Text

Monthly Operating Rept for Apr 1982
	ML20052G416
Person / Time
Site:	Salem
Issue date:	05/10/1982
From:	Miller L; Public Service Enterprise Group
To:	;
Shared Package
ML20052G414	List: ML20052G413; ML20052G416;
References
	NUDOCS 8205180342
	Download: ML20052G416 (18)
	v • d • e

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AVERAGE DAILY UNIT F0hTR LEVEL 4

DOCKET NO. 50-272 1 UNIT Salem No. 1 DATE May 10, 1982 COMPLETED BY L. K. Miller i TELEPHONE 609-541-5900 x507 MD,Vm April, 1982 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY P0hER LWEL D5fe-NET). @3E-NET) 1 17 0 0

2 18 __ 0 0

i 3 19 0 0

4 20 0 0

5 21 0 6 0 22 146 7 0 23 415 8 0 24 384 1

9 0 25 488 10 0 26 826

, 11 0 27 879 12 0 28 938 13 0 29 824 14 0 30 856 15 0 31 ----

16 0 1

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Pg. 2 of 19 8.1-7.R1 8205180 3I

l GTRAT2c tW:1 M:P2r occKr: ro.: 50-272 ca:s : May 10, 1982 caeIz:zo sy: L. K. Miller r.nytoat: 609-541-5900 x507 cycuenc srx:ts

1. tk11t Name Sa1em No. 1 Notas

2. asporting Period April, 1982

3. Licensed 2==t Pcur 0+#t): 3338

4. Namuplate Rating (Gross fede): 1135

5. Desigrs Electrical Rating (Not tote): 1090

6. >== Deparv4=h1. Capacity 1 Gross tese): 1124

7. .h Wie Capacity Diet teen): 1079

8. If Cunges Occur in Capacity Ratings (Itene Ntaber 3 Strough 7) Sinca Last W, Give Raamn None

9. Ptr er Invel Ib 1etidt WJd, If Any Cast lede): None

10. amascms rar aestraians, If Anyt n/n usis atmth Year to Data casalative

11. souzs In w ng w 71.9 2,879 42,384

12. Nuncer Of kurs Anacter Was Critical 273.0 292.7 23,732.9

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13. ammetne asserve Shutdows kurs 60.8 60.8 951.9

14. Eturs Generator on-Line 212.1 231.6 22,684.9

15. Unit asserve Shutdows sours n.0 0.0 0.0

16. Gross 2=-1 maryy GeneratedcoiH) 478.831 514.281 66,608,624

17. Grees Electrical Diargy Generatedoeet) 146,770 157,560 21,811,940

18. Net r_1* ~1 mergy Generatadoes) 125,278 123,308 20,623,490

19. Unit Service Factor 29.5 8.4 53.5

20. tktit Av=41^414 ty Factor 29.5 8.4 53.5

21. Unit Capacity Factor (Using ICC Net) 16.1 4.0 45.0

22. Unit Capacity racter (Using ont Net) 16.0 3.9 44.6

23. thit Forced outage ante 53.0 50.9 31.5

24. Shutzbsis SMlari Over Next 6 femths (Type, Date, and Duration of Eacft):

N/A

(

l l

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

26. thits In Test Status (Prior tn Ccumazmal Operation):

Forecast Achieved INITW. CLMT 09/30/76 12/11/76 6-1-7.R2 INITIAI, EIs.:;xwm 11/01/76 12/25/76 Pg. 3 of 19 coeG AL CPERATEN 12/20/76 06/30/77 l

tatt namnee No toet wwcrI0tG DocxET No.: 50-272 RF3UYr MJmi APRIL 1982 UNIT 'NAME: Salem No. 1 DATE: May 10, 1982 coMrLETED BY: L. E. Miller TELEPlioNE: 609-541-5900 X507 Mente or g DUIETION GRJrritC LICDGE S GNueff CAUSE NO 00RIWCTIVE W. ME TYPE (IKJNtS) REfL Dub 48 EVDir (IOES ACrION 10 <

iencion seUYr 1 PREVDff RHCUNUG 82-016 3-14 S 672.0 B 1 - - - - WB HTEXCH Replacement of #12 Comp. Cooling Heat Exchanger.82-018 4-11 F 188.5 B 1 - - - - WB liTEXCH Replacement of #12 Comp. Cooling Heat Exchanger.82-020 4-19 F 51.6 A 1 - - - - HA BEARN0 # 7 Bearing (Turb.) high Temp.82-021 4-22 S 2.8 B 3 ---- HA TURBIN Turb. Over Speed Test, RX Trip 82-022 4-22 S 65 7 B 5 - RC FLUXMP Flux Mapping, Held 0 47% Pwr.82-024 4-25 S 7.8 B 5 ---- RC IN/EX Incore/Excore Calibration 82-026 4-25 S 6.7 B 5 -

