ML18081B201

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Monthly Operating Rept for Feb 1980
ML18081B201
Person / Time
Site: Salem PSEG icon.png
Issue date: 03/10/1980
From: Miller L
Public Service Enterprise Group
To:
Shared Package
ML18081B200 List:
References
NUDOCS 8003180500
Download: ML18081B201 (15)
v • d • e


Text

M)NlH February 1980 AVERAGE DAILY UNIT POWER. LEVEL IDCKET NO.

50-272

~~~~~~~~

UNIT Salem fll DATE March 10, 1980 COMPLETED BY L. K. Miller TELEPHONE 609-365-7000 X507 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL 1

2 3

4 5

6 7

8 g

10 11 12 13 14

15.

16 Pg.

2 of 16 8.1-7.Rl (MWe-NET)

  • 1,077 936 1,102 1,117 1,100 1,086 1,007
  • ~

939 1,043 891 1,059 899 1,106 635 0

0 (MWE-NET) 17 403 18 1,039 19 986 20 1,114 21 1,112 22 1,108 23 1,111 24 1,085 25 1,088 26 998 27 0.

28 0

29 32 30 31

~

50-272

occKET ro.: _________ _

CATE : __

M_a_r.... c... h-.....-l_o.... '--"'1;.;:;.9.-8_0 __

a::ME'IE.raD BY: __

L_.;......K_._M_i_l_l..;;e..;.,r __ _

~:

609-365-7000 X507

l. UnitNane: ______

s_a_1_e_m_#_1 _______ _

Notes:

2.

Reportinq Period: __

~F.;;;;eb=ru.;;;;a.;;;;r;;.y~l=-9;;..;8;;..;0:;.._ ____ _

3. LicenSed Thernal Pcwer (l+lt) : -----=3,...3,..,,3,.,,8,........ __ _
4.

Naiieplate Rating (Gmss !+lei : _____

1_1_3_5 ___ _

s.

Design El.ectr:i..cal. Rating (Net !+le): __

1_0_9_0 ___ _

6.

Max::iimJm. Dependable Capacity '(Gross l+le):

1124

7.

Max::iimJm. Dependable Capacity (Net K'1e) :

l 0 7 9

8. If Changes Occur in Capacity Ratings (Item NUIIi::er 3 Tmough 7) Since Last Report, Give Reason:

NONE NONE

9.

Power Level To Which Restricted, If Aey (Net !+le) : -----------------------

10.

Reasons For Restrictions, If Aey: __ N_O_N_E-------------------------

'Ibis M:nth Year to Date CUnul.ati ve

u. Hcurs In ReI,:orting Period 696 1,440" '

1

'23,401
12.

NulICer Of Hour's ~ctor Was Critical 653.2 1,349.6 11,437.6

13.

Reactor Reserve Shut:a::Jwn Iburs 0

0 22.7

14.

Hours Generator On-Line.

568.6 1,250.3 10, 781.4 lS. Unit Reserve Shutdown Hours 0

0 0'

16. Gross 'lbemal. Energy Generated (!-fiH) 1,780,714 3,570,430:..

31,106, 727

17.

Gross Electrical Energy Ge!lerated (MWH) 602,650 1,188,730 10,356,230

18.

Net Electrical Energy Generated (MWH) 574,704 1,130,986 9,760,576

19. Unit Service Factor
81. 7 86.8 46.1
20.

Unit Availability Factor

81. 7 86.8 46.1
21. Unit Capacity Factor (Using MOC Net) 76.5 72.* 8 38.7
22. Unit Capacity Factor (Using DER Net)
