ML18138A093

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Monthly Operating Repts for Feb 1980
ML18138A093
Person / Time
Site: Surry  Dominion icon.png
Issue date: 03/01/1980
From: COSTELLO O J
VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To:
Shared Package
ML18138A092 List:
References
NUDOCS 8003180459
Download: ML18138A093 (44)
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Text

. *i. I .. I .\ " VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION r: MONTHLY OPERATING REPORT REPORT NOo 80-02 FEBRUARY, 1980 APPROVED:

' I* 8 O O 3 l B otti;-'f _ .;:

CONTENTS Sect:ion * -Operating Data Report -Unit #1 Operating Data Report -Unit #2 Unit Shutdowns and Power Reductions

-Unit ill -Unit Shutdowns and Power Reductions

-Unit #2 Load Reductions Due to Environmental Restrictions

-Unit ill Load Reductions Due to Environmental Restrictions

-Unit #2 Average Daily Unit Power Level -Unit Dl Average Daily Unit Power Level -Unit #2 Summary of Operating Experience Amendments to Facility License or Technical Specifications Facility Changes Requiring Approval_.

Facility Changes That Did Not Require NRC Approval Tests and Experiments-Requiring UR.C Approval Tests and EA"Periments That Did Not Require NR.C Approval Other Tests and Experiments Chemistry Report Description of All Instances Where Thermal Discharge Limits Were Exceeded *Fuel Handling Procedure Revisions That Changed the Operating Mode Described In Page 1 2 3 4 5 6 7 8 9 10 12 12 13 13 14 . 15 16 17 The FSAR 21 Description of Periodic Tests Which Were Not Completed Within The Time Limits Specified In Technical Specifications 22 Iuservice Inspection 23 Reportable Occurrences Pertaining to Any Outage or Power Reductions 26 Maintenance of Safety Related Systems During Outage or Reduced Power Periods -Unit iil Mechanical Maintenance 27 Maintenance of Safety Related Systems During Outage or Reduced Power Periods -Unit /12 -Mechanical Maintenance

-29 ii.* < -\ ' .. , I t ,-' OPER/..TING

'***., ** DOCKET NO.

DATE 06 MAR 80 COMPLETED BY O.J. COSTELLO TELEPHONE OPERATING STt.TUS 1. UNIT N/.J.JE 2. REPORTING PEP.IOD 3. LICENSED THER!.JAL POWER (!.fwT) 4. N/.l.JE?LJ..TE R/..TING (GROSS W../E) 5. DESIGN ELECTRIC/...L R/..TING (NET MWE) 6. MAXIMl.:/.'.i DEPENDABLE Ck?ACITY (GROSS /.fvl'E) 7. M/.J.IMl!M DEPENDABLE CAPACITY (NET MWE) 8. IF CHt!.NGES OCCUR IN C/..?ACITY RATINGS (ITEMS 3 THROUGH 7) SINCE LAST GIVE REASONS SURRY UNIT 1 TO 2441 ,------------------------, 847.5 !NOTES I 822 I I 811 I I 775 I I NIA 9. POWER LEVEL TO WHICH IF ANY lJ/A (NET MWE) 10. REASONS FOR IF ANY N/A 11. HOURS IN REPORTING PEP.IOD 12. NUMBER OF HOURS REACTOR WAS CRITIC /..L ,13.w REACTOR RESERVE SHUTDOWN HOl/RS HOl'RS GENERA!.fOR ON'P.LINE l'NI1! RESERVE SHUTDOWN HOURS 16. GROSS THERMAL ENERGY GENERATED (MWH) 11.

  • GROSS ELECTRIC/..L ENERGY GENERATED (MWH) 18. NET ELECTRIC/..L ENERGY GENER/..TED (l&H) 19. VNIT SERVICE FACTOR 20. UNIT AVAILABILITY FACTOR 21. UNIT C/..PACITY FACTOR ([]SING MDC NET) 22. UNIT CAPACITY FACTOR ([,'SING DER NET) 23. UNIT FORCED OUTAGE RK!E 240 SHUTDOWNS SCHEDULED OVER NEXT 6 MONTHS Dl'RATION OF EACH) 25e IF SlilJT DOWN AT END OF RE?ORT PERIODs. ESTIMi1.TE DA.TE OF STAKfl'P 2 6 o UNITS IN TEST ST /.!fl! S ; (PRIOR TO COMMERCIAL OPERATION)

INITI/..L CRITICALITY INITIAL ELECTRICITY OPERAPION THIS MONTH CUMULATIVE 696.0 1440.0 63024.0 454.8 1016.2 39169.8 o.o 182.6 3v31.5 454.3. 1010.4. 38915.4 o.o 187.9 3740.5 1100867.0 2438340.0 90153212.0 355410.0 29466153.0.

331791.0 2g973109.0 65.3 o/o 70.2 o)o 61.1 o/o 65.3 o}o 83.2 oJo oJ.o 62.6 o/o 66.9 o/o 51.3 ojo 59.0 o/o 63.1 ojo 54.0 o/o 34.7 o/o 29.8 o/o 25.0 o/o REFl!ELING Jl'NE 19 8 O 6 WEEKS FORECAST 11CHIEVED s*ection --Maintenance of Safety Related Systems During Outage 'Power Periods -Unit #1 -Electrical Maintenance Maintenance of Safety Related Systems During Outage Power Periods -Unit #2 -Electrical Maintenance Maintenance of Safety Related Systems During Outage Power Periods -Unit ill -lnstrLllilent Maintenance

?iaintenance of Safety Related Syst.ems During Outage Power Periods -Unit #2 -Instrument Maintenance Health Physics Summary ee or Reduced or Reduced or Reduced or Reduced Procedure Deviations reviewed by Station Nuclear Safety and Operating Committee after Time Limits Specified in Page \ ' \ ' 32 34 36 38 40 41

' ,-, ' . O?ERCfING D.A ** RZ' DOCKET NO.

