ML18139A321
| ML18139A321 | |
| Person / Time | |
|---|---|
| Site: | Surry  |
| Issue date: | 06/05/1980 |
| From: | Costello O, Saunders R VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.) |
| To: | |
| Shared Package | |
| ML18139A320 | List: |
| References | |
| 80-05, 80-5, NUDOCS 8006170517 | |
| Download: ML18139A321 (49) | |
Text
- - -
VIRGINIA ELECTRIC AND POWER COHPAf.;'Y SURRY POWER S.TATION MONTHLY OPERATING REPORT REPORT NO. 80-05 MAY, 1980 APPROVED:
1'-L4.NAGER 8 006170 5\'J
-i-
- I CONTENTS Section Operating Data Report - Unit ff l 1 Operating Data Report - Unit #2 2 Unit Shutdovms and Power Reductions - Unit #1 3 Unit Shutdovms and Power Reductions - Unit 1/2 4 Load Reductions Due to Environmental Restrictions - Unit #1 5 Load Reductions Due to Environmental Restrictions - Unit #2 6 Average Daily Unit Power Level - Unit #1 7 Average Daily Unit Power Level - Unit f.!2 8 Summary of Operating Experience 9 Amendments to Facility License or Technical Specifications 11 Facility Changes Requiring NRC Approval 12 Facility Changes That Did Not Require NRC Approval 12 Tests and Experiments Requiring NRG Approval 15 Tests and Experiments That Did Not Require :NRC Approval 15 Other Changes, Tests and Experiments 16 Cheoistry Report 17 Description of All instances Where Thermal Discharge Lim.its 18 Were Exceeded Fish Kill Investigation 19 Fuel Handling 21 Procedure Revisions That Changed the Operating Hode Described In 23 n*:~ Fs&-;:z Description of Periodic Tests Which Were Not Completed. Within The 24 Time Limits Specified In Technical Specifications Inservice Inspection 25 Reportable Occurrences Pertaining to Any Outage or *Power Reductions 26 Maintenance of Safety Related Systems During Outage or Reduced Power 27 Periods - Unit ffl - Mechanical Maintenance
-ii-Section Maintenance of Safety Related Systems During Outage or Reduced Power 31 Periods - Unit {,!2 - Mechanical Maintenance Maintenance of Safety Related Systems During Outage or Reduced 35 Power Periods - Unit f.!l - Electrical Maintenance Maintenance of Safety Related Systems During Outage or Reduced 37 Power Periods - Unit /,12 - Electrical Maintenance Maintenance of Safety Related Systems During Outage or Reduced 41 Power Periods - Unit 111 - Instrument Maintenance Maintenance of Safety Related Systems During Outage or Reduced 43 Power Periods - Unit tf 2 - Instrument Maintenance Health Physics Summary 45 Procedure Deviations reviewed by Station Nuclear Safety and 46 Operating Committee after Time Limits Specified in T.S.
DOC!~E/!.: :*v:O
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L fl iiC?J}::J.:li~*G ?SP.IOU 50130 'J.'O 53:!.30
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/44.0 364/ .o 65231.0
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O?EFiATii'iG DATA Fr.E?OR:P DOCKE'.t NO. 50.-2Si D.4TE 05 JZ/N BO C/):'1?LE!.;ED EY ~* .:1. t:;os1iELW
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- 1. ::"AI.'l' NAME S~*'RRY ~*'NIT 2 1
- 2. RE'OR'J.'ING ?EF.IOD 50180 1.'0 52180 1-~*~~~~~~*~~W~Y~Y~~~.....-t
- 3. LICE!/SE'D ':.1 H2FJ~J~AL i'O>IER (.lvfli/T) 2441
- 4. !ul'1Ei'L.4'.!3 RATING (GROSS NllE) 64 /. 5 INO'J.'E'S
- 5. DESIGN ELEC'J.'F. J.C.4L R.:ll'ING UVET M'iiE) 822 I
- 6. !>~AXlff;jf>J DE?END.1BLE C.:l?.:JCI'.Z'Y (GROSS MWE) 811 I
- t. l5.-1Xl!.;;_,:Jvj DE?E!;D.1ELE C..'l?ACl'!.'Y (lvt!.' l1WE) 715 1.
