ML20062J895
| ML20062J895 | |
| Person / Time | |
|---|---|
| Site: | Surry  |
| Issue date: | 11/05/1980 |
| From: | Dunn S VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.) |
| To: | |
| Shared Package | |
| ML18139A821 | List: |
| References | |
| NUDOCS 8011140388 | |
| Download: ML20062J895 (48) | |
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VIRGINIA ELECTRIC AND POWER COMPANY SL/SY POWER STATION MONTHLY OPERATING REPORT REPORT NO. 80-10 OCTOBER, 1980 APPROVED:
_I- L 5/h.
E AGER 801114g3gg
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CONTENTS I
i i
1 Section i
Pm -
f Operating Data Report - Unit #1 1 i
! Operatin'g Data Report - Unit #2 2 1
] Unit Shutdowns and Power Reductions - Unit #1 3
.I i Unit Shutdowns and Power deductions - Unit #2 4 l
l Load Reductions Due to Environmental Restrictions - Unit #1 5 1
j Load Reductions Due to Environmental Restrictions - Unit #2 6 i
j Average Daily Unit Power Level - Unit #1 7 1
[ Average Daily Unit Power Level - Unit #2 8 1 1
Summary of Operating Experience 9 Amendments to Facility License or Technical Specifications 10 Facility Changes Requiring NRC Approval 11 Facility Changes That Did Not Require NRC Approval 11 j Tests and Experiments Requiring ERC Approval 13 Tests and Experiments That Did Not Require NRC Approval 13 1
Other Changes, Tests and Experiments 14 j Chemistry Report 15 i
Description of All Instances Where Thermal Discharge Limits 16
) Were Exceeded 1
Fuel Handling 17 l Procedure Revisions That Changed the Operating Mode Described In 19 The FSAR Description of Periodic Tests Which Were Not Completed Within The 20 Time Limits Specified In Technical Specifications i
Inservice Inspection 21 Reportable Occurrences Pertaining to Any Outage or Power Reductions 23 Maintenance of Safety Related Systems During Outage or Reduced Power 24 4
4 Periods - Unit #1 - Mechanical Maintenance Maintenance of Safety Related Systems During Outage or Reduced Power 32 Periods - Unit #2 - Mechanical Maintenance i
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~ 11 f CONTENTS Section Py i Maintenance of Safety Related Systems During Outage or Reduced 34 l Power Periods - Unit #1 - Electrical Maintenance
- Maintenance of Safety Related Systems During Outage or Reduced 37 Power Periods - Unit #2 - Electrical Maintenance Maintenance of Safety Related Systems During Outage or Reduced 39 Power Periods - Unit #1 - Instrument Maintenance Maintenance of Safety Related Systems During Outage or Reduced 41 Power Periods - Unit #2 - Instrument Maintenance Health Physics Summary 44 i
Procedure Deviations Reviewed by Station Nuclear Safety and 45 Operating Com=ittee af ter Time Limits Specified in T.S.