D/..TE 06 MAR 80 COMPLETED BY O.J. COSTELLO TELEPHONE . O?ER/.!fING ST/..!l.'l'S

t. UNIT NAME SURRY UNIT 2 2. RE?OR'rING PERIOD TO . 3. LICENSED THERlef.AL

?OWER (f..FwT) 4 o N ANE?L/.!fE ii.A.TING (GROSS M"wE) 5. DESIGN ELECTRICAL RATING (NET MWE)

  • 6 o /.:.A.XINl!M DEPENDABLE C.A.PACITY (GROSS M'wE) ':/. M/..XIla!N DEPENDABLE C.A.PACITY (NET Mr'IE) So IF CHANGES OCCl.'R IN CAPACITY RMINGS (ITEMS 3 THROUGH g) SINCE LAST RE?OR'r, GIVE REASONS 2441 ,------------------------, 841.5 !NOTES I s22 I I s11 I I 11s I I UA ' 9. POWER LEVEL TO WHICH IF Ii.NY N /A (NET M'wE) 10. REASONS FOR RESTRICTIONS, IF />.NY NJA THIS MONTH ClJMl'L/J.TIVE
11. HOURS IN REPORTING PERIOD 696.0 12. NUMBER OF HOl'RS REACTOR WAS CRITICAL 130 -REACTOR RESERVE SHUTDOWN HOURS 14. _,HOURS GENERA.TOR 115 UNIT RESERVE SHUTDOWN HOURS 16. GROSS THERJ.tJAL ENERGY GENERATED (MWH) 17. GROSS ELECTRICAL ENERGY GENERATED (MWH) :18. NET ELECTRICAL ENERGY GENER/J.TED (MWH) 19. UNIT SERVICE FACTOR o.o 200 l'NIT AVAILABILITY FACTOR o.o 21. l.,'NIT CAPACITY FACTOR ([}SING /.!DC NET) o.o 22. UNIT CAPACITY FACTOR (USING DER NET) OoO 23g UNIT. FORCED Ol'TAGE RATE OoO 24. SHUTDOWNS SCHEDULED OVER NEXT 6 MONTHS (TYPE

,.AND DlJRA.TION OF EACH) 250 IF SBl.'T DOWN AT END OF REPORT 5/5/80 ESTIM/..TE D/J.TE OF ST/J..RTlJP o.o o.o 0.0 o.o o.o o.o o.o 1440.0 59904.C o.o

.. o.o o.o o.o 33996.2 .. o.o o.o o.o o.o 25868844.0 o.o 56.8 o}o o.o 56.8 o/o o.o . 52e 9 o/o o.o 49.8 o/o OeO -21.0 ojo UNITS IN TEST STAXUS FORECAST . ACHIEVED (PRIOR TO COMMERCIAL OPERATION)

INITIAL CRITICALITY INITIAL ELECTRICITY COMMERCI ;.L OPERATION

.* : * *._.

    • .. ** *-* * *** ., *-*.* ** .... i ' I i . . : Nu. Dale 8-4 2-19-80 F: Forced S: Scheduled CtJ/77)

UNIT SHUTDOWNS AND POWER REDUCYiONS REPORT MONTH FEBRUARY 1980 =-.2 !!? -:s 0 ::s :c c-F 241;,7 Reason: D 1 A-Equipment Failure {Explain)

B-Malnienance oi Test Licensee Even I Report# 80-018 * ('-Refueling Restriction IE-Operator Training & License Examination f'-Administrail've

  • G-Operallonal Error (Explain) , H-Othcr (Explain) 3 Method: I-Manual*

2-Manual Scram. 3-Aulumalic Scram. 4-0lher (Explain)

DOCKET NO. 50:-280 UNIT NAME DATE COMPLETED BY TELEPHONE SURRY UNIT 1

  • 3/1/80 O.J. COSTELLO (804) 357-318(+

Cause & Corrective Action io Recurrence Pipe stress reanalysis on reactor cavity purification

& senl water return lines revealed a poten.tial overstnessetl condition on the piping penetrations in the event of a design basis earthquake.

A turbine inspection was commenced immediately after shutdown due to above normal vibration immediately prior to unit shutdown and to conduct inspections of the low pressure rotor discs. 4 5 Exhibir G

  • Instructions for Preparation of Data. Entry Sheets for Licensee Event Reporl (LER) File (NUREG* 0161) Exhibit I *Same Soun:!?

TIONS DUE TO

' . UNIT NO. 1 MONTH:February, 1980 DATE TiliE . HOURS LOAD, Mw REDUCTIONS, .MW REASON None dt ring this reporting period. MONTHLY TOTAL

"* Nu. D:ilc 80-2 2-1-80 ) . F.: Forced S: Scheduled UNIT SHUTDOWNS AND POWER REDUCTIONS REPORT MONTH FEBRUARY 1980 ...... ... *-0 c_ f"I 0 !:II ... -.:a § c * .,, cu "'O *-"' p. ... :s Ill :J ... u e o "' .c :; °' u :s :I: u .cc c-::!: !I) c s 696 c 1 Reason: A-Equipment Failure (Explain)

B-Maintenance or Test ('-Refueling licensee Even I Repnrl # D-Regulatory Restvictiun E-Operator Training & License Examination F-Administrative G-Operailooal Errm (Explain)

II-Other (Explain) 3 -c E"f' cu.,'I c cu cu u t; "2 0 "t:1 p. 0 >. .... Eu ti] u 0 u Method: I-Manual 2-Manual Scram. 3-Aulomatic Scram. 4-0ther (Explain)

DOCKET NO. UNIT NAME l>ATE COMrLETED BY TELEPllONE 50-281 SURRY UNIT 2 -#.-¥.8 8osTELLO (804) 357-3184 Cause & Corrective Aclion lo Prevent Recurrence

'* Continuation of shutdown for refueling and steam generator replacement which began on 2/4/79. 4 . Exhibir G

  • Instructions for Preparation of Data Entry Sheets for Licensee Event Report (LER) File (NUREG* . 0161) . s Exhibit I
  • Same Source .1 .::--1
  • f * --DOCKET NO l/N. f}JJjRY I DJ.:,, ,, .* 1"80 COMPLETED BY 0 J COSTELLO AVERAGE DAILY UNIT POWER LEVEL MONTH: FEBRl.!ARY 80 AVERAGE DAILY POWER LEVEL AVERAGE D/..ILY POWER LEVEL D/..Y (MWKr1NET)

DAY (MWEtJNET) 1 .1151.1 16 951.0 ... 1150.0 i5Qo3 3 t?50e3 18

"' '1149.,4 19 592 .. 5 5 20 o.o 6 1151., 8 21 o .. o 7 ?49 .. 2 22 o .. o s 23 o .. o 9 ?49.,5 24 o.o 10 949 .. 6 25 o .. o . 11 946.9 26 e.o 12 G .. O 13 28 o.o 14 146 .. 9 29 o.o 15 11411.1 \ DAILY lJNIT POWER LEVEL FORM INSTRUCTIONS ON THIS LIST THE AVERAGE DAILY UNIT POWER LE:VEL IN FOR EACH DAY IN THE REPORTING MONTB.. THESE FIGURES WILL BE l/SED TO PLCff A GRE'H FOR EACH REPOR'J', ING MONTH. NOTE THAT BY l!SING M/..'XIMUM DEPENDABLE CAPACITY FOR THE NET ELECTRICAL RATING OF THE UNIT* THERE MAY BE OCCASIONS WHEN THE DAILY AVERAGE POWER EXCEEDS THE 100 o/o LINE (OR THE RESTRICTED POWER LEVEL LINE). IN SlJCH THE AVERAGE DAILY UNIT POWER OUTPf,'T SHEEJ. 3HOULD BE FOOTNO'PED TO EXPL/>.IN THE A??ARENT ANOMALY e .. ------

-b-LOAD ro:AAs DUE TO ENVIRONMENTAL

,...._ ' ' I UNIT NO. 2 MONTH: February, 1980 DATE TIME HOURS lOAD 2 MW REDUCTIONS 2 MW HWil REASON --

None duI d.ng this reporting period. ,. . . *-.. --..... --MONTHLY TOTAL -------

. , . ,---FEBRUARY, 1980 ---Listed below in chronological sequence by unit is a summary of operating experiences for this month which required load reductions or resulted in ificant non-load related incidents.

