ML20140C326

Monthly Operating Rept for May 1984

ML20140C326
Person / Time
Site:	Salem
Issue date:	05/31/1984
From:	Miller L, Zupko J Public Service Enterprise Group
To:	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE)
References
NUDOCS 8406190267
Download: ML20140C326 (13)

Text

f

. .s .a-AVERAGE DAILY UNIT. POWER LEVEL Docket No. 50-311 Unit Name Salein # 2 Date June 10,1984 Completed by L. K. Miller Telephone 609-935-6000 Extension 4455 Month- May 1984 Day Average Daily Power Level Day Average Daily Power Level (MWe-NET) (MWe-NET) 1 0 17 1098 2 0 18 1103 3 0 19 1108 4 0 20 1088 5 18 4 21 1058 6 869 22 956 7 1108 23 1094 8 1074 24 1104 9 1093 25 1095 10 1103 26 1102 11 441 27 1081

-12 779 28 1088 13 1079 29 1101 14 1104 30 965 15 1094 31 0 16 1098 Pg.~8,1-7 R1 8406190267 840531 PDR ADOCK 05000311 PDR R

Page 2 of 13 f b}Y Yi

OPERATING DATA REPORT Docket No. 50-311 Date June 10, 1984 Telephone 935-6000 Completed by L. K. Miller Extension 4455 Operating Status

1. Unit Name Salem No. 2 Notes

2. Reporting Period May 1984

3. Licensed Thermal Power (MWt) 3411

. 4. Nameplate Rating (Gross MWe) 1162 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 3647 23088

12. No. of Hrs. Reactor was Critical 594.6 1497.3 13205.9

13. Reactor Reserve Shutdown Hrs. 0 1442.9 3533.6

14. Hours Generator On-Line 585.9 1364.2 12781.5

15. Unit Reserve Shutdown Hours 0 0 0

16. Gross Thermal Energy Generated (BORI) 1927080 4398C31 37869103

17. Gross Elec. Energy Generated (bDni) 649970 1454930 12323220

18. Net Elec. Energy Generated (MWH) 620699 1358693 11675941

19. Unit Service Factor 78.7 37.4 55.4

20. Unit Availability Factor 78.7 37.4 55.4 l

21. Unit Capacity Factor (using MDC Net) 75.4 33.7 45.7

22. Unit Capacity Factor (using DER Net) 74.8 33.4 45.4

23. Unit Forced Outage Rate 21.3 62.6 34.5 ,

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

N/A

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

6-12-84

26. Units in Test Status (Prior to Commercial Operation) :

Forecast Achieved Initial Criticality 6/30/80 8/2/80 Initial Electricity 9/1/80 6/3/81 Commercial Operation 9/24/80 10/13/81 8-1-7.R2 Page 3 of 13

UNIT SHUTDOWN AND POWER REDUCTIONS DockSt No. 50-311 REPORT MONTH May 1984 Unit Name Salem No.2-Date June.10, 1984 .

L.K. Miller Telephone 609-935-6000 Completed by 4455 Extension 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 Feedwater Regulating Boiler Level Control-84-134 04-27 F 113.38 A 3 -

HH VALVEX Valve Feedwater Regulating Boiler Level Control'84-146 05-11 F 12.2 G 3 - HH INSTRU Valve High Pressure Safety Injection Core F 32.5 A 1 -

SF VALVEX Injection / Core Spray 84-170 05-30 l

1 2 Reason 3 Method 4 Exhibit G 5 Exhibit 1 F: Forced A-Equipment Failure-explain 1-Manual Instructions Salem as-B-Maintenance or Test 2-Manual Scram. for Prepara- Source S: Scheduled C-Re fueling 3-Automatic Scram. tion of Data D-Regulatory Restriction 4-Continuation of Entry Sheets E-Operator Training & Licensing Exam Previous Outage for Licensee F-Administrative 5-Load Reduction Event Report G-Operational Error-explain 9-Other (LER) File H-Other-explain (NUREG 0161)

Page 4 of 13

MAJOR PLANT MODIFICATIONS DOCKET NO: 50-311 hEPORT MONTH NN: M2 .

