Text

Monthly Operating Rept for Apr 1982
	ML20052G660
Person / Time
Site:	Salem
Issue date:	05/10/1982
From:	Miller L; Public Service Enterprise Group
To:	;
Shared Package
ML20052G656	List: ML20052G655; ML20052G660;
References
	NUDOCS 8205180551
	Download: ML20052G660 (13)
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.- . . . - . - -

AVERAGE DAILY UNIT FCER LEEL -

I DOCET NO. 50-311 UNIT salem No. 2 DATE May 10, 1982 CCt@LETED BY L. K. Miller TELEPHONE 609-541-5900 x507

! MONTH _ April, 1982 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POER LEVEL

@Bfe-NET) . @BiE-NET) 1 1094 17 14 l 2 1162 18 615 3 741 19 1122 4 1067 20 1093

! 5 1118 21 367 6 854 22 1075 7 519 23 1014 8 690 24 1075 9 964 25 1019 t

10 1095 26 1035 11 1110 27 1088 12 1105 28 959 i 13 1119 29 1061 14 1116 30 864 15 1100 31 16 1094 a

i Pg. 2 of 14 8.1-7.R1 820518o551

auscING ces mPaRr 4

Docxrr to.: 50-311 ogg : May 10, 1982 c3rIz:ID sr: L. K. Miller 1 l

mas 2m: 609-541-5900 x507 s

memrING SIMCS

1. thit Names Salem No. 2 Notes l 2. Reporting Peried: April, 1982

3. umn==d 3mmini Power (Poeta: 3411

4. Naumplats Rating (Gross 200m): 1162

5. Design Electrical Rating (Not lede): 1115

3. Mrdman Whte Capacity IGross sede): 1149

7. .h n=pandahim Capacity (Not bede): 1106

8. If &anrps cociar in capacity Ratings (Itans mater 3 Tart:na#t 7) Sisen Iast Report, Give Reason:

None

9. Power Iavel To le112' Restricted, If Arrf (Net teie): None

10. Roastms For Restricticms, If Any: N/A 211s Ptmth Year to Data N 1 =*4 ve 719 2,879 4,825

11. acurs In W Period i 12. maner of sours Reecece was critical 704 3 2,860.3 4,719.6

13. Reactor Reserve Shut 2Wn naurs 0.0 0.0 0.0

14. asurs Generator on-Line 694.1 2,843.9 4,661.6

15. thit Remarve Shutdown Hours 0.0 0.0 0.0

16. Gross normal mergy cenaratadoes) 2,174,431 9,077,434 14,185,453 1

17. Gross Electrical margy Generatadocer) 710,380 3,028,660 4,737,530

18. Not Electrical mergy Generated 0es) 680,474 2,910,094 4,542,161

19. thit Service Factor 96.5 98.8 96.6 i

20. Ohit Av=41=h414ty Factor 96.5 98.8 96.6 l

21. chit Capacity Factor (Usinq ICC Net) 85 7 91.6 85.1

22. Unit Capacity ractne (using osa Net) 84.9 90 7 84.4 3.5 1.2

23. anit Forced outage Rat 2.9

24. Staatdowns SMiad over Next 6 mutths (Type, Data, and Duration of Ead):

None

25. If Shut Down At End of Report Period, Eseimead Date of Startup: N/A

26. ahits In Test Status (Prior to Ccamarcial Operation):

Forecast Achieved l

mImL mT 06/30/80 08/02/80 e-1-7.a2 DI M L E 2 C N CITY 09/01/80 06/03/81 Pg. 3 of 14 CMERCIAL CPERETON 09/24/61 1u/ u/c1 l _ __- . _ . - .-.

