ML18082A175

Monthly Operating Rept for Mar 1980

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

Text

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• AVERAGE DAILY UNIT POKER LEVEL March 1980 DAY AVERAGE DAILY POWER LEVEL 1 2 3 4 5 6 7 8 9 10 11 12 13 14 15 16 Pg. 2 of 20 8.1-7.Rl (MWe-NET)

• 797 908 1023 1117 1125 1123 1110 1084 894 1120 1098 980 1083 1105 1110 1098 DOCKET NO. 5 o-2 72 UNIT Salem 111 DATE April 10, 1980 COMPLETED BY L. K. Miller TELEPHONE 609-365-7000 Ext. 507 DAY AVERAGE DAILY POWER LEVEL (MWE-NET) 17 1081 18 1112 19 1093 20 1094 21 1113 22 1108 23 1068 24 1021 25 1101 26 1075 27 1106 28 1077 29 1072 30 1113 31 1003 e OPERATlN:; REl?OR1' OPERATJN:2 STMUS l. Unit Nana: Salem Ill Notes: 2. Reporting Period: March 1980

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

4. Na!Ieplate Rating (Gzoss 1'fi:!): 1135 ----------

5. Design Electrical Rating (Net 1'fi:!): 1090 6. Maxilmlm Dependable Capacity "(Gross KW!): 1124 ------7. Maximum Dependable Capacity (Net Kole): 1079 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

• 8. If Changes Occur in .Capacity Ratings (Itam NUllCer 3 'lmc1.J;jh

7) Since Last Report, Give Reason: NO 9. Power Level To Which Restricted, If Any (Net KW!) : NONE ----------------------

i O. Reasons Far Restrictions, If Any: NONE ----------------------------

ll. 12. 13. 14. 15. 16. 17. 18. 19. 20. 21. 22. Hours In Rep::>rting Period Nuni:ler Of Hours Reactor was Critical P.eactor Reserve Shutdown Hours Hours Generator On-Line. Unit Reseive Shutdown Hours Gzoss 'lbe:cnal F.nergy Generated (l+IB) Gross Electrical Energy Generated (Mm) Net Electrical Energy Generated(Ml'IH)

Unit Service Factor Unit Availability Factor Unit Capacity Factor (Using MOC Net) Unit Capacity Factor (Using DER Net) 'Ibis M:lnth Year to Date 744 2;184 744 2,093.6 0 0 744 1,994.3 0 0 2,405,018 5,959,980 823,870 2,012,600 792.307 t:!.,923,293 100.0 91.3 100. 0 91.3 98.7 81.6 97.7 80.8 23. -, -Unit Forced Qutaqe Rate 0 8.7 24. Shutdcwns Scheduled Oller Next 6 Mcnths (Type, Date, and Duration of Eadl): Refueling

-9/20/80 Cl.lmulati ve 24,145 12,181.6 22.7 11 525.4 0 33,.496 ,277 11,180,100 10,552,883 47.7 47.7 40.5 40.1 40.9 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

8-l-7.R2 Pg. 3 of 20 INITIAL CRITICALI'lY INITIAL EUX:TRICIT'l OPERATION Forecast 09/30/76 11/01/76 12/20/76 Achieved 12/11/76 12/25/76 06/20/77 ID. DATE 80-062 3/1/80 80-064 3/2/80 80-066 3/3/80 80-068 3/6/80 80-070 3/7/80 80-072 3/9/80 80-073 3/13/80 80-074 3/12/80 80-076 3/16/80 80-078 3/16/80 80-079 3/18/80 80-081 3/18/80 1 F: Forced s: . Scheduled Page 4 of 20 8-1-7.Rl F F F F F F F F F F F F 2 UNIT SlllmxMNS l\ND PCMER REIXcrIONS REPORr MJlmI March 1980 ME:I'IKJD OF OORATION (llXJRS) OCMN REACTOR 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 0 A 5 0 A 5 0 .A 5 Peason: .1\-B:)ui?IE!Ilt Failure(Explain)

D-Maintenance or Test C-Refueling D-Regulatocy Restriction LICENSE EVEN!' REPORI' I ---------------------------------

---E--Operator Training & License EKamination F-1\dministrative Error(Explain)

H-other (Explain)

SYSTEM a:MPOOFNl' OODE4 OODE5 HH FILTER HG DEMINX HH PUMP XX HH HT EX CH HH HTEXCH HH FILTER HH HTEXCH HH FILTER HH HT EX CH HH HTEXCH HH HTEXCH HH HTEXCH 3.

