VIRGINIA ELECTRIC Al'lD POWER COMPANY

·•

VIRGINIA ELECTRIC Al'l"D POWER COMPANY

SURRY POWER STATION

MONTHLY OPERATING REPORT

REPORT NO. 78-07

JULY, 1978

.. __ ~

Superintendent-Station Operations

APPROVED: \ ' \

·~·- \ . , I

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'MANAGER

~· ·"i>2-7-~ i

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CONTENTS

.. Sect;ion

Operating Data Report - Unit 111

Operating Data Report - Unit 112

Unit Shutdowns and Power Reductions - Unit ffl

Unit Shutdowns and Power Reductions - Unit 112

Load Reductions Due to Environmental Restrictions - Unit Ill

Load Reductions Due to Environmental Restrictions - Unit 1/2

Average Daily Unit Power Level - Unit Ill

Average Daily Unit Power Level - Unit 112

Summary of Operating Experience

Amendments to Facility License or Technical Specifications

Facility Changes Requiring NRG Approval

Facility Changes That Did Not Require NRG Approval

Tests and Experiments Requiring N~C Approval

Tests and Experiments That Did Not Require NRC Approval

Other Changes, Tests and Experiments

Chemistry Report

Description of All Instances Where Thermal Discharge Limits Were Exceeded

Fuel Handling

Procedure Revisions That Changed the Operating Mode Described In 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 Ill - Mechanical Maintenance

Maintenance of Safety Related Systems During Outage or Reduced. Power Periods - Unit 112 - Nechanical Maintenance

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25

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• Section (

Maintenance of Safety Related Systems During Outage or Reduced Power Periods - Unit Ill - Electi;ical Maintemance

Maintenance of Safety Rela.ted Systems During Outage or Reduced ~ower Periods - Unit #2 - Electrical Maintenance

Maintenance of Safety Related Systems During Outage or Reduced Power Periods - Unit #1 - InstrUIDent Maintenance

Maintenance of Safety Related Systems During Outage or Reduced Power Periods - Unit #2 InstrUIDent Maintenance

Health Physics Sunnnary

Report of Effluent Release D.ata

Sensitivity Data

Procedure Deviations Reviewed by Station Nuclear S.afety and Operating Committee After Time Limit Specified in T.S.

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31

33

35

37

39

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43

44

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R EPQ RT

COMPL~TED EY O.J. COSTELLO TELEPHONE 80U-357-318u . ·---- -

ST'ri'JUS - --- -------·-----. -------·---------------------

------

g, ?G~EE LE'l~L Ta wa:cE RESTR:CTED. IF ANY NIA ---·---·(NE:T ~·.;;.,7 E) ·- ------ ----------------------

10. REASONS FC2 RESTR:~TIONS, IF ADY NIA

---r:;.-. - Ii OTT:? s .. -:: 1T--P3 F (; 2 'J'I"JI G -p ::,· ,'( .;_ Ou 12. HUU3E2 O? HOURS EEACTOR WiS CR7TICAL

7 ~--u • 0 613,6

s-o-st-:v---tr s-rs;.-:-tJ--.... --~ 3280.6 32597.5 '

13. REA~TQR EESEEVE SHUTDOYN HOURS 0. o- 0-. 0 o.o ---14-.-·-nav.~s· G~i'ls .. rr-~'l'CR-Oll-=L-:i .. lE -----------~-~-. ~ .f2 u :i • o--;,-1-rr:".J-:~- --

1 s. UN:T RESERVE SHUTDOWN HOURS O,O 0.0 0.0 iS. GROSS TiER~AL E1ERGY G2~ERATSD (MWE) 1270651.0 7757403.D 723~S399.0

;;---""- 7 -- r =-"ri c- "t--;--r ~.r·,.rr:r.-·-c· -~-r- ·ri i.:·--.-:, /"" v-r·~ .. n;:-;;-·rm~"D-t;--:ff/.-.}-~·1--u-Q-"':-0--U7"'-.. --~ ·~0~.r~:~. 11----i:i-~Cf'/-~..:--c~·-.~,~ .-;.;.. • - J., • .J•L~~-- -.J}..J..,; ....... • ...:. .r...u ul°:l:JJ.~U' ... : •• ;o..Jl~-·;.LJ-.J.!:.J.., \ • .:-:-r;..... ; . L ~v ..... .... _ ...., __ ',.) ...... '-..., ____ ~;.,J .......