turr ram 10HNS NO MMER RE2RECTION DOCKET E0.: 50-311 RF3UTF Mml APRIL 1982 orIT'NanE: Salem No. 2 oarg, May 10, 1982 COMPLETED DY: L.K. Miller TELEPl!ONE: 609-541-5900 IS07 nenioD or g DURATION SmnTIM LIWEE S GDEUeff CAUSE NO QRRBCTIVE W. WE TYPE (InJPS) RFA90N 00HN EVENT 00f GDES ACTION TO REACIoR REToRF f PREVENT RFEURRENCE 82-132 3-28 F 264.5 B 5 - - - - HF FILTER Traveling Screen / Trash Racks / Canal Screens.82-138 4-02 F .6 B 5 --- HF FILTER Traveling Screen / Trash Racks / Canal

. Screens.82-140 4-03 S 6.0 B 5 ----- HF FILTER Traveling Screen / Trash Racks / Canal Screens.82-142 4-03 F 13 1 B 5 HF FILTER Traveling Screen / Trash Racks / Canal Screens.82-144 4-03 F 6.9 B 5 - - - -

HA TURBIN Turbine Governing Sys. Control.82-146 4-05 F 3.1 B 5 - HC CONDSR 21A Ciro. Condenser Cleaning 82-148 4-05 F 27 B 5 HC CONDSR 21B Cire. Condenser Cleaning 82-150 4-05 F 3.4 B 5 ----

HC CONDSR 22B Cire. Condenser Cleaning 1 2 3 4 5 F: Forced Reasons itethod Exhibit G - Instructions gNbit 1-Sane S Sdeduled A-Itjulpent Failure (E> plain) 1-Manual for Pr g aration of Data B-petintenance or Test Ehtry Sheets for Licensee c-sufueling 2-Manual Scram. %,t seport(Ism) rite t-Regu14 tory Restriction 3-Automatic Scram. (NURfG-0161)

E-operator Training & Lloense Examinatim 4-Continuation of F-Arkinistrative Previous Outage croperational Error (Explain) n-other (Emplain) 5-Load Reduction er Page 4 of 14 8-1-7.R1

~

twir slamKM6 NU IDER IEWCTIONS DOCKET NO. 50-311 Resurr remi APRIL 1982 UNIT NAME: Salem No. 2 DarE May 10, 1982 COMPLETED BY: L. K. Miller TELEPflONE: 609-541-5900 X507 Ncnto or DURATICH SIRHTING LIONE UMOOrr CMISE NO QRRECTIVE

50. DATE TYPE (IK1URS) RERSCDI DUNN EVFNr CODES ACTION 10 Rr>cton Rrsurr I ,

PREVENT REURRFNCE 82-152 4-05 F 0.0 A 5 ----

HG PUMPFW Condensate Polishing Low Suction on S.G.F.P.

l 82-154 4-05 F 27 2 B 5 ---- HF FILTER 21A Cire. Screen Jam, Broken links82-156 4-06 F 17 3 B 5 - - - - HF FILTER Traveling Screen / Trash Racks / Canal Screens.82-158 4-06 F 37 3 B 5 ---- HF FILTER Traveling Screen / Trash Racks / Canal . ,

Screens. ,82-160 4-06 F 8.5 B 5 - - - - HF FILTER Traveling Screen / Trash Racks / Canal Screens.82-162 4-06 F 26.6 B 5 ----- HF FILTER Traveling Screen / Trash Racks / Canal Screens.82-164 4-07 F 12.6 B 5 -

HF FILTER Traveling Screen / Trash Racks / Canal Screens.82-166 4-07 F 18.3 B 5 ----- HF FILTER Traveling Screen / Trash Racks / Canal Screens.82-168 4-08 F 16.8 B 5 ----- HF FILTER Traveling Screen / Trash Racks / Canal Screens.82-170 4-08 F 12 7 B 5 ---- HC CONDSR Condenser Tube Leaks Inspect i