1-Manual 2-Manual Scram. 3-Automatic Scram. 4-Continuation of Previous Outage 5-Load Reduction 9-0ther DOCKET NO.: 50-272 UNIT 'NAME: Salem Ill DATE: April 10, 1980 COMPLETED BY: L. K. Miller TELEPHONE:

609-365-7000 X507 CAUSE AND OJRRECI'IVE ACTION TO PRE.VEN'l' RB:.'URRENCE Clean Cond. Pump Suction Strainers High Differential Pressure Condensate Polishers 13A Vacuum Pump Tagged Out For Repairs Clean 13B Condenser Water*:,Box Clean 13B Condenser Water Box Clean Cond. Pump Suction Strainers Clean 13A Condenser Water Box Clean Cond. Pump Suction Strainers Clean 13B Condenser Water Box Clean 13A Condenser Water Box Clean 13B Condenser Water Box Clean 13B Condenser Water Box 4 5 Exhibit G -Instructions for Preparation of Data Entry Sheets for Licensee Event Report (I.ER) File (NUREG-0161)

Exhibit 1-Saire Source

m.80-083 80-085 80-086 80-088 DATE 3/23/80 3/23/80 3/26/80 3/31/80 Page :5 of 20 8-1-7 .Rl' TYPEl F F F F IXJRATIOO RFA'lON2 (lroRS) 0 A 0 A 0 A 0 A .. UNIT SllU'IlXJolNS 1\ND PrnER REOOCTIOOS REPORI' MJNrH March 1980 Mimm OF SlllJITIOO LICENSE SYSTEM <nn'OOF.Nl' IXMN EVEN!' CDDE4 CIJDES RFJ\C'roR REPORT I 5 ---RH HTEXCH 5 ---RH FILTER 5 ---RH HTEXCH 5 ---RH FILTER " Clean Clean Clean Clean DOCKET NO.: 50-272 UNIT*NJ\ME:

Salem #1 DATE: April 10, 1980 COMPLETED BY: L. K. Miller TELEPHONE:

609-365-7000 X507. CAUSE AM> OJRREx:"I'IVE ACTION 'ID PRIMNI' RIDJRREN::E llB Condenser Water Box Condenser Pipe Strainers 13A Condenser Water Box Cond. Pump Suctrion Strainers "

• MAJOR PLANT REPORT MONTH March 19"0 *DCR NO. PRINCIPLE SYSTEM lED-0062 SGFP lED-0137 Hydrogen Supply lED-0146 "B" Building Services Package 2 1ED-0241A Fire Protection lED-0300 Station Lighting lED-0304 Ventilation lED-0311 eves lED-0314 Fire Protection lED-0334 WDL 1ED-0350A WDL lED-0354-Fire Protection Package 1 Condensate Package 2 lEC-0373-Condensate Package 15 lEC-0373-Condensate Package 16 lEC-0377 Fire Protection lEC-0442 Containment Hatch lEC-0451 Safety Injection lEC-0474 RMS lEC-0480 Fire Protection

• DESIGN CHANGE REQUEST 8-1-7. Rl Page 6 of 20 DOCKET NO: 50-272 UNIT NAME: *e::im*_,.....e-m--1--------

DATE: April 10, 1980 COMPLETEn BY: L. K. Miller TELEPHONE:

609-365-7000 X507 .' SUBJECT Replace 11 & 12BF32*valves Relocate the Hydrogen Storage Install and Relocate Services Additional Fire Protection to Containment and Auxiliary Building Installation of Yard Lighting Automatic Damper in Electrical Pen. Core Bore Monitor Holes in Shield Plug Install Hose Reel in North Pen. Waterproof WDL Trench-Drum Storage Area Waste Evaporator Piping Mod. Expand Fire Protection Condensate Polishing Condenser Tie-Ir Condensate Polishing Controls Condensate Polishing Elect. Tie-In Provide Alarms on Fire Boundry Modify Containment Personnel Hatch CMC Switch on 1SJ67 and 68 Reset lRllA and 1Rl2A Install Additional Fire Detection

