ML20062M494

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Monthly Operating Rept for Nov 1981
ML20062M494
Person / Time
Site: Salem PSEG icon.png
Issue date: 12/10/1981
From: Miller L
Public Service Enterprise Group
To:
Shared Package
ML20062M486 List:
References
NUDOCS 8112170266
Download: ML20062M494 (13)


Text

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AVERAGE DAILY UNIT FChE T.IL EOCKET NO. 50-311 UNIT Sa]em No. 2 DATE December 10, 1981 CCNFLETED BY L.

K. Miller TELEPHONE 609-365-7000X507 BONIH November 1981 l

DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY P0;GR WEL (We-NET)

(ME-NET)

^

J 1

943 17 877 2

1056 18 1003 3

352 le 718 4

1051 20 175 5

844 21 459 6

1088 22 457 7

1041 23 9so 8

1105 24 918 g

1086 25 80 c

l 10 1051 26 420 11 1027 27 584 12 1109 28 651 13 1030 29 639 14 1100 30 633 15 1099 31

.16 187 4

i Pg.

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GTRhIDc GC1 PEPGC rrrrm ro.: 50-311 DA:E :

December 10, 1981 N BY:

L. K. Miller "2:2 Plat: 609-365-7000X507 cyneenc sm2ts 1.

Iktit Neen:

Salem No. 2 noe,

2.

Esporting Periods November 1981 1 h 2=r' ant Pener Qeet):

3411 4.

temmplate Racing (Gross rese):

1162 5.

n==ter r1 - r-= 1 Rat:ag (Not 190s):

1115 4.

>== Dependable Capacity IGross rese):

1149 7.

M== M1= Capacity (Not teen):

1104 8.

If O=wpa occur in capacity an*:dage (Itans ! Amber 3 2 rough 7) Slace Iaet W, Give amasent None 9.

Power Inval Tb Miich Restricted, If Arr; (Not }98e):

None ID. Emmaans For aestricciarts, If Any:

N/A Siis Ptmth Year to Data h *1=+4ve 720 1177 1177 3

i

22. temmer of thns anactor was Critical 689.3 1131.2 1131.2
13. anactra ameerve shutdows sours 0.0 0.0 0.0 14.

Hours Generator On-Line 677.0 1098.5 1098.5

15. thit anserve shutzbe Hours 0.0 0.0 0.0
15. Cross n=r,n=1 maryy GanaratedD98EI) 1.805.837 3,066,53 L 3,066,533
17. czuse r1* r-= 1 t argy Generatadose) 598,880 1,024,780 1,024,780
13. Not r1*r=12ergy GeneratadoSE) 570,363 977,553 _

977,553

13. thit Servica Factor 94.0 93.3 93.3 i
20. thit Av=i1^411ty ractor 94.0 93.3 93.3 21, Insit Capacity Factor (Using ICC Net) 71.8 75.2 75.?
22. thit Capacity ractne (Using DER Net) 71.0 74.5 74.5
23. thit Ibreed outage ants 6.0 6.7 6.7

- 24. 5tuatzbes Sd=dn1=d over Next 6 femths (Type, Date, and Duration of Eadi):

None i

25. If Shut Down At End of angert Period, Est: mated Date of Starttp N/A j

2E. thits In Test Status (Prior to Ccueercial Operation):

rotecan Achieved INI*IAL CN'TY 06/30/80 08/02/80 INrIIAL I:1Len 09/01/80 06/03/80 79 3 of 14 CDGEBC3L CPERA:238 09/24/81 10/11/81

tNIT raamueas we IWER N21CTIM DOCKET NO.:

50-311 paront nuns November 1981 UNIT 'NAME:

Salem No. 2 onyE December 10, 1981 mtPLETED BY:

L. K. Miller j

TELEPilONE: 609-365-7000X507 Mn:ntn or

[UlmTICN SIRRTIIC LIQ 20E SY ODMENr Chl2SE AW NTM I

2 m.

