ML18082A175

Monthly Operating Rept for Mar 1980

ML18082A175
Person / Time
Site:	Salem
Issue date:	04/10/1980
From:	Miller L Public Service Enterprise Group
To:
Shared Package
ML18082A174	List: ML18082A173 ML18082A175
References
NUDOCS 8004150389
Download: ML18082A175 (19)

Text

AVERAGE DAILY UNIT POKER LEVEL

• 5 o- 2 72 DOCKET NO. ~~~~~~~~

UNIT Salem 111 DATE April 10, 1980 COMPLETED BY L. K. Miller TELEPHONE 609-365-7000 Ext. 507 March 1980 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-NET) * (MWE-NET) 1 797 17 1081 2 908 18 1112 3 1023 19 1093 4 1117 20 1094 5 1125 21 1113 6 1123 22 1108 1110 23 1068 7

1084 24 1021 8

9 894 25 1101 10 1120 26 1075 11 1098 27 1106 12 980 28 1077 1083 29 1072 13

. 1105 1113 14 30 1110 1003 15 31 16 1098 Pg. 2 of 20 8.1-7.Rl

'~

eOPERATlN:; ~ REl?OR1' e

r:x:x:xE'l' N:). : 5 0- 2 72 DATE : April 10, 1980 a::Ml?IElEJ BY: L. K. Miller TEI.EPimE: 609-365- 7000 Ext. 507

• OPERATJN:2 STMUS

l. Unit Nana: Salem Ill Notes:

2. March 1980 Reporting Period: ~~~~..;;;.;..;:;.;:_~~~~~-

3. Licensed 'll1e:mal Power (l+lt): 3338

---.,.-.....,..------

4.

5.

Na!Ieplate Rating (Gzoss 1'fi:!):

---

Design Electrical Rating (Net 1'fi:!):

1135 1090 Maxilmlm Dependable Capacity "(Gross KW!): 1124 6.

7. Maximum Dependable Capacity (Net Kole):

---

1079

8. I f Changes Occur in .Capacity Ratings (Itam NUllCer 3 'lmc1.J;jh 7) Since Last Report, Give Reason:

NO 9.

i O.

Power Level To Which Restricted, If Any (Net KW!) :

Reasons Far Restrictions, I f Any: ----------------------

NONE

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NONE

'Ibis M:lnth Year to Date Cl.lmulative 744 2;184 24,145 ll. Hours In Rep::>rting Period

12. Nuni:ler Of Hours Reactor was Critical 744 2,093.6 12,181.6

13. P.eactor Reserve Shutdown Hours 0 0 22.7

14. Hours Generator On-Line. 744 1,994.3 11 525.4

15. Unit Reseive Shutdown Hours 0 0 0

16. Gzoss 'lbe:cnal F.nergy Generated (l+IB) 2,405,018 5,959,980 33,.496 ,277

17. Gross Electrical Energy Generated (Mm) 823,870 2,012,600 11,180,100

18. Net Electrical Energy Generated(Ml'IH) 792.307 t:!.,923,293 10,552,883

19. Unit Service Factor 100.0 91.3 47.7

20. Unit Availability Factor 100. 0 91.3 47.7

21. Unit Capacity Factor (Using MOC Net) 98.7 81.6 40.5

22. Unit Capacity Factor (Using DER Net) 97.7 80.8 40.1

23. Unit Forced Qutaqe

- Rate , 0 - 8.7 40.9

24. Shutdcwns Scheduled Oller Next 6 Mcnths (Type, Date, and Duration of Eadl):

Refueling - 9/20/80

25. If Shut Down At End of Report Peric:xi! Estimated Date of Startllp: _ _ _ N..;./_A_ _ _ _ _ _ _ _ _ _ _ __

26. Units In Test Status (Prior to Camercia.l ~ti.on)  :

Forecast Achieved INITIAL CRITICALI'lY 09/30/76 12/11/76 INITIAL EUX:TRICIT'l 11/01/76 12/25/76 8-l-7.R2 Pg. 3 of 20 ~ OPERATION 12/20/76 06/20/77