B. IF CH.-1tiGES occ:.,;R IN c_.p:JCI'.rY P..*Yl.'INGS NIA (1:7'c'XS 2 T liRo:.,;cH I) SINCE L/iSJ.'
d;?0?.1'. CD'Z REASONS
- 9. ?O'r/E'F. LEVEL TO wh.lCii HES1RlC'!.'£D. IF AllY N/.4 (hET MWE)
'J.'fi.IS t.tOt?l'd YEr:TO<::D/I.TE c;,;,"-1..:*L-1'!.'IVE
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_o. GF..055 '.!.'hERf*:*.1L £M:.RGY GE.NERA'J.'W (M/IH) 0.0 o.o 19!. 940&3. 0 1 /. GA(JSS £LEl}iJ.;R.IC.4L E!~-E;.~GY GENti11.*AJ.:ED (fv~./.7.) 0.0 o.o 25858844.0
- 13. NE,"J.' ELECTF..lC.-'iL Ef\'5F.GY GSNERATED (!>:WH) 0.0 0.0 24535505-.0 1 ::.
- .J. ~ifU'J.' SERVIC8 F:lCTOE 0.0 0. 0 i 54.I o/o
- 22. ,::l)*1r;_: CA?.*l-~IIl'- ?AC7.::Jf. l~~SING DEFr NE'J.:) 0.0 0.0
- 48 .1 o/ o
- 22. ~"NI'J.' PORC2,u o~;1'.1GE J:....1IE.. 0.0 0.0 21.0 o/o
- 24. SH~,-T[)Q;*/I~**s SCH.EDt:;LE!J CfVE*J.~, lVEX~7 6 !*~;CJNTHS 1
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26 * *:.-NI'l.'S lN '!.'EST 5'1.':1'1.'*~*s FORECAST ACHIF:VED
(?F.IOR TO COMMERCIAL O?ERA'l'lON)
INl'.!.'lAL ClJ.'J.'ICALI'.!.'Y nTJ.'lAL EUCTRICI'l'Y CO!tiAi~ER()lAL O"iJtF:./{!.'lO!J
UNIT SllUTIJOWNS AND POWER REDUCTIONS DOCKET NO. -5D=28u.O-~-
UNIT NAME -Surry Iln:i t ~
DATE COMPLETED BY REPORT MONTll MAY* l 980 TELEPllONE
,~,
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0 l.J 6
80-7 5-1-30 F 260.9 D 1 80-01!3 Continuation of shutdown for piping restraint modification and turbine rotor inspection which began 2-19-80.
80-8 5-11-80 F 2.1 G 3 Reactor trip caused by feed flow/steam w flow mismatch with Lo S/G level signal while feeding S/G's in manual during escalation of power 80-9 5-12-80 F 0 G 4 Inadvertant boration of primary system when 11B 11 mixed bed clemineralizer was placed in sc.rvice without verifying boron conc('nU:ation of effluent was equaliz*ccl with primary system boron concentr;:1 t:i.on. Inadvertant boration ca us ell /':, yf to remain outside target band for greater Uwn one hour in a
- 21. hour pccLod necessitating power re-
._di1C..Llnn-1.:o_::;__.5J}Lµru..-Ler llll I' *j] ~ :w:j 1-Jij 0 target ban~ for 24 hour&
J r: rorccJ Reason: Method: Exhibil G - lnslr11cti1111s S: Schcdulcu A*Eq uipmen 1 Failure (Explain) I-Manual fur Prrpa1;1liu11 uf [)ala 0-Maintenance or Test 2-Ma1111al Scram. Entry Slicels fur Licenser
(-Refueling J.J\11t11111alic Scram. Event Report lLlRl File \NURu;.
D-Regulal(HY Restriction 4-0lhcr (Explain) 0161)
E-Opcrator Training & License Examination F-Ad min isl ra I ive -'
G-Opcrational Error (Explain). [;(hibil l - Same S1111r.:I.'
(l)/77) II-Other (Explain)
UNIT SllUTOOWNS ANIJ POWER REDUCTIONS DQCKtT NO. ...__,;.S_,,_0-lli.L_-__
UNl't NAMt ..S.Urry Uul t: _z_
COMPLETED B'\'
fJATE ------
RErORT MONTI!
- MAY~ 1980 TELEPHONE . (804) 357-3184 li1:c11scc Cause & (urrcdivc Dale Event At:tion 111 Rcporl. # P1 cvc111 Rccttttciti:c 80-5 5-1-80 s 744 D 1 Continue.J:Jon of shutdown for refuel-ing & steam generator replacement, which began on 2-4-79. Work still underway on piping restraint modifi-cations required prior to unit .i:-
recovery.