DATE 1YPs (iruns) m:AscN EDM EV1Nr ONES ACTION 10 IEACIOR IE2ngr g PIEMNT NDimENCE 81-020 11-2 F

0.0 A

5 HH HTEXCH Feedwater Chemistry Problem Due To Condenser Leak 81-022 11-5 F

0.0 A

5 HH FTEXCH 21A Condenser Leaking Causing g

Chemistry Problems81-024 11-5 F

0.0 A

5 HH HTEXCH 21A Condenser Leaking Causing Chemistry Problems81-026 11-6 F

0.0 A

5 HF FILTER 22A Circulator Screen Shifted 81-028 11-7 F

0.0 A

5 HH.

PIDiPXX 21 Steam Generator Feed Pump Oscillation 81-032 11-10 F

0.0 A

5 HH FILTER Clean 21 Condeusate Pump Suction Strainer 81-034 11-11 F

0.0 A

5 HH llTEXCH 23A Condenser Leak 1

2 3

4 5

F Ebromi Deasm mthods Exhibit G - Instzuctione g t 1-Same S: Sdaduled A-Bjulgnent Failure (Emplain) 1-Manual for Prepatation of Data B-Maintenance or Test Ditry Slusets for Lionnees 2-Hanual Scram.

c-nerueling m it h porti m ) File p-negulatory neetract. ton 3-Automatic Scram.

(Hump-0161)

E-Oterator Training & Lionnee Examinatlon 4-Continuation of r-M ninistrative Previous Outage G-0porational Error (Euplain) n-other (Eglain) 5-Load Reduction Pig

  • 4 of 14 8-1-7.R1

50-311 tMir stntoes NO MwJt wsteritse noegEr no,,

mnwr nurru Novem*oer 1981 UNtr euwiEn Salem No. 2 a

DATE:

December 10, 1981 COMPLETED SY L. K. Miller TELEPHONE: 609-365-7000X507 prnte or INTICM SIRNTINf3 IJONiB ODEUENT CMISE NO GI4WCTIVE 80.

DME TYPE (10VRS)

IENEM toet EVntr Cmg5 Actgow in 81-036 11-11 F

0.0 A

5 ID INSTRU Quadrant Power Tilt Due To Defective N-I Detector 81-038 11-12 F

0.0 A

5

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HH HTEXCH Inspect 21A Condenser 81-040 11-12 F

0.0 A

5 HH HTEXCH 22A Condenser Tube Leaks81-043 11-13 F

0.0 A

5 HH HTEXCH 23B Condenser tube Leaks81-047 11-16 F

0.0 A

5 HF FILTER 22B Screen Replacement 81-049 11-16 F

11.6 A

3 HH PUMPXX 22 Steam Generator Feed Pump Tripped 81-051 11-17 F

0.0 A

5 ID INSTRU Quadrant Power Tilt Due To Nuclear Instrumentation Problem 81-053 11-19 F

0.0 A

5 HH FILTER High Differential Pressure On 22 Heater Drain Pump 81-055 11-19 F

0.0 A

5 HH FILTER High Differential Pressure On 22 Heater Drain Pump 81-057 11-19 F

4 A

3 HH PUMPXX 22 Steam Generator Feed Pump Trip Due To Low Suction Pressure 81-059 11-19 F

5.5 A

3 CC HTEXCH 24 Steam Generator Hi-Hi Level 81-061 11-20 F

0.0 A

5 HG ZZZZZZ Condensate Polisher Resin Failure rage 5 of 14 0-1-7.R1

tmIT samKM6 NO ItMER IW2tCTIGG DOCEET NO.

50-311 sertwr nwns November 1981 unit NAME:

Salem No. 2 onTE:

December 10, 1981 COMPLETED BYs L. K. Miller TEt.ErnoNE: 609-365-7000X507 temKm or DUIETION RRffrIIC LICf3EE SYS'ID4 UMoeNr CMISE NO 0385ECT1vE NO.

DME TYPE (IKAMS)

WN0N EX 244 EVENT ME4 ME5 ACTICM 10 w>cion Rf2urr 8 PIEVENr IEOUfuEN3 81-063 11-20 F