~\

UNIT SlllmxMNS l\ND PCMER REIXcrIONS DOCKET NO.: 50-272

~~~~~~~~~

REPORr MJlmI March 1980 UNIT 'NAME: Salem Ill DATE: April 10, 1980 COMPLETED BY: L. K. Miller TELEPHONE: 609-365-7000 X507 ME:I'IKJD OF OORATION Sm.nTI~ LICENSE SYSTEM a:MPOOFNl' CAUSE AND OJRRECI'IVE ID. DATE TYP~ (llXJRS) ~ OCMN EVEN!' OODE4 OODE5 ACTION TO REACTOR REPORI' I PRE.VEN'l' RB:.'URRENCE 80-062 3/1/80 F 0 A 5 - - - HH FILTER Clean Cond. Pump Suction Strainers80-064 3/2/80 F 0 A 5 - - - HG DEMINX High Differential Pressure Condensate Polishers80-066 3/3/80 F 0 A 5 - - - HH PUMP XX 13A Vacuum Pump Tagged Out For Repairs80-068 3/6/80 F 0 A 5 - - - HH HT EXCH Clean 13B Condenser Water*:,Box 80-070 3/7/80 F 0 A 5 - - - HH HTEXCH Clean 13B Condenser Water Box 80-072 3/9/80 F 0 A 5 - - - HH FILTER Clean Cond. Pump Suction Strainers80-073 3/13/80 F 0 A 5 - -- HH HTEXCH Clean 13A Condenser Water Box 80-074 3/12/80 F 0 A 5 - -- HH FILTER Clean Cond. Pump Suction Strainers80-076 3/16/80 F 0 A 5 - -

- HH HT EX CH Clean 13B Condenser Water Box 80-078 3/16/80 F 0 A 5 - - - HH HTEXCH Clean 13A Condenser Water Box 80-079 3/18/80 F 0 A 5 - - - HH HTEXCH Clean 13B Condenser Water Box 80-081 3/18/80 F 0 .A 5 - - - HH HTEXCH Clean 13B Condenser Water Box 1 2 3. 4 5 F: Forced Peason: ~thod: Exhibit G - Instructions Exhibit 1-Saire for Preparation of Data Source s: . Scheduled .1\-B:)ui?IE!Ilt Failure(Explain) 1-Manual D-Maintenance or Test Entry Sheets for Licensee C-Refueling 2-Manual Scram. Event Report (I.ER) File D-Regulatocy Restriction 3-Automatic Scram. (NUREG-0161)

E--Operator Training & License EKamination 4-Continuation of F-1\dministrative Previous Outage

~ational Error(Explain)

H-other (Explain) 5-Load Reduction 9-0ther Page 4 of 20 8-1-7.Rl

UNIT SllU'IlXJolNS 1\ND PrnER REOOCTIOOS DOCKET NO.: 50-272 REPORI' MJNrH March 1980 UNIT*NJ\ME: Salem #1 DATE: April 10, 1980 COMPLETED BY: L. K. Miller TELEPHONE: 609-365- 7000 X507.

Mimm OF IXJRATIOO SlllJITIOO LICENSE SYSTEM <nn'OOF.Nl' CAUSE AM> OJRREx:"I'IVE

m. DATE TYPEl (lroRS) RFA'lON2 IXMN EVEN!' CDDE4 CIJDES ACTION 'ID RFJ\C'roR REPORT I PRIMNI' RIDJRREN::E 80-083 3/23/80 F 0 A 5 - - - RH HTEXCH Clean llB Condenser Water Box 80-085 3/23/80 F 0 A 5 - - - RH FILTER Clean Condenser Pipe Strainers80-086 3/26/80 F 0 A 5 - - - RH HTEXCH Clean 13A Condenser Water Box 80-088 3/31/80 F 0 A 5 - - - RH FILTER Clean Cond. Pump Suctrion Strainers

"

"

..

Page :5 of 20 8-1-7 .Rl'

DOCKET NO: 50-272

• MAJOR PLANT MODIFICATIO~ UNIT NAME: *e::im*_,.....e-m--1--------

REPORT MONTH March 19"0 DATE: April 10, 1980 COMPLETEn BY: L. K. Miller

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~~---~-~-

~** .'

TELEPHONE: 609-365-7000 X507

• DCR NO. PRINCIPLE SYSTEM SUBJECT lED-0062 SGFP Replace 11 & 12BF32*valves lED-0137 Hydrogen Supply Relocate the Hydrogen Storage lED- 0146 "B" Building Services Install and Relocate Services Package 2 1ED-0241A Fire Protection Additional Fire Protection to Containment and Auxiliary Building lED-0300 Station Lighting Installation of Yard Lighting lED-0304 Ventilation Automatic Damper in Electrical Pen.

lED-0311 eves Core Bore Monitor Holes in Shield Plug lED-0314 Fire Protection Install Hose Reel in North Pen.

lED-0334 WDL Waterproof WDL Trench-Drum Storage Area 1ED-0350A WDL Waste Evaporator Piping Mod.

lED-0354- Fire Protection Expand Fire Protection Package 1 1Ec~0373- Condensate Condensate Polishing Condenser Tie-Ir Package 2 lEC-0373- Condensate Condensate Polishing Controls Package 15 lEC-0373- Condensate Condensate Polishing Elect. Tie-In Package 16 lEC-0377 Fire Protection Provide Alarms on Fire Boundry lEC-0442 Containment Hatch Modify Containment Personnel Hatch lEC-0451 Safety Injection CMC Switch on 1SJ67 and 68 lEC-0474 RMS Reset lRllA and 1Rl2A lEC-0480 Fire Protection Install Additional Fire Detection

• DESIGN CHANGE REQUEST 8-1-7. Rl Page 6 of 20

- ---~ - -----~~~----------,

DOCKET NO: 50-272