-

-

• MAJOR PLANT REPORT MONTH March 1980 DOCKET NO: 50-272 UNIT DATE: April 10, 1980 COMPLETEn BY: L. K. Miller TELEPHONE:

609-365-7000 X507 *DCR NO. PRINCIPLE SYSTEM SUBJECT lEC-0492 lEC-0534 lEC-0536 lEC-0565 lEC-0590 lEC-0662 lEC-0697 lMD-0081 lMD-0131 lMD-0132 lOD-0035 lPD-0075 lPD-0124 lPD-0141 lPD-0162-Package 1 lSC-0052 lSC-0073 lSC-0081 lSC-0097 lSC-0122 25C-0215 Aux Building Vent. Install Hi Temperature Alarm Solid State Protection Delete Low Pressure Level Coincidence Circuit Aux Feedwater Non Rad Waste eves Stress Calculation Aux Feed water Met Tower Telephone Fire Protection WDL DM Water Nitrogen Communications Non Rad Waste PA TGA -Structural DM_Water Pressurizer Circ. Water Spent Fuel Cooling Modify Controls Construct Baff le and Install Install Snubber on CVCS Charging Pump Seismic Stress Calculations Aux Feedwater Hanger Change Installed Alarm in Control Room Permanent Telephone in Containment Core Bore Holes at Fire Doors Add Two Pumps and Associated Piping Install Heat Trace on DM Water Core Bore Monitor Holes in Shield Plug Install PA at Chlorine House Additional Heat Tracing Install PA in South Penetration Installed Condensate Pump Platform DM Make-Up Water to VAC Pumps Installed Safety Ladder Cages Additional Cathodic Protection Install Chain Operator on 2-SF-35

• DESIGN CHANGE REQUEST 8-1-7. Rl Page 7 of 20 50-272 MAJOR PLANT UNIT N , Salem 111 *DCR NO. lED-0062 lED-0137 lED-0146 Package 2 1ED-0241A lED-0300 lED-0304 lED-0311 lED-0314 lED-0334 1ED-0350A lED-0354 Package 1 lEC-0373 Package_ 2 March 1980 DATE: April 10, 1980 COMPLETED BY: L. K. Miller TELEPHONE:

609-365-7000 X507 lOCFRSO. 59. SAFETY EVALUATION Not a safety related change. This design change involves of H 2 .storage bottles from the 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.

There is no;:fundamental change to seal design or function nor to No. 1 & 2 seals. The change enhances service life. The requirements for an unreviewed safety question are not met. This design change does not affect any presently performed safety analysis nor does it create any new hazards. The bases of the Technical cations are not affected.

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.

The operation of safety related equipment associated is not affected.

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. 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. 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.

Minor revision to provide construction opening and temporary enclosure.

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

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

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

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

• DESIGN CHANGE REQUEST Page 8 of 20 MAJOR PLANT REPORT MONTH, March 1980 DOCKET 50-272 UNIT NAMf9' Salem Ill *DCR NO. lEC-0373 Package 15 lEC-0373 Package 16 lEC-0377 lEC-,0442 lEC-0451 lEC-0474 lEC-0480 lEC-0492 lOCFRSO. 59.

DATE: April 10, 1980 COMPLETED BY: L. K. Miller TELEPHONE:

609-365-7000 X507 SAFETY EVALUATION This design change is not safety related and does not affect any safety related systems or the safe shutdown of the unit. 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 unreviewed safety question per 10CFR50.59.*

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.

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. 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.

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 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). 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. 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

..

vefore postulated effect on safety related equipment occurs. This installation is an NRC requirement.