3 F: Forced Reawn: Method: Exhibit G
- lnstrudinns S: Sclmluled A-Equipment Failure (Explain) 1-Mnnual for Prrparaliun 11f Data B-Maintcnance of Test 2-Manual Scram. Entry Sheets for Licrmcr C'-Rcfucling J-Autu111atic Scram. Event Report (LER) File (NURH;.
D-Rcgulatory Restriction 4-0thcr (Explain) 0161)
!:-Operator Training & License Examination r-Administ rat ive G-Operational Error (Explain) Exhibit I *Same S1111n:c
(
1 1/77) I I-Other (Explain)
- LOAD REDUCTIONS DUE TO ENVIRONMENTAL RESTRICTIONS UNIT N0.1 MONTH: K4.Y, 1980 I
DATE
- - TI11E HOURS LOAD 2 MW REDUCTIONS 2 MW m-m
- - REASON None during this repor; ing peric ki.
i I
I I ..
I II I
Il MONTHLY TOTAL
e - 6 -
e '
LOAD REDUCTIONS DUE TO ENVIRONMENTAL RES.TRICTIONS UNIT N0.2 MONTH: M8Y. ]980 DATE
- - TIME HOURS LOAD 1 MW REDUCTIONS 2 MW I Mf~IH
- - I REASON None :luring this repart~*ng period ..
t I
MONTHLY TOTAL
DOCKE'l' NO so .. 2ao s,:;RRY I D.4'1'!!,' 6.:1.-80 COMPLETED BY 0 J COS'EELW
!j_Q}; tf : M:1Y so AVERAGE DAILY ?Ow ER LEVEL .4VERAGE DAILY ?CJ..IEP. LE:IEL DAY (MflE'"NE'J.') DAY (11.:../Er.NET) 1 0.0 11 6%.8 2 0.0 18 699.8 3 0.0 19 6S/ .0 4 o.o 20 101.0 5 0.0 21 101. 8 6 0.0 22 588.0 1 0.0 23 68/ * .S 8 0.0 24 690.1 9 0.0 25 689.5 10 0.0 26 685.5 11 4. I 21 688~9 12 452. 3 23 684. 2 13 438.8 29 680.3 14 674.6 30 6"/5. 8 15 581.5 31 666.* 1
.!.O 699.5 DAILY .::iiIJ' ?O:.iE.~ LEVEL FORM INS'J.'R,/CTIONS ON 'TnlS FORY1. LlSJ.' 'l'ff.E .*1VEf.AGE DAILY .:.-iVI'J.' ?CMEF: LEVEL IN f*ftlErNE1' FDR E:/CH DAY IN l'HE F.E"L'ORJ.'IfvG /IJON'J.'fj. 'l'h.ESE FIG~;RES raLL BE; ~*sED '1'0 PLO'J.' .1 GR.Pb." FOR EACH RE?OR'l'<<
ING f.iONTd.. NO'!.'E Tft.:l'l EY .::SING M:"!XD,;,;*M DEPENDABLE C.4P:lCITY FOR THE l;f/1' ELEC'J.'F..IC.4L F..-1'1'ING OF 'THE ,:iAJ'J.'. 'l'HEF..£ i1.4Y BE' OCCASIONS Wft6A 'l'iiE DAILY .-WER.4GE ?OWER *EXCEEDS 'l'itt, 100 ° / 0 LLiiE WR 'l'HE RES'J.'RIC'!.'E,D ?0;1ER LEVEL LlNE). IN s;;cH CASES~* '.!.'HE ..1VER.4GE DAILY Z;°NI'J.' I'O~/E;R o;;].'?.:*'"T SHSE'l' SHo.:;LD BE F002';"v(J1'ED 'J.'i) EXPLAI!i 'l'H.E /l??AF.ENT Ali:JMALY.