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OPERATING DATA REPORT 1
} DOCXET NO. 50-280 DATE 05 NOV 80 COMPLETED BY SUE D. DUNf; TELEPHONE 804-357-3184
} OPERATIN.G . STATUS
, 1. UNIT NAME SURR1 J?!!T 1 i
2
- 2. RElORTING PERIOD 100180 103180
- 3. LICENSED THERMAL POWER (Mo'T) 2441 l l
- 4. NAMEPLATE RATING (GROSS KdE) 847.5 l NOTES I
- 7. NAXIMUM DEPENDAELE CAPACITY (NET WE) 704
- 6. IF CHANGES OCCUR II: CA?ACITY RATINGS N/A
\ (ITEMS 3 THROUGH T) SINCE LAST REPORT, GIVE REASONS l
- 9. POn'ER LEVEL TO WHICH RESTRICTED, IF ANY N/A (llE" lWE)
- 10. REASONS FOR RESTRIC:IOl:3, IF Al.1 N/A
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THIS VONTH YR-TO-DATE CUXULATIVE i
1*.. HOURS IN REIGE:IliG PERIOD 745.0 7320.0 68904.0
- 12. NUMEER OF HOURS REA: TOR k'AS CRITICAL 0.0 3786.9 42538.5
- 13. REACTOR RESERVE SHUTDOdi; EOURS C.0 182.6 3731.5 14 HOURS GENERATOR ON-LINE O.0 3763.8 41668.8
- 15. Ui;II RESERVE SHU:DOdi; HOURS 0.0 183.6 3736.2
- 16. GROES THERL:AL EliERGY GENERA:ED (!GH) 0.0 8674529.0 96389401.0
- 17. GROSS ELEC:RICAL ENERGY GENERATED (KdH) 0.0 2621245.0 31301743.0
- 18. NET ELECTRICAL ENERGY GENERATED (Kn'ii) 0.0 2473025.0 29699924.0
- 19. UNIT SERVICE FACTGR 0.0 */* 51.4 */* 60.5 */*
, 20. U:IT AVAILAEILI:1 FACIOR 0.0 */* 53.9 */* 65.9 */*
- 22. UNIT CAPA:I:Y FAC:OR (USIi/C DER NET) 0.0 */* 41.1 */* 52.4 */*
, 23. UNIT FORCED OUTAGE RATE 0.0 */* 39.1 */* 26.4 */*
i 24 SHUTDOdi:S SCHEDULED OVER liEXT 6 MONTES l
(TYPE,DATE,AND DURATIOi! OF EACH) i i 25. IF SHUT DCd6 AT Ei;D OF REPORT PERIOD, SEPT 1. 1981 ESTIVA:E DATE OF STARTU?
- 26. UNITS Il. TEST STA:US FORECAS: ACHIEVED LFRIOR TO COXYERCIAL OPERATIOi;)
II;ITIAL CRITICALITY INITIAL ELECTRICITY COMYERCIAL OPERATION A
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OPERATING DATA REPORT DO:EET NO. 50-281 DATE 05 NOV 80 uo.v..r
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. u va a .. w TELEPHOllE 804-357-3184 OPERATING STATUS
- 1. UliIT NAME SURRY UNIT 2
- 2. REPORTII;G PERIOD 100180 103180 ~^
- 3. LICEiSEL THERMAL PO;;ER (l-ldT) 2441 l ~~- l 4 NAME? LATE RATING (GROSS AVE) 847.5 l NOTES l S. DESIGN ELECTRICAL RATING (iiE' XaE) 822 l l
- 6. MAXIMU'* DEPENDAE:E CAPACITY (GROSS !4'E) 811 l l
- 7. NAXIYUM DEFENDAELE CAPACITY (NET N.'E) 775 l l
- 8. IF :HA;iGES OCCUR IN CA?ATITY RATINGS N/A (ITEMS 3 THROUGH 7) SIN:E LAST REPORT, GIVE REASONS
- 9. P3.;ER LEVEL TO WHICH REETRICTEO. IF Ai Y ui A t ., .r. . , . .,- c. )
- 10. REASONS FOR RESTRICTIONS. IF Al;Y N/A THIS MONTH YR-TO-DATE CUMULATIVE
- 11. HOURS IN REPOETING ?ERIOD 745.0 7320.0 65784.0
- 12. ?!UMEER OF HOURS REA: TOR WAS CRITICA:. 145.0 1828.~ 36326.6
- 13. REA: TOR RESEhVE SHUTDWll HOURS 0.0 0.0 0.0 14 liOURS GENERATOR ON-LINE 745.0 1690." 35686.9 L5. Ui;IT REEERVE SH E DOdl! HOURS o.0 0.0 0.0
- 16. GROSS TH5hKA: ENERGY GE::ERATED (Ydii) 1814032.0 3733719.0 82927802.0 1~. GROES ELE:TRICAL ENERGY GE!;ERATED (?.'un) 596060.0 1209120.0 27077964.0 la. NET ELECTRICAL ENERGY GENERATED (NiH) 567250.0 1139888.0 25676493.0
- 19. UNIT SERVICE FACTOR 100.0 */o 23.1 */o 54.2 */o
- 20. UNIT AVAILAEILITY FACTOR 100.0 */e 23.1 o/e 54.2 */e
- 22. Ui;IT CAPA:ITY FACTOR (URING DER iiET) 92.6 e/o 16.9 e/e 47.5 e/e
- 23. UNIT FOh:EC OUTAGE RATE o.0 4.9 e/o 20.5 e/e 2, . .>...a.:
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- 25. IF SE X DOdi. AT E:iD OF REPORT PERIOD.