RC IN/EX Incore Excore Calibration 82-028 4-25 F 27 A 5 ----

CH PUMPFW Feed Water Pump Problem

)82-030 4-25 F 13 .A 5 ----

CH PUMPFW Feed Water Pump Problem 1 2 3 4 5 r: Formd magon mthod Exhibit G - Instructions g

bit 1-Same S Sdieduled A-Rpl[ ment rallure(Explain) 1-Manual f r Prn = ration of Data B-ftilntenan or Test Ditry Sheets for Li&nsee

'c-Refueling 2-Manual Scram. Event > port (Int) r11e traegulatory nestriction 3-Automatic Scram. (NURfD-0161)

E-Operator Training & Limnse Duunination 4-Continuation of r-artninistrative Previous Outage G-Operational Error (Explain)

IMRher (Eglain) 5-Load Reduction Page 4 of 19

'~ "I e-1-7.R1

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twir mRinues Are r0WER MtCTIOPG DOCKET NO.: 50-272 l

nrz w r potent APRIL 1982 uMIT NANei salem No. 1 DaTE: May 10, 1982 COMPLETED BY L. K. Miller TELEPflONE: 609-541-5900 x507 se:nto 0F' DARTICH SRMTIPC LIOPEE OpgDENT CNEE APU (DRf4CTIVE

80. IRTE TYPE (It]URS) ofA90N DUbel FNFPfr QXJE5 ACTION 'IO m elon nes w r e reevner IEEURM42 82-032 4-25 S 30 B 5 ---- RC IN/EX Incore Excore Calibration 82-034 4-26 S 5.0 B 5 - - - - RC IN/EX Incore Excore Calibration 82-035 4-26 F 111.0 B 5 ---- HF FILTER Traveling Screen / Trash Racks / Canal Screens.82-036 4-26 F 8.2 B 5 - - - - CH FUMPFD Feed Water Drain Pumps82-038 4-27 F 12.4 B 5 --- CH PUMPFD Feed Water Drain Fumps82-040 4-27 F 8.3 B 5 ---- CH PUMPFD Fe.ed Water Drain Pumps82-042 4-28 F 70.7 B 5 - - - - CH PUMPFD Feed Water Drain Pumps82-044 4-28 F . ,,_ 12.0 B 5 --- HF FILTER Traveling Screen / Trash Racks / Canal Screens.82-046 4-19 F 4.2 ,

B 5 ---- HF FILTER Traveling Screen / Trash Racks / Canal Screens.82-048 4-29 F .6 B 5 - HF FILTER Traveling Screen / Trash Racks / Cant.1 Screens.82-050 4-29 F 16.5 B 5 - - - -

HF FILTER Traveling Screen / Trash Racks / Canal Screens.82-052 4-29 F 3 A 5 ----

HF FILTER Loss of Vac/Hi Back Pressure for Unknown cause Page 5 of 19 O-1-7.R1

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DOCKET NO.:

50-272 MAJOR PLANT MODIFICATIONS UNIT NAME: Salem No. 1 REPORT MONTH April 1982 DATE: May 10, 1982 COMPLETED BY: L. K. Miller TELEPHONE: 609-541-5900 x507

DCR NO. PRINCIPLE SYSTEM SUBJECT 1-ED-0208 Computer System Relocate co:ltacts on SGFP Turb Valve to give the Computer the correct information.

1-EC-0674 Ventilation System Revise Dampers to fail open (CAV12, CAV13, CAV33) 1-EC-0763 Auxiliary Feedwater Storage Tank Level Indication Alarm.

1-EC-0764A Control Room Air Conditioning Modify CAACS and EACS Systems.

1-EC-0871 Steam Generator Feedwater Add Flange to guide 1 FTEG-15 1-EC-0877 Service Water Replace Pipe on No. 1 C Diesel.

1-EC-0939 Generator Install Aluminum Plates to generator Terminal Box.