75. 8 72.1 38.3
23. Unit Forced Outage Rate 18.3 13.2 42.3
24.

Shutdowns Scheduled Over Next 6.Malths (Type, Date, and Duration of Each) :

NONE

25. If Shut Down At End of Report Period~ Estimated Date of Startup: ______

N_/_A _________ _

26. Units In Test Status (Prior tc Camercial. <:p!ration) :

8-l-7.R2 Pg.

3 of 16 Forecast 09/30/76 11/01/76 12/20/76 Achieved 12/11/76.

12/25/76 06/20/77

ID.80-082 80-034 80-035 80-039 80-041 80-043 80-045 80-046 80-047 80-049 1

DATE 2/2/80 2/7/80 2/8/80 2/8/80 2/10/80 2/10/80 2/11/80 2/11/80 2/12/80 2/14/80 F: Forced S:

Scheduled Page 0-1-7.Rl 4 of 16 TYP~

F F

F F

F F

F F

F F

2 UNIT sm.mx.ws 1\\ND PCMER REOOCTIONS REPORI' MJNI'H February 1980 METIDD OF OORATICN

~

SHUIT.100 (llXJRS)

IXMN REAC'IDR 0

A 5

0 A

5 0

A 5

0 A

5 0

A 5

0 A

5 0

A 5

0 A

5 0

A 5

60 A

3 Reason:

A-Equi~t Failure(Explain) a-Maintenance or Test C-Refueling O-Regulatory Restriction LICENSE EVENT REPORI' I E--Operator Training & License Examination F-.Administrative G--Operational Error(Explain)

H--Other (E>!plain)

SYSTEM ClH'CNFNl' CODE4 CODES HH FILTER HH FILTER HH FILTER HH FILTER HH FILTER HH FILTER HH FILTER HH FILTER HH FILTER HB MECFUN 3

~thod:

1-Manual 2-Manual Scram.

3-Automatic Scram.

4-Continuation of Previous Outage 5-Load Reduction 9-0ther 50-272 DOCKET NO.: ________

UNIT *NAME:

Salem Ill DATE:

March 10, 1980 COMPLETED BY:

L. K. Miller TELEPHONE: *609-365-7000 X507 CAUSE l\\ND CORREX:'l'IVE ACTION TO PREVENI' RFL'URRENCE Clean Cond. Pump Suction Strainers Clean Cond. Pump Suction Strainers Backflush 11,12 Heater Drain Pumps Clean Cond. Pump Suction Strainers Clean Cond. Pump Suction Strainers Backflush 11,12 Heater Drain Pumps Clean Cond. Pump Suction Strainers Clean 11,12 Heater Drain Pump Suction Strainers*

Clean Cond. Pump Suction Strainers

  1. 14 due 4

Steam Generator Lo-Level, Lo-Flow to 14BF19 Valve Positioner Failure Exhibit G - Instructions for Preparation of Data Entry Sheets for Licensee Event Report (LER) File (NURID-0161) 5 Exhibit 1-Sane Source

tl>.80-055 80-060 DATE TYPEl 2/19/80 F

2/26/80 F

5 of 16 Page B-1-7.Rl OORl\\TIOO RFA']()N2 (IDJRS) 0 A

. 67.45 A

UNIT SHl111XMNS 1\\ND PCMER RIDX:TIOOS REPORT MJNm February 1980 MEnm OF SHl1ITIK; LICENSE SYSTEM

<DIPOOENl' mm EVEN!'

OJDE" OJDE5 RFJl.C'IDR REPORT I 5

HF FILTER 3

HA INSTRU 50-272 DOCKET NO.: _______ _

UNIT *NAME:

Sa!Lem ffl DATE:

March 10, 1980 COMPLETED BY: _L_*._K_._M_i_l_l_e_r __ _

TELEPHONE:

609-365-7000 X50]

CAUSE AtlJ OJRREO'IVE ACTIOO 'ID PREVENI' RmJRREN::E Clean 13A Circ; Wate.r Pump Waterbox Stator Water Cooling Flow Switch Failure

  • MAJOR PLANT MODIFICATI-REPORT MONTH February 1980
  • DCR NO.

PRINCIPLE SYSTEM lED-0143 125 VDC lED-0159 Biocide Monitoring lED-0252 Circ. Water Structure lED-0305 D.G. Ventilation lED-0317 Fire Protection lED-0329 Service Water lED-0361 Met Tower lEC-0371 13kV lEC-0384 Vital Heat Tracing lET-0406 Service Water lEC-0418 Waste Liquid 1EC-0611A S.G. Feed lEC-0628 eves lET-0635 eves lET-0685 S.G. Feed lEC-0716 Aux Feed

  • DESIGN CHANGE REQUEST 8-1-7. Rl DOCKET NO; 50-272 UNIT NAME :*l*.:.ira-l_e_m_l/.-,1-------

DATE: March 10, 1980 COMPLETEn BY: L. K. Miller SUBJECT Authorized Use of 6°Post LCU-33 CellE Install Biocide Monitoring System Install Additional Cathodic Protection Install Automatic Dampers for Fire Protection Install Additional Hose Station in Control Room Area Install CuNi Line Spoolpiece at 11ST900 Install Improved Line Drivers for Data Transmission Replace 13kV CV-8 Relays to Upgrade Protection Relocate VHT Alarms to Doric Alarm System Evaluate Performance of 11ST900 Spoolpiece Modify WMHUT Piping to Allow Chem-Nuclear Processing Install Instrumented Feed Nozzle Fittings Add Spacer Plates in Charging Pump Equalizing Line to Allow Performance Evaluation Conducted Charging Pump Mini Flow Test Install LVDT's and Accelerometers to Monitor Movement of 14 S.G. Feed line Install Upgraded Hanger for 1DR7 Page 6 of 16

  • MAJOR PLANT MODIFICATIW REPORT MONTH February 1980
  • DCR NO.

PRINCIPLE SYSTEM lEC-0720

s. I.

lMD-0133-Hearter Drain 11 lPD-0122 DM Water lSC-0026 Diesel Generator lSC-0038 Steam Generator lSC-0069 Main Generator lSC-0157 Rod Position

  • DESIGN CHANGE REQUEST 8-1-7. Rl DOCKET N0;~0-272 UNIT NAME:~:u:;*o~a-l_e_m~_-li-~1------------~

DATE:

March 10,: :_1980 __

COMPLETEn BY: L. K. Miller TELEPHONE:

609-.365-7000 X507 SUBJECT Increase Containmen~ Sump Screen Area Install Improved Line Shaft Bearings Install Remotely Operated Tank Fill Valves Install Fuses in EVS and GVS Circuit to Isolate Potential Multiple Faults Install Remote ~T Monitoring System Incorporate Westinghouse AIB 7807 to Improve Gas Circulation Install Prototype Rod Position Indication System Page 7 of 16

MAJOR PLANT MODIFICATIO~

DOCKET ~:

50-272 UNIT N~

Salem If 1

  • DCR NO.

lED-0143 lED-0159 lED-0252 lED-0305 lED-0317 lED-0329 lED-0361 lEC-0371 lEC-0384 lET-0406 February 1980