• DESIGN CH.ANGE Page 9 of 20 --------------------

MAJOR PLANT DOCKET 50-272 UNIT N.A.M9' Salem Ill REPORT MONTH March 1980 DATE: April 10, 1980 *OCR NO. lEC-0534 lEC-0536 lEC-0565 lEC-0590 lEC-0662 lEC-0697 lMD-0081 lMD-0131 lMD-0132 lOD-0035 lPD-0075 COMPLETED BY: L. K. Miller TELEPHONE:

609-365-7000 X507 lOCFRSO. 59. SAFETY EVALUATION 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. Logic change complies with NRC question regarding operatO.r flexibility to initiate auxiliary feedwater.

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.

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.

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 cations, document updating, etc., there is no*:unreviewed safety question involved.

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.

Not safety related and does not affect any safety related systems. 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.

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. 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. 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.

• DESIGN CHANGE REQUEST Page 10 of 20 MAJOR PLANT DOCKET N-50-272 UNIT ____ s_a_l_em __ li_11 ________ *DCR NO. lPD-0124 lPD-0141 lPD-0162 Package 1 lSC-0052 lSC-0073 lSC-0081 lSC-0097 lSC-0122 2SC-0215 March 1980 DATE: April 10, 1980 COMPLETED BY: ___ :_.L_. __ K_._M_1_*1_1_e_r

____ TELEPHONE:

609-365-7000 X507 lOCFRSO. 59. SAFETY EVALUATION This change is not safety related and does not affect safety related equipment.

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.

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

The proposed changes do not ;i.nvolve any of the criteria ass,ociated with an unreviewed safety question per 10CFR50.59.

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.

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 safety question:.

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.

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.

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

• DESIGN CH.ANGE REQUEST Page 11 of 20 I I -. WORI\ oi:;;DER Nl.JMBEH 902972 905377 911506 911536 914291 914391 916610 DEPT M M M M M M M Page 12 of 20 EQUIPMENT IDENTIFICATION FLANGE* SERVICE WATER DESCRIPTION OF PROBLEM* CORRECTIVE ACTION, PUMP, SERVICE WATER BAY 4 SUMP DESCRIPTION OF PROBLEMv CAUSE* CORRECTIVE ACTION, VALVE* 14MS17:L DESCRIPTION OF PROBLEM*

CORRECTIVE ACTION, VALVE' 11SW024 DESCRIPTION OF PROBLEM* CORRECTIVE ACTION, PIPE DESCRIPTION OF PROBLEM* CORRECTIVE ACTION, PUMP, 11 CHILLED WATER DESCRIPTION OF PROBLEMv CAUSE* CORRECTIVE ACTIONv VITAL HEAT TRACE* CIRCUIT CONTROLLER T204S DESCRIPTION OF PROBLEM* CAUSE, CORRECTIVE ACTION, EXPLANATION OF WOHK PERfURMED 30 INCH FLANGE AT EXPANSION JOINT FC-3-41 IN BAY 3 ERRODED CLEANED ERROSION, WELDEDr AND COVERED THE FACES OF THE FLANGES WITH BITUMASTIC-300-M BAY 4 SUMP PUMP WILL NOT RUN. MOISTURE FOUND IN CONDUIT. DRIED OUT WIRING AND REPLACED SUMP PUMP, BLOWING THROUGH. SEATING SURFACES CUT BY STEAM.

• REPLACED VALVE STEM AND SEAT. BOLTS ARE LOOSE ALL THE WAY AROUND BOLTS. REJECTED RICHMOND ANCHOR FOUND DURING WALKDOWN VERIFICATION.

WELDED TWO PIECES OF CHANNEL TO HANGER INSTALLED TWO KWIK-BOLTS.

CHILLED WATER PUMP RUNNING HOT. BINDING DURING TEST RUN, PUMP WAS RUN WITHOUT OIL, REPLACED BEARINGS, GREEN POINTERCALARM>

INOPERABLE.

