ML18113A571
| ML18113A571 | |
| Person / Time | |
|---|---|
| Site: | Surry |
| Issue date: | 10/13/1978 |
| From: | Stewart D VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.) |
| To: | |
| Shared Package | |
| ML18113A570 | List: |
| References | |
| NUDOCS 7810230187 | |
| Download: ML18113A571 (44) | |
Text
l VIRGINIA ELECTRIC.AND POWER COMPANY SURRY POWER STATION.
MONTHLY OPERATING REPORT REPORT NO.
78-09 SEPTEMBER, 1978 Q ~ S2~~;:X-Superintendent-Station Operations APPROVED:
MANAGER
R
- ~.-
(
\\'-....
-i-CONTENTS I
' Section Operating Data Report - Unit #1 Operating Data Report - Unit #2 Unit Shutdowns and Power Reductions - Unit #1 Unit Shutdowns and Power Reductions Unit /12 Load Reductions Due to Environmental Restrictions Unit /fl Load Reductions Due to Environmental Restrictions Unit 112 Average Daily Unit Power Level - Unit #1 Average Daily Unit Power Level Unit //2 SUI!IIDB.ry of Operating Experience Amendments to Facility License or Technical Specifications Facility Changes Requiring NRG Approval
, Facility Changes That Did Not Require NRC Approval Tests and Expe::;:*h"ents Requiring NRG.:,_Appr,5r.val Tests.a:::td E..,.-:p~r-f~~nts That.Did Not Require NRC Approval Other Cri.E~ges~ Tests and Experiments Chemistry Report Descrip~ion of P..ll Instances Where Thermal Discharge Limits Were Exceeded Fuel Handling Procedure Revisions That Changed the Operating Mode Described In The FSAR Description of Periodic Tests Which Were Not Completed Within The Time Limits Specified in Technical Specifications Inservice Inspection Reportable Occurrences Pertaining to Any Outage or Power Reductions Maintenance of Safety Related Systems During Outage or Reduced Power.Periods - Unit #1 - Mechanical Maintenance Maintenance of Safety Related Systems During Outage or Reduced Power Periods - Unit f,!2 - Mechanical Maintenance 1
2 3
4 5
'6 7
9 lill
-12 12 13
.lS 15 16 17 20 21
.22 23 24 26
r-*
[<i; L
-ii-
'"Section Maintenance of Safety Related Systems During Outage or Reduced Power Periods - Unit #1 - Electrical Maintenance Maintenance of Safety Related Systems During Outage or Reduced Power Periods - Unit f!2 - Electrical :Haintenance Maintenance of Safety Related Systems During Outage or Reduced Power Periods - Unit /fl - Instrument Maintenance Maintenance of Safety Related Systems During Outage or Reduced Power Periods - Unit 112 - Instrument :Haintenance Health Physics Summary Report of Effluent Release Data Sensitivity Data Procedure Deviations Reviewed by Station Nuclear Safety and Operating Committee *After Time Limi:t Specified in T. S.
28 30 32 36 37 40 41
OPERATING DATA REPORT e DOCKET NO.
}
OPERATING STATUS
- 1. UNIT NAME
- 2. REPORTING PERIOD DATE COMPLETED BY TELEPHONE
- 3. LICENSED THERMAL POWER (MWT)
- 4. NAMEPLATE RATING (GROSS MWE)
- 5. DESIGN ELECTRICAL RATING (NET MWE)
- 6. MAXIMUM DEPENDABLE CAPACITY (GROSS MWE)
- 7. MAXIMUM DEPENDABLE CAPACITY (NET MWE)
- 8. IF CHANGES OCCUR IN CAPACITY RATINGS
{ITEMS 3 THROUGH 7) SINCE LAST REPORT. GIVE REASONS.
50-.280 e 04 OCT 78 O.J. COSTELLO 804-357-3184 SURRY UNIT 1 0001 780901-2400 780930 2441 1---~--------------------1 847.5 INOTES I
82.2 l
l s11 I
I 775*
_ __ I NIA
- 9. POWER LEVEL TO WHICH RESTRICTED. IF ANY N/A (NET MWE)
- 0. REASONS FOR RESTRICTIONS. IF ANY NIA
- 1. HOURS IN REPORTING ?E?...IOD
- 2. NUMBER OF HOURS REACTOR WAS.CRITICAL
- 3. REACTOR RESERVE SHUTDOWN HOURS
- . *HOURS GENERATOR ~ON-LINE
- 5. UNIT RESERVE SHUTDOWN HOURS
- 0. GROSS THERMAL ENEZGY GENERATED (MWH)
- 7. GROSS ELECTRICAL ENERGY GENERATED (MWH)
~. NET ELECTRICAL EBER.GI GENERATED (MWd)
- 9. UNIT SERVICE FACTOR
). UNIT AVAILABILIT.X FACTOR
- l. UNIT CAPACITY FA::TOE (USING MDC NET).
~. UNIT CAPACITY FACTOR (USING DER NET)*
~. UNIT FORCED OuTAGZ RATE
µ_ SHUTDOWNS SCHEDUL~~ OVER NEXT 6 MONTHS i
(TYPE,DATE,AND DUBATION OF EACH)
~. IF SHUT DOWN AT END OF REPORT PERIOD.