UNIT 1 February 1 -February 2 February-:8 February 19 -_ February 20 -February 21 February 29 UNIT 2 February 1 February 25 = February 26 = February 28 -February 29 -This reporting period begins with the unit at 100% power. At 1300 commenced 150MWe/Hr.

rampdown due to loss of Boron Injection Tank (BIT) recirculation line heat tracingc At-1307 aborted rampdown and commenced raising power to 100% after repairs to BIT recirculation line heat tracing were completed.

Uni.t attained 100% power at 1311. At 2025,while checking-for leakage past MOV-1350 Emergency Borate Line MOV, Tave (average reactor coolant system -temperature) decreased rapidly, reduced reactor power to 98%, diluted system by adding 2000 gallons of primary grade (PG) water, and at 2100 commenced power increase to 100% power. Reactor power at 100% at 2130. At 1339 commenced reducing power due to problems with the high pressure secondary drain system. At 1351 secured power reduction at 96% reactor power. Resolved the problem with the ll.P. Drain System and commenced reactor power increase at 1426. Reactor was at 100% _I power at 1455. At 1547 commenced reactor shutdown due to results of pipe *stress reanalysis on reactor cavity purification system and -seal water return piping which revealed an condition on the piping tions would exist in the event of a Design Basis Earthquake. -At 2215 the generator was taken off the line and at 2246 the reactor was shutdown.

Commenced RCS cooldown at 0403. RCS at 350°F/450 PSIG at RCS at cold shutdown at 1257. Commenced inspection of LP turbine rotors due to above normal vibration experienced imlnediately prior to unit shutdown.

This reporting period ends with the unit at cold shutdown.

This reporting period begins with the unit at cold shutdown, all fuel removed from the reactor and steam generator replacement in progresso At 1937 commenced pressurizing Unit 2 containment to 45 PSIG for Type A testo Containment pressure reached 45 PSIG at 0547. At 0353 commenced depressurizing containment.

Containment overpressure (Type A) test aborted to allow repair of those leaks discovered during test. Another Type A test will be perforJ:I!,ed after repairs are complete.

This reporting period ends with the unit at* cold shutdown.

---8-. DOCKET NO c:NIT AR.Arr DA:rE CQ'efPLETED BY 0 J COSTELLO AVERAGE DAILY UNIT ?OWER LEVEL MONTH: FEBRUARY 80 AVERAGE POWER LEVEL AVERAGE DAILY POWER LEVEL DAY (!>fWE':INET)

DAY (M'l'IE f.INET) 1 o.o 16 o.o 2 o.o 11 o.o " o.o 18 o.o .:> 4 o.o 19 ti .a 5 o.o 20 o.o 6 o.o 21 o.o 'J o.o 22 0. t) 8 o.e 23 o.o 9 o.o 24 o.o i' 10 o.o 25 ' fJ. 0 ' 11 0.0 26 o.o 12 o.o 21 o.o 13 .. o ... o 28 o.o 1i.J o.o 29 o.o 15 o.o DAILY UNIT POWER LEVEL FORN. INSTRUCTIONS ON THIS FORMs LIST THE AVERAGE DAILY UNIT POWER LEVEL IN MWE.,.NET FOR EACH DAY IN THE REPORTING MONTH. THESE FIGURES WILL BE USED TO PLOT A GRAPH FOR EACH REPOir.fvi ING MONTH. NO?E THA:f BY USING l*MXIMUM DEPENDABLE CAPACITY FOR THE NET ELECTRIC Mi RATING OF THE UNIT. THERE MAY BE OCCASIONS WHEN THE DAILY AVERAGE POWER EXCEEDS THE 100 °/0 LINE (OR THE RESTRICTED POWER LEVEL LINE). IN SUCH THE AVERAGE DAILY UNIT POWER OUTPUT SHEET SHOULD BE FOOTNOTED TO EXPLAIN THE APPARENT ANOMALY ..

'.J I -----AMEI:IDMENTS" TO FACILITY LICENSE OR TECHNICAL SPECIFICATIONS

--(CO!ITINUED)

--3. Reactor operation shall be terminated if RCS to SS leakage which is attributable to two or more steao generator tubes occurs during a 20 day period. IIB.C approval shall be obtained before resumitig reactor operation.

4. The concentration of radioiodine in the reactor coolant shall be limited to 1 µCi/gram during normal operation and to 10 µCi/gram during power transients as defined in Appendix A-1 to the Technical Specifications of the license. Appendix A-1 was issued with the }lay 6, 1977 Order and shall remain in effect for six equivalent months from October 25, 1979.
  • ' ' r* .Ar*U::NLJrlliNIS ru .fAC.1.Lll l'. LICENSE OR l,t;GHNILAL SP.t.Cll' IGA:IIOHS ee FEBRUARY, 1980 ee On December 20, 1979 the Uuclear Regulatory Commission issued Amendment Uo. 54 to the Operating Licenses for Surry Power Station Unit No. 2, which is designated as Technical Specification Change no. 62. The changes are the result of an llRC request to establish a routine Steam Generator Tube Inspection Program and to incorporate the conditions of the license, Appendix A-1 into the Technical Specifications.

Please note that these changes are applicable only to Unit No. 2. Upon replacement of the Unit No. 1 Steam Generators these specifications will be made applicable to both units. Until such time, Unit Uo*.l is to follow applicable conditions of its license for Steam Generators inspections and reactor coolant activity limitations.

Of significance are the following changes: 1. Revised Specifications incorporating reactor coolant activity limitations similar to Appendix A-1 of the license.

  • 2. Hew Specifications incorporating a routine Steam Generator inspection program similar to Regulatory Guide 1.83, Revision 1. On February 4, 1980, the Nuclear *Regulatory Commission issued amendment No. 55 which modifies Surry Unit No. 1 Operating License. The amendment results from the NRC Staff's review of the Steam Generator Inspection Program. Of significance, the conditions li:rD.it the operation of Surry Unit No. 1 and has the following provisions:
1. Unit No. 1 shall be brought to the cold shutdown *.'condition in order to p*erform an inspection
  • of' the steam generators within six months of equivalent operation from October 25, 1979. Nuclear Regulatory Commission (URC) approval shall be obtained before resuming power operation following this Equivalent operation is defined as operation with the reactor coolant at or above 350°F.
  • 2. Reactor coolant leakage from the reactor coolant system (RCS) to the secondary system (SS) through* the steam generator tubes shall be limited to 0.3 gpm per steam generator, as described in the NRC Safety Evaluation of May 6, 1977. With any steam generator tube leakage greater than this limit the reactor shall be brought to the cold shutdown condition within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.. NRC approval shall be obtained.before resuming reactor operation.