- 8 DOCKEJ.' NO e*
so,.2s1 JNI'J.' s:JRRY II DA'.!.'E 5.,1 .. so COM?LE'J.'SD BY 0 J COS'J.'i:.EW MON'!.'H.: N.-1Y BO AVERAGE DAILY ?01./ER LEVEL .4VER.*1GE DAILY I'O?lEF~ LEVEL DAY lMi-iE ~N E'J.') D.1Y \.!.fdE,,NEJ:) 1 0.0 11 0.0 2 0.0 1S OoO 3 o.o 19 o.o 4 0.0 20 0.0 5 0.0 21 0.0 6 0.0 22 0.0 l 0.0 23 o.o 8 0.0 24 o.o s 0.0 25 0.0 ~.7 ' 10 0.0 26 a.o 11 0.0 21 o.o 12 0.0 23 0.0 13 0.0 29 0.0 1 I: 0.0 30 0.0 15 0.0 ~1
"'- 0.0
- r
.LO 0.0 DAILY .::NJT ?O'..i£-R LEVEL FOPlvi INSTRJCTIONS ON 'J.'HlS FORM. LlSJ.' TH£ .4VER.4GE DAILY ;JiiI'J.' ?OVIER LEVEL IN MWEnNE'l' FOR E.*V.:f:i. D.4Y IN
- 7'fiE F.Ei'ORJ.'ING MON'J.'H. 'J.'HESS FlG.:*"RES WILL EE :..*ssD TO ?LO'l' A GR.4...-,H FOR E/Cfi fr.E?OJ?!..'.,
Il-iG MOiVl'H. NO'J.E 1'H..1T BY :.;"SING M.4XL'vJ.'R1; DE?END.4bLE CA.PACITY FOR :J.'HE !r'5T ELEC1.'E.IC.4L Fr.AT ING OF THE ,*.iNl'J.'. :!!HERE M.*1Y BE OCCASIONS WHEN THE DAILY AVERAGE ?OWER EXCEEDS
'l.'hE 100 o/o LINE (OR THE RES'l.'RIC'J.'ED ?OWSF. LEVEL LIM:;). IN s:,.*cH CASES. 'J.'HE AVERAGE DAILY. :JNI'11 i'OWER OU'l.'?,j"'J.' SHEEJ.' SHO;JLD BE FO(J1'!Wl'ED '.!:'0 EX?L:11N '!.'HE :P?.-1ii.EHT ANOMJi.,Y.
SUMMARY
OF OPER.t'\.TING EXPE~lCE MAY, 1980 Listed below in chronological sequence by unit is a sununary of operating experiences for this month which required load reductions or resulted in sign-ificant non-load related incidents. UNIT 1 Hay 1 This reporting period begins with the unit at cold shutdown for piping restraint modifications and turbine rotor inspection. May 10 Exceed 350°F/450 psig on primary system at 2215. May 11 The reactor was critical at 1547 and the generator was on-the-line at 2055. A reactor trip/turbine trip caused by feed flow/ steam flow mismatch in coincidence with a low level in "C" S/G occurred at 2106 while feeding S/G's. The reactor in manual was critical 2132 and the generator on the line at 2300. Com-menced power escalation. Hay 12 At 0700 reactor power was leveled off and held at 96% due to sodium carry over in the main steam system. At 1220 the control room operator placed the "B" mixed bed demineralizer in s'ervice. after flushing without having determined that the boron concen-tration (CB) of the effluent was equalized with the primary system CB. At this time the primary CB was 315 ppm and the demineralizer e~fluent CB was 1076 pp~. This inadvertant boron addition initiated a rapid power reduction from 95% to 80%. While stabili:dng plant parameters at 80% power the axial flux difference (AFD) deviatt:!d from the target band for greater than orie hour; .A power* i;eduction to 50% was commenced at 1250 and at 1325 the AFD returne~d to the target band. Power reached 50% at 1440.
~1ay 13 Conmenced power increase at 1325. Power reached loo;; at l845.
Hay la At 1033, while attempting to return the "B" H. P. drain pump to service after maintenance, the pump discharge flange. developed a. severe leak. At 1148 a power reduction was corm;ienced to allow securing the "A" H. P. drain pump to facilitate isolation of the leaking pump discharge flange. The power reduction was stopped at 1215 at 92%. At 1632, after leaking flange was isolateJi and main-tenance personnel had tightened the flange bolts> the "A" H. P. clrain pUJ.11p_ was restarted and a power increase. was begun. Power reacr*ie.d 100% at* 1845. An inadvertant boration occurred at 1220 due to leakage of boric acid past MOV-1350. This resulted in a power decrease to 88%. A dilution and power increase was commenced and power reached 100% at 2030. May 20 At 1425 the chemist report the "A" boric acid storage tank (BAST) C was 13.1%. This is greater than T.S. limit of 13.0% and a power r~duction to hot shutdown began at 1438. AT 1514 the C of the "A" BAST was determined to be 12.7% after the addition of 2f 6 gallons of primary grade water and unit was returned to 100% power.