ESTIMATE DATE OF STARTUP
- 26. UllITS IN TEST STATUS FORECAST ACHIEVED (FRIOR TO COM 'ER:IAL OPERATIO!;)
INITIAL CRITICALITY INITIAL ELECTRICITY COMMERCIAL OPERATION
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LOAD REDUCTIONS DUE TO ENVIROhYINTAL RESTRICTIONS UNIT NO. I NONTH: 0CTOBER. 19An REDUCTIONS, Ka' KIri FIASON TI!E HOURS LOAD, Ka' DATE None dur:.ng this reporting )eriod.
MONTHLY TOTAL
LOAD FIDUCTIONS DUE TO ENi'IR0!& ENTAL RESTRICTIONS UNIT NO.2 MONTH: OcTonrt. toAn FIDUCTIONS , %' 5'H FIASON TILE HOURS LOAD, L' DATE None during this reporting period .
L MONTHLY TOTAL
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DOCKET NC 50-280 UNIT SURRY I DATE 11-1-80 COMPLETED BY SUE D. DUNh Al'ERACT DAILY UNIT P^a 'E? LEVE:
MGNTH: OCTOBER 60 AVEEAGE DAI2 PS'EE 2VE: AVERAGE DAI2 PG'EE 2VE DAY (M.'E-NET) DAY t Ma'E-!!ET) 1 0.0 17 0.0 2 0.0 16 0.0 3 0.0 19 0.0 4 0.0 20 0.0 5 0.0 21 0.0 6 0.0 22 0.0 O.0 23 0.0 8 0.0 24 0.0 9 0.0 25 0.0 10 0.0 26 0.0 11 0.0 2" 0.0 12 0.0 28 0.0 13 0.0 29 0.0 14 0.0 30 0.0 15 0.0 31 0.0 16 0.0 DAI:.Y UNIT P3EE lei'E: FGIN IliSTRU:TICNS Gl. TEIS F03':, ::ET THF ALTEAGE EAILY UNIT ?&TE 2VE: In %'E-i;ET FCE EACH DAY IN TEE REPGhTI;.'G KJNTH. THESE FIGUEES .;IL: EF USED TG ?:GT A GRAPH FOR EACH EE?GET-ING '1GNTH. NCTE THAT EY USING MAXIMUM DE?ENDAELE CAPA:ITY FOR THE NET ELECTRICA EATING GF THE UNIT, THERE MAY BE OCCASIONS WHEN THE DAI2 AVEEACE PG;ER EX:EEDS THE 100 */= :.IliE (GR THE EESTRICTED PG'EE LEVE: 2NE). IN SU:n CASES, THE AVERAGE DAILY UNIT ?&'EE QUIPUT SHEET SHOULD EE FOO"NOTED TG EXPLAIN THE APPARENT ANOMA Y.
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DOCKET NO 50-281-UNIT SURRY II (
DATE 11-1-80 !
