Latest revision as of 04:59, 23 February 2020

Text

Monthly Operating Repts for Feb 1980
	ML18138A093
Person / Time
Site:	Surry
Issue date:	03/01/1980
From:	Costello O; VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To:	;
Shared Package
ML18138A092	List: ML18138A091; ML18138A093;
References
	NUDOCS 8003180459
	Download: ML18138A093 (44)
	v • d • e

. *i.

~.

I .. I

.\ "

VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION r:

MONTHLY OPERATING REPORT REPORT NOo 80-02 FEBRUARY, 1980 APPROVED:

I*

8 OO3 l B otti;-'f _

CONTENTS

' ..ii.*,

Sect:ion Page < -\

I

-Operating Data Report - Unit #1 1 Operating Data Report - Unit #2 2 Unit Shutdowns and Power Reductions - Unit ill 3

-Unit Shutdowns and Power Reductions - Unit #2 4 Load Reductions Due to Environmental Restrictions - Unit ill 5 Load Reductions Due to Environmental Restrictions - Unit #2 6 Average Daily Unit Power Level - Unit Dl 7 Average Daily Unit Power Level - Unit #2 8 Summary of Operating Experience 9 Amendments to Facility License or Technical Specifications 10 Facility Changes Requiring l~C Approval_. 12 Facility Changes That Did Not Require NRC Approval 12 Tests and Experiments-Requiring UR.C Approval 13 Tests and EA"Periments That Did Not Require NR.C Approval 13 Other Changes~ Tests and Experiments 14

. 15 Chemistry Report Description of All Instances Where Thermal Discharge Limits 16 Were Exceeded

Fuel Handling 17 Procedure Revisions That Changed the Operating Mode Described In 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

t ,- '

OPER/..TING DOCKET NO.

50~280

- ~

DATE 06 MAR 80 COMPLETED BY O.J. COSTELLO TELEPHONE 804~357~3184 OPERATING STt.TUS

1. UNIT N/.J.JE SURRY UNIT 1

2. REPORTING PEP.IOD 2~01~so TO 2~29~so

3. LICENSED THER!.JAL POWER (!.fwT) 2441 ,------------------------,

4. N/.l.JE?LJ..TE R/..TING (GROSS W../E) 847.5 !NOTES I

5. DESIGN ELECTRIC/...L R/..TING (NET MWE) 822 I I

6. MAXIMl.:/.'.i DEPENDABLE Ck?ACITY (GROSS /.fvl'E) 811 I I

7. M/.J.IMl!M DEPENDABLE CAPACITY (NET MWE) 775 I I

8. IF CHt!.NGES OCCUR IN C/..?ACITY RATINGS NIA (ITEMS 3 THROUGH 7) SINCE LAST REPORr~ GIVE REASONS

9. POWER LEVEL TO WHICH RESTRICTED~ IF ANY lJ/A (NET MWE)

10. REASONS FOR RESTRICTIONS~ IF ANY N/A THIS MONTH YR~To~DATE CUMULATIVE

11. HOURS IN REPORTING PEP.IOD 696.0 1440.0 63024.0

12. NUMBER OF HOURS REACTOR WAS CRITIC /..L 454.8 1016.2 39169.8

,13.w REACTOR RESERVE SHUTDOWN HOl/RS o.o 182.6 3v31.5

'14~ HOl'RS GENERA!.fOR ON'P.LINE 454.3. 1010.4. 38915.4 15~ l'NI1! RESERVE SHUTDOWN HOURS o.o 187.9 3740.5

16. GROSS THERMAL ENERGY GENERATED (MWH) 1100867.0 2438340.0 90153212.0

11.

GROSS ELECTRIC/..L ENERGY GENERATED (MWH) 355410.0 185655~0 29466153.0.