0.0 A

5 HH FILTER Clean 21 Steam Generator Feed Pump Suction Strainer 81-065 11-22 F

0.0 A

5 HH FILTER Clean 22 Steam Generator Feed Pump Suction Strainer 81-067 11-22 F

0.0 A

5 HH FILTER Clean 22 Steam Generator Feed Pump Suction Strainer 81-069 11-23 F

0.0 A

5 HH PUH5XX 21 Steam Generator Feed Pump Low Suction Pressure 81-071 11-24 F

0.0 A

5 HH PUMPXX 21 Steam Generator Feed Pump Low Suction Pressure 81-073 11-24 F

21.9 A

3 CC HTEXCH 24 Steam Generator Low-Low Level 81-075 11-26 F

0.0 A

5 HH PUMPXX Repair 21 Steam Generator Feed Pump Casing 81-077 11-29 F

0.0 A

5 HF FILTER 22B Traveling Screen Jammed l

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Page 6 of 14 i

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DOCKET NO; 50-311 t

i MAJOR PLANT MODIFICATIONS REPORT MONTH Nov*mbar 1981 UNIT NAME:

Salem 2 DATE:

- December 10, 1981.

4:

COMPLETED BY:

L.

K. Miller 1

TELEPHONE:

609-365-7000X507

  • DCR NO.

PRINCIPLE SYSTEM SUBJECT 2EC-0863 Steam Generator Addition of eight drain lines to Internal secondary dryers (No. 22, 23, 24 Steam Generators) 2EC-0864 Vital Trays and

- Wrapping' vital cables required for Conduits

- hot shutdown of plant-in the event of fire 2EC-0865 Condensate Replace existing condensate pump 4

steady bearings with new split i

type bearings (No. 22 Pump only) i 2EC-ll50 Safeguard Equipment Install line filters Control 2EC-1160 Radiation Shielding Extend wall at spent resin storage tank doorway 3

i 2EC-1299 Spent Fuel Modify spent fuel handling tools

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2EX-1325 Radiation Monitoring Warning alarm set points System 1

4 l

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  • ' DESIGN CHANGE REQUEST i

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DOCKET NO.:

50-311 MAJOR. PLANT MODIFICATIONS UNIT NAME:

Sclem No. 2 PJEPORT MO!PrH Novemb:r 1981 DATE:

December 10,-1981 COMPLETED BY:

L. K. Miller TELEPHONE:-

609-365-7000X507

  • DCR NO.

10CFR50.59 SAFETY EVALUATION 2EC-0863 Sections 3/4.4.6 and 3/4.7.12 of Unit No. 2 technical specifications was reviewed, as was the applicable sections of the FSAR:

the modifi-cation being made does not affect or require change to either document.

The additional secondary dryer drains (eight per s/g) will ensure the quality of main steam moisture carryover does not exceed 0.25% of the steam flow at rated conditions. This modification has been successfully performed on W three loop designed s/g's.

The safe stitdown of the reactor plant is not adversely affected and an unreviewed safety question is not involved. The modification does not involve any increased radiological hazard.

2EC-0864 Wrapping of cables / conduit will not affect any safety function, margin or analysis: no U.S.Q. present.

2EC-0865 This design change does not affect any safety related components or systems. The design change has been completed on Unit No. I with no adverse conditions developing. No change to the technical specifications or to 'the FSAR is required. No unceviewed safety question i's involved and the safe shutdown of the plant is not jeopardized.

2EC-1150 This change (1) adds power supply filtration to improve noise immunity and (2) replaces a light emitting diode (LED) with new device required as old LED is no longer manufactured.

This change does not modify function and improves reliability. This modification will not alter any plant procecs or discharge.

2EC-1160 Installation of this shield wall will not inhibit the shutdown of the reactor or adversely affect the building integrity.

2EC-1299 This modification does not affect any safety related system and does not present an unreviewed safety question.

The cha'nge to the tool will prevent galling due to the sliding motion between the guide pin and matching surfaces. The change does not alter the operation of the spent fuel tool. This modification does not increase the probability of dropping a spent fuel assembly, does not result in an increase in the amount of radioactive effluents, does not require a change in the environment technical specifications, and does not involve an unreviewed environmental question.

i DESIGN CHANGE REQUEST

.Page 8 of 14

DOCKET NO.:

50-311

  • MAJOR PLANT MODIFICATIONS UNIT NAMES Salem No. 2 REFO;T MO"TH Novemb:r 1981 DATE:

December 10, 1981 COMPLETED BY:

L. K. Miller-TELEPHONE:

609-365-7000X507

  • DCR NO.

10CFR50.59 SAFETY EVALUATION 2EX-1325 This DCR involves the raising of the alarm setpoints for the Steam Generator Blo"down Radiation monitors. This temporary change is necessary to enable the performance of the Na 24 carryover testing.