COMP 2TED BY SUE D. DUNN i
i AVEEAGE DA!:Y UNIT _PN_ER *EVEL MONTH: OCTOBER 80 d
AVERAGE DAILY PG'EE LEVEL AVEEAGE DAI Y PWER EVE: -
DAY (WE-NEI' ) DAY (IGE-NET) 1 757.0 17 759.1 2 757.2 1E 760.5 ;
3 ~59.0 19 756.8 -
4
~63.6 20 763.1 ,
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5 "62.5 21 765.3 L
6 764.7 22 765.0 i
7 "61.5 23 "62.0 8 ~55.6 24 759.9 t
- 4. i 75".0 ~62.3 9 25
- 10 75".1 26 762.6 11 75".3 27 "64." .,
12 760.6 26 -
~61.6 t
13 761.0 29 763.9 ;
1 14 "63.0 30 ~64." !
15 763.0 31 766.4 -
16 762.4 I I
I 541 2 Ul;IT POWER
- EVE: F0EM INSTRUCTIONS
, ON THIE F0ip', :IST THE AVEEAGE DAILY U.VIT PWEE :ZVE: IN WE-NET FOR EA:H DAY II; THE REP 0 ICING MONTH. THESE FIGURES n'IL: EE USED TO P:GT A GRAPH FOR EACH REPOR- ,
ING MONTH. NOTE THAT EY USING MAXIXUM DEPENDAELE CAPACITY FOR THE N.*T E*ECTRICA: ,
RATING OF THE UNIT, THERE NAY EE OCCASIONS WHEN THE DAI:Y AVERAGE POVEE EXCEEDS :
THE 100 */* LINE -(OR THE RESTRICTED FWER :SVE 2NE). IN SUCH CASES, THE AVEPAGE !
DAI2 UNIT PWEE OUTPUT SHEET SHOU:D EE FOOTNOTED TO EXPLAIN THE APPAPENT ANOMALY. l l f l
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SUMMARY
OF OPERATING EXPERIENCE l
l OCTOBER, 1980 l
Listed below in chronelegical sequence by unit is a summary of operating experiences for this month vnich required load reductions or resulted in sign-ificant non-load related incidents.
, UNIT 1 OCTOBER 1 This reporting period begins with the unit at cold shutdown (CSD) and defueled for steam generator (S/G) replacement.
OCTOBER 26 At 0200 the clocks were set back one hour to conform with eastern standard time.
OCTOBER 31 This reporting period ends with the unit CSD and defueled for S/G replacement.
UNIT 2 OCTOBER 1 This reporting period begins with the unit at 100% power.
OCTOBER 31 This reporting period ends with the unit at 100% power. ,
. . . . . - . - _ - _ - _ . . - - . .. . . -=... .- .- - - - - - .
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A!END ENTS TO FACILITY LICENSE OR TECHNICAL SPECIFICATIONS
' OCTOBER, 1980
?
L The Nuclear Regulatory Com=ission issued, on August 29, 1980, Amendment l l
No. 60 to the Operating Licenses for Surry Power Station Units No. I and No. l t
- 2. The changes correct the inadvertent omission of language allowing the I possession of byproduct material, as revised by amendments to the Surry licen- f ses dated October 31, 1974. Of significance, paragraphs 2.D and 2.E of the [
l Surry Unit No. 1 and No. 2 Operating Licenses are amended to read as follows:
[
"D. Pursuant to the Act and 10 CFR Parts 30, 40 and 70, to receive, ;
possess and use in amounts as required any byproduct, source or l
special nuclear material without restriction to chemical or physi-cal form, for sample analysis or instrument calibration or associa- f ted with radioactive apparatus or components;
- E. Pursuant to the Act 10 CFR Parts 30 and 70, to possess, but not t
' separate, such byproduct and special nuclear materials as may be !
produced by the operation of the facility." !