"""'9 ' .., .

--*--. . *' . "J. .!:.::> .L"O::i Al'W J!.Ar

1.;::, J.U:.'=t U .L.t\..Lm., --NRC APPROVAL FEBRUARY, 1980 --None during this reporting period. TEST AlID EXPERIMENTS THAT DID NOT REQUIRE NRC APPROVAL FEBRUARY, 1980 None during this reporting period.

-*

\ .\ y NRC APPROVAL --FEBRUARY, 1980 Uone during this reporting period. Design Changes FACILITY CHAUGES THAT DID NOT .REQUIRE NRC APPROVAL FEBRUARY, 1980 1. DC-79-S28

-Safety Injection on Low Pressurizer Pressure Only Description Unit 1,2 This change converted the automatic safety injection initiated from one of three pair of low pressurizer levels coincident with low pressurizer pressure to a safety injection initiated on two out of three to prevent an RCS underpressure condition from occurring without safety injection.

Summar"y of Safety Evaluation this design change precipitates various Technical Specification changes and impacts upon certain sections of the FSAR, it does constitute an Unreviewed Safety Question.

2. DC-79-S58

-Reactor Coolant System Subcooling Monitor System 2 Description This change installed two subcooling meters on the main control board to provide indications of reactor coolant margin to saturation conditions.

Summary of Safety Evaluation This modification in conformance with THI-2 UUREG-0578 and URC letter of October 30, 1979 does not create an "unreviewed safety question" as defined in lOCFRS0.59.

3. DC-79-S59 High Range Effluent Honitors ls2 Description This design change installs additional effluent monitors with higher ranges as directed in the NRC letter of October 30, 1979. These monitors will be located at the following effluent po in ts. 1. Ventilation Vent Stack 2*. Process Vent 3. Main Steam Lines Summary of Safety Evaluation This modification*

will have no effect on the operation of safety related equipment and will. provide assurance that necessary monitoring capabilities for anticipated release paths are available during and after an accident.

'*--.. ----*---*--*--*------

.. -. -*--******-------------

*---

-*-* -. ------

"' ' ( ) FEBRUARY, 1980 ) --Llone during this reporting period.

) --SURRY POWER. STATION . . CHEMISTRY REPORT

  • FEBBIIABY , 19 _fill_ T...S. 6. 6 .A.11 PRIMARY COOLANT UNIT NO. 1 ANALYSIS MAXIMUM MINIMUM AVERAGE MAXIMUM Gross Radioact., µCi/ml 4.64E-1 l.34E-2 2.35E-l 1.57E-3 Suspended Solids, ppm 1.3 o.o 0.1 . o.o Gross Tritium, µCi/ml 1.43E-1 Ll7E-2 9.42E-2 (*) Iodine-131, µCi/ml 9.82E-3 7 .83E-'3 8.85E-3 *.(*) I-131/I-133 0.4340 0.3800 0.4156 (*) Hydrogen, cc/kg 47.97 3.60 28.12 * (*) Lithium, ppm 1.55 ** 0.61 1.02 (*) . Boron-10, -ppm + 322.03 36.46 122.73 61.94 . OL..-yg en_; 16, ppm. 1.500 o.ooo 0.220 *** SAT. Chloride, ppm 0.09 0.05 0.05 0.05 pH @ 25°C 7.34 4.87 6.42 5.23 +.Boron-10 Boron x Phosphate Sulfate 50% NaOH Remarks: ** Added 1500 . NON-RADIOACTIVE CHEMICAL(!)

RELEASES, POUNDS T.S. 4 .13 .A * .8 5 lbs. >>or on 1,128 lbs. Chromate l1gQQ lb!ii* Chlorine grams of LiOH to ill RCS @ 02-11-80 194 0.07 -1600 UNIT NO.

  • 2 MI;NIMUM 1.57E-3 ,_ o.o (*) (*) (*) (*) (*) 60.96 0.05 5.22
  • includes data during degassing of ill RCS -Unit tripped off line 02-19-80 @ 2215 *** for #2 RCS considered to be saturated

-Local sample AVERAGE l.57E-3 o.o (*) (*) (*) (*) (*) 61.45 ***SAT. 0.05 5.22 (*) #2 Primary isolated from sample sink for maintenance purposes -Letdown secured. These levels of chemicals should present no major adverse environmental impact. c i l ' '* ' ' *' t ; -* ... *I'* **

'*' :**1 . . *.... . : _., .. DESCRIPTION OF ALL INSTANCES WHERE LIMITS "WERE EXCEEDE'

  • February, 1980 Due to impairment of the circulating water system on the following days the thermal discharge limits were exceeded as noted. February 2, 1980 February 11, 1980 February 12, 1980 February 13, 1980 February 14, 1980 February 15, 1980 February 16, 1980 February 17, 1980 February 18, 1980 * * * * *
  • Exceeded 15°F 6T Across Station Exceeded 15°F 6T Across Station Exceeded 15°F 6T Across Station Exceeded 15°F 6T Across Station Exceeded 17.5°F Across Station Exceeded 17.5°F 6T Across Station Exceeded 17.5°F 6T Across Station Exceeded 17.5°F 6T Across Station Exceeded 17.5°F AT Across Station *Indicates dates where station 6T was <15.0°F across the station for time during the day. The 6T excursions were allowable under Technical Specifications 4.14.B.2.

There were no reported instances of. significant adverse environmental

    • -.*.*.
            • -*----*** .

-*--*****----***-**

... -------------*--****----

-.L.,-FUEL HA?IDi.IHG FEBRUARY, 1980 -,. I Forty-Eight (48) new assemblies for Unit 1 5 Cycle 6 were received during February, 1980. '

-U.L't.L.L

  • .l. FUEL HANDLING . ' .. FEBRUARY.

1980 '

  • DATE NO OF ANSI NO. NEW OR SPENT FUEL " '-'-"--'.."--

RECEIVED ASSEMBLIES PER SHIPMENT INITIAL ENRICHMENT SHIPPING CASK ACTIVITY LEVEl 02-07 *80 12 LMOSLK/3.2%

2.5mR/hr.

LM08LN/3.2%

  • 2.5mR/hr.

LM08LR/3.2%

2.5mR/ilr.

LM08LW/3.2%

2.5mR/hr.

LMOSMU/3.4%

2

  • 51!1R/hr
  • LMOSMN/3.4%

2.SmR/hr.

-LMOSMV/3.4%

2.SmR/hr.

LMOBMY/3.4%

2.SmR/hr.

U108/MX/3.4%

2.SmR/hr.

2.SmR/hr.

LM08MU/3.4%

2.SmR/hr.

LMOS/MP-3.4%

2.5mR/hr.