18. NET ELECTRIC/..L ENERGY GENER/..TED (l&H) 331791.0 ~46810.0 2g973109.0

19. VNIT SERVICE FACTOR 65.3 o/o 70.2 o)o 61.1 o/o

20. UNIT AVAILABILITY FACTOR 65.3 o}o 83.2 oJo 67.~ oJ.o

21. UNIT C/..PACITY FACTOR ([]SING MDC NET) 62.6 o/o 66.9 o/o 51.3 ojo

22. UNIT CAPACITY FACTOR ([,'SING DER NET) 59.0 o/o 63.1 ojo 54.0 o/o

23. UNIT FORCED OUTAGE RK!E 34.7 o/o 29.8 o/o 25.0 o/o 240 SHUTDOWNS SCHEDULED OVER NEXT 6 MONTHS REFl!ELING Jl'NE 19 8 O 6 WEEKS (TYPE~DATE.AND 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 FORECAST 11CHIEVED

(PRIOR TO COMMERCIAL OPERATION)

INITI/..L CRITICALITY INITIAL ELECTRICITY COMMERCI~.L OPERAPION

s*ection

-- ee Maintenance of Safety Related Systems During Outage or Reduced

'Power Periods - Unit #1 - Electrical Maintenance Page

\

32

~ ' \ '

Maintenance of Safety Related Systems During Outage or Reduced Power Periods - Unit #2 - Electrical Maintenance 34 Maintenance of Safety Related Systems During Outage or Reduced Power Periods - Unit ill - lnstrLllilent Maintenance 36

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

O?ERCfING D.A* *RZ'

'. DOCKET NO. so~281 D/..TE 06 MAR 80 COMPLETED BY O.J. COSTELLO TELEPHONE 804~357~3184 .

O?ER/.!fING ST/..!l.'l'S

t. UNIT NAME SURRY UNIT 2

2. RE?OR'rING PERIOD 2~01~so TO 2~29~so .

3. LICENSED THERlef.AL ?OWER (f..FwT) 2441 ,------------------------,

4 o NANE?L/.!fE ii.A.TING (GROSS M"wE) 841.5 !NOTES I

5. DESIGN ELECTRICAL RATING (NET MWE) s22 I I

6 o /.:.A.XINl!M DEPENDABLE C.A.PACITY (GROSS M'wE) s11 I I

':/. M/..XIla!N DEPENDABLE C.A.PACITY (NET Mr'IE) 11s I I So IF CHANGES OCCl.'R IN CAPACITY RMINGS UA '

(ITEMS 3 THROUGH g) SINCE LAST RE?OR'r, GIVE REASONS

9. POWER LEVEL TO WHICH RESTRICTED~ IF Ii.NY N/A (NET M'wE)

10. REASONS FOR RESTRICTIONS, IF />.NY NJA THIS MONTH YR-rtTO~D/J.TE ClJMl'L/J.TIVE

11. HOURS IN REPORTING PERIOD 696.0 1440.0 59904.C

12. NUMBER OF HOl'RS REACTOR WAS CRITICAL o.o o.o 34499~9 130 -REACTOR RESERVE SHUTDOWN HOURS o.o .. o.o o.o

14. _,HOURS GENERA.TOR ON~LINE 0.0 o.o 33996.2 115 ~* UNIT RESERVE SHUTDOWN HOURS o.o .. o.o o.o ** .... i

16. GROSS THERJ.tJAL ENERGY GENERATED (MWH) o.o o.o ~9194083.0

17. GROSS ELECTRICAL ENERGY GENERATED (MWH) o.o o.o 25868844.0

18. NET ELECTRICAL ENERGY GENER/J.TED (MWH) o.o o.o 24536605~0

19. UNIT SERVICE FACTOR o.o o~o 56.8 o}o 200 l'NIT AVAILABILITY FACTOR o.o o.o 56.8 o/o

21. l.,'NIT CAPACITY FACTOR ([}SING /.!DC NET) o.o o.o . 52e 9 o/o

22. UNIT CAPACITY FACTOR (USING DER NET) OoO o.o 49.8 o/o 23g UNIT. FORCED Ol'TAGE RATE OoO OeO - 21.0 ojo

24. SHUTDOWNS SCHEDULED OVER NEXT 6 MONTHS (TYPE ~D~.TE ,.AND DlJRA.TION OF EACH) 250 IF SBl.'T DOWN AT END OF REPORT PERIOD~ 5/5/80 ESTIM/..TE D/J.TE OF ST/J..RTlJP 26~ UNITS IN TEST STAXUS FORECAST . ACHIEVED (PRIOR TO COMMERCIAL OPERATION)

INITIAL CRITICALITY INITIAL ELECTRICITY COMMERCI;.L OPERATION I

.* : * *._. ***~ **.. ~-~ ** *-* ~~T * *** ., *- *.* ~---*-*---. ~--1

--",.~

DOCKET NO.