l
- 10
.SUH!*lJ..RY OF OPERATING EXPERIEN. (continued)
MAY, 1980 Listed below in chronological sequence by unit is a Slnnmary of operating experiences for this month which required load reductions o::- resulted in sign-ificant non-loacl related incidents. UNIT 1 1'1"..a.y 26 Unit power was reduced to 96% at 1855 due to decreasing condenser vacuum. Unit power was returned to 100% at 2115 after condenser vacuum returned to normal. May 31 Power was reduced to 95% at 1835 to reduce sodium carryover in the main steam system. At 2240 power was increased to 97%. This report-ing period ends with the unit at reduced power due to sodium carry-over in the main steam system. UNIT 2 May 1 This reporting period begins with the unit at refueling shutdm..'-n with the core loaded and the reactor vessel head removed. May 3 Reactor vessel head in place. May 9 Reactor vessel head bolted down. May 26 Type "A" test on conta.inment completed satisfactorily. May 31 This reporting period ends with the unit at cold shutdown with maintenance, piping restraint modifications and design changes continuing.
AHEJ:ID.MENTS J'PFACILITY LICENSE OR TECHNICAL * *CI.FI CATIONS HAY, 1980 The Nuclear Regulatory CoIIIm.ission issued, on Hay 16, 1980, amendment. No. 58 to the Operating License for Surry Power Station Unit No. 2, which was designated as Technical Specification Change No .. 65. The change is a result of our request to revise the Unit 2 specifications to reflect a tube plugging limit to 3% for the new steam generators. Of significance are the following changes:
- 1. The limit for the heat flu.~ hot channel factor, FQ (~),has been raised to 2.19.
- 2. A curve of normalized operating envelope K(~), has been added for Unit 2.
- 3. The limits for nuclear enthalpy rise hot c:b.annel factors, kg~A N LOCA N
FliH and FliH and 1.476, respectively. I Assm, have been raised to 1.55
- 4. Deletion of power distribution monitoring requirements.
-****::-=***---~
- FACILITY CHA..NGES REOUIRIHG NRC APPROVAL MAY, 1980 Hone during this reporting period.
FACILITY CHAHGE.S THAT DID NOT REQUIRE NRC APPROVAL The following facility changes were implemented during the month of }1ay: Design Changes Unit
- 1. DC/79-S37 ASCO Solenoid Valve Replacement 1 This modification precipitated by IE Bulletin 79-01 provided for the replacement of solenoid valves presently installed with others which are enviroTu.~entally qualified.
Suillillary of Safety Evaluation Since this design change merely replaces the pres~nt valves with identical ones having an environmental qualification, no new safety considerations have been surfaced beyond those previously addressed.*
- 2. D/C-79-58 Reactor Coolant System Subcooling Monitor System 2 In an effort to weet requirements of THI 2 NUREG 0578 Section 2. L 3 b and subsequent NRC clarification, two subcooling meters have been in9talled on the main control board to provide indication of reactor coolant l!lE.rgin to saturation conditions.
Suill!ilary of Safety Evaluation This system will provide the operator with an indication of the reactor* coolant system margin to saturation conditions. It does not effect the operation of any safety-related equipment, therefore there are no safety probleras created with this modification.
- 3. D/C-79-59 High Range Radiation Monitor 2 To confor-m 1Jith section 2 .1. 8 b of NUREG 0578 resulting from THI, additional high range effluent monitors have been located in the service building, au..xiliary building, and main steam valve house.
Summary of Safety Evaluation These instruments will provide assurance that the necessary monitoring capabilities for anticipated release paths are available during or after an accident. In such case the modification would have no effect on the operation of safety related equipment.
13 - FACILITY CHANGES TH.AT DID HOT REQUIRE NRC APPROVAL (Continued) HAY, 1980
- 4. D/C-79-85 Replacement of Diesel Fire PUEp Starting Contactors This modification initiated in response to IE Circular 79-13 replaced the components which were determined to be defective with the new 217588 magnetic switch.
Summary of Safety Evaluation This design change has no adverse effect upon the safety considerations of the fire protection system since the modification provides for the replacement of a switch with another which will improve the reliability of the system.
- 5. D/C-80-06 Replacing Westinghouse BFD Relays in Safety Related l Systems In response to I.E. Bulletin 79-25 BFD relays usen in engineered safeguards systems logic were checked to assure proper performance.