ESTIMATE DATE OP STARTUP
- c. UNITS IN TEST STATUS (PRIOR TO COMMERCIAL OPERATION)
INITIAL CRITICALITY INITIAL ELECTRICITY COMMERCIAL OPERATION THIS MONTH YR-TO-DATE CUMULATIVE 720.0
- 6551.0 50615~0 642.-4 4F59.1
.33976.~'.0 -- -
D.O
- 0.0 0.0 *
-639.9 4577.* 9 33143.1---->*
-0.0 0.0
-0.0 15 4 6 7 91 ~ 0 --:11 0 7 7 0 0 8. 0 -7 6 2.18 0 0 4 * : 0. -~
-493855. 0 36.15655. 0 24975498. 0 *.~::
- 469687.o
_343a121:-o 237ossas.:o
---~
- a a. g.o / o_
6 9. 9.o / o
. s s. *5 o / o *
- 8 8, 9 * -<O / o
- 6 9 * *9 o / o
- 5 5
- 5 -*o /o a 4. 2 o f--0 6"7.:7 -o lo **:
6 o.-4 o Io 7 g
- 4 o f-o 6 3 * *a
- o / o
- _ s 7 ;o o / o o. o
-* - o. :2
,o / o
- 16. o
-o / o SNUBBER INSPECTION, SG INSPECTION ~/9/79 3 WEEKS -
N/A FORECAST
.ACHIEVED
OPE RAT ING DATA REPORT. I
' }
OPERATING STATUS DOCKET N-0.
DATE COMPLETED BY TELEPHONE 50-281
- 04 OCT O.J. COSTELLO 804-357-3184
- 1. UNIT NAME SURRY UNIT 2
- 2. REPORTING PERIOD 0-001 780901-2400 780930
- 3. LICENSED THERMAL POWER (MWT) 2441 1------------------------1
~
NAMEPLATE RATING (GROSS MWE) 847.5 INOTES
. I
~. DESIGN ELECTRICAL RATING (NET MWE) 822 I
I
- 6. MAXIMUM DEPENDABLE CAPACITY (GROSS MWE) 811 I
I
- 7. MAXIMUM DEPENDABLE CAPACITY (NET MWE)
- 775 l _____ *-----~-1
- 8. IP CHANGES OCCUR IN CAPACITY RATINGS NIA (ITEMS 3 THROUGH 7) SINCE LAST REPORT, GIVE REASONS
- 9. POWER LEVEL TO WHICH RESTRICTED,.IF ANY 'NIA (NET MWE)
- 0. REASONS FOR RESTRICTIONS, IF ANY NIA
- 1. HOURS 'IN REPORTING PEP..IOD
- 2. NUMBER OF HOURS REACTOR WAS CRITICAL
- 3. REACTOR RESERVE SHUTDOWN HOURS
- 4. HOURS GENERATOR ON-LINE
- 5. UNIT RESERVE SHUTDOWN HOURS 5.* GROSS THERMAL ENERGI GENERATED (MWH)
'7. GROSS ELECTRICAL EYE2G7 GENERATED (MWB)
- 8. NET ELECTRICAL ENERGY GENERATED (MWH)
- 9. UNIT SERVICE FACTOR O. UNIT AVAILABILITY ?ACTOR
- 1. UNIT CAPACITY FACTOR (USING MDC NET)
- 2. UNIT CAPACITY ?ACTOR (USING DER NE1)
- 3. UNIT FORCED OUTAGE RATE
~. SHUTDOWNS SCHEDULED OVER NEXT 6 MONTHS (TYPE,DATE,AND DUH.PT' ION OF EACH)
!)
- IF SHUT DOWN AT END OF REPORT PERIOD, ESTIMATE DATE OF.STARTUP E. UNITS IN TEST STATUS (PRIOR TO COMMERCIAL OPERATION)
INITIAL CRITICALITY INITIAL ELECTRICITY COMMERCIAL OPERATION THIS -MONTH YR-TO-DATE CUMULATIVE
- 7 2 0. 0.
6 5 51.. 0 4'7 4 9 5
- 0 720.0 5310.*4 317.23.2.
- o * *o -
-o. *o o ~ o 720.0 5297.4 31226.3 o ~ o
- o. -o o. *o 1739042.0 12845618.. 0 72555852.0 s1r5s6o. o 4138035.~o -23705429.. o 516674.0 3928794.0 22481911.0 100.0 o/o -
80~9.. o/o 65.7 *o/o 100.0.olo 80.'9 olo 65.-7 o/cr.*
- 92. 6 o /o 7 7.. 4
- O /o 61.1 "o / o
- 87. 3 -o / o
, *7 3.. 0 o /o
- 57. 6. o / o 0.0
.2.5 o/o
'22.4 olo
. SNUBBER INSPECTION 10/7/78 ONE WEEK; REFUELING 12l25l7B SIX WEEKS N/A
'FORECAST ACHIEVED
Date 78-5 780916 f; forced
- S: Scheduled
('1/77) ur.tit siiUToowNs ANo rowEn 1rnnucTioNs
. REPORT MONTH SEPT* i978
.... u 0..
J-s ri j 80.l D
i Reason:
A-Equipment Fallure (Expl:tln)
D-Malntenancc oi Test Licensee Evc1il l{cpotl #
'I Method:
- . * : l *Ma1tti:ii
.. 2*Mam.ial Scrain.
J-Autumal!c Scr:un.
I o
4-0lhcr(Expl:iln)
C'-Rcfucllng
". i.