50:-280 UNIT SHUTDOWNS AND POWER REDUCYiONS SURRY UNIT 1

UNIT NAME DATE 3/1/80 COMPLETED BY O.J. COSTELLO REPORT MONTH FEBRUARY 1980 (804) 357-318(+

TELEPHONE Dale

=-

.2 !!?

-~ :s Licensee Even I Cause & Corrective Action io Nu. 0

s :c Report# Prc~*cnl Recurrence c-8-4 2-19-80 F 241;,7 D 1 80-018 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.

i . A turbine inspection was commenced immediately after shutdown due to above normal vibration experi~nced immediately prior to unit shutdown and to conduct inspections of the low pressure rotor discs.

3 4 F: Forced Reason: Method: Exhibir G

Instructions S: Scheduled A-Equipment Failure {Explain) I-Manual* for Preparation of Data.

B-Malnienance oi Test 2-Manual Scram. Entry Sheets for Licensee

('-Refueling 3-Aulumalic Scram. Event Reporl (LER) File (NUREG*

O~Regulatory Restriction 4-0lher (Explain) 0161)

IE-Operator Training & License Examination f'-Administrail've

5 G-Operallonal Error (Explain) , Exhibit I *Same Soun:!?

CtJ/77) H-Othcr (Explain)

TIONS DUE TO ENVIRONMENTA~ ' .

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

MONTHLY TOTAL 50-281 UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO.

UNIT NAME SURRY UNIT 2 COMrLETED BY l>ATE

-#.-¥. 8osTELLO 8

REPORT MONTH FEBRUARY 1980 TELEPllONE (804) 357-3184

- c_

.:a ~

f"I

§ 0 c

!:II ...

0

.,, licensee E"f' cu u c

cu.,'I c cu Cause & Corrective cu 0 "t:1 Nu. D:ilc

~

p. ...

e :s o

s :I: ~

Ill

"'u

J *-

"'O

.c :;

u .cc

°'u Even I Repnrl #

t; "2 ti] u

p. 0 Eu 0

Aclion lo Prevent Recurrence c- ::!: !I) ~ u c '*

80-2 2-1-80 s 696 c 1 Continuation of shutdown for refueling and steam generator replacement which began on 2/4/79.

. .1 1

) .

3 4 F.: Forced Reason: Method: Exhibir G

Instructions S: Scheduled A-Equipment Failure (Explain) I-Manual for Preparation of Data B-Maintenance or Test 2-Manual Scram. Entry Sheets for Licensee

('-Refueling 3-Aulomatic Scram. Event Report (LER) File (NUREG* .

D-Regulatory Restvictiun 4-0ther (Explain) 0161) .

E-Operator Training & License Examination s -~

F-Administrative G-Operailooal Errm (Explain) Exhibit I

Same Source II-Other (Explain)

DOCKET NO so~2ao l/N. f}JJjRY I

f

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 1~ i5Qo3 3 t?50e3 18 94~.,1

'1149.,4 19 592 .. 5 5 ~49e6 20 o.o 6 1151., 8 21 o. o 7 ?49 .. 2 22 o. o s ~50.3 23 o.. o 9 ?49.,5 24 o.o 10 949 .. 6 25 o.. o .

11 946.9 26 e.o 12 ~445.8 2~ G.. O 13 ~4_6.3 28 o.o 14 146 .. 9 29 o.o 15 11411.1

\

DAILY lJNIT POWER LEVEL FORM INSTRUCTIONS ON THIS FORM~ LIST THE AVERAGE DAILY UNIT POWER LE:VEL IN MWE~NET 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 CASES~ 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 ~*IONS ,...._ ' ' I UNIT NO. 2 MONTH: February, 1980 DATE

- - TIME HOURS lOAD 2 MW REDUCTIONS 2 MW HWil

~.-*~r 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 sign-ificant non-load related incidents.