~~~~~~~~~~~~

DATE:

March 10, 1980 COMPLETED BY:

L. K. Miller

~~~~~~~~~~~~

TELEPHONE:

609-365-7000 X507

~~~~~~~~~~~~

10CFRSO. 59.

SAFETY EVALUATION Change of battery cell external connections in no way alters the capacity or performance data listed in.the Technical Specifications.

The revisions to this DCR are in no way safety related as the biocide monitoring project is a test operation external to the station.

This DCR will not affect any safety function of the system involved.

The proposed changes do not inv~lve any of the criteria associated with an unreviewed safety question per 10CFR50.59.

The subject change does not affect any presently performed safety analyses nor does it create any new safety hazard.

The bases of the Technical Specifications are not affected.

The installation of this hose station does not increase the probability of occurrance or increase the consequences of an accident or malfunction of equipment important to safety previously evaluated in the safety analysis report and does not create the possibility for an accident or malfunction of a different type than any evaluated previously in the safety analysis report.

The addition of this hose station does not affect the bases of the Technical Specifications.

This hose station is to be added in the listing of Fire Prot. Tech; Spec.

Addition of item to listing of Tech.

Spec. to be accomplished per Lie. Change Request 78-10.

Implementation may proceed pr<ior to Lie. Change.

The proposed change involves a temp0rary substitution of a por.tion of**

non safety related service water piping located in the turbine building for material testing purposes.

This change does not affect any safety related system or equipment.

It does not affect any Tech. Spec. and does not require any additional safety evaluation to be performed.

It merely changes the 0-lVDC output of the transformer to a 0-1 MA.DC output.

Safety related equipment will not be affected and Tech. Specs. are not involved.

This DCR interfaces with existing alarms an indicating circuits to improve without degrading performance of safety related circuits and therefore does not involve an unreviewed safety question as defined in 10CFR50.59.

The proposed change involves a temporary substitution of a portion of non safety related service water piping located in the turbine building for material testing purposes.

  • DESIGN CHANGE REQUEST Page 8 of 16

MAJOR PLANT MODIFICATIO~

DOCKET ~:

50-272 UNIT N~

Salem Ill

~~~~~~~~~~~~

DATE:

March 10, 1980 REPORT MONTH February 1980

  • DCR NO.

lEC-0418 1EC-0611A lEC-0628 lET-0635 lET-0685 lEC-0716 lEC-0720 lMD-0133-11 lPD-0122 lSC-0026 lSC-0038 lSC-0069 lSC-0157

~~~~~~~~~~~~~

COMPLETED BY:

L

  • K. Miller

~~~~~~~~~~~~

TELEPHONE:

609-365-7000 X507

~~~~~~~~~~~~

10CFR50. 59.

SAFETY EVALUATION This design change does not affect any presently performed safety analyses as the system is utilized only under manual control of the Operations Department.

It does not create any new hazards as it is similar to other pipe systems.

It does not affect the bases of the Tech. Specs. as the system is not addressed in *.the Tech. Specs.

The functional operation of the system is not changed.

This change is implemented for monitoring purposes only.

The equalizing line is a low pressure line.

If the pressure gauge tubing were to rupture there would be not adverse affect to safety related equip-ment in area or to safe shutdown of the unit.

There is no change to FSAR or Tech. Spec. by implementing this DCR.

The operation of charging/safety injection pumps 11 & 12 on_,min; flow with equalizing line spacers installed does not present an unreviewed safety question.

A change to the Tech. Specs. or FSAR soes not exist.

Installanion of the monitoring equipment does not impair the integrity of the related plant/piping equipment, does not affect any presently performed safety analysis nor does it create any new safety hazards.

The bases of the Tech, Specs. are not affected.

1DR7 valve is safety related and was qualified to meet Seismic Class I loading.

This design change will provide additional conservatism in the safety analyses on the flow blockage of the containment sump screen in the Bost-Loca condition.

We have reviewed the design change and have found t~at it does not affect any safety related systems or components.

This change is not safety related and does not affect safety related equipment.

Safety re1ated equipment will not be affected.

This change will increase the margin of protection of the equipment and operation.

Design change made to comply with Tech. Spec. change.

Not a safety related change involving an USQ.

These changes dow not affect safety function, decrease margin or jeopardize safety analysis.

The changes are being made to increase unit reliability.

This DCR in not safety related nor does it affect any safety related equipment or system.

Page 9 of 16

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90\\J235 906144 Dr) TE Wl=<:ITTEN 09 14 79 07 19 79 SALEM GENERATING STATION MONTHLY REPORT OF SAFETY RELATED REPAIRS PROBLEM DESCRIPTION

      • MAINTENANCE DEPARTMENT WORI\\ ***

Br.Yrr1::i:r1.LB

.L 2~'iV c;1;LL§_Z_L"~ 2_ LD_VJ_ *--- *-----

BrYJ'TEFr1*.l(1 125\\.'