18. fiET ELECTRICAL EYERGY GEYERATED iMWH) 381029.0 2il38356;0 22705920.0 19. UNIT SEEV:CE FACtOR

·---2-0 ~--UI·l:~r" / ... F A:L/..3: LITY--F'ACTOP. 21. UN:T CA?AC:TY FACTOR (US:NG UDC 22. U[IT CA?ACIIY FACTOR (US:NG DER

----2-3-~--i'i/:-T--FO?.C E D--o-o·T-;:,,,·G-~-R A'i'"E sau~~o~;s SCEEDULED OVER ·vEXT s

63 .. 0 o/c 54.6 o/o /-2-.··c,-Of-o--6-~.-iJ-O)o----OlI;-:6-c7--o - ·---··

NET) 56.1 o/o 61,8 o/o 59.5 o/o NET) 52,3 o/o 58.3 c/o 56.2 o/o

-----0-:rs--01 o u-:O o / o -:;:;-:0-c-;·-0--

MONTES SNUBBER :NSPECT:ON 9/10/78 ~TY?E,DATE,AllD DURATION OF EACE) 1 ~EEK; S/G :NS?2CTION

-·- . .. - -·--·-·- ---·---· - . ------··-----------1797"7 9~-';./::,2KS ---

25 .. U~ITS :~ TEST STATUS FOR'5CAST ACHI~VED

.:_ -------~.?.P..=?J! __ ;r:;;_q_O_J!j_~~c._:::!:~_J?E~~-T:::o.~_1_) ___________________ _

:~:T:AL c~:T:CAL:TY

=~IT:AL [LgcrR:c:TY -- co:.J!·1'ERC: J..L--O?~RA.'i.'-::·ou

1----~·- ·---· ·- -- ·- ---- ·----- ----- ---'

1-------------------·-··- ------

------ ----··---·------·-- .. ·· . ----·------------------------------------

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-·····----- -,

-2-0 PER t. T .:-1.:.;A~ A REPORT

DOCKET llO. 50-281 -·· --··· .. ·-- -·--·--·-·-·--- -- ····v-AT'E-0""3--A7FGr t'

COM?L2TED BY O.J. COSTELLO TELEPHONE ~04-357-318U

1. v~=T vA~s SURRY UN.:-T 2 -----2-:· .. ?.'E?ORT ::,-.;c-.. PEi::CJ'D v1JOT/1rOTOT=-:'.lf0v/ 8v7:r1

3. i:czcsED THERMAL ,?OWEE lMWT) 2U41 ,------------------------! LJ. ~AXE~L~TE Et.T:NG (~ROSS U~S) 847.5 IDOTES I 5 .·· -D~S:G,7 .EL~CTEICAf--R/:.T:f,7 G-(!/E1'-f.fll?·)-----822 l ----- -~-

5. ~AX:~u~ DEPENDABLE C~FAC:TY lGROSS M~E) 811 I 7. J.:AXI:W2: D?P~i'iDABLE CA?t.C::IY (1~1 ET !{iiE) 775 l_ ________________ ..;.... __ i

--- . .---8. :: F c n.4!iGES occrr§- I1V. ·c APAC ":'iY-7d?PtNGs·-1n A --------.. -----·-----·---- --·- -------- -

lITE~S 3 THROUGH 7) S~NCE LAST __________ F:~PC?.~. G:l[_fc ii§.f:.~_q __ N_S __ ----------·-----·---

9. POWE3 L5VEL TO WHICH RZSTR7CTED, :F ANY NIA ----------------10. REASOliS FOR RESTRICTIONS, IF AllY

-·--:n·-:-·- BGUF.S :N· ?.'EPORTING-PEIC'OD. 12 NUMBER.OF HOYRS REACTOR WAS CRITICAL 13. REACTOR RESERVE SHUTDOWN HOURS

-··-·-1u • .. HCU?.S -G5FER ATOR- O!i=tiliE ______ . -----15. UHIT RESERVE SHUTDOWN HOURS

NIA

/1!4. u :iut! 7·:-v----i.rti·u-3r.D---148. 1 3860.6 30273.4

0.0 0.0 0.0 -i-1.rB . ...: ~--~::SB su-.--1-·----2 977s-:v---

o. o o.o 0.0 16. GRQSS THERMAL ENERGY GENEEATED (M~E) 351672.0 935U683.0 69064917.D

· <;-~··r~ .. ·1;?.-oss~--E i:;cr7!°Ic·xr,· ·5x7 t:f?Gj'-c;:;:r;1s~r?7:1' EiFTkfl H) --1-12010~0-·3-0 3 s5·90-:·v-2ro-05·0-sii-:-o--~ • 18. NET tLECTEICAL EYERGY SENER~TED (M~E) 10635U.O 2888011.0 21ll4112B.O

19. V~IT SERVICE FACTOR 19.9 olc .75.7 °10. 6U.7 °10 .· -··- 2·0 ~ .. - U iCT AV'"J.I LASI iIT'F.? fi.cj'(iR_____ fg ·:9-;,7-c--7 5 :·7-·0 ; o .... -.. t·u·: r-0:;-0··--· .