Page 5 of 14 ,

8-1-7.Rt

UNIT simpe6 MO IWER IW211CTIOPE

DOCKET NO. 50-391 Rrrurr Mmmt APRIL 1982 UNIT NAME: Salem No. 2 DATE: May 10, 1982 COMPLETED BY: L. K. Miller TELEPilONE: 609-541-5900 1507 wnts or IURATION ganTINil LIO NIE ONUENT CMISE NU UNtRECTIVE to. DME TYPE (IE)URS) IEAM D0004 EVENr CDDES gTr(N go WEIUR RE7 W r 1 PREVfNT RELUUWM2 82-172 4-08 F .6 A 5 ---- CH PUMPFW 22 SGFP Tripped, Low Suction 82-174 4-09 F 39 2 B 5 --- HF FILTER Traveling Screens / Trash Racks / Canal Screens82-178 4-17 F 21.4 A 3 - - - - CH PUMPFW 21 SGFP Trip Caused Low-Low Level in 24 Steam Generator 82-180 4-21 F 35 A 3 - - - - CH PUMPFW 21 SGFP Over Speed Trip 82-182 4-21 F 2.6 A 5 - CH PUMPFW SGFP Problem 82-184 4-22 F 26.3 B 5 ----- HC CONDSR 23B Condenser Tube and Water Box Cleanirg 82-186 4-25 F 6.5 A 5 ----

HF FILTER 23A Traveling Screen Jammed 81-188 4-25 F 1.6 B 5 - HF FILTER 22A Traveling Screen 82-190 4-25 F 70.4 B 5 - HF FILTER 22A Traveling Screen 82-192 4-25 F 2.8 A 5 -

CH PUMPFW SGFP Problem 82-194 4-25 F 10 7 A 5 - - - - CH PUMPFW 21 SGFP Low Suction 82-196 4-26 F 4.5 B 5 ---- HH HEATER Moisture Seperater/ Reheater 82-198 4-26 F 76 B 5 - - - - HH HEATER Moisture Seperater/ Reheater rage 6 of 14 0-1-7.R1

UNIT SRmKMES NO KM:R IEIRCTIONS DOCKET NO. 50-311 -

sener Mwmi April 1982 UNIT NAME: ___ Salem No. 2 DATE: May 10, 1982 conPLETEo ny: L. K. Miller TELEPflONE: 609-541-5900 X507 mmun or DURATIm 9tfrrING LIO3EE ODf0NENT CMEE APU CORRECTIVE l

NO. .MM TYPE OKimS) WASON DUM4 EVMr GDES ACTION 10 82-200 4-26 F 36 7 A 5 ---- CH PUMPFW Other Feed Water Pump Problems82-202 4-27 F 27 B 5 ---- HH HEATER Moisture Seperater/ Reheater 82-204 4-28 F 92 A 5 - - - -

HF CIRhIR , High Cire. Water Temperature.82-206 4-28 F 6.6 A 5 --

CH FUhPFW Other Feed Water Pump Problems82-208 4-28 F 3 A 5 ----

CH PUMPFW Other Feed Water Pump Problems82-210 4-28 F 19.1 A 5 - - - - CH FILTER Traveling Screens82-212 4-29 F 33 7 A 5 - - - - CH FILTER Traveling Screens82-214 4-30 F 12.7 A 5 ----

CH FILTER Traveling Screens82-216 4-30 F 4.7 A 5 ----

CH FILTER Traveling Screens82-218 4-30 F 35 -

A 5 ----

CH FILTER Traveling Screens I

rage 7 of 14 .

e-1-7.nl

- l DOCKET NO.: 50-311 MAJOR PLANT MODIFICATIONS UNIT NAME: Salem No. 2 REPORT MONTH APRIL 1987.

DATE: May 10, 1982 COMPLETED BY: L. K. Miller TELEPHONE: 609-541-5900 X507

DCR NO. PRINCIPLE SYSTEM SUBJECT 2-EC-0587 Fire Protection Auxiliary Building Structure 2-EC-1318 Radiation Monitorint System 4" Lead Spacer Plug Installed in 2R31.

2-EX-1374 Steam Generator Change Steam Generator nornal Water Level from 44% to 40%.

2-SC-0666 Liquid Wa'ste Disposal Remove FT1007 and Replace with Spool Piece.