MAY 1984 DATE: JUNE 10, 1984 COMPLETED BY: L. K. MILLER

("'S TELEPHONE: (609) 339-4455 V)

's

• DCR NO. PRINCIPLE SYSTEM SUBJECT 2EC-0508 Ventilation in Unit 2 North Non-safety related unit coolers (PACU-21, Penetration Area El. 100' 22, 23) are to be installed and serviced by present chilled water systen to provide cooling to the North Penetration area El. 100' for Unit 2. Control valves 2G31, 2G151 are to be used to isolate this area unit coolers frcm safety-ralated equipnent during energency.

2EC-1727 Heating Steam and Condensate Replace the cooler upstream of Padiation Fbnitor (RA-8354-2) by finned pipe, of the same design that exists on Unit 1.

2EC-1758 Beactor Coolant-Shaft bbdify the shaft vibration monitor Vibration Fbnitors systen to eliminate erroneous vibration monitor reading. Changes to include improving design of bracket, replacing M90 probes with M93 probes, and isolate drivers fran ground. An equivalent M93A probe nny be used in place of the M93.

q 2EC-1777 Circulating Water Upgrade materials of construction to HC-250 (Abex) or equivalent of No. 23 Screen Wash Pump.

2EC-1883 Reactor Coolant- Change alarm setpoint on the vibration Vibration bbnitors monitors fran 10 mils to 15 mils as per Field Directive S-C-R200-FFD-217, Bev.1.

2SC-0248 Fire Protection Provide test circuit for lights on 2RPS Fire Protection Panel.

2SC-0364 Condensate bbdify 23B Circulator Water Pump bbtor to allow filling of oil reservoirs.

2SC-0420 Se._vice Water (Bay #2) Replace existing small bore carbon steel piping to service water pump-motor bearing a3olers with 316 SS and install flex hoses at the inlet and outlet connections. .

2SC-0714 Fuel Handling Building bbunt brackets to hold fuel handling slings on wall El. 130'.

2SC-0859 Public Address Extend public address systen to include stations in #21 and #22 Diesel Fuel Oil Storage Tank Iboms.

• DESIGN CHANGE REOUEST 9-1-7.R1 Page 5 of 13

MAJOR PLANT MODIFICATIONS DOCKET NO.: 50-311 REPORT MONTH MAY 1984 UNIT NAME: Salem 2 DATE: June 10, 1984 COMPLETED BY: L.K. Miller TELEPHONE: 609/339-4455 DCR NO. 10CFR 50.59 SAFETY EVALUATION 2EC-0508 .All potential realistic failure modes have been identitied and are not applicable. All applicable regulatory requirements have been considered but are not affected.

No unreviewed safety or environmental questions are involved.

2EC-1727 The installation of finned pipe on the heating steam condensate return system is an improvement to the station startup operation. No unreviewed safety or environmental questions are involved.

2EC-175E All potential realistic failure modes have been considered but are.not applicable. This modification will not change any-plant process or discharge. No unreviewed safety or environmental questions are involved.

L2EC-1777 This material change of Nos. 21 and 22 Screen Wash Pumps does not affect any presently performed safety analysis

'nor does it create any new safety hazards. No unreviewed safety or. environmental questions are involved.

2EC-1883 Increasing the alarm setpoint does not violate design basis nor does it create any new safety hazards. No unreviewed safety or environmental questions are involved.

2SC-0248 Implementation of this Design Change may actually enhance the operation of the RP5 Panel by detecting one of the two bulbs used to illuminate the warning windows.

2SC-0364 The change in the upper and lower bearing oil fill piping

-will not affect the operation of the motors. No unreviewed. safety or environmental questions are involved.

2SC-0420 Implementation of this change will prevent erosion and corrosion of the pipe, thereby increasing the reliability of the pipe, thereby increasing the realiability of the system. No unreviewed safety or environmental questions are involved.