2.SmR/hr. . '*

... 12

/ 1

  • li. "!. ... -*-** .. LM08MR/3.4'l 2.5i.iR/hr.

LM08M0/3.4'l 2.Sm.R/hr.

U108MC/ 3. 2.SmR/hr.

LM08M8/3.4%

2.SmR/hr.

LM08M9/3.4%

2.5mR/hr.

LMOBMS/3.4%

2.SmR/hr.

I i.MOSNK/3.4%

2.SmR/hr.

LM08M7/3.2%

2.5mR/hr.

LMOGLQ/3.2%

2.SmR/hr.

... LMOBLJ/3.2%

2.SmR/hr.

LM08U2/3.2%

2.Sm.R/hr.

02-21-80 . 12 LMOSNG/3.4%

2.SmR/hr.

2.5mR/hr.

LM08UQ/3.4%

2.5mR/hr.

LMOSMF/3.4%

2.SmR/hr. , . -

-**-J.. .... -.-..L FUEL HANDLING Page 19 FEBRUARY.

1980 . . (* J -. . DATE NO OF ANSI NO. NEW OR SPENT FUEL HIPPED/RECEIVED ASSEMBLIES PER SHIPMENT INITIAL ENRICHMENT SHIPPING CASK ACTIVITY LEV: .. .. LMOSMK/3.4%

2.5mR/hr.

Uf08NM/ 3. 4% 2.5mR/hr.

LM08NA/ 3. 2.5mR/hr. . LM08lrn/3.4%

\ 2.5mR/hr.

LM08UR/3.4%

2.SmR/hr.

LH08HE/3.4%

2.5mR/hr.

' -LMOSNC/3.4%

2.5mR/hr. ' LHOSMD/3.4%

2.SmR/hr.

I ' 02-28-80 12 LM08lfZ/3

.4% 2.SmR/hr.

U108MT/:3.4%

2.SmR/hr.

  • -LMOSMA/3.4%

2.SmR/hr. " LM08H9/3.4%

2.SmR/hr.

LMOSMG/3.4%

2.SmR/pr .*

2.SmR/hr.

LM08N0/3.4%

2.5mR/hr.

  • LMOSNF/3.4%

2.SmR/hr.

-LU081U/3.4%

2.SmR/hr.

_ .. LUOSN6/3.4%

2.SmR/hr.

LM08NH/3.4%.

2.SmR/hr.

-LMOSND/3.4%

2.SmR/hr.

-... . .. -*-. ------

1J..4M.1UU..U.1\.:J

---*** *---

  • --No*o-***
  • FEBRUARY, 1980 -DArl:
  • FUEL I NO OF ANSI NO. NEW OR SPENT HIPPED/RECEIVED ASSEMBLIES PER SHIPMENT INITIAL ENRICHMENT SHIPPING CASK ACTIVITY LEVl ' I -None durinsz this reoortinP neriod. .. -;, .. -. -*: r,-... .. I ' ' i i I .. '

-*-. **-*--***

., -* -*----... --* -*-** ..

.. ---*--****-*-------*--***-* -. *-*****--***-----.

-

LDL. OPERATING MODE .DESCRIBED IN THE FSAR e FEBRUARY, 1980 * -.. None during this reporting period.

.. I DESCRIPTION OF PERIODIC TESTSWHICH WERE NOT C LETED WITHIN THE TIME SPE IED IN TECHNICAL SPECIFICATicllr FEBRUARY, 1980 PT-38.29 Service Air and Breathing Air.Compressor Sampling was not completed on the scheduled date (12-29-79).

This test insures that the quality of air used with self contained breathing apparatus, airline respirators, and air supplied hoods and suits meets grade D specifications required by the Surry Respiratory Protection Manual. The air was tested and results received on 02-26-80, approximately two weeks beyond the 25% grace period permitted by Technical cations 4.0.

FEBRUARY, 1980 The ultrasonic, liquid penetrant and visual inspections required by IE Bulletin 79-17, Rev. 1 (Pipe Cracks in Stagnant Borated Water Systems) is complete on Units 1 and 2. No reportable indications were noted. Liquid Welds, Unit were noted. if the unit Penetrant Testing was completed on all Pressurizer Safe End 2, per Westinghouse recommendations.

No reportable indications The Unit 1 Safe End Welds will be inspected in Uarch, 1980, is available.*

The Pre-Service Inspection associated with Uni.t 2 Steam Generator Replacement Project is complete.

No reportable indications were noted. Eddy Current Inspection of the Condenser Unit 2, is in progress.

Eddy Current Inspection of Unit 1 Steam Generator Tubing is in progress, based on Wesinghouse recommendations.

Magnetic Particle Inspection of the Unit 2 Feedwater Penetration Fillet Welds was completed, per Nuclear Regulatory Commission request. No reportable indications were noted. Visual Inspections of the Unit l Hanger Modifications is in progress.

D8'!T=Nfll' f!NITiv< 3/0q/eo (MAINTENANCE OF SAFETY RF.LATED SYS'fEMS DT!RING Ol!TAGE OR RF.Dl!CED lYJWE1? T'ERIODS)

RETS8HVDT SYS COMP MARKNO

SUMMARY

WKT'ERF 02/28/80 CH PIPING UT+Pr WELDS PER IEB '19nH REVI COMrLETED INSP. REST!C,T SAT 02/28/80 RH PIPING VT+!"l' WELDS PER IEB REVI INSPECTION COMPLETED RES/!LW Slt'T' 02/28/80 c.c; PIPING i!T+!"l' WELDS PER IF.:B 19"11 REVI INSPEC'fION COMPL8TED RESllLT SA'f' 02/28/BO RS PIPING UT+IT WELDS PER IEB REVI COMPL8T8D INSPECTION R8Sl/LT SAT 02/28/80 FC I'IPING l/T+TT WELDS I'ER IEB 79"17 REVI COMPLET8D INSP. R8Sl1LT SAT 02/28/80 SI PIPING l!T+FT WELD PER IEB '19d'1 REVI COMPLE.T.eD INSP, RESl!LT SAT DEI'T TOTAL ----------------------MAR 80 11:33 AM I'Ar,F. q I' Mii 'fOTIJ..INTM 1 001250856 6'17 1 001250857 209 1 001250858 6'17 1 001250859 209 1 001250955 6'12 1 001250956 209 ., .. " .... 2653 I N .f:--1 D8Pf=N!Jl l.'NI'f2., 3/04/80 WAIN'l'ENANCE SA1ETY REliA'rED SYSTEMS Df!RING Ol'TAGE OR 17.'fi:Vl.'CED

!'OWl!.'R

!'ERIODS)

RETSERVllf SYS COMP MARKNG Sf.'MMARY WKPl!.'RF 02/14/BO FW I'IrING '&fl! !'l!.'NE'fRA'l'ION lo/ELDS 1'ERf'ORMTf:D ur INS!'ECTIONS