PERFO~A SfNGLE CELL CHARGE ON CELLS Dr:1TE COi*iPLETED 09 J. 5' *79

.l2 :31 '79

-9 lr:<ir7-0".2V5!3v __________ -- --

Vr-'1LV1::*-15~J:','~, --*.. --*--.. *--***---

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.l 0.I.! *7 'i' 9f,,lJ.98--iO_l_6_7_9_ --------- --*--

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914199 10 J.6 '79 Page-Ta-* of 1-6-----------*---- *- --*

Pf.1Cl\\Ii'1G u::r:il\\

.I. ~5 S TE{.fri. -C1ENEl'i:(1 TOI=<: FEEDWr"1 TER LI i'IE THERMOCOUPLE WELL LEAl\\ING

  • *or:iL*)L:;:-**1~~sw7s ____ - - ----

CANNOT BE CLOSED,

~AHMED

-~IR LO~R;-ib6-ELEVATION INNER DDOR FAILED AIR FLOW SURVEILLANCE DI E!:iECr-:i. li _____. --------- -..

HORN ON ALARM PANEL INOPERATIVE

  • --Bt1TTER'Y--.IJ1 *12:'5V PERFORM SINGLE CELL CHARGE ON CELL.LB Br.Yl'Tl:Jrr rn.L2:'5V CELLS 7.L9 i 56 WILL NOT COME WITHIN

... SPECIFii':i:1TIDi'l Br'1TTEl~'i'"-I'f.i.. :L2~N CELLS 7 & 47 WILL NOT COME WITHIN SPEC I FI(~rYr:Di:lS.

El rYI' T EJ((.l (1

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'5(} WILC.-i-JDT COME WITl*II°i'l SPEC IF I Cr-'.1TI Oi~S (i ;,~ (i8 80 02 06 f:hi

\\i2 12 BO (i2 L:\\ 80 (i2 04 BO

.1.0.1.2 l't l <:1 2B '7'1

.l.(i 2't ?'I 0001 DESCRIPTION OF REPAIR CELLS CHARGED BY SINGLE CELL FURi*i(1i-JlTl::If -------*-----*

,.:1s Ih!STl~UCTED-----*--------- - -.

REPLACED WITH CELLS FROM

  • if2ri 125V Br:iTTEl'rT i=<:Ef'lj1cEt1wffHtELLS FTRfrl - --- ---..
  • B*2B L?.5V B1'.ITTEJrr REPLACED WITH CELLS FROM

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Vf'.11...VE*.l.Li*iS.1.6"7 WILL NQI.REHAIN_IN.Cl...OSED POSITION PUMP. 11 FUEL HANDLING BUILDING SUMP

_WILL __ NQJ_.15Jr:1R]_Ji.~- r'.1UTD 13 CONTAINMENT FAN COIL UNIT MOTOR COOL.ER LEAKING BrYT'TERY.Lf1 125V r:iDi) --;.:1cTr"l'f01~1~CC-8 Pl~F<- Dli: iiD0ti64 915975--oBITff-- *-

er:1TE1'rr"--n~ -f2~5v ADD ACID TO CELL 36 AS PER DR MD0666 ADD ACID TO CELL 56 AS PER DR MD066"7 91607*1 10 11 79 916898-~0=9-v~-,~1*~*=71~:;--*----***-* *-* -*

919599 92'79~54 01 31 80 911476 02 ii"l EIO Page 11 of 16 CONTAINMENT SPRAY SUPPORTS lC-CSG-5 i 6 ADD WEL6 METAL TO RESTORE SUPPORT TO IblTEi*ffJED DESIGi~

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MOTOR COOLER LEAKING 13 SERVICE WATER PUMP LOWER HOTDR BEARING COOLING LINE 1:-1i:*-1~;