UNIT 1 February 1 - This reporting period begins with the unit at 100% power.

February 2 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.

February-:8 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.

February 19 - 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 ov~rstressed condition on the piping penetra-

,- 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.

_February 20 - Commenced RCS cooldown at 0403. RCS at 350°F/450 PSIG at 0855~

RCS at cold shutdown at 1257.

February 21 ~ Commenced inspection of LP turbine rotors due to above normal vibration experienced imlnediately prior to unit shutdown.

February 29 ~ This reporting period ends with the unit at cold shutdown.

UNIT 2 February 1 This reporting period begins with the unit at cold shutdown, all fuel removed from the reactor and steam generator replacement in progresso February 25 = At 1937 commenced pressurizing Unit 2 containment to 45 PSIG for Type A testo February 26 = Containment pressure reached 45 PSIG at 0547.

February 28 - 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.

February 29 - This reporting period ends with the unit at* cold shutdown.

DOCKET NO 50~281 c:NIT AR.Arr DA:rE ,.~1~0 CQ'efPLETED BY 0 J COSTELLO AVERAGE DAILY UNIT ?OWER LEVEL MONTH: FEBRUARY 80 AVERAGE D~.ILY 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 CASES~ THE AVERAGE DAILY UNIT POWER OUTPUT SHEET SHOULD BE FOOTNOTED TO EXPLAIN THE APPARENT ANOMALY ..

AMEI:IDMENTS" TO FACILITY LICENSE OR TECHNICAL SPECIFICATIONS

'.J I 3.

(CO!ITINUED)

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.

~ .Ar*U::NLJrlliNIS ru .fAC.1.Lll l'. LICENSE OR l,t;GHNILAL SP.t.Cll' IGA:IIOHS """'9 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 r* 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 inspect~on.

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.

-. --*- **-<'*-----~---:-~~--*-. -*

~--.

"J. .!:.::> .L"O::i Al'W J!.Ar J:..l\.Lr'J..C.l~ :1.;::, J.U:.'=t U .L.t\..Lm.,

None during this reporting period.

NRC APPROVAL FEBRUARY, 1980 TEST AlID EXPERIMENTS THAT DID NOT REQUIRE NRC APPROVAL FEBRUARY, 1980 None during this reporting period.

NRC APPROVAL FEBRUARY, 1980 Uone during this reporting period.

FACILITY CHAUGES THAT DID NOT .REQUIRE NRC APPROVAL FEBRUARY, 1980

\

Design Changes Unit

.\

y 1. DC-79-S28 - Safety Injection on Low Pressurizer Pressure Only 1,2 Description 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

~n1ile this design change precipitates various Technical Specification changes and impacts upon certain sections of the FSAR, it does n~t 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 10CFRS0.59.

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 UNIT NO.

2 i ANALYSIS l MAXIMUM MINIMUM AVERAGE MAXIMUM MI;NIMUM AVERAGE '

Gross Radioact., µCi/ml t; 4.64E-1 l.34E-2 2.35E-l 1.57E-3 1.57E-3 l.57E-3 Suspended Solids, ppm 1.3 o.o 0.1 . o.o o.o 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 60.96 61.45

. *I'*

OL..-yg en_;16, ppm. 1.500 o.ooo 0.220 *** SAT. ***SAT~ ***SAT.

~

Chloride, ppm 0.09 0.05 0.05 0.05 0.05 0.05 pH @ 25°C 7.34 4.87 6.42 5.23 5.22 5.22

+.Boron-10 ~Total Boron x 0~196 NON-RADIOACTIVE CHEMICAL(!)