.. SA'l' 02/19/BO Cl/ PIPING & .. c11,,502 RE'MOVE ARC S'!RIKE REMOVTf:D ARC S'fi?IKE 02/21/BO RC PZl7 2 .. Rc-.E .. 2 INSPECT SAFE E'ND WE'LDS ON NOZZLE DID f'f INS!' f.II'r/J 811'1' RJ.JSf!L'fS U2/22/80 MI OTHER PE'RFORM PSI cmtPLT','TED SA'I'WfACTORY 02/28/BO SI PIPING Pf WC:LDS PER IEB '19"11 Rl!.l' 1 COMI'LE'rri.'D l"NSP. RE'Sl!L'I' SA'!' 02/28/BO CH PIPING TT WELDS !'ER IED 79"17 REV 1 COMI'LE'I'ED INS!'. RE'Sf!LT SA'l' 02/28/BO RS l'II'ING l"f WELDS !'ER IEB 79.,17 RE'V 1 COMPLE'fED INSP. RESllLT SAT 02/2B/BO RH !'IPING '!"! WELDS I'ER IEB 79w11 REV 1 COMPUTED INSI'EC'!ION RESf.'L'I' SAT 02/28/80 cs PIPING Pf WELDS I'Eil !EB '19*1'1 RBV 1 COMPL."fl'!ED INSPECTION RE'Sl'L'f SAT DE'Pf T(Yf AL *., .,, If MAR eo 'I< 11:1!0 Alf 1'AGE: s /.' MR 2 001111346 530 2 002011qo9 360 2 001031525 1155 2 908220906

'1322 2 001041140 209 2 0010ll1141 209 2 001041142 209 2 001041145 20!1 2 001oq11116 209 Ol""""-0 '11112 e -r ' . I I'.) l.11 I

  • ' f
  • OCCURRENCES_

PERTAINING TO--OUTAGE OR POWER REDUCTIONS FEBRUARY, 1980 Unit Ho. 1 outage occurred on 02-19-80, when the Architect Engineer analyzing the piping prescribed in IE Bulletin 79-14 reported on stressed condition on lines inside containment leading to penetrations.

The details of this event are recorded in LER 80-018/0lT-0 (050-0280).

        • --*---*****-**-----..o-
  • -*------*---*----***.

--27-Maintenance of Safety Related Systems During Outage or Reduced Power Periods UNIT Ill Mechanical Maintenance

.

....... " OE."f'l*MECll II ftlAR BO ,. 11:33 11M !'AGf: 1 i.'NI'fb 3/011/BO (MAINTENANCE OF SAn:TY RELATED SYSTEMS DURING OlfTAGE Oil Rl!:Vl.'CED

!'OWER PERIODS) RE'l'SEiNllf SYS COMP P.MRKNO Sl.'MfttARY WK PERE' I! r.tR 'fOTWNTM 02J19/BO BR I't!/.JF' 1 .. aR.,r .. 9 INSTALL COVER FOR rt:MP COM!'LETED i 00211122111 101 02)19/80 vs 1 .. vs .. 111: .. 11 RE!'LAC'I!:

E'IL'fEil INSTALLED ROLL TYPE FILTER 1 002160818 5 02/20t80 vs nL'fER 1 .. vs.Ac..i CHANGE E'ILTER REPLACED E'ILTERS 1 0021112119 5 02/20/BO OG VALVE 1roo,s REPLACE BLOWN DIAPHRAGM i CHANGED lJONNE.'T+DIAPHR11M i 002161000 3 02/21/80 vs E'AN/BL'ilR 1"VS11F.OB C/JF.'CK BELTS REPLACED BKLTS 1 002062350 2111 02/21/80 IA PIPING 1"ES .. 101 REPAIR AIR LINE REPAIRED AIR LINE 1 002191130 lj 02/22/BO CH PIPING a .. cn DC '19r832C INSTALL CONSTRAINT COM!'LE'.fED 1 002111111116 126 02/22/BO CH !'I!'ING 3.,cn DC '19,.S32C INS'!ALL CONSTRAINT COMPL8TED 1 002111111l!'l 126 02/22/BO CH PIPING 3*Cll DC INSTALL CONSTRAINT COMPLETED 1 002111111118 126 02/22/80 CH PIPING a .. cH DC 19.,S32C INSTALL CONSTRAINT COMPLE'fT!.'D 1 0021'111fl!9 126 02/22/BO en PIPING 3wCH DC 19mS32C INSTALL CONSTRAINT CON!'LETED 1 00211111151 126 02J22/80 CH PIPING 311Cli DC W9"S32C INSTALL CONSTRAINT COMPLETED 1 00211111152 126 02/22/BO CH PIPING 3:tCH DC INSTALL CONSTRAINT COMPLETED 1 0021l!11153 126 e 02t22/BO CIJ PIPl'NG 3*CH DC INSTALL CONS'.fRAIN'f COMPLETED 1 00211fll!511 126 02/22/BO Cl/ 1'1PING 3"CH DC 99sS32C INSTALL CONSTRAINT COMPLETED 1 00211111156 126 02/22/.80 SS VALVE TV"ss .. 201B llALVE WILL NOT S.fAY CLOSED TESTED SAT 1 0021'11000 120 02)22/BO RC INST ii INSTALL RCS LEVEL HOSE RETl.'RNED RX COOLANT SYS L.W HOSE TO 1 002211900 6 02/22/BO RC PIPING. RA'MOil BLANK E'LANGE INSTALL S!'OOL PIECES 1 022220100 " 02/23/BO CH PIPING 3ooCJI DC 19nS32C INS'.f ALL CONSTRAINT COMPLE'PED 1 0021111115'1 151 02/23/BO CH PI!'ING 3 .. cH DC 1 19nS32C INS.TALL CONSTRAINT COMPLF:TED 1 0021l!1'15B 151 I 02/23}80 Cl/ '!'IPING a .. cn DC 19*S32C INSTALL CONSTRAINT COMPLETED 1 00211111159 151 N. 02/23/BO RH VALVE FCVn160!i ACTCATOR BOLTS ARE MISSING WORKED PERFORMED BY Ql!ALIFIED TECH i 0022111150 30 0' I 02/25/80 MS VALVE BODY TO BONNET LEAK RESl!BMITTED MR TO RESEAT VLV 1 001120'152 2l! tl2/25/80 MS PIPING ELBOW LEAKlNG REPAIRED LEAK AT ELBOW 1 002091500 65 02/26/80 *CH PIPING a .. ocHw99 DC 19 .. S32C INS'IALL CONSTRAINT INS'PALL STRAP CONTRAINT 1* 002181337 5 02/26/BO RL !'I!'ING 3..,RLro DC 99"S32C INSTALL S'.fRA!' CONS'rRAINT INSTALL STRAP CONSTRAINT 1 0021813113 5 02/26/80 RL PIPING 3.,RLs6 lJC 'l9,,S32C INSTALL STRAP CONS'.fRAIN'f INSTAf,L STRAP CONSTRAINT ll. 0021813l!l!