This design change replaced those relays which were determined to be substandard. S'..!.EJ.arv of Safety Evaluation tfnile this design change will improve system reliability, no changes to Technical Spec:i.fications (Section 3. 7 Instrumentation Systems) have been made nor will the protection logic specified in Section 7.2 of the FSAR be altered.
- 6. D/C-80-19 Interiill ?:-fodiffrations Providing Relief to Service \*;'ater 1 Temperature Restrictions A number of hardware modifications were installed to upgrade the performance of the contailliilent spray and recirculation spray systems.
'l.'i:~e overall effect: of tfi_is design change is to insure adequate net
- positive suction head is available in case of a Design Basis Accident.
Summary of Safety Evaluation This design change will not affect any station operating procedure. or the operation of safety related equipment. It should be. noted that a change is required to a periodic test in order to account for the difference in pump discharge flow.
- FACILITY CHANGES THAT DID NOT REQUIRE NRC APPROVAL (Continued)
K.\Y, 1980
- 7. D/C-80-35 Diverse Insolation Signals To Containment Trip Valves 1
*In response to section 2.1.4 of NUREG-0578 which addresses the possible consequences of depending solely on containment high pressure signals to isolate non-essential penetrations, diverse signals were supplied to non-essential containment trip valves.
Summary of Safety Evaluation This modification involved the deletion of outputs from the CLS system, replacing them with Safety Injection Signal outputs. This is the only change in the operation of the Engineered Safeguards System. Station Operating and Testing Procedures are to be updated to reflect this change. This design change improves the containment isolation system and has no effect on the operation of the other safety systems or safety related equipment.
- 8. D/C-80-38 Addition of Isolation Valve To 3"-BR-163-154 1, 2.
The Boron Recovery Tanks vent through line 3"-BR-163-154 to the Gaseous Waste Disposal System. This portion of the system is Seismic Class I and the Boron Recovery Tank vents are non-seisuic. The installation of. this manual isolatio,11!J. valve is required. to provide a seismic boundary to isolate the non-seisnic piping should the nee<l arise. Su..TilI!l.8.rv of Safety Evaluation This modification will have no adverse effect on safety related equipment and will enhance the reliability of the system.
- 9. D/C-80-29 Condenser Air Ejector Containment Isolation l Valve Relocation This modification relocates isolation valve TV-SV-102 close~ to the contairnnent in line 6"-AJA-4-121, installing a new valve at the old location. This was done to reduce the extent of seis;nic analysis required to insure the adequacy of containment isolation design for this line.
Summary of Safety Evaluation This design change involves only the relocation of an existing valve maintaining the system process thus constituting no safety hazard.
TESTS AND EXPERIHENTS REC,'<.IN.'G NRC APPROVAL K"i.Y, 1980 J:.Jone during this reporting period.. TEST AND EXPERIMENTS THAT DID NOT REQUIRE NRG APPROVAL None during this this reporting period.
A - 16 - ,A 8'fu:R CHA..'iGES, TESTS AND EXPERIH:fws HAY, 1980 None during this reporting period.
SURRY PO wER STATIO!-.
- CHEMISTRY REPORT j.gy 19--8.Q_
T.. s . 6 . 6 . 3.. d PRUIARY COOLANT UNIT NO. 1 UNIT NO. 2 ANALYSIS MAXIMUM MINIMUM AVERAGE MAXIMUM MINIMUM AVERAj Gross Radioact., µCi/ml h hh°F. 1 1 Q1F *? 2.71E-l 2. R 1-P.-? c:; !J.l:P-6 .l c:;717_ Suspended Solids, ppm
.. 7 1 n n , n 2.4 0.0 0.2 Gross Tritium, µCi/ml r:. r:.nv. .? 1 ':l/, p .? 1 C::.C::.F-? - - - . ..