1-EC-0966 4KV Additional Level of Undervoltage Protection.

1-EC-1022 Various Perform scheduled maintance on NAMCO Limit Switches.

1-EC-1059 Aux. Flow Transmitter Replacement Transmitter with new model.

1-EC-1082 Service Water Replace controls.

1-EC-1127 Cold Shutdown Panel Add Reactor Coolant System to Panel 213 1-EC-1205 Auxiliary Feedwater Install Permanent 2" Recirculation Flow Line across Pump 13 1-EC-1212 Auxiliary Feedwater Install 8 Check Valves in Aux Feedwater Pump Discharge Piping.

1-EC-1227 Demineralizer Plant Revise Floor Drain System by installing Drain through liner with Acid Proof Bracket.

1-EC-1233 Safety Injection System Reactor Coolant System Modify Pressure Isolation Vales.

DESIGN CHANGE REQUEST 8-1-7.R1 Page 7 of 19

DOCKET NO.: 50-272

. MAJOR PLANT MODIFICATIONS UNIT NAME: Salem No. 1 REPORT MONTH anril. 1082 DATE: May 10, 1982 COMPLETED BY: L. K. Miller TELEPHONE: 609-541-5900 x507

DCR NO. PRINCIPLE SYSTEM SUBJECT 1-EC-1244 Circulating Water System Installation of Stakes between Condenser Tubes.

1-EC-1279 LP Rotors Replace LP Rotors.

1-EC-1290A Main Steam Steam Trap located down steam of 1MS-55. Valve replacements.

1-EC-1312 Containment Pressure Rework Control Valves to accept mounting of environmentally qualified Limit Switches.

1-EC-1401 Main Steam Turbine Replace thrust bearing shoe and replace ring.

1-EC-1403 Steam Generator #14 Steam Generator remove A portion of tube for purpose of analysis.

1-SC-0574 Control Air Assign Generation Numbers to ,

Instrument Valves outside redundent .

Air Supply Panel. '

1-SC-0697 Auxiliary Annunciator Add " Auto Test Fault" to Legends for Auxiliary Annunciator Points.

1-SC-0715A Auto Stop 011 Replace existing Auto Stop 011 Relief Valve.

1-SC-0785 Service Water Install 6" Drain Connection between Valves 11SW23 and 12SW23

DESIGN CHANGE REQUEST 8-1-7.R1 Page 8 of 19

DOCKET NO.: 50-272 MAJOR PLANT MODIFICATIONS UNIT NAME: Salem No. 1 REPORT MONTH April,1982 DATE: May 10, 1982 COMPLETED BY: L. K. Miller TELEPHONE: 609-541-5900 x507

DCR NO. 10CFR50.59 SAFETY EVALUATION 1-ED-0208 The design change entails a minor fix for non-Safety related equipment.

1-EC-0674 This change does not involve an unreviewed safety question. The damper positions being modified were not used in the calculations for any presently performed safety analysis 1-EC-0763 Neither an ETS change is required nor does a U.E.Q. exist because all proposed changes are internal to the plant and do not affect directly or indirectly air, water or solid waste releases to the environment.

1-EC-0764A The installation of 3/16 inch plate above the corridor between control rooms at '14' line & 'BB' line at EL.122' in the Aux. Building does not require a change to the FSAR or present an unreviewed safety question.

1-EC-0871 The modification to the guide for the exhaust from No. 11 Steam Generator Feed Pump Turbine will not affect the Tech. Spec., FSAR or create any unreviewed safety question. The area of work does not involve any safety related equipment.

^

1-EC-0877 The addition of break flanges in the supply piping to the No. 1C Diesel Generator Jacket Water Cooler does not alter the original design concept of the piping system in any way. An unreviewed safety question is not involved.

1-EC-0939 This is a non-safety related system and as such the modification will not affect safety margin or have any safety implications.

Added plates reduce electrical resistance and alleviate an over heating problem. No change in function or operation of unit and no change to air or water emissions.

1-EC-0966 This installation requires that cable be installed 'between 4KV vital buses & Aux. control relay cabinets, in accordance with our Standard Cable Control Manual Procedures; therefore no USQ exists.

1-EC-1022 This DCR is written to ensure proper maintenance is performed on installed NAMC0 limit switches during the 1980 outage. This maintenance will increase the future reliablility of the switches and does not in any way affect the function of the said switches.