5 02/26/80 RL !'IPING 3mRL"6 DC 79rS32C INSTALL STRAP CONSTRAINT INSTALL CONSTRAINT STRAP 1 0021813115 5 02/26/80 RL PIPING 3,.RLw6 DC INSTALL STRAP CONS'IRAINT INSTALL CONSTRAINT STRAP 1 002181352 5 02/2'1/80 RM MONITOR RM"109/110 LO'il FLOW THROl!GH DETECTOR ADJUSTED INDICATOR ZERO 1 002260730 29 02/2'1/80 RS PIPING MOV.,,RSwlSS.:!

INSTALL BLANK FLANGE FOR l"f 16.11 R.T<:MOVED BLANKS 1 901161530 55 02/27/80 MS VALVE VALVE HAS FLANGE LEAK FIXED FLANGE LE1tK RESEA'l'ED VALB 1 911271330 115 ." .. ., .. DE:!'l' '!OT AL 2349 . Maintenance of Safety Related Systems Durin.s Outage or Reduc.ed Power Periods muT 112 Mechanical Maintenance

iiETSEill/IYl ll'IS COMP 02/26/Btl RS HJ! 02/26/BO Ill V 1ILVE 02/26/80 BS OTllER 02/27/80 CH VALVE DEl"l' TOTAL l!NIT2" 3/0ll/80 (MAINTENANCE OF ,SAFETY RELATED SYSTEMS Dl.'RING O/!TAGE OR 1"?F.Vl!C'f,D

!'OWE1"? '!'ERIODS)

MARKNO Sl!MM1IRY 2 .. RSnE*U B1111NKOf.'F RS SIDE FOR Ll!:AK CllF.CK 2-IA,.701!

VALVE DAMAGE EQl!lP llATCll TES'l' :1. .. c11 .. u*o VALVE DI A!'llR AGM Rrlf'Tl.'RF.:D

f.}i.

F!KI'ERf' llF.MOVEIJ RLllNKS NO MAKS HX LA'!'I'ED GATE VALVP.S TAPPED Tllt"?EADS RE!'LACl!:D BONNET II MAR 80 * :i.1:1!0 AM PAGl'J 2 I! MR TO'rmmw 2 001280902 678 2 002221250 95 2 002231313 27 2 00220221!0 153

"'""il1't'6 I w I-' I

...

  • 0 " .
  • Maintenance of Safety Related Systems During Outage or Reduced Power Periods UNIT /11 Electrical Maintenance DEf'l=t:LEC RETSEilVlll' S'JS COMP 02/19/80 FW MOV 02/26/BO DA INSTR 02/2'1/BO CH HT 02/27/BO RC O'!HER D8I'T TOTAL If l'*MR BO
  • 11:33 AM PAGE 2 f!NI'.f1*

3/04/RO (MAINTENANCTi OF SAFETY RF..'LATETJ SYSTP.MS Dl1RING Of!TAGE OR REDl!CED '!'OWER rERIOVS) MA17KNO SNINMAR'l ii MR TOTDlmTM MOVnFf.1.,,151E DISCONNECT AND RECONNECT

'!'OWER MOV R8!'LACED ON 11/VIT i 1 001061825 1046 .ts .. oA .. UOA ALARM IN Sf/M!' ENTRY T8STED SAT i 0021B201JS 8'1 CHECK AMI'S CHECK CIRCl!ITS CA/!SING AT,/IRAIS ALL OK 1 002211600 49 1 .. RC .. PooiC SHAFT VIBRATION READING 2 MILS LOW 88N'rLEY NF.:1/ ADA PICKl!!'S AlJJl!ST'f.D 1 901012222 355 ""l" ...... ., 1539 i w w I **

.. Maintenance of Safety Related Systems During *outage or Reduced PoYer Periods UNIT 112 Electrical Maintenance

    • --:*-. DF:f"f:rELEC II MAR BO A ii:'IO AN I'AGI!: 3 l!NU'2.., 3/011/80 (MAINTENANCE OF SAFF.T'I RELATED SYS'fl!:MS DURING Of!TAGF.:

OR R/i:DT.'CEIJ

'!'OWER PERIODS) RETSERVllr SYS COM'!' MARKNO SIJMMAR'I WK!'ERF 1.'

'fO'fTX/N'rM 02/03/80 SI INSTR DIC 79 .. 28 RET./IRE !'ZR SI liC'I'f!llTION TO SE'GDS LOG Cl/1lNGE COM!'f,8'I'lf 2 908290Rll'I 1326 02/03/80 IA COMPRESS 2"1,, .. c.,w ill!:MOVE MOTOR !'f.'LLEY INSTAf,Lf!:D NF-'W rf!f,U."Y 2 910262205 953 02/06/BO EPDC BATT 2.,.ED*BATT PERFORM CLEANf.D BATTERIES 2 002030830 79 02/11/80 CH HT BAD HEAT TRACING CIRCllIT RETflRNF:D TO SF:R'IICE 2 002081245 q9 02/11/80 CH HT BAD HEAT TRACING CIRCl!I.T Rl!.'Tl!RNED TO SERVICE 2 0020812116 48 02/13/BO !'E OT/IER 11 .. n PENETRATION LEAKING AND Sl!.ALING I'ENETRllTION 2 001241101 192 02/13/80 PF. OTHl!:R A"n l!NACCEI'fABLE LEAKAGE (!'T 16o2) TESTING AND SEALING PENETRATION 2 001261500 309 -02/13/80 PE OTHER ll2 ELECTRICAL

'l'ENE'.fRATION A,.2 LE11K TESTING AND SEALING PENETRATION 2 001310730 309 02/111/80 SI MOV Mov .. sr,.2a69B MOV !'MS COf.II'LETED l'iS !'ER EMr .. r .. Mov .. 115 2 901251515 2155 02/111/80 . SI MOV Mov .. sI.,2B69B MECHANICS RE'ff!RNED

'1'0 SERVICE 2 903051905

!1295 02/111/80 CH INSTR ncv .. cn .. 2200A INSTALL NEW !J'fY£: 50£f.;NOIOS VALVE SAT 2 904050835 509 02/111/80 vs FAN 2"vs .. F .. 1c CHECK FAN FOR VIBRATION TESTED SAT 2 911020055 22'19 02/lq/BIJ EPDC BATT 281 ONE LIGHT DIM ON GROf!ND PROBLEM CLEARE'D 2 912131200 863 02/15/80 NS NOV MOV .. NS.,,200A MOV f'MS COMI'LETED AS I'ER EMP .. 'l'rof.fOV., 14 5 2 9012511112 18 02/15/80 NS MOV uov .. t1s .. 200B MOV PMS COMI'LETED AS 'l'ER EMP .. UOVellS 2 901251413 18 02/18/80 PE OTllER Jl,,10 'PENETRATION VMKING TESTING AND SEALING PENE'.fRATlOW 2 0012111100 312 02/19/BO SI lJT l'Kf.,2Ml!Ji REPLACE BAD HEAT TAPE REPLACED ENTIRE CIRCUIT 2 907190930 11776 02/22/80 RS MOV Mov .. ns .. 2ssB MOV l'NS COMPLETED AS PER l?Af!'.,P*MOV*ll 5 2 9012515111 112117 02/22/80 RS MOV MOhRS.,2558 ELECTRICALLY DISCONNECT MOY COMPLETED AS PER EMP"C .. MOVr11 2 9011201206 Y312 i 02/22/80 RS MOV Mov .. ns,.255A ELECTRICALLY DISCONNECT MOV COMPLE'l'ED AS I'ER