This new setpoint does not allow any technical specification limits to be exceeded. To be conservative, a 50% value was utilized.

This setpoint change has been analyzed and found not to involve any unreviewed safety question; or result in any hazards to the safety and welfare of the public.

l

  • DESIGN CHANGE REQUEST Page 9~of 14

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SUMMARY

NOVEMBER 1981 11-01-81 Power increased to 100% following load reduction on 10-31 for secondary system high~ conductivity,

(condenser leak).

11-02-81 2050 hours0.0237 days <br />0.569 hours <br />0.00339 weeks <br />7.80025e-4 months <br /> - reduce power to 25% due to secondary system high conductivity.

11-03-81 1000 hours0.0116 days <br />0.278 hours <br />0.00165 weeks <br />3.805e-4 months <br /> - begin lnerease in power, secondary system conductivity corrected.

1. _

11-04-81 Continue increasing power to 100%.

11-05-81 0315 hours0.00365 days <br />0.0875 hours <br />5.208333e-4 weeks <br />1.198575e-4 months <br /> - reduce power for high secondary conductivity.

Conductivity corrected and begin power increase at 0950 hours0.011 days <br />0.264 hours <br />0.00157 weeks <br />3.61475e-4 months <br />.

Haached 100% at 2310.

11-11-81 1600 hours0.0185 days <br />0.444 hours <br />0.00265 weeks <br />6.088e-4 months <br /> - reduce p3wer : bo 90% for high QPTR (N43) indication.

11-12-81 QPTR corrected by INC/FXO calibration, increase power to 100%.

11-16-81 Reactor tripped @ 0258 on low steam generator level due to low feed pump suction.

Began power incr, ease at 1000 hours0.0116 days <br />0.278 hours <br />0.00165 weeks <br />3.805e-4 months <br />.

11-17-81 Reached 95%, QPTR was high (N43).

Reduced power to 90%.

11-18-81 QPTR corrected by INC/EXC calibration.

Began power increase at 1700 hours0.0197 days <br />0.472 hours <br />0.00281 weeks <br />6.4685e-4 months <br />.

11-19-81 Reactor tripped at 1706 on low steam generator level due to low feed pump suction.

Tripped again during power increase at 2112 hours0.0244 days <br />0.587 hours <br />0.00349 weeks <br />8.03616e-4 months <br /> on low steam generator level.

11-20-81 Power increased to 50% by 2400 hours0.0278 days <br />0.667 hours <br />0.00397 weeks <br />9.132e-4 months <br />.

11-23-81 Detector N43 declared inoperable.

11-24-81 Reactor tripped at 2009 hours0.0233 days <br />0.558 hours <br />0.00332 weeks <br />7.644245e-4 months <br /> on low steam generator level.

Detector N43 replaced.

11-25-81 Began power increase at 1700 hours0.0197 days <br />0.472 hours <br />0.00281 weeks <br />6.4685e-4 months <br />.

11-27-81 Holding power at 60% for feed pump 21 repair.

INC/EXC calibration performed to reset NI currents.

Page 13 of 14

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REFUELING INFORMATION I

DOCKET NO.: 50-311 I

UNIT: Salem No. 2 DATE: December 10, 1981

~

CCMPLETED BY: L.

K. Miller TELEPHONE: 609-365-7000x507

- ', F.ONTH:

No wmber 1981 y

1 4

Refueling information has changed from last month:

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(G YES NO X

a 2.-

Scheduled date of next refueling:

.Tanuary 8, 1983 3.

Scheduled date for restart following refueling:

Anril 3,

1983

-4.

A.

Will Technical Specification changes or other license amendments be required?

YES

_NO NOT DETERMINED TO-DATE November 1981 B.

Has the reload fuel design been reviewed by the Station Operating Review Committee?

YES NO If no, when is it scheduled?

December 1982 5.

Scheduled date(s) for submitting proposed licensing action:

December 1982 (If Required) 6.

Important licensing considerations associated with refueling:

l 7.

Number of Fuel Assemblies:

A.

In-Core

^

193 0

B.

In Spent Fuel Storage 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 March 2000 pool assuming the present licensed capacity:

Page 14 of 14

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8-1-7.R4