• MAJOR PLANT MODIFICATIO~ UNIT NAME:~4'-.._i_e_m_l~--~----

REPORT MONTH March 1980 DATE: April 10, 1980 COMPLETEn BY: L. K. Miller

~----~-----,-,,-

TELEPHONE: 609-365-7000 X507

• DCR NO. PRINCIPLE SYSTEM SUBJECT lEC-0492 Aux Building Vent. Install Hi Temperature Alarm lEC-0534 Solid State Protection Delete Low Pressure Level Coincidence Circuit lEC-0536 Aux Feedwater Modify Controls lEC-0565 Non Rad Waste Construct Baff le and Install lEC-0590 eves Install Snubber on CVCS Charging Pump lEC-0662 Stress Calculation Seismic Stress Calculations lEC-0697 Aux Feedwater Aux Feedwater Hanger Change lMD-0081 Met Tower Installed Alarm in Control Room lMD-0131 Telephone Permanent Telephone in Containment lMD-0132 Fire Protection Core Bore Holes at Fire Doors lOD-0035 WDL Add Two Pumps and Associated Piping lPD-0075 DM Water Install Heat Trace on DM Water lPD-0124 Nitrogen Core Bore Monitor Holes in Shield Plug lPD-0141 Communications Install PA at Chlorine House lPD-0162- Non Rad Waste Additional Heat Tracing Package 1 lSC-0052 PA Install PA in South Penetration lSC-0073 TGA - Structural Installed Condensate Pump Platform lSC-0081 DM_Water DM Make-Up Water to VAC Pumps lSC-0097 Pressurizer Installed Safety Ladder Cages lSC-0122 Circ. Water Additional Cathodic Protection 25C-0215 Spent Fuel Cooling Install Chain Operator on 2-SF-35

• DESIGN CHANGE REQUEST 8-1-7. Rl Page 7 of 20

50-272 DOCKET~

MAJOR PLANT MODIFICATION~ UNIT N , Salem 111 March 1980 DATE: April 10, 1980 COMPLETED BY: L. K. Miller TELEPHONE: 609-365-7000 X507

• DCR NO. 10CFRSO. 59. SAFETY EVALUATION lED-0062 Not a safety related change.

lED-0137 This design change involves the*~relocation of H .storage bottles from the 2

interior to the exterior *of a safety related structure (the Auxiliary Building). The potential for or.consequences of this change affecting plant safety are non-existant.

lED-0146 There is no;:fundamental change to seal design or function nor to No. 1 & 2 Package 2 seals. The change enhances service life. The requirements for an unreviewed safety question are not met.

1ED-0241A This design change does not affect any presently performed safety analysis nor does it create any new hazards. The bases of the Technical Specifi-cations are not affected.

lED-0300 This DCR will not affect any safety function of the system involved.

The proposed changes do not involve any of the criteria associated with an unresolved safety question per 10CRF50.59.

lED-0304 The operation of safety related equipment associated is not affected.

lED-0311 Modification of the shield plugs over the CVC demineralizers will not affect the safe operation or shutdown of the plant. The access holes drilled in the shield plugs will be covered with an equivalent amount of steel shielding to maintain design radiation levels at the outer surface of the concrete shield plug. This change has no effect on the Tech. Specs.

lED-0314 The:bases of the Tech. Specs. are not affected by the addition of this hose station. This hose station is to be added to the list of hose stations in the Technical Specifications. Implementation of this DCR may proceed prior to submittal of License Change Request No. 78-10.

lED-0334 Applying waterproofing to areas in the liquid waste disposal trench and the drum storage vault where seepage is suspected does not alter any approved design criteria, procedures or setpoints.

1ED-0350A Minor revision to provide construction opening and temporary enclosure.

This does not alter any approved design criteria, procedures or setpoints.

lED-0354 This DCR will not affect any safety function of the system involved. The Package 1 proposes changes do ::not involve any of the criteria associated with an unresolved safety question per 10CFR50.59.

lEC-0373 Change involves addition of non safety related valves. This change w0ri.lt Package_ 2 affect any safety related function nor r~quire safety analysis or margin of safety stipulated in the Tech. Specs. No unreviewed safety question is involved for this mechanical portion of the DCR.