. D-Rcgulatory Restricth>ri
- E-Opcrntm Tr:ilnlng & Ucchsc Examination
- F-Atlministrnt1*1e G-Opera tluual Errt>r ( i:xpiatn) l l-01hcr (Explain) t
{ '*
50-280 DOCKET NO. Surry 1 Io-3-78 UNIT NAME DATE CO~U'LETED llY TELEl llONE
- o. J, Costello
({304) 357-3184 C:iusc & Correc\\lve
- Act Ion to Prevent Rectmcnce Requi.red Snubber Inspec:tiqn
- s Exi1lblt G
- insi ructions for Preparation of Data.
Entry Sheets for Licensee Evcni Repur1 (LERl file (NUREG* *.
'0161)
Exhibit i *Sam~ Sour~~
Oatc F:* Forced
- S: Scheduled (IJ/77)
UNIT SHUTDOWNS AND POWER REPUCllONS itEPOitT MONTH SEPT. 1978 r I d 0 v c1!
Uccnsti<l Evon I Ht:pott #
~
""L la
. 0 u
. NONE DURING Tl is PE~- OD.
.i Reason:
A-Equipment Failure (Expialn)
U-Malnlcnance or Test C-Rcfucllng I
. D-Hcgulatory Restriction E-Opcralor Training & License Ex3mlrtatloli * *
- F -A tl min isl ra I i*1c G-Opcra1loi1al Errur (Explain) ll*Olhcr (Explain)
Method:
- I-Manual
- / 2-Manual Scram.
- 3-Auiomallc Scram.
.'.,;. 4-0lher (Explain)
- it'.
DOCKET NO.
50-281 UNIT NAME l>/\\TE COMPLETED UY TELE! llONE Surry 2 10-3-78 O. J. Cos te*llo csot1) 35~-3lM 5
Cause & Corm:llve
- Acllon 111 Prevent Recurrence Exhibit G - lnslrut:llons forPrep:uatlon or Dat::t.
. Entry Sheets for Licensee Event Report (l.ERl File (NUREG*
0161)
Exhibil I* Saml! Soura bI
DATE C.LETED.BY 10-.1-78 0 J COSTELLO..
/'
6VERA~ IM.LL.I. QN.J.X EQflKB L.EZ~L 10NXH:
SEPTEMBER.1978 DAY 1
2 3
4 5
6 8
9 10 11 12 13
. :14 15 AVERAGE DAILY POWER LEVEL
- (MWE-NET) 734.7 740.0 736.0 735.0 73.2. 9 737.8 7 38.. 1 7 36.* 5 7 3 7. ~a 736.0
- 7,3 7... 0
. 7 3 8.-1 738.0 7 4_1. 6 715.8 AILY UNIT POWER LEVEL FORM INSTRUCTIONS DAY 16 17 18
.19 20 21 AVERAGE DAILY POWER LEVEL (NWE-NET)
- 11.s o.o 0.0 329. *o 725. 0 743.0 22 ~* *.. - - -
742.8
. --23
- 24 - - -
.747 ** 5.
... 7-46. 9
. '748. 3 28. ----*
'7 4 7 * *9.
.29
-749.* 0 30
. '748.8 JN THIS FORM. LIST THE AVERAGE DAILY UNIT POWER LEVEL IN MWE-NET FOR EACH DAY IN "HE REPORTING MONTH. THESE FIGURES WILL BE-USED TO PLOT A GRAPH FOR EACH REPORT-.
fNG MONTH. NOTE THAT BY USING MAXIMUM DEPENDABLE CAPACITY FOR THE NET ELECTRICAL qATING OF THE UNIT. THERE MAY BE OCCASIONS WHEN THE DAILY AVERAGE POWER EXCEEDS rHE 100 °/ 0 LINE (OR THE RESTRICTED POWER LEVEL LINE). IN SUCH CASES. THE AVERAGE PAI LY u*NIT POWER OUTPUT SHEET SHOULD BE FOOTNOTED TO EXPLAIN 'THE APPARENT ANOMALY.
i UNIT DATE ceLETED BY SURRY II 10-1-78 0 J COSTELLO li.'!LE.B..Mi.E. 12AI.L.1.. LLlil.X. EQJ:l.E.R.LU.EL
~llXJ.!..:
SEPTEMBER 1978 AVERAGE DAILY POWER LEVEL DAY (MWE-NET) 1 735.4 2
735.5 3
737.8
.4
- 712.:3 5
72 6 *. 1 6
731 :1 7
730.2 8
724.9 9
727.1.
10 733.8
. ~:*
11 730.5...
12
'7'2 5.':3
-~***** -- -*... :...
1*3
- 7 3 6. 4
-14
- 7.34.*o*
15 7 3.2. 8
~AILY UNIT POWER LEVEL FORM INSTRUCTIONS DAY 16 17 j_ 8 19 20
- 21
-.:22 23
". 24 25
.28 AVERAGE DAILY POWER LEVEL (MWE-NET) 731. 4 729.4
- 7 24.*9
'709.*8
>702.9
- 7 21.*1
'732.* :3
'? 2 7.-4
- ..,.;, '. --... -. - *1,2 8.* -4
. -*--**------~* -*** -723.0 -
. -~*~....;--~-:---***,,.._ ---*.*.
.,,~-******....::-~..... _,.. -:-_.,,_.
. -6 92.*8
- 2 9
- *6 '3 9. *7
.30 555.3 1N THIS FORM. LIST THE AVERAGE DAILY UNIT POWER LEVEL IN MWE-NET FOR EACH DAY IN
'HE REPORTING MONTH. THESE FIGURES WILL BE USED TO PLOT A GRAPH FOR EACH REPORT-
~NG MONTH. NOTE THAT BY USING MAXIMUM DEPENDABLE CAPACITY FOR THE NET ELECTRICAL
?ATING OF THE UNIT~ THERE MAY BE OCCASIONS WHEN THE DAILY AVERAGE POWER EXCEEDS
'HE 100 °/ 0 LINE (OR THE RESTRICTED POWER LEVEL LINE). IN SUCH CASES. THE AVERAGE JAILY UNIT POWER OUTPUT SHEET SHOULD BE FOOTNOTED TO EXPLAIN THE APPARENT ANOMALY.