1-EC-1059 The design change is for a direct replacement of transmitters not i involved a functional or logic change to the System. Therefore an USQ is not involved.

1-EC-1082 This DCR simply upgrades an existing system with a better quality instrumentation. No functional change is involved; therefore no USQ is present.

4

DESIGN CHANGE REQUEST Page 9 of 19

DOCKET NO.: 50-272 MAJOR PLANT MODIFICATIONS UNIT NAME: Salem No.1 ;

REPORT MONTH April, 1982 DATE: May 10, 1982 COMPLETED BY: L. K. Miller TELEPHONE: 609-541-5900 x507

DCR NO. 10CFR50.59 SAFETY EVALUATION 1-EC-1127 This modification does not involve an unreviewed safety question.

The indicators being modified were not used in the calculations for any presently performed safety analysis-further, their failure does not constitute a new hazard not previously analysed.

1-EC-1205 Installation of the pipe access through this shield will not affect safe shut down of the reactor er the structural integrity of the shield or building structure. No UEQ is involved.

1-EC-1212 This DCR will not alter or add to effluent releases specified in the ETS or NPDES permit, nor result in an UEQ.

1-EC-1227 Implementation of this DCR will not affect the integrity of any safety related structure or affect safe shut down of the Reactor.

This DCR will not add or alter offluent limitations of the ETS or NPDES permit; nor result in an UEQ.

1-EC-1233 Safety injection flow paths. A failure or malfunction of any of the new valves would not compromise the ability for the Safety Injection System to provide emergency core cooling if required.

Mis-operation of these valves would not compromise containment integrity. Existing valve 1SJ 123 will still provide the required containment isolation. This modification will not alter any plant process or discharge and will not affect the existing plant impacts.

1-EC-1244 The work to be done on the condenser does not involve an unreviewed safety question or a change to the FSAR or Tec. Spec. The condenser structure integrity remains intact.

1-EC-1279 This DCR will not add or alter effluent limitations of the ETS or NPDES permit; nor result in an UEQ.

1-EC-1290A The installation of a restricting orifice will not affect in any way the basic function of the system. There is not an USQ involved and no changes to the FSAR will take effect.

1-EC-1312 This modification does not involve an unreviewed safety question. The control valves being rewerked were not used in the calculations for any presently performed safety analysis. Their failure does not constitute a new hazard not previously analyzed.

1-EC-1401 The replacement with a heavier groove wall retaining ring will correct the radial position of the thrust bearing shoes. This new design Retaining Ring does not affect the FSAR or Tech Spec. This new Retaining Ring replaces the original equipment supplied with the T.G. set.

DESIGN CHANGE REQUEST Page 10 of 19

DOCKET NO.: 50-272 MAJOR PLANT MODIFICATIONS UNIT NAME: Salem No. 1 REPORT MONTH April, 1982 DATE: May 10, 1982 COMPLETED BY: L. K. Miller TELEPHONE: 609-541-5900 x507

DCR NO.- 10CFR50.59 SAFETY EVALUATION 1-EC-1403 The tube in Row 44, Column 62 in steam generator 14 has the highest amount of wall thinning. The tube will be cut approximately 4" above the tube sheet on the cold leg side through access from primary side manway.

At the other end, that tube will be cut approximately 2" from the lower anti vibration bar. Entire tube cannot be removed because of difficulty in cutting and removing, all in the field of significant radiation.

Similar sampling for investingation has been done previously on Prairie Island 1, and Ginna.

1-SC-0574 An USQ is not involved as this DCR entails identification of equipment only not a plant operational or equipment identified.

1-SC-0697 This modification does not involve an unreviewed safety question. The legends being changed were not used in the calculations for any presently performed safety analysis. Their failure does not constitute a new hazard not previously analyzed.

1-SC-0715A The installation of a new Auto-Stop Relief Valve will improve the reliability of the Turbine Control System. This replacement Valve should reduce the wear and subsequent failure experienced by the original equipment shipped with the Unit. The proposed orificed parallel circuit should provide the desired pressure to the Auto-Stop Valve should the Relief Valve fail. The old design has proven unreliable and requires manual operation to keep System Pressure within Specification.

This design change does not affect the FSAR or Technical Specification.

1-SC-0785 The addition of a low point drain does not alter the original design concept of the piping System in any way. An unreviewed safety question is not involved.