Page 8 of 20

• DESIGN CHANGE REQUEST

DOCKET N~ 50-272 MAJOR PLANT MODIFICATIONS~

UNIT NAMf9' Salem Ill March 1980

~---"'""'-...;.;.;;.,....;;......;._~~~~~~

REPORT MONTH, DATE: April 10, 1980 COMPLETED BY: L. K. Miller TELEPHONE: 609-365-7000 X507

• DCR NO. 10CFRSO. 59. SAFETY EVALUATION lEC-0373 This design change is not safety related and does not affect any safety Package 15 related systems or the safe shutdown of the unit.

lEC-0373 This DCR will not affect any safety -function of the system involved. The Package 16 proposed changes do* .not involve any of the criteria associated with an unreviewed safety question per 10CFR50.59.*  :

lEC-0377 This change expands the present fire protection system to meet some requirements of Branch .. Tech. Position 9. 2, Appendix A. It is not safety related and does not require a revision to any Tech. Spec. No additional safety analysis need be performed.

lEC-,0442 Worn internal parts of containment personnel air lock doors are to be replaced by new parts under the supervision of original vendor. No change in design or parts or operation of air locks will take p1ace. They will be rebuilt to their original condition and therefore, no unresolved safety question is involved as the finished condition will be as indicated in existing Tech. Specs., design drawings, Engineering Specs. and FSAR.

lEC-0451 This change will satisfy the simple failure criteria required for safety related equipment and will increase the margin of safety operation. No additional safety analysis required; no previous safety evaluation will be violated.

lEC-0474 The lRllA and 1Rl2A provide a safety related .. function. in isolating the containment on high activity due to primary coolant leakage, however, the ambient radiation levels in the containment are known to increase with time. If the leakage in the containment is known to be within specifi-cation, then the setpoint may be altered to :twice the background value.

The setpoint change will not be altered such that an excessive amount of activity could be discharged before the channels isolate the containment.

(See Engineering instructions section for further explartation ori why this change does not constitute and USQ).

lEC-0480 This design change provides fire detection for areas not previously protected. It will interface with and complement the existing fire detection system. It will not affect the function or operation of any equipment involved with the safe:shutdown of the plant.

lEC-0492 The installation of temperature monitoring devices will improve overall plant reliability by alerting the .Gontrol Room Operator to potentially elevated ambient temperature conditions in areas where equipment vital to plant aper.at.ion and safety is located. By using these devices, aetton ma¥'.'..be .. ta~eri. vefore ~any. postulated effect on safety related equipment occurs. This installation is an NRC requirement.

Page 9 of 20

• DESIGN CH.ANGE R~QUEST

DOCKET N~ 50-272 MAJOR PLANT MODIFICATION~ UNIT N.A.M9' Salem Ill

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

REPORT MONTH March 1980 DATE: April 10, 1980 COMPLETED BY: L. K. Miller

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

TELEPHONE: 609-365-7000 X507

• OCR NO. 10CFRSO. 59. SAFETY EVALUATION lEC-0534 Logic change complies with NBC positions regarding use of pressurizer level coincidence circuitry. Cha.nge improves reliability of S.I. function for small breaks in pressurizer steam space.

lEC-0536 Logic change complies with NRC question regarding operatO.r flexibility to initiate auxiliary feedwater.

lEC-0565 Installation of weir wall in Non-radioactive.Waste:Basin will not affect any previously performed safety analysis, will not affect the safe operation of the plant and doe-s:_not constitute an unreviewed safety question.