LOAD REDUCTIONS DUE TO ENVIRONMENTAL RESTRICTIONS UNIT NO.l MONTH:
SEPTEMBER, 1278 DATE Til1E HOURS LOAD 2 MW REDUCTIONS 2 MW Milli REASON None during this reportir g period.
~
~--~-.*
I I
I I
I I MONTHLY TOTAL 0
I
1 I
THfE I
I I
I
- e LOAD REDUCTIONS DUE TO ENVIRONMENTAL RESTRICTIONS UNIT NO.
2 MONTH: SEPTEMBER, 1978 HOURS LOAD, HW REDUCTIONS, MW
_None. c uring this reportitlg *perio*d MONTHLY TOTAL 0
SUMMARY
OF 0PERATING EXPERIENCE SEPTEMBER, 1978 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 relat:ed incidents.
UNIT 1 September 1 This::report period begins with the unit at 100% power.
September 15 -
At 2117 a load reduction was commenced to perform a snubber inspection as part of a scheduled outage.
At 2400 the load was 48%.
September 16 -
At 0128 the unit was taken off the line and at 0200 the reactor was shutdown.
At 0734 the reactor was <350°F/450 PSIG as part
- of the normal cooldown procedure.
September 18 -
At 2140 the reactor was brought to >350°F I L150 PSIG as part of the normal unit recovery.
September* 19 -
At 0.734 the reactor was taken critical.and at 0935 the unit was.*.*
paralleled to the system. A load increase was begun.
At 1530 power was held at, 90% due to secondary -system chemis_try.
September 20 -
At 0550 the unit was _returned to 100%,
the chemistry having_.
been corrected to the desired values.
Septembe!'.' 25 At 1030 a unit ramp down. ~was commenced due to a suspected heat_
~~~t=acing problem.
At 1045 with the unit at 97% the pr°-blem was resolved and found not _to be plant limiting.
A*-ramp-up was begun and at 1100 the unit was returned to *100% power.
September 30 -
'Ili..is report ends with the unit at 100% power.
UNIT 2 Septe!!lber 1 This report period begins with the unit at 100% *power.
September 4 At 0355 a load reductian,was commenced at the request of the syst:em operator for the purpose of load following~ At 0530 load was at 71% and holdi~g. At 0625 a load increase was begun and at 0748 load was returned to 100% power.
I September 5 At 0240 a load reduction was connnenced at the request of the system operator for the purpose of load following.
At 0312 load was at 90% and holding.
At 0448 a.. load increase was begun and at 0552 the unit was returned to 100% power.
September 25 -
At 1030 a unit rampdown was commenced due to a suspected heat tracing problem.
At 1046 with *the unit at 94% the problem was resolved and found not to be plant limiting.
A ramp-up was begun and at 1103 the unit was ret:.urned to 100% power.*
UNIT 2 September 28 Seotember 29 -
SUMMARY
OF OPERATING EXPERIENCE
( CONTI:NUED)
At 1400 a rampdoWn to 97% was performed to stabilize a de-creasing* condenser vacuum.
Repair work on "D 11 traveling screen required stopping flow through ":P" :waterbox.
At 1545 the unit was returned to 100% power.
The vacuum problem had been brought under control.
At 1320 the condenser vacuum was again decreasing with waterbox flow stopped while traveling screen.repairs continued.
At 1330 the load had been reduced to 97%.
Again~ at 1515 load was reduced to 93% power.
At 1711 load was.further reduced to 82% _power.
September 30 -
- This report period ends with the unit at 80~~ power with water-box and high level screen repairs underway.
- A****--***-**-*******,_ *.. _,..
~~***
., ----*-------*-**<4-*-*"
.... ~--*--*
-~-:..
-ll-Af1ENDHE.O FACILITY LICENSE OR TECHNia SPECIFICATIONS SEPTEMBER, 1978 There were none during this reporting period.
FACILITY CHANGES REQUIRINll NRC APPROVAL SEPTEMBER, 1978 There were none during this reporting period.
FACILITY CHANGES THAT DID NOT REQUIRE NRC APPROVAL SEPTEMBER, 1978 There were none during this reporting period.
'ST-52 ST-52 TESTS AND EXPERD:1E.~S REQU-NG "NRC APPROVAL SEPTEMBER, 1978 There were none during this reporting period.
TESTS AND EXPERIMENTS THAT DID NOT REQUIRE NRC APPROVAL SEPTEMBER, 1978 Precision Primary Flow Measurement Unit Precision flow measurement test was conducted September 6, 1978.
.1 Test results displayed repeatability, within* the expected ~bana. __
of uncertainty, from previous test results.
Precision Primary Flow Measurement *
- Test was conducted on September 15, 1978.
The test results ge~ 0~ally reflected the degree of tube plugging accomplished on tne unit, within the _expected uncertainty band.
2 erTHER CHANGES, TESTS AND EXPE.mPS SEPTEMBER, 1978 There were none during this reporting period.
-rr..:-
- SURRY POWER STATION CHEHISTRY REPORT SEPTEtfBER 19 79 T.S.6.6.A-11 PRULUY COOL.ANT UNIT NO. 1 UNIT NO.