  • p:(1~i~61.:.1~ -u:f:i1*:s- **-

Vf"iLVE.l.:5r:.1F;!.:5 Fu 11: ri r'*I,~-TtiT *i;i:!'.i'iC -,:-.: ING f1I f"(

  • F;r:11~*(]: tlll~i'fi'E-DETr::tTDli:

PUMP SEIZED-230V BREAKER TRIPS DF< PD09"7"7 INSTRUMENTvPD2736

()l.JTPl.Ji*-i~i::vt:."r~ W1IUES *.l6 f:iE/( 1JICE WrYfER SCREEN WON'T START ON AUTO, OJ. 2"1 BO 12 (1~) 79 02 04 El0 v... 04 ElO 10 2'7 79 f2 0~) *79 01 2.l EIO (i2 04 8(i (i2 (i<\\ 80 011(i2 DESCRIPTION OF REPAIR

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r:1D..JUSTED --~* I_ii_:[J__~!-JI_T!=.[-l_!__

1::1 REPLACED LEVEL DEVICE REPLACED WITH MOTOR COOLER FROM 124 FAN COIL UNIT AS HJS Tl~UC TED J i

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929879 Page 12 of 16 SALEM GENERATING STATION MONTHLY REPORT OF SAFETY RELATED REPAIRS PROBLEM DESCRIPTION W1LVE*;-Tvc5---*-*

NO CLOSED 'INDICATION ON BEZEL 13 STEAM GENERATOR STEAM FLOW CHANNELS I & II DO NOT AGREE HlSTl'<UiiEi-.iT rn.i.'B REPLACE GEIGER-MULLER TUBE LIQUID-WASTE MONITOR Ii-.iSHWMEiH.l.l'<!B RE~(~Ct-GEYGE~ ~ULLER TUBE DR PD0976 r::i I 1;: - Pi'.11~'r I c'LJl~r"1TE DETEC TOI'~

ONLY 1 DRIVE BELT IS LEFT Ii"STl'WHEi*rr* r-PM~'i36B OUT OF SPECITICATION FAILED DYNAMIC RESPONSE TIME TEST INSTRUMENT 1LM528 OUT-DF~--*c,~LIBl;:r\\T'i:Di-.J;*-.

INSTRUMENTv-lR12A El'~l'<(*1TIC INSTRUMENTv.LTA0016 RTD 1TE423B FAILED D(-1TE COi"iPLETED.

\\i2.1.4 BO

()! 21 80 OJ. 2.L Bii 12 24 '79 DESCRIPTION OF REPAIR f:1D.JU!:i TF.ti:i. i~EEDLi::--iJ,:iCVE--;-

ADJUSTED LIMIT SWITCH, FOUND LEAK ON-VENT-VALVE SECUF;;ED LEr:.1K RECALIBRATED CHANNEL REPLACED DETECTOR 'C' REPLACED DETECTOR 'C'

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REP1...r:1cED !'(TD.

REPLACED DC AMPLIFIER, I;

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SALEM UNIT /11 OPERATING

SUMMARY

FEBRUARY 1980 2/1 Power stabilized at 100% for the day.

2/2 Power stabilized at 100% until 0421 when a power reduction was commenced to 70% by 1033 to allow cleaning of condensate pump strainers.

Power held at 70% until 1339 when load increase was commenced to 100% by 2028.

2/3 Power stabilized at 100% for this period.

On 2/7 at 0500, at power thru 2/7 reduction was connnenced to clean heater drain pump and condensate pump strainers.

Power reduced to 70% by 0900 and a power increase commenced at 1130 to 100%.

Power stabilized at 100% by 1710 and maintained for the day.

2/8 Power reduction connnenced from 100% at 0040 to 85% by 0310.

Heater drain pump strainers cleaned and load increase commenced at 0500.

Load reduction secured at 0700 at 92% power to evaluate cause of

  1. 11 heater drain pump cavitation.

Further load reduction commenced at 1037 from 92% to 70% by 1200 to clean condensate pump and heater drain plimp strainers.