lEC-0590 The addition of 1A-CVCVE-427A does. po:t present an unrel{iewed safety question .. The vibration elirii:imator will reduce vibration of 8" suction line without need for modifying the pipe configuration. A change to both the SAR and Technical Specifications are not involved.

lEC-0662 This DCR is issued to authorize changes on safety related piping systems such as pipe hardware modifications, document updating to reflect all "as built" conditions as required by NRC Bulletin I&C iJ9-14 to verify seismic inputs. Since the majority of changes are minor support modifi-cations, document updating, etc., there is no*:unreviewed safety question involved.

lEC-0697 This DCR incorporates design changes to implement provisions of NRC Bulletin IE 79-07 which requires utilities to reanalyze piping systems using algebraic summation to combine earthquake loads. This DCR does not present any unreviewed safety question as a result of changes to pipe support and installations.

lMD-0081 Not safety related and does not affect any safety related systems.

lMD-0131 This DCR will not affect any safety functtion of the system involved. The proposed changes do ri.ot involve any of the criteria associated with an unresolved safety question per 10CFR50.59.

lMD-0132 Providing core bore holes with removal fire seal plugs does not change the SAR or' Tech. Specs. or present and unreviewed safety question. There is no change to the safety features which protect .the plant from fire hazards.

lOD-0035 This design change pachage is not safety related and does not in _any way affect any safety related systems or the safe shutdown of the plant.

lPD-0075 Th;ts DCR will not affect the safety function of any system. The proposed changes do not involve any of the criteria associated with an unreviewed safety question per 10CFR50.59.

Page 10 of 20

• DESIGN CHANGE REQUEST

DOCKET N- 50-272 MAJOR PLANT MODIFICATIONS~ UNIT N~ ____s_a_l_em __li_11________~

March 1980 DATE: April 10, 1980 COMPLETED BY: ___:_.L_.__K_._M_1_*1_1_e_r____~

TELEPHONE: 609-365-7000 X507

• DCR NO. 10CFRSO. 59. SAFETY EVALUATION lPD-0124 This change is not safety related and does not affect safety related equipment.

lPD-0141 This DCR will not affect any safety function of the :system involved.

The proposed changes do not involve any of the criteria associated with an .unresolved safety question per 10CFR50.59.

lPD-0162 This DCR will not affect any safety function of the system involved. The Package 1 proposed changes do not ;i.nvolve any of the criteria ass,ociated with an unreviewed safety question per 10CFR50.59.

lSC-0052 This DCR will not affect any safety function of the system involved. The proposed changes do not involve any of the criteria associated with an unresolved safety question per 10CFR50.59.

lSC-0073 Installation of platforms to condensate discharge isolation valves will not affect any previously performed safety analysis, will not affect the safe operation of the plant and does not constitute an~unreviewed safety question:.

lSC-0081 The modification to this system does not affect any presently performed safety analysis*nor does it create any new hazards. This system is not a safety related system. The bases of the Technical Specifications remains unchanged.

lSC-0097 Installation of cage around ladder to pressurizer penthouse will not change any previously performed safety *analysis, will not affect the safe operatior of the*plant and does not constitute an unreviewed safety question.

lSC-0122 Th+/-s DCR involves additional cathodic protection on condenser water boxes and is not safety related. Criteria for an unrevie~ed safety question are not met.

2SC-0215 The addition cifa chain operator to a valve does not affect the design philosophy of the system. This modification does not affect any present analysis rior does it create any new hazards. The Tech. Specs. are not affected.