2
.ANALYSIS MAXIMUM MINIMUM AVERAGE MAXIMUM MINIMUM AVERAGE Gross Radioact._, µCi/ml 3.63E-l
- 1. 22E-2 z.-36E-l
-2.47E-l 2.43E-2 l.55E-l Suspended Solids, ppm 0.6 0.1 0.2 0.2 0.1 -
0.2 Gross Tritium., µCi/ml 2.24E-l
- 1. 07E-l l.59E-l 2.17E-l
- l. 79E-l 2.02E-l Iodine-131, µCi/ml 2.47E-2 6.82E-4 2.56E-3 5.52E-4 2.26E-4 3.71E-4 1-131/I-133 I u.-1912 0.0542 0.1055 0.* 1108
- 0.0586 0.0957 Hydrogen, cc/kg
! '? '
! ;.;-_.o
-8. 6 ' (1) 28.4 42..~6 24.9 33.4 j Lithium, ppm i ') -5
! ~ *..)
l 1.66 2.21
-0.72 0.59
- o. 65 r
1379. 5 l J3oron-..10, ppm +
139.6 l65.4
- ' 54.3 1.3-.;.7 49.2 Oxygen-16, -ppm i
(1 0.000 0.003 o~*ooo 0.000 0.000 l 0.080 I
Chloride, ppm I 0.08 0.05 0.05 0.05
-0.05 -
0.05 pH @ 25°C I 1.09 5.98 6.-S2 i.22 --
6.88 7.03
+ Boron-10 = Total :Boron x 0.196 NON-RADIOACTIVE CHEMICAL RELEASES, POUNDS T.S. 4.13.A.8 Phosphate 0.0 Boron 3334 Sulfate 556 Chromate 0.0 50% NaOH 700 Chlorine
0.0 Remarks
(1) Unit at col<l shutdown.
SEPTEMBER, 1978.
On September 15, 1978, during the rampdo;;.m on Unit 1 we exceeded a 3°F/hr change in river temperature.
This was reportable under Technical Specifications 4.14.
Also, due to impairment of the circulating water system on the follow-ing days the thermal discharge limits were exceeded as noted:
September 1, 1978 Exceeded 15°F !1T across *station September 2, 1978 Exceeded 15°F !:J.T across station September 3, 1978 Exceeded 15°F /1T acres$* station September 4, 1978 Exceeded 17.5°F f:.T aero.as station September 5, 1978 Exceeded_l7.5°F /:J.T across station September 6, 1978 Exceeded 17.5°F f:.T across station September 7, 1978 Exceeded 15°F f:.T across station September 9, 1978 Exceeded 15°F b.T across station September 10, 1978
- Exceeded 15°F b.T across station September 11, 1978 Exceeded 15°F /lT across station.
September 12, 197.8 Exceeded 15°F b.T across station September 13, 1978
- Exceeded l7.5°F b.T across station September 14, l978 Exceeded 17.5°F /lT across station Sept0 mher 15, 1978 Exceeded 17.5°F /lT across station September 16, 1978 Exceeded 17.5°F f:.T across statiort September 19, 1978 Exceeded 17.5°F /lT.across station Sept"'~ber 20, 1978 Exceeded 17.5°F /1T across station Sept:;:.mber 21, 1978 Exceeded l5°F b.T across station September 22, 1978 Exceeded l5°F b.T across station Sen!:ernber 24, 1978 Exceeded 15°F /1T.acrbss station Sept6'1ber.25, -1.978 Exceeded l7.5°F /::,.T across station Sep~e1iber 2 6, 1978 Exceeded 17.5°F/::,.T across station September 27, 1978 Exceeded l7.5°F l1T across station Sep::ember 28, 1978
- Exceeded 17 ;5°F./:J.T across.station
.September.29*, 1978 Exceeded 17.5°F./lT across station Se:pn~mber 30, 1978
- .Exceeded 15 °F /lT across.station These JlT excursions were allowable under Technical Specifications 4.14.B.2. There were no reported instances of significant adverse environ-ment:al icrpact.
FUEL HANDLING SEPTEMBER, 1978 e No fuel handling was done during this month.
DATE
- -rr0 PED/RECE;IVED
- ~ *.:
I i
- ..---~-..... :.--
- .. *.- **:* --~:;:
FUEL HA!.'IDLINGU SEPTID-IBER, 1978 NO OF ASSEMBLIES PER SHIPMENT ANSI NO.
INITIAL ENRICHMENT NONE DURING.THIS REPORTING PERIOD-
_.,.-~- -
-~*.. -
-~.:..:-*.. :..:.... -
-~ ~*--.
- -:\\...
NEW OR SPElIT FUEL SHIPPING CASK ACTIVITY LEV
- . ~-
~*.".
- ': ~-
.. ~-.
- . ---*-----** ***-*--- **_*_*_***_.--_-__c.~~.--_
... "* - - * *- * -- - **
- _-_-~_**_* - - - *** -
DATE HIPPED/RECEIVED
. ~
. '~~;~~ -
~;a.:;;-:.
- -:~:>£.
- ~'*.~~-. -~
. i l
FUEL HANDLING SEPTEMBER, 1978 ANSI NO.
NO OF ASSEMBLIES PER SHIPMENT INITIAL ENRICHMENT NONK.DUI>JNG T IIS REPORTING *-PERIOD."
-~ -
..;.- *:... *.-... ~-
~'EW OR SPENT FUEL SHIPPING CASK ACTIVITY LEVE
.. ~-:..