.. 11 2 9011201207 7312 w V1 02/26/80 Fl/ OTl/ER INSTALL I'OWER Sf!PPLY CARD COMPLETE 2 00211111125 170 I 02/26/80 RS HOV MOV,,,RS.,255A MOV PHS COMPLETED AS PER 2 9012515110 520 '!lllJllll"'" .... OEPf TOTAL ****** ' . ..,

.. ... l

  • ff. ,, ... f. *
  • Maintenance of Safety Related Systems During Outage or Reduced Power Periods UNIT Ill Instrument Maintenance .

Dl':FT*INST RETSERVDT SYS COMP 02/19/.80 Cll IllSTR 02/19/BO CH INSTR 02/20/BO cc INSTR 02/25/BO RH INSTR 02/26/BO RM MONITOR 02/26/BO RM MONITOR 02J2vJeo RM MONITOR 02/21/BO CH VALVE 02/21/BO . SI INSTR 02/.2V/BO SI INSTR 02/2?/BO SI INSTR TJEI"l TOTAL II MAR 80

  • 11:33 AM tlNITh a;oq/eo (MAINTENANCE OF SAE'E'lI REL/i.'l'ED SYSTEMS DllRING OUTAGE OR REDl!C.T!:D l'OWER '!'ERIODS)

MARKNO Sl!MMARY FIKI'ERF f.' /ltR T1w1"1110 TEMP INDICATOR SCALES HIGH REl'AIRiD LEAK 1 00111!06115 T .. 11110 RTD BELIEVED TO BE BAD RE!'AIRED LEAK 1 0011110038 ic .. cc .. 101 VALVE TJOES NOT RESIYJND RE!'LACED FLA!'PER4ADJUSTED CONT 1 002191000 FCV"1605 VLV DOES NOT RESI'OND TO SIGNAL BL.T!:WDOWN R.T!:Gl!LATORS 1 002201200 RM .. vG .. 109 CHECK ALARM AVJl!STED FLOf{ RATE 1 002250'1115 RMnGw .. 101 CHECK. ALARM CHECKED VALV8 LIN'f: 111' AND now 1 002250'1118 RMS .. 163 REPAIR AS NECESSARY VOID DONE ON MR 1002011000 1 001281605 FCV,,CH.,1160 FCV 1160 LEAKS BY ADJl!STED E/.1' VALVE CllECKED SAT 1 002150630 Fhh963 DID NO'l' INDICATE FLO'J ADJl!STED ZT!:RO TRANSMITTER SAT 1 912200900 F1wh962 DID NO'l' INDIC1ITE FLOII ZERO SHIF'l' CHECKED S1IT AF'l'E11 ADJl!S'f 1 912200901 . .fi .. h961 DID NO'l' INDICATE FL<Jrl CHECK8D SAT NO ADJllSTMENT R8Ql!IRED 1 912200902

!'AGE 3 TOTWNTM 99 99 3 9'1 22 22 0 31 126 121 121 °' ...... q e *-I I w """ I *

  • , . '. ,. . *. * * '

of Safety Related Systems During Outage or Reduced Power Periods UNIT 112 Instrument Maintenance DEI'f=INST RETSEii'Vllf SYS COM!' 112/01/80 RM .IIYSTii!

02/13/80 RC VALVE 02/15/80 cc INSTR 02/26/80 RC INSTR 02/26/80 RC INSR 02/26/80 RC INSR DEl"l' TOT AL II MAR BO l'I 1l: 110 AM !'11GE II l.'NIT2., 3/0'i/80 (MAINTE.'NANCE OF SAE'o'TY RELA'fED SYS'fo'MS Dl'RING Ol"f11GE' OR RED/.'CEO I'Olo/l!:R MARKNO Sl!MMARY JIKI'!'RF If MR TO'fDWNT,lf RR.,200 iJfiOKE AC'f ARM RECONNECTED 2 0013106116 211 I/CV., ii'C" 2 5119 CHECK S'fROl!E TRAVE'L FOR '!"1' 16.IO CHECKED VALVE /.fR TO MECHANICS 2 002120900 . 'i n .. cc.2011B i'LOll INS'l'R INO!' RE!'f,ACED TRANSMITTER 2 002031535 9 LT .. 2 .. 11n DOES NO'f TRACK LEVEL TIGHTE'NED WOSE E'ITfINGS FILLED REF 2 002241601 211 L'.f.,2.,481 VOES NO'f TRACK LEVEL TIGHTENED LOOSE FITTING FILLED REF 2 0022111602 24 L'r,,2 .. 1191 DOoS NO'f TRACK LEVEL LOOSE HTTING FILLED REF 2 0022111603 24 .,., ....... 112 ., -e i w . l.O I --) r *I j HEALTH PHYSICS FEBRUARY, 1980 There was no single release of radioactivity specifically associated with an outage that accounted for more than 10% of the allowable annual values in 10CFR20. There was one individual who received a single radiation exposure specifically associated with the Unit no. 2 outage, which accounted for more than 10% of the allowable annual values in 10CFR20 * .101.

-J.-EVIATIONS REVIEWED BY STATION !filCLEAR SAFETY , OPERATlNG COMMITTEE AFTER T IMITS SPECIFIED IN TECHNICAL SPECIFICATIONS FEBRUARY, 1980 NUMBER UNIT TITLE UOP-7.13 2 Leak Test of 2-RS-E-lA r ... , .. -. ' .. "*-'\* DEVIATIONS Steps 3.1, 4.5.5 and 4.6 -Change 45 psig to 40 psig. The above procedure was deviated on February 5, 1980 and reviewed by the Station Nuclear Safety and Operating Comm.ittee February 20,, 1980. PT-16.2 2 Contaimnent Penetration Local Leakage Steps 5.3 and 5.4 -Change pressure to 45 psig. Step 6.1-Change allowable leak ratee Appendix B -2b electrical penetrations not tested due to lack of internal "O" rings. Fuel Building Penetration

-Indicate "body" leakage rather than "weld" leakage. This procedure was c:teviated January 28, 1980 and reviewed by the Station Nuclear Safety and Operating Comm.ittee February 28, 1980.

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