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'. . FACILITY CIIANGES REQUIRINO NkC APPROVAL OCTOBER, 1980 4
None during this reporting period. :
i 4
1 FACILITY CHANGES THAT DID NOT REQUIRE NRC APPROVAL Design Changes D/C 78-10 Condensate Polishing Addition Unit Portions of this design change involving yard 1,2 5 Fire Piping (78-10C), instrument Erection (78-10M), Demineralizer Bypass (78-10NR), and l Condensate Polisher 4160V Tie in (78-10R0 were implemented. '
Summary of Safety Evaluation This design change neither constitutes,an unreviewed safety question ner requires a change to Technical Specification.
i D/C 78-21-D Cordensate Tube Cleaning 2 This modification includes using smaller cleaning balls in the Amertap system, modifying the circuitry; modifying the elbows, etc. ;
Summary of Safety Evalun ion The syste= is being rebuilt to original design criteria creating no I new affect to the operation of safety related equipment. i
, i D/C 78-32 Main Transformer Over Excitation Protection 2-This change installed an STV relay designed to protect the main trans- l 3
formers from over excitation. Basically it assures the voltage does !
not increase beyond design limits. i
- , Su= mary of Safety Evaluation This design change will not impact adversely on station operations or
safety related equipment, but will enhance the present safety protection. l D/C 79-48 RTD Relocation and Installation 2 This design change replaces the presently installed RTD's with ones !
newly calibrated, relocating them and four new ones with computer points, i 4
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Facility Changes That Did Not Require NRC Approval (Continued) f i
I Design Changes Unit [
r D/C 79-48 i
Summarv of Saf ety Evaluation {
i Containment integrity was not affected and no safety implications [
were created with this design change. ;
ILRT Air Pressurization System 2 D/C 79-49 This modification provides for installing a temporary containment i air pressurization system for the type A ILRT.
Summary of Safety Evaluation l Since this system is to be installed only during the test and the !
unit is shutdown at the time, there is no effect on Tech. Specs.
l D/C 80-06 Replacing Westinghouse BFD Relays in 2 [
Safety Related Systems l l
L
, Because of a fallibility of the BFD relays initially installed in !
the engineered safeguards system they were replaced with ones which are designed to give improved performance, j i
i Summary of Safety Evaluation By replacing these relays, system reliability has been improved with j no adverse affects to the overall safety of the syste=. l i
D/C 80-S36 Short Term Containment Atmosphere Sampling 1,2
- Syst em 4 This modification will provide a temporary post accident sampling system for containment air to be used until a more permanent 7 facility is installed.
Summary of Safety Evaluation ,
i This modification does not affect normal station operations or the function of any safety related equipment. )
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- * -13 TESTS AND EXPERIt!ENTS REOUIRING NRC APPROVAL OCTOBER, 1980 Uone during this reporting period. !
1 1
i TEST /dD EXPERIMENTS THAT DID NOT REQUIRE NRC APPROVAL WIT e
ST 52 Reactor Coelant Syste: Flow Measure =ent Data Test was completed on October 2, 1980. This test obtained sufficient data to provide on accurate determination of reactor coclant syste= loop flow.
1 ST 60 The Reactor Coolant Pump Terminal Voltage Test was completed on f October 10, 1980. This test measured the terminal voltage and related para =eters of 13 Reactor Coolant Pu=p.
1.2 ST 65 The Heat Tracing Panel Performance Test was completed on October 10, 1980. This test is perf ormed to verify that the heat tr acing panel responds as required and to relate line numbers and circuit numbers.
2 ST 102 Stea= Generator Auxiliary Feedwater Pu=p (2-FW-P-2) 48 hour5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> test was co=pleted on October 16, 1980. This test demonstrated the [
operability of the stear generator auxiliary f eedwater pump and booster pump.
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CTHER CHANGES, TESTS AND EXPERTMENTS OCTOBER, 1980 None during this reporting period.