DESIGN CHANGE REQUEST 8-1-7.R1 Page 8 of 14

DOCKET NO.: 50-311 MAJOR PLANT MODIFICATIONS UNIT fiAME: Salg.m No. 2 REPORT MONTH April, 1982 DATE: May 10, 1982 COMPLETED BY: L. K. Miller TELEPHONE: 609-541-5900 x507 l *DCR NO. 10CFR50.59 SAFETY EVALUATION 2-EC-0587 Implementation of this DCR increases fire protection in the structure by providing a fire barrier between elevations in the building. This installation does not affect in an adverse manner the safe shut down of the safety related equipment.

2-EC-1318 This change of radiation monitor is an anticipated change and does not involve any increase in radiological effluents. Therefore, there is neither an ETS change required nor an USQ involved.

2-EX-1374 The Level change is still within the. operating limitations of the Steam Generators and will not alter effluent limitations of the ETS or NEDES permit nor result in an UEQ.

2-SC-0666 The removal of the Flow Transmitter does not involve an unreviewed safety question or require a change to either the FSAR or Tech. Specs.

The system is not required for the safe shut down of the Reactor Plant.

The Design Change will allow flow through the system without the potential to be plugged due to reduced pipe I.D. and flowmeter probe.

l

DESIGN CHANGE REQUEST Page 9 of 14

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9 nEC'n iITEM ON RP4 FOR CM.CC AND AllXFEFD.

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CnRRECTTVF ACTION, REPLACFD DTODER(CONTROL CAPSULE)FOR L410, V L41TeL436 RFPAIREn RROMEN WIRE CONN AT. _ _ _ _ _ . .

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!Page 12 of 14

SALEM UNIT 2 OPERATING

SUMMARY

REPORT APRIL 1982 4-01-82 Reactor is operating at 100% power.

4-02-82 Power was reduced to 95% at 1057 hours0.0122 days 0.294 hours 0.00175 weeks 4.021885e-4 months due to problems with 23A circulator traveling screen.

The problems were corrected and power increased to 100% was initiated at 1135 hours0.0131 days 0.315 hours 0.00188 weeks 4.318675e-4 months .

l 4-03-82 Power was reduced to 80% at 0007 hours8.101852e-5 days 0.00194 hours 1.157407e-5 weeks 2.6635e-6 months due to problems with 23A circulator traveling screen.

Power increase to 100% was initiated at approx-imately 1200 hours0.0139 days 0.333 hours 0.00198 weeks 4.566e-4 months .

4-04-82 Power reached 100% at 0500 hours0.00579 days 0.139 hours 8.267196e-4 weeks 1.9025e-4 months .

4-05-82 Power was reduced to 94% at 1135 hours0.0131 days 0.315 hours 0.00188 weeks 4.318675e-4 months due to low steam generator feed pump suction alarm.

Feed pump suction was restored and power was increased to 100% at 1500 hours0.0174 days 0.417 hours 0.00248 weeks 5.7075e-4 months .

4-06-82 Power was reduced to 46% at 1241 hours0.0144 days 0.345 hours 0.00205 weeks 4.722005e-4 months due to 21B and 22A circulator trips. 21B ciruclator was placed back in service at 1250 hours0.0145 days 0.347 hours 0.00207 weeks 4.75625e-4 months and power increase was initiated at approximately '

1600 hours0.0185 days 0.444 hours 0.00265 weeks 6.088e-4 months .

4-07-82 Power was reduced from 80% to 42% at 0345 hours0.00399 days 0.0958 hours 5.704365e-4 weeks 1.312725e-4 months .

21A circulator was taken out of service due to problems with traveling screen. Power increase was delayed due to continuing problems with circulators.

4-08-82 Power was increased to 95%. 22A circulator was taken out of service at 1325 hours0.0153 days 0.368 hours 0.00219 weeks 5.041625e-4 months and power was reduced to 72%. 22 steam generator feed pump tripped at 2230 hours0.0258 days 0.619 hours 0.00369 weeks 8.48515e-4 months and power was further reduced to 55%. The feed pump was placed in service

, at 2245 hours0.026 days 0.624 hours 0.00371 weeks 8.542225e-4 months and power increased was initiated.

