ML18093A833

Monthly Operating Rept for Apr 1988.W/880514 Ltr

ML18093A833
Person / Time
Site:	Salem
Issue date:	04/30/1988
From:	Ronafalvy J, White P, Zupko J Public Service Enterprise Group
To:	NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
References
NUDOCS 8805200103
Download: ML18093A833 (10)

Text

e AVERAGE DA, LY UN, T PafER IVEL Docket No~ 50-311 Unit Name* Salem i 2 Date Apri I 10, 1988 Comp I eted by **::"*:.,Pe I I White Telephone 609-935-6000 Extension 4451 Month *APRIL 1988 Day Average Daily Power Level Day Average Daily Power Level

. (MWe-NET) (MWe-NET) 1 1089 17 1100 2 1072 18 1095 3 1065 19 1095 4 1088 20 1110 5 1093 21 684 6 1094 22 0 s

• . *=- *~

7 1092 23 0 .... -

c 8 1096 24 924 9 1083 25 1079 10 1091 26 1100

' 11

' 1090 27 1114 l:l 1119 28 1097 13 1104 29 1099 1095 30 1091 14 .

15 1074 31 16 1094-Pg. 8.1-7 Rl

'8805200103 880430 PDR ADOCK 05000311 R DCD

e 0PERATING DATA REPORT Docket No.' 50-311 Date -T-A-Er-i-*1.--.1~0~,-1-9-g-9 Telephone 935-6000 Completed by -**Pell White Extension 4451 Operating Status

1. Unit Name Salem No. 2 Notes

2. Reporting Period April 1988

3. Licensed Thermal Power (MWt) 3411

4. Nameplate Rating (Gross MWe) II'1rr

5. Design Electrical Rating (Net MWe) 11T3"

6. Maxim'ilm Dependable Capacity(Gross MWe)~

7. Maximum Dependable Capacity (Net MWe) ITifO

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

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~--------------~

This Month Year to Date C~lative 11 .. Hours in Reporting Period 719 2903 57408

12. No. of Hrs. Reactor was Critical 689.3 28 73. 3 35236. 2

13. Reactor Reserve Shutdown Hrs. -.....,0_ __ 0 0

14. Hours Generator On-Line 664.04 2844.34 4126.14

15. Unit Reserve Shutdown Hours O 0 0

16. Gross Thermal Energy Generated

' ' (MWH) 2249256 9570418 55220939

17. Gross Elec. Energy Generated (MWH) 750550 3190410 34819940

18. Net Elec. Energy Generated (MWH) 719576 3062440 33081818

19. Unit Service Factor 92.4 98.o 59.4

20. Unit Availability Factor 92.4 98.o 59.4

21. Unit~Capacity Factor

• • (usingMDCNet) 90.5 95.4 52.1

22. Unit Capacity Factor (using DER Net) 89.8 94.6 51.7

23. Unit Forced Outage Rate 7. 6 2 29. 3

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

Refuelin . Outa e Scheduled to be in 9-1-88 and lastin for

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

N/A 8-1-7.RZ

lltlIT SHUTDOWN AND POWER REDUCTIONS Uock.et No * .)U-.ll 1 REPORT MONTH APRIL 1988 Unit Name Salem No.2 Date A~ril 10 1988 Completed by Pell White Telephone 60 -935-6 600

~.; ... *. ,*:~. *~!' *. Extension 4451

. *.* :_ 'i: *: *1......::,: ~

• Method of Duration Shutting License Cause and Corrective No. Date Type Hours Reason Down Event System Component Action to 1 2 Reactor Report Code 4 Code 5 Prevent Recurrence REACTOR COOLANT FLOW 0078 4-21-BtS F 22.7 A 3 CB INSTRU INDICATION STEM GENERATOR

• 0079 4-22-88 F 32.27 A 3 CB HT EXCH LEVEL e*

1 2 Reason 3 Method 4 5 t:xhibit G Exhibit F: Forced A-Equipment Failure-explain I-Manual Instructions Salem as S: Scheduled B-Maintenance or Test 2-Manual Scram. for Prepara- Source C-Refueling 3-Automatic Scram. tion of Data D-Regulatory Restriction 4-Continuation of Entry Sheets E-Operator Training & Licensing Exam Previous Outage for Licensee 1;.

I'*' 1*

F-Administrative 5-Load Reduction Event Report

i!) *,; G-Operational Error-explain 9-0ther (LER) File

• • • • 1 .. ,

        .

H-Other-explain (NUREG 0161)

PSE&G SALEM GENERATING STATION SAFETY RELATED WORK ORDER LOG SALEM UNIT 2 WO NO UNIT EQUIPMENT IDENTIFICATION 870609036 2 23SW228 FAILURE DESCRIPTION: REPLACE/ RESTORE LINE 1619 UPSTREAM 23SW228 TO ORIGINAL FORM 870713077 2 2MS219 FAILURE DESCRIPTION: VALVE LEAKS THRU, CUT OUT VALVE AND REPLACE 870729104 2 22 AUX FEED PUMP FAILURE DESCRIPTION: EXCESSIVE LEAKAGE 871016130 2 21 SERVICE WATER PUMP FAILURE DESCRIPTION: DECLARED INOPERABLE DUE TO LOW FLOW.