• Design Change Request Page 6 of 13

DCR NO. 10CFR 50.59 SAFETY EVALUATION 2SC-0714 Installation of a support bracket for the fuel handling slings does not affect any previously. performed structural safety analysis. No unreviewed safety or environmental questions are involved.

2SC-0859 Implementation of this Design Change does not involve any unreviewed safety or environmental questions.

1

• Design Change Request I

l l

Page 7 of 13

P S E & G . SALEM GENERMPING STPfrION SAFEIT REIA'ITD WDRK ORDER IDG SALEM UNIT NO.-2 WO NO Deist WIT EUJIPMENT MNnFICATICN 932537 IC 2 2R45 GSP-1 ,

FAIIURE DESCRIPTICN: LIMIT SWI'ICHES CN VI and V2 NEED 'IO BE REPIACED. 'IEESE SWI'ICHES WERE CANABALIZED EOR USE IN UNIT Iw>. l' (072083)

Cuous.:nVE PCTICN: INSTALLED AND CALIBRATED LIMIT SWITCHES (040284)-

939066 CD 2 VALVE 2CV18 FAIIURE DESCRIPTICN: VALVE FLUCIUATES 60 PSIG WHEN IN USE (080183)

CucatnVE AC'fICN: REPIACED CCNrRnrJFR AND PERFORMED CALIBRATICN (101283) 941085 20 2 2B 125VDC BATTERY FAILURE DESCRIPTICN: REINSTALL CELL NO. 36 (112183)

CORRECTIVE 7CTICN: CELL REINSTALLED, BATTERY FAILED 'IO MEEf SURVEILLANCE REQUIRENENf, WORK C0tifINUED UNDER WORK ORDER 941247 (032584) 941247- @ 2 2B 125VDC BATfERY FAILURE DESCRIPTICN: BATTERY FAILED 'IO MEEP SURVEILIANCE REQUIRENENT (021183)

CORRECTIVE PCTION: FAIIERE 'ID OBTAIN PROPER OUTPUT 'IO BE RESOLVED UNDER RESOIIIIICN OF DR-!O83-079 (032584) 941254 10 2 2B 125VDC BATTERY FAILURE DESCRIPTION: CHANGE N IR 39, 42, 43, and 47 AS PER a-MD83-079 (121283)

Cucut'nVE ACTICN: REPIACED NIR AND PEREUMED SURVEILIANCE TESTING ( 123083)

Page 8 of 13

PSE&G SALEM GENEPATING STATIN SAFETY PEIATED WORK ORDER IOG 941565 IC 2 VAINE 22SW305 ,

FAIIURE DESCRIPTIW: VAINE CWNECTING LINK IS BRNEN I-(020784) ,

CuKKtL'r1VE 7CTICN: REPAIRED CONNECTING LINK (020984) 941600 IC 2 NO. 22 STEAM GENERATOR FEED FION CHANNEL II FAIIERE DESCRIPfIW: CHANNEL FCOND TO BE OUT OF CALIBFATIN 9041684) 1,

Cu<xtL'r1VE ICTION

ADJUSIMENT MADE TO SQUARE ROUP MTULE (041684) l, R1633 1C 2 VAINE 22MS132 ,

s FAIIURE DESCRIPTIN: VALVE STEM CONNECTING BLOCK PULT.ED IOOSE (022384) s , -

t "

t 1 Cuo<tx;r1VE JCIION: CIANGED XT. JATOR STEM 'IHREADS 9022384) 943115\ 10 2 VALVE 24MS46 FAIIURE DESCRIPTIW: OFIN AND INSPECT INTERNALS FOR DISIORPICN OR DAMAGE 9041084)

CUKKtLr1VE JCTIW: REPIACED HANGER AND DISC. PERFORMED REPAIRS TO SMALL STEAM CUPS ON GASKET SURFACE 9050384) 943716 m 2 VALVE 23MS46 FAIIURE DESCRIPTIW: OPEN AND IMSPECT INTERNALS FOR DISIORTICN OR DAMAGE 9041084)

CutKEL:r1VE ACTIW: REPIACED HANGER (050384) 948011 CD 2 NO. 23 CHARGING PUMP SPEED INCREASER FAIIURE DESCRIPTICN: REPIACE FLEZ GASKEP W SUCTICN LINE OF FOMP (042984) wxKtL'r1VE ACTICN: REPIACED BRWEN SPLIT PIN CN COTTROL ARM AND REPI1CED TWO FLEX GASKETS (050584)

Page 9 of 13 _ _ _

D PSE&G SAIJ!M GEBERATING 919&ICN - .

