 101.3 B 5 HF PUMPXX #13 A&B CIRC WATER PUMPS 0051 07-05-90 F 88 B 5 HF PUMPXX #13 A&B CIRC WATER PUMPS 0053 0056 0057 07-15-90 07-21-90 07-22-90 F

F F

7.6 12.7 220.1 B

A A

5 5

1 HF SF CD HTEXCH VALVEX INSI'RU

1. 11 A& 12A WATERBOX CLEANING 1SJ167 RELIEF VALVE 11-14 MS167 VALVES 1

F: Forced 2

Reason:

3 Method:

4 Exhibit G - Instructions 5

Exhibit 1 - Same S: Scheduled. A-Equiiment Failure (Explain} 1-Manual for Preparation of Data Source B-Maintenance or Test 2-Manual Scram Entry Sheets for Licensee C-Refueling 3-Autanatic Scram Event Report (LER) File D--Regulatory Restriction 4-continuation of (NURID-0161)

E-Qperator Training &License Examination Previous outage F-Adrninistrative 5-I.oad Reduction

~~~t\~JKyar (Explain} 9-other

_J

SAFETY RELATED MAINTENANCE DOCKET NO: 50-272 MONTH: - JULY 1990 UNIT NAME: SALEM 1 DATE: AUGUST 10, 1990 COMPLETED BY: M. MORRONI TELEPHONE: (609) 339-2068 WO NO UNIT EQUIPMENT IDENTIFICATION 900726126 1 1CV55 FAILURE DESCRIPTION: VALVE WILL NOT FULLY OPEN -

INVESTIGATE

MAJOR PLANT MODIFICATIONS DOCKET NO: 50-272 MONTH: - JULY 1990 UNIT NAME: SALEM 1 DATE: AUGUST 10, 1990 COMPLETED BY: M. MORRONI TELEPHONE: (609) 339-2068

• DCR PRINCIPAL SYSTEM DESCRIPTION lEC-1076 Various Systems This design change was performed as part of a long term pipe support modification project committed to in response to NRC Bulletin 79-07.

These modifications ensure additional conservatism and satisfy the original design criteria.

lEC-2122 Reactor Containment This design change provided for Fan Cooler Motors refurbishment of two Reactor Containment Fan Cooler Unit (RFCU) motors to improve their reliability.

lED-0351 Auxiliary Feedwater This design change provided for the replacement of a 1" feedwater globe valve with one of an improved design.

lSC-2006 Service Water This design change added:chlorination analyzers to monitor the Service Water total residual chlorine (TRC);

chlorine injection flow control valves on the SW headers; a flow control system to automatically control each SW header chlorine concentration, and SW flow instrumentation. The chlorine injection pumps were also replaced.

• DCR - Design Change Request

MAJOR PLANT MODIFICATIONS DOCKET NO: 50-272 MONTH: - JULY 1990 UNIT NAME: SALEM 1 DATE: AUGUST 10, 1990 COMPLETED BY: M. MORRONI TELEPHONE: ( 609) 339-2068

• DCR SAFETY EVALUATION 10 CFR 50.59 lEC-1076 This design change was performed as part of a long term pipe support modification project committed to in response to NRC Bulletin 79-07. These modifications ensure additional conservatism and satisfy the original design criteria. The modifications resulting from this DCR have no impact on the analysis performed in the FSAR or to any basis of the Technical Specifications. Additionally, there is no chance of creating a new accident/malfunction or aggravating a currently analyzed one. There is no change to any plant process or discharge or to the environmental impact of the plant. No unreviewed safety or environmental questions are involved.

lEC-2122 This design change provided for refurbishment of two Reactor Containment Fan Cooler Unit (RFCU) motors to improve their reliability. Certificate and qualification documentation, including workmanship qualification and seismic requalification to the original specifications and requirements, are provided by the vendor. There is no change to any plant process or discharge or to the environmental impact of the plant. No unreviewed safety or environmental questions are involved.

lED-0351 This design change provided for the replacement of a 1" feedwater globe valve with one of an improved design. The replacement valve meets all of the original design criteria. There is no change to any plant process or discharge or to the environmental impact of the plant. No unreviewed safety or environmental questions are involved.

lSC-2006 This design change added: chlorination analyzers to monitor the Service Water total residual chlorine (TRC) ; chlorine injection flow control valves on the SW headers; a flow control system to automatically control each SW header chlorine concentration, and SW flow instrumentation. The chlorine injection pumps were also replaced. The control system will shutdown the chlorination system automatically upon detection of excessive TRC at any Circulating Water discharge line. The purpose of this modification is to place the plant in a "zero violation" condition with respect to the Environmental Permit stipulations on TRC.

No unreviewed safety or environmental questions are involved.

• DCR - Design Change Request

SALEM GENERATING STATION MONTHLY OPERATING

SUMMARY

- UNIT 1 JULY 1990 SALEM UNIT NO. 1 The Unit began the period operating at reduced power while repairs were performed to 12B and 13B Circulating Water (CW) pumps. On July 8, 1990, the Unit was restored to 100% power following the return to service of one of the CW pumps. On July 15, 1990, power was briefly reduced to 75% for condenser water box cleaning and turbine valve testing. The Unit returned to 100% power, later the same day, and continued to operate at that level until July 21, 1990, when load was reduced to 60% to replace the 1SJ167 Valve. On July 22, 1990, the Unit briefly returned to 100% power and was later shutdown in response to the findings of an engineering safety evaluation. The evaluation had been performed as part of a Unit 2 design change on the main steam isolation valves, and indicated that it could not be ensured the valves would close during certain postulated main steam line pipe breaks. The Unit remained shutdown throughout the rest of the period while additional analyses and evaluations were performed.

J '

REFUELING INFORMATION DOCKET NO: 50-272 MONTH: - JULY 1990 UNIT NAME: SALEM 1 DATE: AUGUST 10, 1990 COMPLETED BY: M. MORRONI TELEPHONE: (609) 339-2068 MONTH JULY 1990

1. Refueling information has changed from last month:

YES X NO

2. Scheduled date for next refueling: February 9, 1991

3. Scheduled date for restart following refueling: April 10, 1991

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?: January 1991

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 564

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

CHALLENGES TO PORVs OR SAFETY VALVES Salem Unit 1 In accordance with the requirements of Salem Generating Station Unit 1 Technical Specifications Section 6.9.1.6, the following recent challenges to PORVs or Safety Valves are being reported:

07/25/90 - On July 25, 1990, with Salem Unit 1 in Mode 4, the 1PR2 Power Operated Relief Valve actuated (POPS actuation) immediately after being armed in accordance withrProcedure OP-II-2.3.4, "Pressurizer Overpressure Protection Operability Checking and Arming of lPRl and 1PR2". The indicated RCS pressure and temperature was 340 psig and 320°F. The root cause of this event has been attributed to an equipment failure. The Hagan module pressure comparator had drifted low.