Page 11 of 20

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WORI\

oi:;;DER Nl.JMBEH DEPT EQUIPMENT IDENTIFICATION EXPLANATION OF WOHK PERfURMED 902972 M FLANGE* SERVICE WATER DESCRIPTION OF PROBLEM* 30 INCH FLANGE AT EXPANSION JOINT FC-3-41 IN BAY 3 ERRODED CORRECTIVE ACTION, CLEANED ERROSION, WELDEDr AND COVERED THE FACES OF THE FLANGES WITH BITUMASTIC-300-M 905377 M PUMP, SERVICE WATER BAY 4 SUMP DESCRIPTION OF PROBLEMv BAY 4 SUMP PUMP WILL NOT RUN.

CAUSE* MOISTURE FOUND IN CONDUIT.

CORRECTIVE ACTION, DRIED OUT WIRING AND REPLACED SUMP PUMP, 911506 M VALVE* 14MS17:L DESCRIPTION OF PROBLEM* BLOWING THROUGH.

C~~SE, SEATING SURFACES CUT BY STEAM. *

'-*

CORRECTIVE ACTION, REPLACED VALVE STEM AND SEAT.

911536 M VALVE' 11SW024 ~-

DESCRIPTION OF PROBLEM* BOLTS ARE LOOSE ALL THE WAY AROUND CORRECTIVE ACTION, ~IGHTENED BOLTS.

914291 M PIPE HAN~ER, CTAG-~07 .._..

DESCRIPTION OF PROBLEM* REJECTED RICHMOND ANCHOR FOUND DURING WALKDOWN VERIFICATION.

CORRECTIVE ACTION, WELDED TWO PIECES OF CHANNEL TO HANGER INSTALLED TWO KWIK-BOLTS. *-~

I 914391 M PUMP, 11 CHILLED WATER I

DESCRIPTION OF PROBLEMv CHILLED WATER PUMP RUNNING HOT. *-*

BINDING DURING TEST RUN, CAUSE* PUMP WAS RUN WITHOUT OIL, 916610 M CORRECTIVE ACTIONv VITAL HEAT TRACE* CIRCUIT CONTROLLER T204S REPLACED BEARINGS,

• -

DESCRIPTION OF PROBLEM* GREEN POINTERCALARM> INOPERABLE.

SET AT 35 DEGF AND CAN NOT BE RAISED.

CAUSE, POINTER <ALARM> BROKEN Page 12 of 20 CORRECTIVE ACTION, F~EPl... ACED.

WORI\

Ol~D1:::i:;;

Nl.JMBEI'< DEPT EQUIPMENT IDENTIFICATION EXPLANATION OF WORK PERfDRMED 916662 M BTRAINER.13 SERVICE WATER .-

DESCRIPTION OF PROBLEMv CORRECTIVE ACTION, REPLACED PAC:l<ING 916663 M PUMP, 12 COMPONENT COOLING DESCRIPTION OF PROBLEM* EXCESSIVE OIL LEAK AT OUTBOARD BEARING CORRECTIVE ACTIONr REPLACED GASKET ON THRUST BEARING, 916679 M VITAL HEAT TRACEr CIRCUIT 702 DESCRIPTION OF PROBLEM, UNABLE TO MAINTAIN CORRECT TEMPERATURE, CORRECTIVE ACTIONr REPLACED THERMOSTAT, REPLACED PRIMARYHHEAT TRACE, 916689 M TRAVELLING SCREEN, 12 SERVICE WATER DESCRIPTION OF PROBLEM* SHEAR PIN BROKEN CORRECTIVE ACTIONr 1:;;EPLACED PIN, 916698 M INSTRUMENT, PT6298 DESCRIPTION OF PROBLEM* 12 COMPONENT COOLING PUMP SUCTION GAUGE HAS EXCESSIVE ~OVEMENT WHEN PUMP IS IN SERVICE, CORRECTIVE ACTIONr SECURED GAUGE BY USING A BACKING PLATE BEHIND GAUGE AND BOLTING IT TO AN EXISTING ANGLE IRON, 916701 M DAMPERr 1CAA003

.._,;

DESCRIPTION OF PROBLEM* DAMPER 1CAA003 WILL NOT OPEN.

CAUSE, LUBRICATION PROBLEM, CORRECTIVE ACTIONv LUBRICATED AND FREED DAMPER.

916762 M PUMP* 11 CHILLED WATER DESCRIPTION OF PROBLEM* THERMAL OVERLOAD IN BREAKER KEEPS TRIP-PING AFTER PUTTING THE PUMP IN SERVICE *-*

~PPROXIMATELY THREE HOURS CORRECTIVE ACTION, REPLACED OVERLOADS. TIGHTENED ALL CON-NECTIONS, TESTED SAT+

• -

918933 M DAMPER r l CAAOO 1 DESCRIPTION OF PROBLEM* DAMPER 1CAA001 WILL NOT OPEN.

CAUSE, LUBRICATION PROBLEM, Page 13 of 20

~nRRF~TIUF A~TJaN. UBEJ't PENEH;:AT:r.NG Oii... TO FT~EE DAMF'E:J;;~

WORI\

Dl~DEI'<

NUriBEH DEPT EQUIPMENT IDENTIFICATION EXPLANATION DF WORK PERfOkriED

.-

927722 M STRAINER, 11 SERVICE WAl'ER PUMP DESCRIPTION OF PROBLEM, CORRECTIVE ACTION, REPACl\E::r:i.

927889 M DAMPER' 1CAA003 DESCRIPTION OF PROBLEM, DAMPER 1CAA003 WILL NOT OPEN, CALISE, SHAFT JAMMED+

CORRECTIVE ACTIONr FREED SHAFT, 927893 M COMPRESSOR, 2 EMERGENCY AIR DESCRIPTION OF PROBLEMr ON LOW STATION AIR HEADER PRESSUREr EMERG AIR COMPRESSOR RAN ~OR THREE MINUTES AND TRIPPED ON LOW LUBE PRESSURE CAUSE, INVESTIGATION SHOWED CRANKCASE FILLED WITH WATER+ SOURCE OF WATER UNKNOWN+

CORRECTIVE ACTION, CLEANED SUMPr BEARING, AND OIL PUMP.

FLUSHED WITH OIL TWICE AND INSTALLED A NEW FILTER.

927894 M PUMP, CONTAINMENT SUMP DESCRIPTION OF PROBLEM* EXCESSIVE RUN TIMES.

CAUSE, DEBl'!IS IN SUMP+

CORRECTIVE ACTION* CLEANED SUMP AND STRAINERS.

927906 M ENGINE* lA DIESEL DESCRIPTION OF PROBLEM* EMERGENCY DIESEL WILL NOT SHUTDOWN NORM-ALLY+ EMERGENCY STOP MUST BE USED+