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- SURRY P0k'ER STATION CHEMISTRY REPORT OCTOBER , 19 80 T. S . '6. 6. 3. 6 PRIMARY COOLANT UNIT NO. 1 UNIT NO. 2 ANALYSIS MAXIMUM MINIMUM AVERAGE MAXI M. MINIMUM AVERAGE Gross Radioact., pCi/cl 7.58X10E-3 4.21X10E-3 5.4?v10F-1 3.22X10E-1 1.17v10F-1 2.10X10E-:
Suspended Solids, pp= 0.3 0.1 0.2 n.1 0.0 0.1 Cross Tritiu=, UCi/ml * *
- 2.33X10E-1 1.95X10E-1 2.10X10E-:
Iodine-131, pCi/cl * *
- 9.13X10E-3 ND ( )5.32X10E-:
I-131/2-133 * *
- 2.6131 0.1664 1.0817 Hydrogen, cc/kg * *
- 48.7 34.1 40.7 Lithium, ppe * *
- 2.25 1.93 2.08 l
E ron-10, pp: + 431 423 1 427 178 _
164 171 0xygen-16, ppm 3.1 2.0 2.4 0.000 0.000 0.000 Chloride, pp: 0.05 0.05 0.05 0.05 0.05 0.05 pH @ 25*C 5.65 5.40 5.55 6.81 6.53 6.71
+ Baron-10 = Total Baron x 0.196 .
NON-RADIOACTIVE CHEMICAL (1)
RELEASES, POUNDS T.S. 4.13.A.Q Phosphate o Boron 1445.9 Sulfate O Chromate .06 50 NaOH 0 Chlorine o Remarks:
- Unit #1 RCS drained 10-06-80.
WOTE 1: For three (3) davs (10-1. 10-3. and 10-4T there uns inen##4cion* T 111 to be detec-table on GELL.
(1) These levels of chemicals should present no major adverse environmental impact.
DESCRlFTION OF ALL INSTANCES WHERE THER"Jd. DISCHARGE LIMITS WERE EXCEEDED OCTOBER, 1980 Due to i=pairment of the circulating water syste= on the following days the thermal discharge limits were exceeded as noted.
October 1, 1980
- Exceeded 15 F AT across station October 2, 1980
- Exceeded 15 g F ST across station October 8, 1980
- Exceeded 15 F AT across station October 13, 1980
- Exceeded 15 F LT across station October 14, 1980
- Exceeded 15 F AT across station October 15, 1980
- Exceeded 15 October 16, 1980
- Exceeded 15,F ST across station g F LT across station October 17, 1980
- Exceeded 15 F AT across station October 21, 1980
- Exceeded 15 g F AT across station October 22, 1980
- Exceeded 15 F LT across station October 25, 1980
- Exceeded 15 l g F AT across station i October 26, 1980
- Exceeded 15 g F LT across station l
October 27, 1980 * {
Exceeded 15 g F AT across station j October 28, 1980
- Exceeded 15 F LT across station l
- Indicates dates where station ST was less than 15.0 F across the station for sometime during the day.
The LT excursicns were allowable under Technical Specifications 4.14.B.2'.
There were no reported instances of significant adverse environmental impact.
1
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1
-a _ _ _ - - _ - - -
-17 FUEL HANDLING .
UNIT 1 OCTOBER, 1980 None during this reporting period.
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FUEL HA'!DL111C
- UhAA 2 OCTOBER, 1980 None during this reporting period.
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PROCEDURE RE\'ISIONS THAT CHANGED THE OPERATING MODE DESCRIBED IN THE FSAR OCTOBER, 1980 None during this reporting period.
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'. DESCRIPTION OF PERIODIC TESTS WHICH kT.RE NOT COMPLETED b'ITHIN THE TIME LIMITS SPECIFIED IN TECH"ICAL SPECIFICATIONS OCTOBER, 1980 None during thisireporting period.
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_21_
INSERVICE INSPECTION OCTOBER, 1980
- 1. Unit 1 Inservice Inspection is in progress. To date the inspection has been satisfactory with no major indications identified.
, 2. A magnetic particle inspection was completed on Unit 1 H. P. rotor and blade rings. A magnetic particle, ultrasonic and liquid pene-trant inspection is in progress on all miscellaneous parts and I
equipment associated with Unit 1 turbine.
- 3. Completed a radiographic and ultrasonic inspection of Unit 1 main feed water 16" X 14" piping reducer welds. No indications were noted.
j Completed a radiographic inspection of the base metal 14" downstream i of the auxiliary feed water tie-ins on the main feed water piping.