RELEASES, POUNDS T.S. 4 .13 .A *.8 Phosphate 5 lbs. >>oron 194 Sulfate 1,128 lbs. Chromate 0.07 50% NaOH l1gQQ lb!ii* Chlorine Remarks: ** Added 1500 grams of LiOH to ill RCS @ 02-11 1600

includes data during degassing of ill RCS - Unit tripped off line 02-19-80 @ 2215

- - O~ for #2 RCS considered to be saturated - Local sample

(*) #2 Primary isolated from sample sink for maintenance purposes - Letdown secured.

(~) These levels of chemicals should present no major adverse environmental impact.

c

DESCRIPTION OF ALL INSTANCES WHERE

~DISCHARGE. 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 Exceeded 15°F 6T Across Station February 11, 1980

Exceeded 15°F 6T Across Station February 12, 1980

Exceeded 15°F 6T Across Station February 13, 1980

Exceeded 15°F 6T Across Station February 14, 1980

Exceeded 17.5°F ~T Across Station February 15, 1980

Exceeded 17.5°F 6T Across Station February 16, 1980

Exceeded 17.5°F 6T Across Station February 17, 1980 Exceeded 17.5°F 6T Across Station February 18, 1980 Exceeded 17.5°F AT Across Station

Indicates dates where station 6T was <15.0°F across the station for some-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 impact*~

- 1 .

- - - - -*----*** . *-*~*--.---*-- *****----***-** ... - ---- --------*--****----

FUEL HA?IDi.IHG FEBRUARY, 1980 -,. ~. '

I Forty-Eight (48) new assemblies for Unit 1 5 Cycle 6 were received during February, 1980.

FUEL HANDLING

.' .. FEBRUARY. 1980

' ~

~I

DATE NO OF ANSI NO.

'-'-"--'. "-- RECEIVED NEW OR SPENT FUEL

" ASSEMBLIES PER SHIPMENT INITIAL ENRICHMENT SHIPPING CASK ACTIVITY LEVE 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.

LMOSNP/3.4~~ 2.SmR/hr.

LM08MU/3.4% 2.SmR/hr.

LMOS/MP-3.4% 2.5mR/hr.

02-J.,~-so

... 2.SmR/hr.

12 T.M:nJ:~M~ / 1

li. "!. ... -*-** ..

LM08MR/3.4'l 2.5i.iR/hr.

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

U108MC/ 3. 4~' 2.SmR/hr.

LM08M8/3.4% 2.SmR/hr.

LM08M9/3.4% 2.5mR/hr.

LMOBMS/3.4% 2.SmR/hr.

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.

LM08M6/3.47~ 2.5mR/hr.

LM08UQ/3.4% 2.5mR/hr.

LMOSMF/3.4% 2.SmR/hr.

..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. 4/~ 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.

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.*

LM08N5/3.4i~ 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.

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

No*o- ***

FEBRUARY, 1980 DArl: *I NO OF ANSI NO. NEW OR SPENT FUEL HIPPED/RECEIVED ASSEMBLIES PER SHIPMENT INITIAL ENRICHMENT SHIPPING CASK ACTIVITY LEV I

None durinsz this reoortinP neriod.

~

I

--- ... --* - *-** .. ---p~*--*-* .. --- *-

rAU~~~UL'U:. ~VL~~v~~ ~n...~~ ~W\l.'l~Ll.I LDL.

OPERATING MODE .DESCRIBED IN THE FSAR e FEBRUARY, 1980 * -..

None during this reporting period.