,_.

CAUSEr LOOSE WIRE ON SDR RELAY CORRECTIVE ACTIONr 927946 M VITAL HEAT TRACEr CIRCUIT 603 DESCRIPTION OF PROBLEM* SECONDARY CIRCUIT UNABLE TO MAINTAIN

• -

TEMPERATURE ABOVE 145 DEGF WITH PRIMARY CIRCUIT OUT OF SERVICE DUE TO LACK OF P1:ir-i:TS CAUSE* HEAT TRACE BURNED OPEN, Page 14 of 20 CORRECTIVE ACTION, REPAIRED AND REINSULATED HEAT TRACE.

WORK DRDEH Nl.JMitEI'( DEPT EQUIPMENT IDENTIFICATION EXPLANATION OF WORK PERf8RMED 928017 M ELECTRICAL SEALS, 11 CONTROL ROOM .-*

DESCRIPTION OF PROBLEM, CHECK ALL ELECTRICAL SEALS FROM tl CONTROL ROOM TO 11 RELAY ROOM.

CORRECTIVE ACTION, FOUND ONE DAMAGED SEAL IN 1RP3+

REPAIRED SEAL USING 3 aoz. SEMKIT 928178 M VALVE' :L1MS168 DESCRIPTION OF PROBLEMP f.l()NNET LEAK.

CORRECTIVE ACTION, Ft.mMANITED TIGHTENED PACKING NUTS.

928194 M PUMP, 12 COMPONENT COOLING DESCRIPTION OF PROBLEM, HIGH VIBRATION NOTICED BY SITE PERSONNEL.

CAUSE, WORN BEARINGS 0

CORRECTIVE ACTION, REPLACED MECHANICAL SEALr OIL SEALr AND BEARINGS.

928200 FIRE SEALS, CONTROL ROOM DESCRIPTION OF PROBLEM' INSPECT AND REPAIR CONTROL ROOM FLOOR FIRE SEr:iLS CORRECTIVE ACTION, REPAIRED HOLES' IN 1RP4 AND 1RP5 929418 M VALVE OPERATOR, 14BF019 DESCRIPTION OF PROBLEM' CONSOLE INDICATES 50 PERCENT WHILE LOCAL INDICATOR READS 70 PERCENT. LEVEL CONTROL .._,

ERRATIC PERIODICALLY GETTING 10 PERCENT LEVEL SWINGS.

'*-'

CAUSE, FAILURE DUE TO NORMAL DEGRADATION OF VALVE DPEl~ATOR

• CORRECTIVE ACTION, CALIBRATED POSITIONERr REPLACED CAM AND CAM HUB AND CHECKED LIMIT SWITCHES.

STRIJl<:ED VALVE.

e '-

• -

M COMPRESSOR, 11 WASTE GAS DESCRIPTION OF PROBLEM' EXCESSIVE NOISE AND WATER LEAKING FROM *-*

SEALS, CORRECTIVE ACTION, INSTALLED REBUILT COMPRESSOR. *-

933717 M PIPEr SERVICE WATER DESCRIPTION OF PROBLEM, PIPE LEAK NEAR 12BW124.

CAUSE, ERROSION/CORROSION.

CORRECTIVE ACTIONr INSTALLED NEW PIPE AND FLANGE.

Page 15 of 20

WORI\

Dl~DEI:;;

NLJMBEI'( DElT EQUIPMENT IDENTIFICATION EXPLANATION OF WORK PER~ORMED 933740 M OVERHEAD ALARMr 12 RHR SUMP OVERFLOW DESCRIPTION ~~ PROBLEMv 12RHR SUMP OVERFLOW ALARM ANNUCIATED WITH NO OVERFLOW CONDITION, J

i C(-'IUSE r GROUNDED WIRE ON MICROSWITCH, L,

iL CORRECTIVE ACTIONr REINSULATED WIRE.

i I....

• ~ . 933754 M DAMPERr 1CAA003 j DESCRIPTION OF PROBLEMr CONTROL ROOM INTAKE DAMPER 1CAA003 FROZEN

.~

CAUSEr LUBRICATION PROBLEM.

CORRECTIVE ACTIONr LUBRICATED DAMPER. TEST SATISFACTORY.

933760 M FLANGEr SERVICE WATER

-*,

DESCRIPTION OF PROBLEMr FLANGE LEAK IN SERVICE WATER STRUCTURE BAY 3 CORRECTIVE ACTIONr REPLACED GASKET 933761 M VALVEr 14SW024 DESCRIPTION OF PROBLEMr VALVE l4SW024 HAS A RUPTURED DIAPHRAGM.

CORRE~TIVE ACTIONr REPLACED DIAPHRAGM.

933807 M VALVEr 11SJ134 DESCRIPTION OF PROBLEMr PACKING LEAK CORRECTIVE ACTIONr ADJUSTED PACKING, CLEANED BONNET STUD AND PACKING NUTS, 933825 M STRAINERSr 16 SERVICE WATER PUMP DESCRIPTION OF PROBLEMr SHEAR PINS BROKEN.

CAUSEv SF.:J~I... PLATES WORN CORRECTIVE ACTION* REPLACED 3 SEAL PLATES AND INSTALLED NEW SHEr~I:;: Pii-1 935518 M PUMPr 13 COMPONENT COOLING DESCRIPTION OF PROBLEMr HIGH VIBRATION NOTICED BY SITE PERSONNEL WORN THRUST BEARING.

CORRECTIVE ACTION, REPLACED THRUST BEARING AND INBOARD BEr:i1' I NG HOUSING*

Page 16 of 20

• WOi':K*

Ol~DEI;;

Nl.Ji"iBEH DEPT EQUIPMENT IDENTIFICATION EXPLANATION OF WORK PERfORMED 935533 H STRAINER, 12 SERVICE WATER DESCRIPTION OF PROBLEM, HAND HOLE LEAKING CORRECTIVE ACTIONr l'~EPL(1CED Gr'.iSl\ET 911416 p FILTER, AIR PARTICULATE DETECTOR DESCRIPTION OF PROBLEM, FILTER FAILURE ALARM RECEIVED FOR AIR PARTICULATE DETECTOR.

CAUSEr SHEAR PINS ON DRIVE MECHANISM BROKEN.

MICRO SWITCH HAD ALSO FAILED. FAILURE OF I SWITCH THOUGHT TO BE RESULT OF MISHANDLING i' DURING SHEAR PIN REPAIR.

CORRECTIVE ACTION, REPLACED SHEAR PINS AND MICROSWITCH.

~

914476 p INSTRUMENT, R31B

~

.

DESCRIPTION OF PROBLEM, FUEL PROTECTION-RATIO LOW ALARMS WITHOUT Cf~USE

) CORRECTIVE ACTION, REPLACED PC BOARD. *- ...