871202144 2 23SW2 FAILURE DESCRIPTION: LEAKING PAST ITS SEAT, REMOVE EXISTING VALVE &

REPLACE.

,.o SALEM UNIT 2 WO NO UNIT EQUIPMENT IDENTIFICATION 880211069 2 21CV16 2 FAILURE DESCRIPTION: LEAKING DIAPHRAM/REPLACE.

880216092 2 22 BAT PUMP FAILURE DESCRIPTION: MECHANICAL SEAL LEAKING/REWORK FAILED MECHANICAL SEAL ON #22 BAT PUMP REPAIR/REPLACE.

880307088 2 22SW133 FAILURE DESCRIPTION: NO/FLOW/DISASSEMABLE & INSPECT 880316078 2 2SJ300 FAILURE DESCRIPTION: LEAK THROUGH/REMOVE INSULATION/FA-127.

I~JOR PLANT MODIFICATIONS DOCKET NO.: 50-311 REPORT MONTH APRIL 1988 UNIT NAME: Salem 2 DATE: May 10,1988 COMPLETED BY: J. Ronatalvy TELEPHONE: 609/339-4455

• OCR NO. PRINCIPAL SYSTEM DESCRIPTION 2SC-13 23 Containment This modification installed Spray drain valves on the Containment side of 21CS48 and 22CS48 to allow draining of valve bodies for leak rate testing. These valves have been added to the Technical specification requirement for leak rate testing.

2SM-00188A Service Water This design change replaced Valve 22SW99. As there were 4" mission duo check valve available, this valve was replace with a 4" Clow duo check valve.

• Design Change Request

MAJOR PLANT MODIFIC,IONS DOCJT NO: 50-272 REPORT MONTH - APRIL 1988 UNIT NAME: ~S-a~l-e-m~-2~--~~

DATE: May 10,1988 COMPLETED BY:J.Ronafalvy TELEPHONE: (609)339-4455

• DCR SAFETY EVALUATION 10 CFR 50.59 2SC-1323 This design change did not increase the probability or consequences of an accident. By allowing the testing of 21 & 22CS48 Valves, this design change increases safety by furthering Containment integrity verification. This modification did not alter any plant process or discharge or affect the environmental impact of the plant. No unreviewed safety or environmental questions are involved.

2SM-00188A This modification did not alter the original design of the system. The duo check valve is no longer manufactured by TRW but is now made by Clow. A review of the design specifications show that the new valve is identical in every way to the old one. This modification did not alter a~y plant process or discharge or affect the environmental impact of the plant. No unreviewed safety or environmental questions are involved.

• DCR - Design Change Request

) .

SALEM GENERATING STATION MONTHLY OPERATING

SUMMARY

- UNIT NO. 2 APRIL 1988 SALEM UNIT NO. 2 The Unit began the period operating at 100% power and continued to operate at full power until April 21, 1988, when the Unit tripped due to a spike on a Reactor Coolant Pump flow transmitter during maintenance. During startup, the Unit tripped due to a level spike on No. 23 Steam Generator caused by the EH Control System. Following repairs to the EH Control system, startup was commenced with the Unit achieving full power on April 24, 1988. The Unit continued to operate at full power for the remainder of the period. The primary to secondary leak rate calculation for Nos. 22 and 24 Steam Generators continues to indicate less than ten gallons per day.

REFUELING INFORMATION DOCKET NO.: 50-311 UNIT NAME: Salem 2 COMPLETED BY: J. Ronafalvy DATE: Max 10, 1988 TELEPHONE: 609)935-6000 EXTENSION --,.4~4=5=5~~~~~~-

Month APRIL 1988

1. Refueling information has changed from last month:

YES NO X

2. Scheduled date for next refueling: September 3, 1988

3. Scheduled date for restart following refueling: November 2,1988

4. A) Will Technical Specification changes or other license amendments be required?

YES NO X B) Has the reload fuel design been reviewed by the Station Operating Review Committee?

YES NO X If no, when is it scheduled? August, 1988

5. Scheduled date(s) for submitting proposed licensing action:

August 1988 if required

6. Important licensing considerations associated with refueling:

NONE

7. Number of Fuel Assemblies:

A) Inc ore 19 3 B) In Spent Fuel Storage 224

8. Present licensed spent fuel storage capacity: 1170 Future spent fuel storage capacity: 1170

9. Date of last refueling that can be discharged to spent fuel pool assuming the present licensed capacity: March 2003 8-l-7.R4

OPS~G Public Service Electric and Gas Company P.O. Box E Hancocks Bridge, New Jersey 08038 Salem Generating Station May 14, 1988 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 Specification, the original copy of the monthly operating reports for the month of April 1988 are being sent to you.

Average Daily Unit Power Level Operating Data Report Unit Shutdowns and Power Reductions Safety Related Maintenance Major Plant Modification Operating Summary Refueling Information Sincerely yours, r~y-J. M. Zupko, Jr.

General Manager - Salem Operations RH:sl cc: Mr. William T. Russell Regional Administrator USNRC Region I 631 Park Avenue King of Prussia, PA 19406 Enclosures 8-l-7.R4

/,z,4.

j.Y I, The Energy People \*

95-2189 (11 M) 12-84