DESCRIPTION OF PERIODIC TESTSWHICH WERE NOT C LETED WITHIN THE TIME LIMITS.~

I 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 Specifi~

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 Penetrant Testing was completed on all Pressurizer Safe End Welds, Unit 2, per Westinghouse recommendations. No reportable indications were noted. The Unit 1 Safe End Welds will be inspected in Uarch, 1980, if the unit 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 ~fain Condenser Tubing~ 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' ~ MAR 80 ~ 11:33 AM I'Ar,F. q 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 I' Mii 'fOTIJ..INTM 02/28/80 CH PIPING UT+Pr WELDS PER IEB '19nH REVI COMrLETED INSP. REST!C,T SAT 1 001250856 6'17 02/28/80 RH PIPING VT+!"l' WELDS PER IEB 79~17 REVI INSPECTION COMPLETED RES/!LW Slt'T' 1 001250857 209 02/28/80 c.c; PIPING i!T+!"l' WELDS PER IF.:B 19"11 REVI INSPEC'fION COMPL8TED RESllLT SA'f' 1 001250858 6'17 02/28/BO RS PIPING UT+IT WELDS PER IEB 79P1~ REVI COMPL8T8D INSPECTION R8Sl/LT SAT 1 001250859 209 02/28/80 FC I'IPING l/T+TT WELDS I'ER IEB 79"17 REVI COMPLET8D INSP. R8Sl1LT SAT 1 001250955 6'12 SI PIPING l!T+FT WELD PER IEB '19d'1 REVI COMPLE.T.eD INSP, RESl!LT SAT 02/28/80 DEI'T TOTAL 1 001250956 2653 209 I

N

.f:--

1

D8Pf=N!Jl If MAR eo 'I< 11:1!0 Alf 1'AGE: s l.'NI'f2., 3/04/80 WAIN'l'ENANCE o~* SA1ETY REliA'rED SYSTEMS Df!RING Ol'TAGE OR 17.'fi:Vl.'CED !'OWl!.'R !'ERIODS)

RETSERVllf SYS COMP MARKNG Sf.'MMARY WKPl!.'RF /.' MR 'rOTl~NTM 02/14/BO FW I'IrING '&fl! !'l!.'NE'fRA'l'ION lo/ELDS 1'ERf'ORMTf:D ur INS!'ECTIONS .. SA'l' 2 001111346 530 02/19/BO Cl/ PIPING &.. c11,,502 RE'MOVE ARC S'!RIKE REMOVTf:D ARC S'fi?IKE 2 002011qo9 360 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 2 001031525 1155 U2/22/80 MI OTHER PE'RFORM PSI cmtPLT','TED SA'I'WfACTORY 2 908220906 '1322 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'!' 2 001041140 209 02/28/BO CH PIPING TT WELDS !'ER IED 79"17 REV 1 COMI'LE'I'ED INS!'. RE'Sf!LT SA'l' 2 0010ll1141 209 02/28/BO RS l'II'ING l"f WELDS !'ER IEB 79.,17 RE'V 1 COMPLE'fED INSP. RESllLT SAT 2 001041142 209 02/2B/BO RH !'IPING '!"! WELDS I'ER IEB 79w11 REV 1 COMPUTED INSI'EC'!ION RESf.'L'I' SAT 2 001041145 20!1 02/28/80 DE'Pf T(Yf AL cs PIPING Pf WELDS I'Eil !EB '19*1'1 RBV 1 COMPL."fl'!ED INSPECTION RE'Sl'L'f SAT 2 001oq11116 209 Ol""""-0

'11112 e I

I'.)

l.11 I

-r

~~LE OCCURRENCES_ PERTAINING TO-

- OUTAGE OR POWER REDUCTIONS f

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 over-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- *-*------*---*----***. -

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 ~'IL'PER 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 19~S32C 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 02t22/BO CIJ 02/22/BO Cl/

02/22/.80 SS PIPING PIPl'NG 1'1PING VALVE 3:tCH 3*CH 3"CH TV"ss .. 201B DC 19~S32C INSTALL CONSTRAINT DC ~9~S32C INSTALL CONS'.fRAIN'f DC 99sS32C INSTALL CONSTRAINT llALVE WILL NOT S.fAY CLOSED COMPLETED COMPLETED COMPLETED TESTED SAT 1

1 1

1 0021l!11153 00211fll!511 00211111156 0021'11000 126 126 126 120 e

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 02/23/BO CH PIPING PI!'ING 3ooCJI 3..cH DC 19nS32C INS'.f ALL CONSTRAINT DC 119nS32C INS.TALL CONSTRAINT COMPLE'PED COMPLF:TED 1

1 0021111115'1 0021l!1'15B 151 151

" 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 0' i 0022111150 30 I 02/25/80 MS VALVE 1~MSn83 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 79~S32C 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 DE:!'l' '!OT AL VALVE llCVwMSw10~ VALVE HAS FLANGE LEAK FIXED FLANGE LE1tK RESEA'l'ED VALB 1 911271330 115 2349