Iodine-131, µCi/ml 2.53E-2 8.93E-4 6.QSE-1 - - - I-131/I-133 0.6673 0.1672 0.2707 - - - - Hydrogen, cc/kg 44.6 5.4* 33,11 - - - Lithium, ppm 1.30 O.lOH 0.68** 0.10 0.10 0.10 - Boron-10, ppm + 516.46 26.66 192.59 441.196 ; 405.132 421. 431 Oxygen-16, ppm - 2.3 0.000 0.400 0.06 () r>.:; n oc:; Chloride, ppm
.0~05 0.05 0.05 0.06 0.05 O.O"i
- pH @ 25°C 7.50 5.29 6.06 5.59 4.72 5.03
+ Boron-10 Total Boron x 0.196 NON-RADIOACTIVE CHEMICAL *-** RELEASES, POUNDS T. S . 4 . 13 . A ".~§*1 Phosphate Boron 1088 Sulfate 379 Chromate ---"-..L-.-4-L----- 50% NaOH Chlorine
----='-=-----
Remarks: /fl Rx (<l 5-11 80 ?131 ;,*#1A(217) MIXED BED Flnshed and pnt in Service ou 5-19-80 *Notified Supervisor of Operations to Increase Press on VCT
#2 Refueling completed 5-9-80 @2 Rx @ COLD SHUTDOWN (l) These levels of chemicals should present no major adverse environmental impact.
.* CRIPTION OF ALL INSTANCES WHE DISCHARGE LWITS WERE EXCE ~D 1'L<\Y' 1980 Due to impairment of the circulating water system on the following days the thermal discharge limits were exceeded as noted. Exceeded 15°F m: across station May 13 through 19
- Exceeded 15°F m: across station May 23, 1980
- Exceeded 15°F &' across station Me.y 25, 1980
- Exceeded 15°F m: across station May 26, 1980
- E.xceeded 15°F !St across station Hay 27, 1980 *
- Exceeded 15°F m: across station Hay 28, 1980 Exceeded 15°F m: across stat:i,.on May 29, 1980
- Exceeded 15°F IJJ: across station May 30, 1980 *
- Exceeded 15°F m: across station Hay 31, 1980
*Indicates dates where station lT was less than 15.0°F across the station for sometime during the day.
The liT excursions were allowable under Technical Specifications 4.14.B.2. There were no reported instances of significant adverse environmental impact *. On May 28 or 29, 1980 a fish die-off which occurred was investigated. The die-off does not appear to be related to any temperature effect but a natural occurrance.
- FISH KILL I"NIJESTIGATION NAY, 1980 On the morning *af May 29, 1980, a commercial fisnenr.a.n reported seeing, " ...*. thousands of dead menhaden floating out of the discharge canal". He had observed the fish while tending trot lines located at the Surry Power Station discharge groin sometime during the night of Hay 28-29, 1980.
An investigation was initiated innnediately to determine the validity and extent of the reported fish kill. Intake and discharge temperatures were determined for the night in question, beach and water surveys were conducted, and individual_ specimens were e..~amined. A total of 65 dead menhaden were located in an area from 100 yards upstream from the discharge groin to a point one mile downstream. Of this total 34 were found in the slack water inside the groin and 31 were floating in the water near shore throughout the remainder of the area. None of these fish were found on the beach which seems to indicate the fish had died recently. Also, none of the fish were in the flowing water of the discharge canal indicating the reported fish kill was not occurring at the time the surveys were conducted. Menhaden (Brevoortia tyrannus) was the only species observed. All specimens ranged in length from lOOram to 140mm which indicates they were age I fish.. None of the 20 .specimens examined showed any signs of mechanical damage which rules out *the po"er station screens and culling by fishermen as the cause of death. Observations were made periodically throughout the evening of
- Hay 29, 2.nd the early morning hours of May 30, 1980, to watch for any reoccurrc:nce of the reported fish kill. Only two dead fish were observed during the entire night even though the b.T 0 across the station and the maximum. water temperature were approximately the same as when the dead fish were observed by the fisherman.
Observations during the hours of darkness revealed a possible explanation for the discrepancy between the fisherman's report of "thousands" of dead fish and the small numbers found in .our surveys. Fo2.m generated in the turbulence of the Unit 1 discharge breaks into small cohesive patches about the size of the dead menhaden observed. With the use of artificial lighting 2.t night it is extremely dHficult to d.iffere~1tiate between the foam. and dead fish without. moving to within 2. couple feet of the object observed. When -the light was cast across the canal it appeared as if a fish kill was in progress. Additional beach surveys were conducted on May 30, and June 2, 1980~ but no dead fish were found. Conclusions Evidence indicates a minor Menhaden die-off occurred in the station discharge canal during the evening of May 28 or. the morning of May 29, 1980.