CESIGN CHANGE REQUEST Page 11 of 19

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SDRTFD BT SALFM GFNFRATTNn STATTON DEpADTMENT, WO#K_08 DER NO._ SAFETT RFLATFD EDUTP"ENT MnRM nRDER L0n . _ . . _ _ . . . . _ On01 lWO!K

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s DESCRIPTION OF PenRLEN, GRnUND AT OC14-7 NT(PRT VALVFS). _ _ _ _ _ _ _ _

f P 'd CnenECTTVF AcTInN, F0HND TMO RURNT WIDES TN RC14-7. REPLACEn "I WIRES ann ANPHENnL CONNECiteRS.._ __ .. __ _ . . _ _ _ _

00310 M DC RU9,1A !?5V

'd DESC#IPTTON nF PDnRLFM, THF IG9x ACR FOR 11 #DO nRTVE VENT FAN HAS b DRnUND ON CONTROL POWED.

CORRECTTVF ArTInN, F0llND OROUND ON CONNECTOR AT MTSSLE SHTELD 1

D REPATRFD CONNECTnR.

COR402 4 EMREG OTESEL,lB n

__ . . . ___.__. ___. . D E S C R I P T I O N O F P R n R L F M , JACRFT MATFR HEATER ALAR 4 _ . _ _ _ .

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l 'iC022T3 M VALVE,14AF21

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nESCRIPTTON OF P#n"LFM, REPLACF VAlVF TNTEONALS.

CORDECTTVE ACTION, REPLACED VALVE INTERNALS. _ . _ _ _ _ . . _ _

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L jC02393 M VALVE.15SN54 nESCpIPTTON OF PDnRLFM, CEMENT LYNTND TN PTPF TNTERFFRES MTTH C "! VAlvF OPFRATTON.

~ ~ ~ - ' ' ~ cnRoECTTVF AtTInN, DEMOVED SOME CFMENT LINING. *Nn0THED EnGES i4 ann RLFNDEn WITH RFL70NA-R MFTAL.

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' MORTED BY SALFM GFNFRATTNG MTATTON SAFETY RFLATED EQUTPMENT MnRK ORDEO Lnn _._ 0007

'1DEP A%TMENT , _ WORK . 0# DER . NO.__.. _..

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g NUuRER nEPT EDUTPMENT IDENTIFTCATTON FXPLANATTON nF MnRK PERFnRMEn x[j935529 M VALVE 11AF21 "l . nESCRIPTION 0F F#nRLEMe. OPEN, TNSPFCT ann nVERHAl'L IF.NECESSART.. .____. .___._._

' CnRRECTIVF ActinN, PLilG HAD SMALL CtlT. MACHTNFD AND INSTALLF.D M VALVE,14AF21

[035550 nESCRIPTION OF..PRnRLFM, _.

nPEN, INSPECT AND DVERM AlfL IF .NECESS ARY.___ ___

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CnR#ECTTVF acTinN, PLilG HAD SMALL C11T. MarHTNFD AND INSTALLFD

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9378E7 M VALVE,1NSt3R

DESCRIPTION.0F PRn9LEM, ._ REPLACI;. REWORK DISC, PLilG.AND SEAT ON._ .. _

" tMM192. SEATTNG ARFA HAS STEAM CllTS.

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REPLACED PLUG ASMT, CANE AND SEAT RING.I._..___

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nE SCEI'P'T T ON' nF P#nRLFMe VALVF FATLFD LFAK RATE TFST.

.CORRECTTVE ACTION, #EPLACED STEM ANO GASKET. _ _ _ . _ _

"442317 M VALVE.11SW65 DU~CRIPITON'nF PR'nRLFM[ TNSPFCi VALVF FLANCE SilRFAbE9 50R FVfD[NCE

nF CnRRORInN ATTACK. VFRTFY THAT A CnATING w nF REL70NA EPONY WAS APPLIFD. . _ _ _

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TNSTALLED WITH NEN NUTM ann PnLTS.

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C89I99 M Pi!MD ,11 CHILLED WATER

" DESCRIPTTON nF PenRLFM, PUMP WAS I/S FnR I.s HnURS WTTH MUCTTON O > VALVE 9 Hilt. TNSPFCT FOR PUMP / MOTOR DAMAGE.