Maintenance of Safety Related Systems Durin.s Outage or Reduc.ed Power Periods muT 112 Mechanical Maintenance

II MAR 80 * :i.1:1!0 AM PAGl'J 2 l!NIT2" 3/0ll/80 (MAINTENANCE OF ,SAFETY RELATED SYSTEMS Dl.'RING O/!TAGE OR 1"?F.Vl!C'f,D !'OWE1"? '!'ERIODS) iiETSEill/IYl ll'IS COMP MARKNO Sl!MM1IRY F!KI'ERf' I! MR TO'rmmw 02/26/Btl RS HJ! 2.. RSnE*U B1111NKOf.'F RS SIDE FOR Ll!:AK CllF.CK llF.MOVEIJ RLllNKS NO MAKS HX 2 001280902 678 02/26/BO Ill V1ILVE 2-IA,.701! VALVE DAMAGE LA'!'I'ED GATE RE!~ACEIJ VALVP.S 2 002221250 95 02/26/80 BS OTllER EQl!lP llATCll TES'l' TAPPED Tllt"?EADS 2 002231313 27 02/27/80 CH VALVE :1. .. c11 .. u*o VALVE DI A!'llR AGM Rrlf'Tl.'RF.:D RE!'LACl!:D BONNET 2 00220221!0 153 e,"P"~""'*w DEl"l' TOTAL "'""il1't'6 I

w I-'

I

f.}i.

_~:

0 Maintenance of Safety Related Systems During Outage or Reduced Power Periods UNIT /11 Electrical Maintenance

DEf'l=t:LEC 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)

RETSEilVlll' S'JS COMP MA17KNO SNINMAR'l YllI'ER~' ii MR TOTDlmTM 02/19/80 FW MOV MOVnFf.1.,,151E DISCONNECT AND RECONNECT '!'OWER MOV R8!'LACED ON 11/VIT i 1 001061825 1046 02/26/BO DA INSTR .ts.. oA .. UOA ALARM IN Sf/M!' ENTRY T8STED SAT i 0021B201JS 8'1 02/2'1/BO CH HT CHECK AMI'S CHECK CIRCl!ITS CA/!SING AT,/IRAIS ALL OK 1 002211600 49 02/27/BO RC O'!HER 1.. RC .. PooiC SHAFT VIBRATION READING 2 MILS LOW 88N'rLEY NF.:1/ ADA PICKl!!'S AlJJl!ST'f.D 1 901012222 355

""l" ...... .,

D8I'T TOTAL 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.' ~117 '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 EMP~r~l!:I'DC-29 CLEANf.D BATTERIES 2 002030830 79 02/11/80 CH HT BAD HEAT TRACING CIRCllIT RETflRNF:D TO SF:R'IICE 2 002081245 q9 CH HT BAD HEAT TRACING CIRCl!I.T Rl!.'Tl!RNED TO SERVICE 02/11/80 2 0020812116 48 02/13/BO !'E OT/IER 11.. n PENETRATION LEAKING ~rT~S.TING 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 DISCONNECT~RECONNECT.FOR 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 TE.~fED 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 TRACIN~ 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 EMr~cPMov .. 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 F.MP~r-uov~11s 2 9012515110 520

'!lllJllll"'" . . . .

OEPf TOTAL ******

~ .. ...

l

ff. ,, . . .

Maintenance of Safety Related Systems During Outage or Reduced Power Periods f.

UNIT Ill Instrument Maintenance .