SET AT 35 DEGF AND CAN NOT BE RAISED. POINTER <ALARM> BROKEN

... ACED. '-* I .._ .. i *-* *-

WORI\

Nl.JMBEI'<

916662 916663 916679 916689 916698 916701 916762 918933 DEPT M M M M M M M M Page 13 of 20 EQUIPMENT IDENTIFICATION BTRAINER.13 SERVICE WATER DESCRIPTION OF PROBLEMv CORRECTIVE ACTION, PUMP, 12 COMPONENT COOLING DESCRIPTION OF PROBLEM* CORRECTIVE ACTIONr VITAL HEAT TRACEr CIRCUIT 702 DESCRIPTION OF PROBLEM, CORRECTIVE ACTIONr TRAVELLING SCREEN, 12 SERVICE WATER DESCRIPTION OF PROBLEM* CORRECTIVE ACTIONr INSTRUMENT, PT6298 DESCRIPTION OF PROBLEM* CORRECTIVE ACTIONr DAMPERr 1CAA003 DESCRIPTION OF PROBLEM* CAUSE, CORRECTIVE ACTIONv PUMP* 11 CHILLED WATER DESCRIPTION OF PROBLEM* CORRECTIVE ACTION, DAMPER r l CAAOO 1 DESCRIPTION OF PROBLEM* CAUSE, EXPLANATION OF WORK PERfDRMED REPLACED PAC:l<ING EXCESSIVE OIL LEAK AT OUTBOARD BEARING REPLACED GASKET ON THRUST BEARING, UNABLE TO MAINTAIN CORRECT TEMPERATURE, REPLACED THERMOSTAT, REPLACED PRIMARYHHEAT TRACE, SHEAR PIN BROKEN 1:;;EPLACED PIN, 12 COMPONENT COOLING PUMP SUCTION GAUGE HAS EXCESSIVE WHEN PUMP IS IN SERVICE, SECURED GAUGE BY USING A BACKING PLATE BEHIND GAUGE AND BOLTING IT TO AN EXISTING ANGLE IRON, DAMPER 1CAA003 WILL NOT OPEN. LUBRICATION PROBLEM, LUBRICATED AND FREED DAMPER. THERMAL OVERLOAD IN BREAKER KEEPS PING AFTER PUTTING THE PUMP IN SERVICE THREE HOURS REPLACED OVERLOADS.

TIGHTENED ALL NECTIONS, TESTED SAT+ DAMPER 1CAA001 WILL NOT OPEN. LUBRICATION PROBLEM, UBEJ't PENEH;:AT:r.NG Oii... TO

.-.. _,; *-* *-

WORI\

NUriBEH 927722 927889 927893 927894 927906 927946 DEPT M M M M M M Page 14 of 20 EQUIPMENT IDENTIFICATION STRAINER, 11 SERVICE WAl'ER PUMP DESCRIPTION OF PROBLEM, CORRECTIVE ACTION, DAMPER' 1 CAA003 DESCRIPTION OF PROBLEM, CALISE, CORRECTIVE ACTIONr COMPRESSOR, 2 EMERGENCY AIR DESCRIPTION OF PROBLEMr CAUSE, CORRECTIVE ACTION, PUMP, CONTAINMENT SUMP DESCRIPTION OF PROBLEM* CAUSE, CORRECTIVE ACTION* ENGINE* lA DIESEL DESCRIPTION OF PROBLEM* CAUSEr CORRECTIVE ACTIONr VITAL HEAT TRACEr CIRCUIT 603 DESCRIPTION OF PROBLEM* CAUSE* CORRECTIVE ACTION, EXPLANATION DF WORK PERfOkriED REPACl\E::r:i.

DAMPER 1CAA003 WILL NOT OPEN, SHAFT JAMMED+ FREED SHAFT, ON LOW STATION AIR HEADER PRESSUREr EMERG AIR COMPRESSOR RAN THREE MINUTES AND TRIPPED ON LOW LUBE PRESSURE INVESTIGATION SHOWED CRANKCASE FILLED WITH WATER+ SOURCE OF WATER UNKNOWN+ CLEANED SUMPr BEARING, AND OIL PUMP. FLUSHED WITH OIL TWICE AND INSTALLED A NEW FILTER. EXCESSIVE RUN TIMES. DEBl'!IS IN SUMP+ CLEANED SUMP AND STRAINERS.