~. ~:._~*-f > ** **, ~.
- ;~:~;:*~:~*-.:-: -.~ *
~'~..'... :._
-~~ -~ *-
...,r_..
PROCEDURE REVISIONS THAT CHANGED THE e OPERATING MODE DESCRIBED IN Tl FSAR SEPTEMBER, 1978 There were none during this reporting period.
lJ.b:::il..;Kl..t'Tl.Ul'I u.r r.C.l\\..LU.U.Lv
.LL...:JJ...:J YHl..LvU
)'IDIU:. HU.1.
COMPLETED W:LTHIN THE TIME LIMITS SPECIFIED IN TECHNICAL SPECIF.TIONS __
SEPTEMBER, 1978 There were none during this reporting period.
-*~ ---*.. --------*--- --=--** -.r* *~-
---**~----~......,., __ *-
- -*.---,-~*-**-*-*****-.--------..., --..., __..,.. *----~~,.~,.*--**. --*-*'"""
INSERVICE INSPECTION SEPTEMBER, 1978 There was none during this reporting period.
REPORTABLE OCCURRENCES PERTAINING TO
.M'Y OUTAGE OR POWER REDur101~s SEPTEMBER, 1978 There were none during this reporting period.
. /
- -.. * ****- ~-r*--**--*...,.. ~* ** "'"" * **-****-*..,, -....*~---,. *~--- * ""* * --. -- *" **-. --* ** --.. - *-*** * ** * *. -** ***-***-*****.._ *-***--* **.-- -~ - -* -*. ~-***-----**-*-
(
\\.'--
/~-
(
Maintenance. of Safety Related Syst'ems During Outage*ar*Reduced.Power*Periods UNIT ill Mechanical Maintenance
.:i,.
-:~*
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(N!1INTENANCE OF SAFl':Ti k11tA1;ed *sYSTeMS DU/1ING OUTAG/i on 11TIDUCED l'OWER PERIODS)
Ni1Tll<NO
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3 3
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115 79 6
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¥..aintenance of Safety Related Systems During Outage or.Reduced Power.Periods UNIT f/2 Mechanical Maintenance
- Mechanic.al Maintenance UNIT 2 There was none during this reporting period.
- -,_,~ --*"*-~--** - -* ***-*
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- ----*~------*---,.. -* ~ -*
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Maintenance of Safety Related Systems During Outage*ar*Reduced Power.Periods UNIT ill Electrical Maintenance
l*
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(MAINTENANCE or SAFETY RfitAfaiJ SYSTf{HS t}URlNG OUTAGi: oii tdmUcft/j Po"F.il ;)F:iU'ODS)
CONP MAllT<NO
-..... SUMM~nr MR 1'07'Vl¥NT,I/
NOV MOV NOV-1536 DID NOT FU/,f,Y CWSF: /JUlliNG ot*s i.NSl'EC1'ElJ LrMCTS CYCT,fW VAT,Vr. SAT
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}iaintenance of Safety Related Systems During Outage or Reduced.Power*Periods UNIT 112 Electrical Maintenance
Electrical Maintenance UNIT 2
- There was none during this reporting period.
('
-c Maintenance of Safety Related Systems During Outage or Reduced Power.Periods UNIT ill Instrument Maintenance
- '(
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COMP INST lNST CON1' ACC iNST 1NS1' INST
. UNIT. i.. stiPJ'EMiJgn. i 97 0. -..... - "........ "......
(MAINTENAilCE or SAFETY nii)msv SYSTEMS DURING OUTAGS Ok,'r/P,DUCF:D Porrtil Pl<:RIODS) f'I-CC-i07A n-cc-iosc....
RV-NS-101D 1-S.C-7'iC pl155 p1156 r11s1
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- TOTDWNTM 22 22 211 22 73 73 73 30ll
(.
- Maintenance of Safety Related Systems During
- outage or.Reduced Power.Periods UNIT /f2 Instrument Maintenance
Instrument Maintenance UNIT 2 There*-was none during this reporting period.
HEALTH PHYSICS SEPTEMBER, 1973.
- There was no single release..-of radioactivity or radiation exposure specifically associated with an outage that accounted for more than 10%
of the allowable annual values in 10CFR20.
r
- ~trtt~r;pj
- ~,~~f~:!TI~~~':75'r1r:mza 11~:-mr;~~~>i?Z!!~r"~':"rn~,.~re~~~r"*i*"~1"1!~.;"7"~rqY"7~rs~~~~,a~;y.~~-mi'f"'"WP='l<Bm'Emrt;r,p~*P.tfffi...-~?P?!-~~~""Wtll~it',~"'~~_.
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}.
.!il~ill\\.'LlH"...J\\!\\~!. OAC:'l'l VJ' EFFLUENTS PAGE l YEAR: 1978 Facility: Surry Power Station UOCKWI';
l!.fl:__?_~_!!.!Hl 50-Z!Jl
- --*---~~~-....._;:-**-*
I.
LIQUID ltELEASijS
- ------;:.;.,a...
-~~:...""~"" *****-
- e
-. *ufrr;r s-**
=*--
JULY AUGUST Sl\\l"l'EMllER
- l.
Gross Rndioactivitzi <rl:y ~
(a}
Total !le lease Curies
- 1. 99E-l*
2.05E-l l.31E-l
{b 2 Avg. Concentration Released
µCi7ml 1.07E-9 8,78E-10 5.96E-l0 I
{c}
Haximum Concentn1tion Released pCi/ml
- 1. 95E-9
- 1. 4 7E-9
- -b.96E-lo
- 2.