Dl':FT*INST II MAR 80

11:33 AM !'AGE 3 tlNITh a;oq/eo (MAINTENANCE OF SAE'E'lI REL/i.'l'ED SYSTEMS DllRING OUTAGE OR REDl!C.T!:D l'OWER '!'ERIODS)

RETSERVDT SYS COMP MARKNO Sl!MMARY FIKI'ERF f.' /ltR TOTWNTM 02/19/.80 Cll IllSTR T1w1"1110 TEMP INDICATOR SCALES HIGH REl'AIRiD LEAK 1 00111!06115 99 02/19/BO CH INSTR T.. 11110 RTD BELIEVED TO BE BAD RE!'AIRED LEAK 1 0011110038 99 02/20/BO cc INSTR ic..cc .. 101 VALVE TJOES NOT RESIYJND RE!'LACED FLA!'PER4ADJUSTED CONT 1 002191000 3 02/25/BO RH INSTR FCV"1605 VLV DOES NOT RESI'OND TO SIGNAL BL.T!:WDOWN R.T!:Gl!LATORS 1 002201200 9'1 02/26/BO RM MONITOR RM.. vG .. 109 CHECK ALARM AVJl!STED FLOf{ RATE 1 002250'1115 22 02/26/BO 02J2vJeo 02/21/BO CH 02/21/BO . SI RM RM MONITOR MONITOR VALVE INSTR RMnGw .. 101 RMS.. 163 FCV,,CH.,1160 Fhh963 CHECK. ALARM REPAIR AS NECESSARY FCV 1160 LEAKS BY DID NO'l' INDICATE FLO'J CHECKED VALV8 LIN'f: 111' AND now VOID DONE ON MR 1002011000 ADJl!STED E/.1' VALVE CllECKED SAT ADJl!STED ZT!:RO TRANSMITTER SAT 1

1 1

1 002250'1118 001281605 002150630 912200900 22 31 126 0 e 02/.2V/BO SI INSTR F1wh962 DID NO'l' INDIC1ITE FLOII ZERO SHIF'l' CHECKED S1IT AF'l'E11 ADJl!S'f 1 912200901 121 02/2?/BO SI INSTR . .fi.. h961 DID NO'l' INDICATE FL<Jrl CHECK8D SAT NO ADJllSTMENT R8Ql!IRED 1 912200902 121

°' ...... q TJEI"l TOTAL ~111 I

w

"""I

-I

~..aintenance of Safety Related Systems During Outage or Reduced Power Periods UNIT 112 Instrument Maintenance

DEI'f=INST II MAR BO l'I 1l: 110 AM !'11GE II r

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 !'~'RIODS)

RETSEii'Vllf SYS COM!' MARKNO Sl!MMARY JIKI'!'RF If MR TO'fDWNT,lf 112/01/80 RM .IIYSTii! RR.,200 iJfiOKE CON~l' AC'f ARM DISCOl'INeCTE'D~ RECONNECTED 2 0013106116 211 02/13/80 RC VALVE I/CV., ii'C" 2 5119 CHECK S'fROl!E TRAVE'L FOR '!"1' 16.IO CHECKED VALVE /.fR TO MECHANICS 2 002120900 . 'i 02/15/80 cc INSTR n ..cc.2011B i'LOll INS'l'R INO!' RE!'f,ACED TRANSMITTER 2 002031535 9 02/26/80 RC INSTR LT .. 2.. 11n DOES NO'f TRACK LEVEL TIGHTE'NED WOSE E'ITfINGS FILLED REF 2 002241601 211 02/26/80 RC INSR L'.f.,2.,481 VOES NO'f TRACK LEVEL TIGHTENED LOOSE FITTING FILLED REF 2 0022111602 24 02/26/80 RC INSR L'r,,2 .. 1191 DOoS NO'f TRACK LEVEL TIGllT.~'NED LOOSE HTTING FILLED REF 2 0022111603 24 DEl"l' TOT AL 112

-e i

w

. l.O I

~-

)

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 r ...,..-.

~;

SAFETY ,OPERATlNG COMMITTEE AFTER T IMITS "*-'\*

SPECIFIED IN TECHNICAL SPECIFICATIONS FEBRUARY, 1980 NUMBER UNIT TITLE DEVIATIONS UOP-7.13 2 Leak Test of 2-RS-E-lA 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 Steps 5.3 and 5.4 -

Local Leakage 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.

ML18138A093: Difference between revisions

Latest revision as of 04:59, 23 February 2020

Text

SUMMARY

Navigation menu

ML18138A093: Difference between revisions

Latest revision as of 04:59, 23 February 2020

Text

SUMMARY

Navigation menu

Search