EMERGENCY DIESEL WILL NOT SHUTDOWN ALLY+ EMERGENCY STOP MUST BE USED+ LOOSE WIRE ON SDR RELAY SECONDARY CIRCUIT UNABLE TO MAINTAIN TEMPERATURE ABOVE 145 DEGF WITH PRIMARY CIRCUIT OUT OF SERVICE DUE TO LACK OF P1:ir-i:TS HEAT TRACE BURNED OPEN, REPAIRED AND REINSULATED HEAT TRACE. .-,_. *-

WORK DRDEH Nl.JMitEI'( 928017 928178 928194 928200 929418 933717 DEPT M M M M M M Page 15 of 20 EQUIPMENT IDENTIFICATION ELECTRICAL SEALS, 11 CONTROL ROOM DESCRIPTION OF PROBLEM, CORRECTIVE ACTION, VALVE' :L1MS168 DESCRIPTION OF PROBLEMP CORRECTIVE ACTION, PUMP, 12 COMPONENT COOLING DESCRIPTION OF PROBLEM, CAUSE, CORRECTIVE ACTION, FIRE SEALS, CONTROL ROOM DESCRIPTION OF PROBLEM' CORRECTIVE ACTION, VALVE OPERATOR, 14BF019 DESCRIPTION OF PROBLEM' CAUSE, CORRECTIVE ACTION, COMPRESSOR, 11 WASTE GAS DESCRIPTION OF PROBLEM' CORRECTIVE ACTION, PIPEr SERVICE WATER DESCRIPTION OF PROBLEM, CAUSE, CORRECTIVE ACTIONr EXPLANATION OF WORK PERf8RMED CHECK ALL ELECTRICAL SEALS FROM tl CONTROL ROOM TO 11 RELAY ROOM. FOUND ONE DAMAGED SEAL IN 1RP3+ REPAIRED SEAL USING 3 aoz. SEMKIT f.l()NNET LEAK. Ft.mMANITED TIGHTENED PACKING NUTS. HIGH VIBRATION NOTICED BY SITE PERSONNEL.

WORN BEARINGS REPLACED MECHANICAL 0 SEALr OIL SEALr AND BEARINGS.

INSPECT AND REPAIR CONTROL ROOM FLOOR FIRE SEr:iLS REPAIRED HOLES' IN 1RP4 AND 1RP5 CONSOLE INDICATES 50 PERCENT WHILE LOCAL INDICATOR READS 70 PERCENT. LEVEL CONTROL ERRATIC PERIODICALLY GETTING 10 PERCENT LEVEL SWINGS. FAILURE DUE TO NORMAL DEGRADATION OF VALVE

• CALIBRATED POSITIONERr REPLACED CAM AND CAM HUB AND CHECKED LIMIT SWITCHES.

STRIJl<:ED VALVE. EXCESSIVE NOISE AND WATER LEAKING FROM SEALS, INSTALLED REBUILT COMPRESSOR.

PIPE LEAK NEAR 12BW124. ERROSION/CORROSION.

INSTALLED NEW PIPE AND FLANGE. .-* .._, '*-' e '- *-*-* *-

J i L, i L i I .... . j -*, WORI\

NLJMBEI'( DElT 933740 M 933754 M 933760 M 933761 M 933807 M 933825 M 935518 M Page 16 of 20 EQUIPMENT IDENTIFICATION OVERHEAD ALARMr 12 RHR SUMP OVERFLOW DESCRIPTION PROBLEMv C(-'IUSE r CORRECTIVE ACTIONr DAMPERr 1CAA003 DESCRIPTION OF PROBLEMr CAUSEr CORRECTIVE ACTIONr FLANGEr SERVICE WATER DESCRIPTION OF PROBLEMr CORRECTIVE ACTIONr VALVEr 14SW024 DESCRIPTION OF PROBLEMr ACTIONr VALVEr 11SJ134 DESCRIPTION OF PROBLEMr CORRECTIVE ACTIONr STRAINERSr 16 SERVICE WATER PUMP DESCRIPTION OF PROBLEMr CAUSEv CORRECTIVE ACTION* PUMPr 13 COMPONENT COOLING DESCRIPTION OF PROBLEMr CORRECTIVE ACTION, EXPLANATION OF WORK 12RHR SUMP OVERFLOW ALARM ANNUCIATED WITH NO OVERFLOW CONDITION, GROUNDED WIRE ON MICROSWITCH, REINSULATED WIRE. CONTROL ROOM INTAKE DAMPER 1CAA003 FROZEN LUBRICATION PROBLEM. LUBRICATED DAMPER. TEST SATISFACTORY.