~ 20 -
FISH KILL INVESTIGATION (continu~d) A die-off is indicated as opposed to a fish kill directly related to the operational e£f ects of Surry Power Station. The deaci fish were exclusively age I menhaden and did not include any age 0 menhaden* which are extremely abundant in the river. This pattern has been observed in other natural die-offs of menhaden which have occurred frequently else-where in the river. Also, live menhaden were observed in the discharge canal in very large numbers after the reported fish kill. Operational and water temperature conditions during these observations were almost identical to those occurring during the period when the fish kil],. was reported to have occurred. The die-off can be termed minor relative to the large natural die-off s observed elsewhere in the river. A die-off on June 14, 1979 inves-tigated by this office and the State Water Control Board found several thousand fish per mile which is much larger than the 65 fish per mile
. found in this investigation. Fish from the June, 1979 die-off were found on several miles of beach whereas this investigation did not find any fish beyond one mile downstream from the groin.
UNIT 1 FlJEL HA!WL ING NAY, 1980 I DATE NO. OF I ANSI HO. };".C:W OR SPE!~T FUEL
- =:.IPPED/RECEIVED ASSEXBLIES PER SHIPMENT INITIAL ENRICIDE-r-;T SHIPPING CASK ACTIVI'IT LE' 1
I I I I I Jin~ I [ I None tbjq :r:epo:z:U:ag .l pt.5~;tgr* I f. I l I .. I I I* - ... I I I I I ' I I I
----* J__ ________
~
. UNIT II -
e FUEL HANDLING Ki\Y. 1980
- 22 e L DATE NO. OF ANS.I NO. NEW OR SPENT FUEL 03IPPED/RECEIVED ASSEMBLIES PER SHIPMENT INITIAL ENRICHMENT SHIPPING CASK ACTIVITY LEVEL I I I
Noneldurine: thi i::: rP-nortincr
-n=* .; nt1 I
I I I I .. I I I I I I
- PROCEDURE REVISIONS THAT Clli ""- ED THE OPERATING*HODE DESCRIBED IN HAY, 1980 None during this reporting period.
FSAR
. *, IPTION OF PERIODIC TESTS WHIC RE NOT COMPLETED WITHIN THE TllIE LIM rs SPECIFIED IN TECHNICAL SPECIFICATIONS MAY, 1980 PT-24.6 Fire Protection, Halon 1301 System (Records Vault) was not conducted on Unit t;o. 1 when scheduled (4-13-80). This monthly test requires that the fire suppression system be checked for proper operation. The test was conducted on April 23, 1980 th~ee days beyond the 25% grace period permitted by Technical Specification 4.0.
PT-34 Electrical Penetration Leakage Test was not conducted on Unit No. 2 when scheduled (5-9-80). This weekly test to verify the integrity of the containment electrical penetrations was conducted on May 13, 1980 two days beyond the 25% grace period established by Technical Specification 4.0.
IN SERVICE INSPECTIQe* HAY, 1980 None during this reporting period. I
26 - ORTABLE OCCURRENCES PERTAININ Al\TY OUTAGE OR POWER REDUCTIO. MAY, 1980 LER 80-026/0lT-0 Delta Flux out of Band longer tnan one hour Date of Occurrence: 1-fay 12, 1980 Date Report Submitted: May 22, 1980 LER 80-030/0lT-0 Excessive Boric Acid in "A" Boric Acid Storage Tank and No. 1 Boron Injection Tank Date of Occurrence: May 20, 1980 Date Report Submitted: Due June 3, 1980
Maintenance of Safety Related Systems During Outage or Reduc'ed Power Periods UNIT f.!l Mechanical Maintenance
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Maintenance of Safety Related Systems During
*outage or Reduced Power Periods UNIT 112 Electrical Maintenance
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HEALTH PHYSICS - - HAY, 1980 There was no single release of r2dioactivity or radi2tion exposure. specifically associated with an outage that accounted for more than 10% of the allowable annual values in 10CFR20.
....J ** .' r a - 46 - ** a PROCEW£ DEVIATIONS REVIEWED BY STATI-~lJCLEAR SAFETY AND OPERATING COHUITTEE AFTER TIME LllfITS SPECIFIED IN TECHNICAL SPECIFICATIONS 1-Ll\.Y, 1980 NUMBER UNIT TITLE DEVIATION OP4.4 2 Full Length RCC Steps 4.1 *through 4.1.17 Drive Shaft Tool Not Applicable Step 4.35 - Did not use Use 1000# scale The above procedure was deviated on April 25, 1980 and reviewed by the Station Nuclear Safety and Operating Committee May 16, 1980.}}