SAFETY IU!IJt1TD NGtK OE0ER IOG 948048 CD 2 - 2C DIESEL GENERA'ITE PREWBE PGP

)

FAIIURE DESCRIPfICE: AIAIM KEEPS CGENG UP AND HEATERS TRIP CAUSING OIL 'ITMPERA'ItJRE TO GO

~

BEECW 100 DEGREES (051084)

CCRRBCTIVE 7CPIN: CLEANED OUP CIIECK VALVE AND INSTALTID HEAER (051884).

948157 CD 2 SIEAM DtMP SYSITM FAIIURE DESCRIPTICE: SYSTEM WIIL N0r GO INIO AUITNATIC (042784) 00RRBCPIVE 7CTICN: REPIACED REIAY IN K4 SENO SETPOINE STATIN APO CLEANED POITNTICHETER (050184) l 948185 CD 2 VALVE 23BF40 FAIIURE DESCRIPTIN: VALVE HAS NO OPEN OR CIOSED DDICATICN (041584) l CumrLnVE ACTICN: REPLACED BBmEN POTENTIGETER LINKAGE (041684)

{

l l 948200 CD 2 VALVE 22CV16I FAIIURE DESCRIPTICN: VALVE HAS A BOMEP LFAK (042684) l CumrLnVE JCIION: REPIJCED BONET ASSENLY A10 DIAPHRACM (042784) 948723 IC 2 BCD POSITICN DOICATICNS FAIIURE DESCRIPTICN: ID4, 2SA2, AND 2D3 RCD POSITINS DOICATIWS CN CONSOLE OUT OF SPECIFICATICN (042484)

CCRRECTIVE ACTICN: CALIBRATED 'IHE AFFECTED MODULES (042484)

Page 10 of 13 l

PSE&G SALEM GDERATING STATICE SAFEIT RELATED WCRK ORDER IOG 948735 IC 2 NOS. 21-24 STEAM GENERATOR FEEDWATER FLON RECORDERS FA11URE DESCRIPTIN: CALIBRATE FIEM RECORDERS (042884) .

Cuo<EL'nVE PCTION: CAIJBRATED FION INDICATIONS (042884) 948895 CD 2 NO. 23 CCNTAINMENT FAN COIL UNIT FAILURE DESCRIPTIW : FI4W INDICATIW NOT NORKING (042084)-

Cuc<EL:nVE ACTIN: RECCNNECTED TRAVEL PIN, SERCEGD VALVE, AND VERIFIED PROPER FION (042084) 952713 W 2 VALVE 23MS132 FAIIURE DESCRIPTIW: VALVE CANNOT BE OPERATED, ACTUA'IOR SHAPI HAS SEPARATED FRCN CCNNECEING BIOCK (051384)

Cutu<tL'nVE PCfICN: REPIICED STEM AND SPLIT CLAMP, VERIFIED PROPER OPERATICN (050384) 945225 OD 2 VALVE 23MSlu FAIIERE DESCRIPTICN: LIMIT SWI'ICH MOVED FRCM NORMAL POSITICN (050484)

COlu<tL'nVE ACTION: ADJUSTED LIMIT SWI'ICH AND VERIFIED PROPER OPERATICN (050484)