FLANGE LEAK IN SERVICE WATER STRUCTURE BAY 3 REPLACED GASKET VALVE l4SW024 HAS A RUPTURED DIAPHRAGM.

REPLACED DIAPHRAGM.

PACKING LEAK ADJUSTED PACKING, CLEANED BONNET STUD AND PACKING NUTS, SHEAR PINS BROKEN.

PLATES WORN REPLACED 3 SEAL PLATES AND INSTALLED NEW Pii-1 HIGH VIBRATION NOTICED BY SITE PERSONNEL WORN THRUST BEARING. REPLACED THRUST BEARING AND INBOARD BEr:i1' I NG HOUSING*

I i' )

• WOi':K*

Nl.Ji"iBEH 935533 911416 914476 914491 914559 921020 921100 DEPT H p p p p p p Page 17 of 20 EQUIPMENT IDENTIFICATION STRAINER, 12 SERVICE WATER DESCRIPTION OF PROBLEM, CORRECTIVE ACTIONr FILTER, AIR PARTICULATE DETECTOR DESCRIPTION OF PROBLEM, CAUSEr CORRECTIVE ACTION, INSTRUMENT, R31B . DESCRIPTION OF PROBLEM, CORRECTIVE ACTION, INSTRUMENT, FA5694 DESCRIPTION OF PROBLEM, CAUSEr CORRECTIVE ACTIONr SWITCHr BIT TANK RECIRC LOW FLOW ALARM DESCRIPTION OF PROBLEMr Cf'.1USE, CORl:::ECTIVE ACTIDi",*

INSTRUMENTr TA4554Z DESCRIPTION OF*PROBLEM, CAUSE, CORRECTIVE ACTION, INSTRUMENT, 1LC459 DESCRIPTION OF PROBLEM, CORRECTIVE ACTION, EXPLANATION OF WORK PERfORMED HAND HOLE LEAKING Gr'.iSl\ET FILTER FAILURE ALARM RECEIVED FOR AIR PARTICULATE DETECTOR.

SHEAR PINS ON DRIVE MECHANISM BROKEN. MICRO SWITCH HAD ALSO FAILED. FAILURE OF SWITCH THOUGHT TO BE RESULT OF MISHANDLING DURING SHEAR PIN REPAIR. REPLACED SHEAR PINS AND MICROSWITCH.

FUEL PROTECTION-RATIO LOW ALARMS WITHOUT REPLACED PC BOARD. FALSE INDICATIONS FAIL.ED MIDRr4NGE.

REPLACED AMPLIFIER BOARD. IS ON WITH GREATER THAN 10 GPM RECIRC DEFECTIVE REED SWITCH SWITCH DESTROYED AND REPLACED.

REACTOR COOLANT LOOP 11 CHANNEL DELTA T I TAVG OUT OF CALIBRATION._

SIGNAL ISOLATOR OUT OF SPECIFICATION REPLACED SIGNAL ISOLATOR.

OLD ISOLATOR TO BE REWORKED.

SIGNAL COMPARATOR OUT OF SPECIFICATIONS. . REPLACED COMPARATOR.

OLD COMPARATOR TO BE 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 3/11 3/12 Remained at 100% load for this period. 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 3/22 3/23 thru 3/24 3/25 3/26 3/27 thru 3/29 3/30 thru 3/31 Remained at 100% load for this period. At 100% load until 2100 when started decreasing load to 70% to allow cleaning of condensate plilllp strainers.

Reached 70% at 0100 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. Remained at 100% load for this period. At 0300, started reducing load to 86% in preparation to clean l3B condenser.

Load was increased to 100% by 0800. Load at 100% for this period except for 5% load reduction at 1509 on 3/28/80 due to drop in steam generator feed pump suction pressure.

Load returned to 100% at 1630 on 3/28 and remained there for the rest of this period. At 100% load until 2150 when load reduction began at 7% per hour down to 70% to allow cleaning of condensate pump strainers.

Load 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

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 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 20 of 20 8-l-7.R4 193 40 264 1,170 to the spent fuel September 1982