Load increase from 70% commenced at 1630 and load stabilized at 100% by 2055 for the remainder of the day.

2/9 Load stabilized at 100% until 2334 when a load reduction was connnenced to 70%.

2/10 Load reduction in progress.

By 0255, load stabilized at 70% to allow cleaning of condensate pump and heater drain pump strainers.

Load increase commenced at 0625 from 70% to 90% by 1015.

Load reduced to 85% by 1042 to allow cleaning #11 heater drain pump suction strainer and further reduced to 70% by 1530 to clean condensate pump strainers.

Load increase to 100% from 70% commenced at 1854 and load stabilized at 100% by 2400.

Page 13 of 16

2/11 Load stabilized at 100% until 1644 when a load decrease was commenced at 1644 to 85% by 1940.

Load was decreased to 85% to clean #11 heater drain pump strainers.

Load held at 85% for the remainder of the day.

2/12 Load reduction commenced from 85% at 0025 to 70% by 0330 to clean condensate pump strainers.

Load increase commenced at 0625 from 70%

to 85% by 0900.

Load held at 85% between 0900 thru 1915 to evaluate performance of heater drain pumps.

Load increase commenced at 1915 to 100% by 2235.

Load held at 100% for remainder of the day.

~2/13 Load stabilized at 100% until 1400 when load was reduced to 95% to evaluate operation of #11 main feedwater pump.

Power stabilized at 95% for the remainder of the day.

2/14 Load stabilized at 95%.

Reactor tripped at 1452 due to feedwater regulating valve failing shut.

2/15 Reactor critical at 0227.

Xenon flow test commenced.

2/16 Reactor critical most of the day.

Power increased to 4% after 2100 for turbine roll and sychronization.

2/17 Power increasing during the day.

Reached 70% by the end of the day.

2/18 Power reached 100% at 0800.

At 1000 commenced load reduction to 95%

to clean feed pump strainers.

At 1900, commenced increasing load back up to 100%.

2/19 Load stabilized at 100%.

At 0500, commenced power decrease to 75%

2/20 to clean condensate pump strainers.

At 1300, load increase commenced and power was back to 100% at 1900.

thru Power stabilized at 100% for this period.

2/25 Page 14 of 16

2/26 Power stabilized at 100%.

Reactor tripped at 2118 due to loss of stator water cooling to generator from 100% power.

Reactor sub-critical for remainder of the day.

2/27 Reactor sub-critical for this period.

  1. 14 RCP taken out of service at 0029 and put back in service at 1314.
  1. 11 RCP taken out of service at 0105.

2/28

  1. 11 RCP put back in service.

At 0245, shutdown banks fully withdrawn.

Reactor critical at 0426.

2/29 Entered Mode 1 at 1457 and going up in power at 5% per hour.

By the end of this period power was at 41%.

Page 15 of 16

~UELING INFORMATION February 1980 DOCKET NO.:

50-272 0 NIT:

Salem Ill DATE: March 10, 1980 COMPLETED BY: L. K. Miller TELEPHONE: 609-365-7000 x 507

l.

Refueling information has changed from last month:

2.
3.
4.

x YES NO Scheduled date of next refueling:

September 20, 1980 Scheduled date for restart following refueling:

November 16, 1980 A.

Will Technical Specification changes or other license amendments be required?

YES NO NOT DETERMINED TO-DATE February 1980 B.

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

YES NO x

If no, when is it scheduled?

August 1980

~---~----

5.

Scheduled date(s) for submitting proposed licensing action:

August 1980 (If Required)

6.

Important licensing considerations associated with refueling:

NONE

7.

Number of Fuel Assemblies:

A.

In-Core B.

In Spent Fuel Storage

8.

Present licensed spent fuel storage capacity:

Future spent fuel storage capacity:

9.

Date of last refueling that can be discharged pool assuming the present licensed capacity:

Page 16 of 16 8-l-7.R4 193 40 264 1,170 to the spent fuel September 1982

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