4-09-82 Power reached 100% at approximately 1400 hours0.0162 days 0.389 hours 0.00231 weeks 5.327e-4 months .

4-17-82 21 steam generator feed pump tripped at 0046 hours5.324074e-4 days 0.0128 hours 7.60582e-5 weeks 1.7503e-5 months .

The reactor tripped due to low low level on 24 steam generator. The reactor was taken critical at 1349 hours0.0156 days 0.375 hours 0.00223 weeks 5.132945e-4 months , but entry to mode 1 was delayed due to inoperable containment air lock. The turbine was placed on line at 2210 hours0.0256 days 0.614 hours 0.00365 weeks 8.40905e-4 months .

4-18-82 Power was increasing at 3% per hour all: day.

4-19-82 Power reached 100% at 0315 hours0.00365 days 0.0875 hours 5.208333e-4 weeks 1.198575e-4 months .

Page 13 of 14

l 4-21-82 21 steam generator feed pump tripped at 0017 hours1.967593e-4 days 0.00472 hours 2.810847e-5 weeks 6.4685e-6 months , ,

and the reactor tripped due to low low level on 22 steam generator. The reactor was taken critical at 0157 hours0.00182 days 0.0436 hours 2.595899e-4 weeks 5.97385e-5 months and the turbine was placed on line at 0345 hours0.00399 days 0.0958 hours 5.704365e-4 weeks 1.312725e-4 months .

4 4-22-E2 Power reached 100% at 1220 hours0.0141 days 0.339 hours 0.00202 weeks 4.6421e-4 months .

4-24-82 Power was reduced to 90% at 0452 to conduct turbine valve test. The test was completed at 0605 hours0.007 days 0.168 hours 0.001 weeks 2.302025e-4 months and power was increased to 100%.

i 4-25-82 Power was reduced to 95% due to 23 east and west 4 MSR trip at 0214 hours0.00248 days 0.0594 hours 3.53836e-4 weeks 8.1427e-5 months and isolation of 26C feedwater heater at 0300 hours0.00347 days 0.0833 hours 4.960317e-4 weeks 1.1415e-4 months . Power was increased to 100%

by 0740 hours0.00856 days 0.206 hours 0.00122 weeks 2.8157e-4 months . Power was reduced to 90% from 1200 to 1600 hours0.0185 days 0.444 hours 0.00265 weeks 6.088e-4 months due to steam generator feed pump low suction alarms. Power was increased to 100% by 2400 hours0.0278 days 0.667 hours 0.00397 weeks 9.132e-4 months .

4-28-82 Power was reduced to 60% due to 21 steam generator feed pump trip at 1544 hours0.0179 days 0.429 hours 0.00255 weeks 5.87492e-4 months . The feed pump was placed in service at 1623 hours0.0188 days 0.451 hours 0.00268 weeks 6.175515e-4 months and power increase was initiated.

4-30-82 Power was reduced to 70% at 1857 hours0.0215 days 0.516 hours 0.00307 weeks 7.065885e-4 months due to problems with 21B and 22B circulator traveling screens.

Y j

Page 13A of 14 l

,.I

REFUELING INFORMATION DOCKET NO.: 50-311 UNIT: Salem No. 2 DATE: May 10, 1982 COMPLETED BY: L. K. Miller TELEPHONE: 609-541-5900 x507 MONTH: April, 1982

1. Refueling information has changed from last month:

YES NO x

2. Scheduled date of next refueling: January 22, 1983

3. Scheduled date for restart following refueling: April.24, 1983

4. A. Will Technical Specification changes or other license amendments be required? YES NO NOT DETERMINED TO-DATE April, 1982 B. Has the reload fuel design been reviewed by the Station Operating Review Committee? YES NO x If no, when is it scheduled? December, 1982

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

Deceuiber , 1982 (If required)

6. Important licensing considerations associated with refueling:

None

7. Number of Ftel Assemblies:

A. In-Core , 193 B. In Spent Fuel Storage 0

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 I pool assuming the present licensed capacity: March, 2000 Page 14 of 14 m-JL-LA4

ML20052G660

Text

SUMMARY

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