• 914491 p INSTRUMENT, FA5694 DESCRIPTION OF PROBLEM, FALSE INDICATIONS CAUSEr FAIL.ED MIDRr4NGE.

CORRECTIVE ACTIONr REPLACED AMPLIFIER BOARD.

914559 p SWITCHr BIT TANK RECIRC LOW FLOW ALARM

• ._,.

DESCRIPTION OF PROBLEMr IS ON WITH GREATER THAN 10 GPM RECIRC Cf'.1USE, DEFECTIVE REED SWITCH CORl:::ECTIVE ACTIDi",* SWITCH DESTROYED AND REPLACED.

921020 p INSTRUMENTr TA4554Z DESCRIPTION OF*PROBLEM, REACTOR COOLANT LOOP 11 CHANNEL DELTA T I TAVG OUT OF CALIBRATION._

CAUSE, SIGNAL ISOLATOR OUT OF SPECIFICATION CORRECTIVE ACTION, REPLACED SIGNAL ISOLATOR.

OLD ISOLATOR TO BE REWORKED.

921100 p INSTRUMENT, 1LC459 DESCRIPTION OF PROBLEM, SIGNAL COMPARATOR OUT OF SPECIFICATIONS. .

CORRECTIVE ACTION, REPLACED COMPARATOR. OLD COMPARATOR TO BE Page 17 of 20 1:;:i:::wo1:;:1..:Er:i

SALEM UNIT #1 OPERATING

SUMMARY

MARCH 1980 3/1 Escalating power at 5% per hour. At 2000, power reached 100%.

Reduced power at 2355 to 70% to allow cleaning of condensate strainers.

3/2 At 0500, reached 70% power to clean condensate strainers. Started increasing load from 70% at 0625 until 1430 when load reached 100%.

At 1430, started decreasing load to 80% to clean heater drain pump strainers. Power remained at 80% for the remainder of the day.

3/3 At 0001, load was increased until 0930 when load reached 97%. Load remained there for the remainder of the day.

3/4 Load remained at 97% for the entire day.

3/5 Load was increased from 97% to 100% at 0830 on 3/5/80. The load thru remained at 100% for the rest of this period.

3/8 3/9 At 0100, started load decrease to 70% to allow cleaning of condensate pump strainers. At 0110, started load increase until 2300 when load reached 100%.

3/10 thru Remained at 100% load for this period.

3/11 3/12 Started decreasing load at 0550 to 70% to allow cleaning of condensate pump strainers. Started increasing load at 1300 until 2300 when load was at 100%.

Page 18 of 20

3/13 thru Remained at 100% load for this period.

3/22 3/23 At 100% load until 2100 when started decreasing load to 70% to thru allow cleaning of condensate plilllp strainers. Reached 70% at 0100 3/24 on 3/24/80. Started increasing load at 0200 until 100% load was reached at 2000. Remained at 100% load for the remainder of this period.

3/25 Remained at 100% load for this period.

3/26 At 0300, started reducing load to 86% in preparation to clean l3B condenser. Load was increased to 100% by 0800.

3/27 Load at 100% for this period except for 5% load reduction at 1509 thru on 3/28/80 due to drop in steam generator feed pump suction pressure.

3/29 Load returned to 100% at 1630 on 3/28 and remained there for the rest of this period.

3/30 At 100% load until 2150 when load reduction began at 7% per hour thru down to 70% to allow cleaning of condensate pump strainers. Load 3/31 increase began at 0500 on 3/31/80 until 100% load was reached at 1130. Load remained at 100% for the rest of this period.

Page 19 of 20

,, "'

• iAtuELING INFORMATION DOCKET NO.: 5o- 272 UNIT: Salem Ill DATE: April 10, 1980 COMPLETED BY: L

• K. Miller TELEPHONE: 609-365- 7000 Ext. 507 March 1980 MONTH=--~----------~--------------

l. Refueling information has changed from last month:

YES NO

---X

2. Scheduled date of next refueling: September 20, 1980

3. Scheduled date for restart following refueling: December 7, 1980

4. A. Will Technical Specification changes or other license amendments be required? YES _____NO ____

NOT DETERMINED TO-DATE March 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:

September 1980 (If Required)

6. Important licensing considerations associated with refueling:

NONE

7. Number of Fuel Assemblies:

A. In-Core 193 B. In Spent Fuel Storage 40

8. Present licensed spent fuel storage capacity: 264 Future spent fuel storage capacity: 1,170

9. Date of last refueling that can be discharged to the spent fuel pool assuming the present licensed capacity: September 1982 Page 20 of 20 8-l-7.R4