No indications were noted.
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i REPORTABLE OCCURRENCES PERTAINING TO ANY OUTAGE OR PO'n'ER REDUCTIONS OCTOBER, 1980 j None during this reporting period.
-24 1
r Maintent: ce of Safety Relcred Systems During Outage or Reduced Power Periods 0:IT f'1 Mechanical Mcintenance
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SUMMARY
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bEriACE IUITING Str/Al tu STUlrisNUTS IN VALVF 004260812 21%
10/01/80 h$ VALVE 1
- K5 - % .s i hWL ArtVU STulGeNdTS IN VALVE 00%26088) 21%
RS VALVE t-US %l N!!' LACE ICLIENG 1
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VA:VE t RS-E ktVIACT IULTING E 0091608 t'e 21%
I S0/01/60 SS MPLACLU STutt9enUTS lN VALVE 82 i-k7-%U hFrLACE ikil. TING t Uu110ud L%
to/01/80 NS VALVE StPLACf: ItllTikG kErlActu hTUICieNU'l$ AN VAlVt Uon10 ant % E2
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S0/U1/60 CS VALVE INSTALL SulTOWT oun2ngass %9n e,
Sojus/mu hk Pit
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112 Solueleo CC PiriNG io-CC-89 V/C 13-SskA INSTALL Nfv SVkiNG 1 00ntus%nn
? INSTALL HANGEN Nu t'a 0
- SolueluG CC VirtNG 6 -lT- 8 6 5 D/i: 74-SJ2A INSTALL $PSING HUR VulD NO U:AhS $ U nun 6nino CONrhESS 2 HEAU LEAK 1 050 7tiin 2n6 S0/08/no IE RtPLArtu STUIG ANI* NUTS IN VALVE '*
t-CS-%1 REPLACE ik1LTING uluUlitil los l0/Usino CS VALVE StriACE IULTING kFPLAtl.O S1 DIG ANU NUT I
t u nuna g%U% 206 Solun/no CS VALVF s-CS-Li hEPLArhu STUl* AND NitTS t-CS-68 hEPi 1CE IULTING 01008s%ns 106 c4 50/un/00 CS Solunfuo CS VALVE VALVE S-CS-64 KfflACE IULTING REVLArtWV STUAGeNUTS kwlACLU STUV ANU NUTS 1
t usaunt%ul 2ns og t -CS -6*l REriACE IvlTING t Cluontn09 2ns
(* I soluuleG CS VALVE 1-CS-6% RFPLACE ItILTING bfrlACVU Sivu AND NUTS utuunt%so 206 sulonloo CS VALVL MPLACE IULTING herlAltWU STUU AND NUTS S usuonn%ll Ju6 *.
Sulon/80 CS VALVE s-CS-6% MPIMEU STulG*kUTS AN VLV 1 t-CS-66 kEPL ACE JULTING 1 u tunu t% t t tub
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- _41 Maintenance of Safety Related Systems Durinc Outage or Reduced Power Periods UNIT #2 Instrument Maintenance
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< o HE.ALTH PFYSICS OCTOBER, 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 were 2 individual. vho received single radiation exposure specifically associated with Unit 1;o. 2 outage, which accounted for more than 10% of the allowable annual values in 10CFR20.101. U
PROCEDURE DEVIATIONS REVIEWED BY STATION NUCLEAR
'* SAFETY AND OPERATINC CO'0!ITTEE AFTER TIME LIMITS SPECIFIED IN TECIU;ICAL SPECIFICATIONS OCTOBER, 1980 Date SNSOC Jio,. Unit Title Date Deviated Reviewed OP-4.1 1 Controlling Procedure 9-16-80 10-2-80 For Refueling PT-18.7 2 Charging Pu::1p Operability 4-19-80 10-14-80 and Perfor=ance PT-30.2 2 RHR System MOV Cycling 4-17-80 10-14-80 l}}