Tritium (a)
Total Released Curies l.l3E+2 1141E+l 3.46E+l
{b)
Avg. ConcentratJon Released pCi/ml
~lE-J 6.04E-8
- 1. 57E-7 I
- 3.
Dissolved Noble Gases (a)
Total Itel ease Curies
---zi:TTJr-'t.
- 1. 39E-l l.69E-2 (b)
Avf!.. Concentration Released pCi/ml
-Z:-Z:>t;-.lU 5.95E-10 J:b9E-II I
Gro1;s Alpha Radioactivity
{a2 Total Released Curies
- 2. Ol1E-5 4.36E-6 O.OOE+O (b)
Avl!.. Concentration Released pCJ./ml l.lOE-13 *
- l. 86E-14 O.OOE+O I
- 5.
Vol. of Li9uid to Disch. Canal Liters 3.90E+7 3.64E+7
. !1, 75E+7 I
- 6.
Vol. of Dilution Water Liters l.85E+ll 2.34E+ll 2.20E+ll
- 7.
!so top es Released HPC \\!Ci/ml Curies I
I-131 3 x 10-1 7.52E-5 6.08E-4 l.38E-3 1-132 8.x 10-*
8.63E-3 1-133 1 x 10-<>
l..'l/E-'4 3.07E-3 I
I-13!1 2
10-=5 x
l.lOE-2 1-135
,, x lo-"
--r.77il..~
6.0lE-3 Cs-134 9 x io- 0 3.15E-2
- l. 64E-l 7.07E-2 Cs-136 6 x 10,
~
Cs-1.37 2 x io-5 8.27E-2 2-;/'.lE-I l.87E-l Cs-138 Cn-57 4 x 10- I 3.9SE-4 4.03E-5 2.27E-li Co-SB 9
10,
- 1. SliE-1 x
5.33E-l 7.S3E-2 Co-60 3 x 10,
3.62E-l l.llE-1 8.88E-2 Mn-54 l x 10-~
1.0SE-2
- 4.21E-3 l.69E-3 Na-24 3 x 10--5 7.74E-4 3.69E-2
- 1. OOE-2 Cr-51 2 x 10-'
l1.13E-2 3.lSE-3 S.23E-4 Fe-59 5 x 10 *b 4.44E-4
- ti Nb-95 1 x 10- 11 6.13E-3 3.68E-4 5.96E-4 Ua-l.a-140 2 x 10-5 3.liliE-5
- iJ llh-88 tr I
I i
i 1
- ,['.
1.:*
- ~*.. '
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FACILI'l:Y:
Surry Power Station I.
- 8.
II.
1..
- 2.
- 3.
-c 5,
- 6.
- 7.
LIQUID RELEASES (CONl:)
Ce-141 9 x io-~
Ce-144 1 x.10- 0 Xe-133 3 x io-"
Xe-135 3 x io-0 Ar-41 3 x io- 0 Sr-89 3 x 10-*
Sr-90 3 x 10.,
C-14 8 x lO-'
Percent of 10CFR20 AIRllOl\\NE REI.EASES Total Noble Gases Total Halogens
'l:otal Particulate Gross Radio-activity (Sy)
Total Tritium Total Particulate Gross Alpha Radioactivity Maxlnwm Noble Gas Release Rate PercQnt of Applicublo Limit for Technical Specifications (a)
Noble Gases (b)
Halogens (c)
Partjculaces
- 8.
Isotopes Released:
(a)
Particulates Cs-135 Co-60
.bw;_fill.L Curies Curies Cud.es Curjes Curt es uCi/sec Percent Percent Percent Cui:ies ltlil'01tI...9J..J!._AJ!l!.lMJ'.l.Yf El1Lo'LllENTS llOCKWl'I.~(t~l~I 50:2U}c 4.96E-2 2.79E-4
~=E-~2,,._--1-~~-
4.09E-3
- 1. 93E-2 6.56E-5 l.40E-4 l.90E-2 3.74E-2 3.92E+l
- 1. 4.lE+l 2.16E-7 2.79E-5 2.80E-3
- 5. 71E-5 l.63E+l 2134E+l 2.91E-5
- 3. 71E-6 l.06E+3 l,59EH 2.99E-2 l.17E-2 l.80E-6 2.99E-I\\
6.93E-2 6.07E-4 2, l10E-6 l.OlE-10 l.09E-5 4.47E-6
-r.-4@-5 2.llE-5
-:5:TIE-'.3 3.74E-5
-9. 2i6E-li 1.23E-5 ti<
ctr l..41E-2 Z.!l/E-3
~
- 1. 72E-2 l.81E+2
.l.4)1!:-)
l.05E-4 J.
- U'f.1!."t'J.
J:BOE-6
- 1. 89E+3
- 1. 66E-2 l.26E-4 4.41B-3
- 5. 77E-7 lb 5.54E-b
- t.~:iE-4 2i.38E-5 2.501'-5
'yEAR:
1978 PAGE 2 2.47E-5 1<1-Pl Mn-511
*ll---,,....-----ll--..,,.-----v--------+------+--------1l------ -------
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.I
- 1 FACILITY:
Surry Pow~r Station*
REPORT bF RAn:toAc'i'iVE EFFLUENTS DOCKET; 50-280 and 50-281 II.