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' DESCRIPTTON OF P#nRLFM, PUMP PLACEn TN SERVICE FnR VFNDER O " SERVTCTNC OF CHILLFR UNIT. CHILLFR NOT AVAILARLE FOR COOLING. SnMETTME LATER, 230V_ _.

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EPLACFD ALL RFA#INGM, SFAtS AND SHAFT.

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'! DEPARTMENT..WOPM. ORDER NO..

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't ORD EC DEPT EDUTPMENT IDEhffFTCATTON FXPLANATTON OF mnRK PE# FORMED r [NUM8FR

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NEW SUPPLY ATR RFGULATOR. - . _ _ .

000341 P VALVE.173W273 ... - - . . . . . . .

DESCRIPTTON OF PRnMLFM, TRANSMTTTER FATLFD.

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" LINKAGF. EYF#CTZFD VALVE UNTTL IT REnAN TO

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DESC#tPTTON OF P#0RLFM, PLEASE CALTBOATE 2nS IRPT, 17 STEPS LOW.

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_ _ . _ _ . .CORRECTTVF ACTION . AT 27A STEPS FDLLOWING 1HR WAITe OUTPUT WA_. . . . . _ _ .

77 MTL LOW. ADJUSTFD SPAN, ZFRn OK. 2 MTFP LOW AT 100, READJUMTFD. 7EPO AND 90 STFPS

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SORTED RV 5ALFM GFNFR4TTNG 9TATTON DEPADTMENT,. WORK.0# DER.NO._ _ SAFETY RELATED EDUIPMENT WORM nRDER L0f; _. . 0001 WOIK __ _. _ . . __

DRDE2 .

nEPT EDUTPMENT IDENTTFTCATTON FxPLANATTON nF MnRK PEDFnRMEn

, } NUMBER

~

C5555U P F'h'RF' PRnIF'ETInN f

nESCRIPTION OF PRnMLFM,_ FIDE.ALADMS INTTTATE HTGH FLitz AT SHtlTDOWN._.._ _ __.. ._

' AND CONTAINMFNT FVACllAfinN.

CORRECTTVF AhTION, RERUTLT ALL TRTax CONNFCTupS AT PREAMP AND . , _ _ _

MR DDAWER. TOIFD SFVFRAL TTMFS in RESEARCH I " SR STILL AFFFCTED RY WFLDING AND OTHFR SPilRT0tlS SIGNALS AND TS CONSTDERFD NORMAL.. . -.

O C0fiTT P PtIM#,13 REACTnR Cn0LANT

' nEMCRIPTTON nF PenRLFM, SEAL LFAKOFF RFAnING ERRATTC.

o3 '

.__CORRECTTVE. ACTION ._. . REPLACFD FLOW SENSOR FnR HTGH FLOW._ .__ _.

TRAN9MTTTER.

C0i778 P PUMP 14.REACinR C00LANT. _ . _ . . . __. _

'O " DESCRIPTTON OF PRnRLFM, SEAL LFAKOFF NOT INDTCATTNC. FLOW CHECKEn LOCALLY AND FLOW WAS PREMENT. . . _ . . _ _ _ _ _ . _ _

C' CnRRECTTVF AhTION, FLnW SFNMOR JAMMFD. IN97 ALL En NEW SENSOR.

h~3be'2~ P CONiA5NMENT F A N uni'L' ~ bN'T T,11

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DESCRIPTTON nF PRnRLFM,' LIMIT SWITCHFS ON ROUGMING FTLTER DAMPERS. . _ . _ _ _ _ _ _ _ _ _

i WILL NOT MAKF UP.

C *

'- CnRRECTTVE Ar.TInN, REAR DAMPER WOHLD MOT MOVE.' CHFCMEn

CYLINDERS AND MATNT FRFEn DAMPFRS.

L d "942156 P VALVES,ISS48&lSS49 _ _ . . . . - -

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[Page16of19

e, l ' SDNTFD BY

- SALF4 GFNFRATTNG MTATTON

. DEP A~wf MENT . , WORK. ORDER _NO. MAFETY RFLATFD EQUTPMENT wnRK ORnE# LOG ____._ - _ __0006 4

^

w0 K __ .__ __________

.0RDED NU48FR DEPT EnUTP4ENT IDENTTFTCATTOW FuPLANATTON OF wn#w PERFORMED e

DEMC#IPTTON nF PDnRLFM, V ALVFS LF AKING THROUGH OtlRTNG LE AK RATF n " TESTTNG. STROKF VALVFS AND AMSitRF FULL

" _ _ . . _ _ _ - _ . CLOStlRE. . . . . _ . - _

CnPRECTTVF AcT!nN, MT90 ken VALVFS.' ROTH STIrKTNG ON LIFT OFF.