Page 11 of 13

OPERATIONS

SUMMARY

REPORT MAY 1984 Unit No. 2 began the month shutdown in order to replace No. 23 Feedwater Flow Nozzle which was damaged during the previous water hammer event. Repairs were completed followed by a reactor startup on Saturday, May 5, at 0541 hours0.00626 days <br />0.15 hours <br />8.945106e-4 weeks <br />2.058505e-4 months <br />. The reactor was critical at 1245 hours0.0144 days <br />0.346 hours <br />0.00206 weeks <br />4.737225e-4 months <br /> and the unit synchronized at 1713 hours0.0198 days <br />0.476 hours <br />0.00283 weeks <br />6.517965e-4 months <br />. The unit remained at power until May 11, 1984, when at 1006 hours0.0116 days <br />0.279 hours <br />0.00166 weeks <br />3.82783e-4 months <br />, a reactor trip occurred while troubleshooting a steam generator level recorder. The reactor was brought critical at 1812 hours0.021 days <br />0.503 hours <br />0.003 weeks <br />6.89466e-4 months <br /> on May 11, 1984 and the unit synchronized at 2216 hours0.0256 days <br />0.616 hours <br />0.00366 weeks <br />8.43188e-4 months <br />. The unit remained at full power until May 30, 1984, when a controlled shutdown was ordered by station management because of suspected inoperability of two Emergency Core Cooling System Valves, 21 and 22 SJ16. As a result of plug / stem problems with Rockwell valves on Unit No. 1, radiography of similar type valves on Unit No. 2 was performed. The results revealed slight unthreading of the plug from the stem on Valves 21 and 22 SJ16. Since there was no way to verify proper throttle settings for these valves, which are required for high head charging into the cold legs, a controlled shutdown was ordered in order to satisfy the Technical Specification requirements and facilitate repairs. During the shutdown process, as the generator output breakers were being opened and the P-10 permissive automatically reset due to decreasing reactor power, a reactor trip occurred due to Intermediate Range High Flux.

An evaluation of this trip revealed that a too conservative setpoint and a large reset deadband, which combined with core conditions, prevented the Intermediate Range Channel 35 from reaching its reset point prior to P-10. The Intermediate Range Channel setpoint will be changed upon the next return to power of the Unit based upon new measured values.

Page 12 of 13

...,s.

REFUELING INFORMATION Docket No. ~ 50-311 l Unit Name Salem #2 l l

Date June 10, 1984 Completed.by L. K. Miller Telephone 609-935-6000 Extension 4455 Month May 1984

'l. Refueling information has changed from last month:

YES X NO

2. Scheduled date of next refueling: January 5, 1984

3. Scheduled date for restart following refueling: March 17, 1985

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

YES NO NOT DETERMINED TO DATE 6/1/84 B. Has the relcad fuel design been reveiwed by the Station Operating Review Committee? YES NO- X >

If no, when is it scheduled? Novmeber 1984 5.- Scheduled date (s) for submitting proposed licensing action:  ;

December 1984 (if required)

6. Important licensing considerations associated with refueling:

NONE

7. Number of Fuel Assemblies:

A. Incore 193 B. In Spent Fuel Storage 72 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 2004 8-1-7.R4 Page 13 of 13

r I

O PSEG Public Service Electric and Gas Company P.O. Box E Hancocks Bridge, New Jersey 08038 l

Salem Generating Station June 10, 1984 Director, Office of Inspection and Enforcement U.S. Nuclear Regulatory Commission Washington, DC 20555

Dear Sir:

MONTHLY OPERATING REPORT SALEM NO. 2 DOCKET NO. 50-311 In Compliance with Section 6.9, Reporting Requirements for the Salem Technical Specifications, 10 copies of the following monthly operating reports for the month of May 1984 are being sent to you.

Average Daily Unit Power Level '

Operating Data Report l Unit Shutdowns and Power Reductions Major Plant Modification Safety Related Work Orders Operating Summary Refueling Information

. Sincerely yours, J M. upko, Jr.

G neral Manager - Salem Operations LKM:sbh cc: Dr. Thomas E. Murley Regional Administrator USNRC Region I 631 Park Avenue King of Prussia, PA 19406 Director, Office of Management Information and Program Control U.S. Nuclear Regulatory Commission Washington, DC 20555 Enclosures Pagel of 13 ggg 8-1-7.R4

]hV

'\\

The Energy People n ewm n e,