AIRBORNE RELEASES (CON 1 T)
=====~===o==;=;======*'IF=U?N,,,,,1=1c='S== ~irl'='Y=== ~1li-:fili]'1= _SEt~HilER.. *=====~
=if.= Isotopes Released (con l"t')
Curies (b)
Halogens I-131
_!,~_l!_lE-7 __
- 2. 67E-5
- l. fJ!ll~-5 PAGE 3 H-------l-"-1~3'-2,-------*-------I-----
- ---,;---** -l"'"'-"'---I------!
I=l33
----- S. 551'-U*-- --.f:15Tl::ci--:
J-. 6-*_.,-.E---7---n-----V------A------<<
M--------'l::..-...:;l;c;):..:l;...1 ----'--------- ----
7i--*--
-*--~-----*
s
- --7(-*--* ----w--*- --f"-c-.---M------U M----..,-.,--*-1_-_1_)_5 _____________,. ______ -*--*---*--*-.. --------* ---------- --**----M*------- -*------M------A*-----11
( c)
Gases xe-lJ:i
- -*"'.l777imr-*- *--r.*21in:1-- --r. 791\\H Xe-133m
- ---- 3; 90E.:.-6--* ---*-*----* --*-~---*----- *-*-----B-------ll------*lf------*~------11 11------:.0.xc::..--"1"==:i-=-s:.::..----------*i----'1-4.ourr=r- --1-:12rn:o-2. Gorrru- -*
Kr-85m
-g,rliE-2--5.iffi*::J- -*
~--------'K"'r"'"--s'"'s~------------11------ii--*...-----11---r--- -~-*--- ----'--
11 ______
...:K;::;:r:....-..::.8.:..7 ___________
~----u-~*----11
- 9. 44E-4
- 4. CiOE-3 Kr-88 Ar-Ill III.
SOLID RADIOACTIVE WASTE DISPOSAL
- 1.
(a)
Total Amount Solid Waste Packaged (b)
Estimated Total Actlvitv (c)
Date of Shlpment and Disposition FT 3 Curies
--:L.T.m+u 3.25E+3 9.19E+l Jlarnwell; s.c.
7-6-78 7-9-78 7-15-78 7-17-78 7-22-78 7-22-78 7-25-78 1-27-78 7-27-78 7-3i-78 9.70E-3 3.09E+3 8.15E+2 9.23E+O l,JbE+2
- Barnwell, llarnweTI, s.c.
s.c.
8-2-78 9-11-78 il-4-78 9-14-78 8-7-78 9-15-78 8-is-18 9-22-78 8-25-78 9-26-78
- ~-"~* **-*****-*-~.~ '* *!;.*::,:_:*. ~7*
- ~-~~~--:*-~,,*-,;:;~7~~~~*-*-. --~~\\'.~~~~:-. -.. --~'"":'-- -------... ----:--*--**--.... '..-----... -... -*--** --~~.~'.~;......... -**-:-*.~~. -- --*-............. _..,.,......... *--........ -.....
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Page 40
- G=oss.t:..l~hQ; 5.27E-9
µCi/!tl.
T~~tillz:l; 4.0E-6 µCi./!!!.L Sc~ont.i.?.:::.-89; less tna~ 3.0E+l pc~
S t:::-ont:i.i-=--90; less t:h.<m 2.:0E+-0,Oei..
COz-14-; le.ss S t:rontiu::-89 ;*
. S-t:=ontlu;:;i-90; than 7.0:2:-10 µCi./cl..
less.
less ti:'.~ 9. OZ-':1 µGi./mJ.._
th.;:ui. 3.0E-10 µCi./cl.
- Liauid. a.D.rl/ or R.ad.io,gasas -* lOOc:e
- Ba-:-La-.J.40:
r-131..
X-o-133 xe-l35 Cs-137
.Cs-l34-C.o-OO-
-C--58.
C=-5l.
li::c-54.
Fe-59
- A-.-41.
I.-l.34-I-132..
2.... 0E-T-5.;.lE-S-.
5*4E-8.
2:.. 9E-a:-.
9* *.2E-8"...
.T.. 2E-8:
I.5E;.;.T 9.8E-8 3.8.E-T 140E-J:
2.4E:.-.7 J... 6E.,.-T 1.. 1.E-T _:;>*,:-
-l. OE-7"
- l... 7E-T t:ct:a.l t:ota..1.
lia-24--..,__
I-1.33.
- 6'~9E.-S
.4:..;5E~/
I-D.S._
K=-85*
K-~8-L--8T---*
-. K..--85:'*
- . ;:~*Xa-138*.
. ~13.Sm:: -::*,,,==,----
~
1331:1:-~ ". ::. *-.*
Rb-88 r-131.
I-133 I-132
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Number Unit P'I'-24.2 l DEVIATIONS REVIEWED BY STA'T' AND OPERATING COMMITTEE AFTE SPECIFIED IN TECHNICAL SPECIFICATIONS SEPTEMBER, 1978 Title High Pressure C02 System (Emergency Service Water Pump House)
Deviation.
Step 5.4-Did not weigh bottle No. 7.
Step 5.10-Not performed.
Step 6.4-Did not perform test on exhaust fan.
This procedure was deviated 08-23-78 and reviewed by the Station Nuclear Safety and Operating Committee 09-27-78.
EMP:..c-EPL::-lL. L Safety Related 480V Motors Mark No. l-CC~P-2A.
Steps 5.6, 5.13, 5.15, 5.18, 5.20, 6.4, 6.7-Not applicable.
Step 7.1 - Delete 5.20 & 6.4.
This procedure was deviated 08-22-78 and reviewed by the Station Nuclear Safety and Operating Committee.09-27-78.