SUPPORTED MATNT FOR VALVF #EPATR.. . _ _ . . . . . . _ _.

O C42402 P COMPRESSOR,12 WASTE GAS '

DEM'C#IU TON OF P#nRLEM,~ COMPDF95nR STARTM AND TRTPS Ot[T AT 57 MEC.

y "i ALMO SHOWS NO DIMCHARGF PRFSSUDE.

, ~

~

CnR#ECTTVF AcTinN, REPLACFD FLAPPFR AND N0Z7LF ON CONTROLLE#

. , [2' FOR 12WGP2 AND TTGHTFNFD SFNSING LINF TO

" _ . _ _ . . _ _ _ . _ . _ RELLOMS TNSIDE CONTROLLER. _ _ _ _ _ . _ _ _ . _ _ _ _ .

O 4852h P VALVEel5SwSA . _ _ , _ _ _ . _ _ _ .

" nEMC#IPTTON nF P#nRLFM, NO ODEN TNOTCATInN. R20375 0 n

" ._CDRRECTTVE.AcTInN,. _ #ENENEn RRnKFN BOACKET AMD OFFECTIVE __ .

" R0nSTER DELAY. MAINTTNANCE RFNFWED

'L r AUTTFRFLY VAtVF. STRnKFD AND SFT LTMIT 9 WITCHES. 820327 "i

!U 485260 P VALVE, IPR 15

' DEMC#IPTTON OF PPnRLFM, val.VF WILL NOT OPERATE F#04 00NT90L #00H.

L- 1 R2n371

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L TOTAt_ LINEM s on0127 dTOTAL 4-#ECS s 000n25 _. . .____ __._. . _ ..___. _ _ _ . . _

U ILART UPDATF . _ . _ _ . . _ .

$C20505__._. _ _ _ _ _ _ _ _ _ _ _ . _ _ .

1123454 U jFNTER COMMANns Pi END OF Rt'N . ...

M v4 ja3%KPT_ PRINTS _

L 4

<iPage 17_.of 19 v

l SALEM UNIT 1 OPERATING

SUMMARY

REPORT APRIL 1982 4-11-82 Start of fuel cycle 4. Reactor critical at 0600 to on April 12. Zero power physic tests were completed 4-14-82 by April 13. However, prior to mode 1 operation, the repair of two valves necessitated going to mode 5.

4-19-82 Reactor critical at 1253 hours0.0145 days 0.348 hours 0.00207 weeks 4.767665e-4 months and power increased to 14% to synchronize generator with grid. However, power was reduced to zero at 2130 hours0.0247 days 0.592 hours 0.00352 weeks 8.10465e-4 months due to high turbine temperature on number 7 bearing.

4-21-82 Reactor power increased to 29% for 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months (minimum load on generator) to stabilize temperature on turbine prior to overspeed test.

4-22-82 Reactor tripped at 0945 hours0.0109 days 0.263 hours 0.00156 weeks 3.595725e-4 months while generator was being removed from grid to perform overspeed test.

Reactor critical at 1108 hours0.0128 days 0.308 hours 0.00183 weeks 4.21594e-4 months , test completed, and power was increased in accordance with reactor startup sequence.

4-23-82 Maintaining power at approximately 48% for incore/

excore calibration.

4-24-82 Maintaining power at approximately 48% - Incore/excore calibration repeated because of faulty nuclear instrument meter for N41 lower detector current.

4-27-82 Power increased limited to approximately 83% because of maintenance requirements for number 11 Heater Drain Pump.

i l

l l

t l

l j

Page 18 of 19

l REFUELING INFORMATION DOCKET NO.: 50-272 UNIT: Salem No. 1 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: October 16, 1982

3. Scheduled date for restart following refueling: December 26, 1982

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? August, 1982

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

September, 1982 (If required)

6. Important licensing considerations associated with refueling:

None

7. Number of Fuel Assemblies:

A. In-Core , 193 B. In Spent Fuel Storage 160

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 pool assuming the present licensed capacity: September, 1996 Page 19 of 19 lil LJRA

ML20052G416

Text

SUMMARY

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