21. UNIT CAPACITY FACTOR (USING MDC NET) 18,Ll olo 73.3 ~lo 60.1 01°. 22. U~IT CAPACITY FACTOR (USIYG DER NET) 17.U o/o 69.1 olo 56.? olo

--23 ~-u l.'::'f Fd?.cirT "oj'J iGE RJ.'fE-- (). 0 ° I c 3-:-407-0 --z-3-:3-o-ro--2u. SHUTDOWns SCHEDULED OVER NEXT 6 MONTHS SNUBBER INSPECTION 9125178

(TYPE.DATE.AND DURATIOP OF EACH) 1 WEEK-REFUEL:NG --- ---·--- ... ---- - .. -...... -.. - ... -- .. ----------·--·127 2 s77e.·::.·5-~-p; t.Ii.s--·--------~ ·

25. IF SHUT DO~N AT END OF REPORT PERIOD, NIA -----E s'i:f.: A''i't"-D ki'E--oF·-517i"PiTU P ·-----------------

2 s. UN:TS IR TEST STATUS FORECAST AChIEl'ED (PF.IOR TO COMM3RCIAL OPERATION)

IN:TIAL CRIT:CALITY IEITIAL ELECTRIC:TY

·- -- -·- .. ·- C0!~:.1.J2 RC: AL-~OPERAT ;·all

---·------·---

-------------·--------

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78-1 780701

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F: Forced · S: Scheduled

(IJ/77)

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UNIT SHUTDOWNS AND POWEil JtEPUCilONS

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Reason: A-Equipment f-ailure (Explain) D-Maintemince or Test· (''l~cfucling

ilEPORT MONTI! July 1978

Licensee Even I

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Method: · I-Manual

2-Manual Scram. 3-Aulomallc Scram. 4-0lhcr (Explain) . D-llcgulatory Restriction

E-Opcrator Training & License Examination F-/\drninistrali'ic · G-Opcralional Error (Explain) 11-0lhcr (Expl:1in)

DOCKET NO. UNIT NAME

DATE COMrLETED llV

TELEI llONE

C:iusc &. Currccllve Acllun lo

Prevenl Recurrence

50-:-280 Surry l 8-1-78 -o. J. co.:t•:!l1o (804) J57-3I84

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Unit shutdown at beginning of period.

Turbine repairs in progress.

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Exhibit G • Instructions for Preparnllun of Data . Entry· Sheets for l.ktnsec

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• Event Report (LER) File lNUREG-0161)

Exhibil I ·Same Souri:t

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~u. Date

78-4 780707

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F: Forc:cd · S: Scheduled

. (lJ/77)

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UNIT SHUTDOWNS AND FOWER REJ)UC:TIONS

RErORT MONTI I July 1978

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Reason: A·f:quipmenl Failure (Explain) 0-Mainlehancc or Tc:it C'-Rcfucling .

Licensee Even I

Rcpotl #

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. ().J{cgulatory Restriction . E-Opcralor Training & License Examination r-Ad111i II isl rat i·1c

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G·Ppcrational Error (Explain) ll·Othcr (Explain)

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c: u u GJ .... -0 0 'Cl

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Method: I-Manual 2-Manual Scra1n. 3-Aulunrnllc Scram. 4-0thcr (Explain)

ECS Pump Shutdown period~

DOCKET NO. UNIT NAME

DATE COMl'LETEO DY

TELEl llONE

Cause&. Cnrtcdlve ·Acllon lo

Prcvc111 Rccurrcm:e

50-:-281 Surry 2 8-1-78 -o. J. Co~tello (804) 357-3184

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Modifications. at

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the end of this report

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Exhibit G • lnstrudlons for Preparation of Oa13 .. Entry Sheets for Licensee. Event Report (lERl File (NUREG· 0161)

Exhibit I ·Same Snuri:t

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LOAD REDUCTIONS DUE TO ENVIRONMENTAL RESTRICTIONS

UNIT NO. 1 MONTH: JULY, 1978

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DATE Til1E HOURS LOAD 2 MW REDUCTIONS 2 MW MWH REASON I - '

(NONE DURIN G THIS REPORTING P!RIOD).

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I I I ' I

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. I

! I I t I I • I I I I

I I I

I

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MONTHLY TOTAL 0

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LOAD REDUCTIONS DUE TO ENVIRONMENTAL RESTRICTIONS

. UNIT NO. 2 MONTH: JULY, 1978

DATE Til1E HOURS LOAD 2 MW REDUCTIONS 2 H.W MWH REASON -

(~ONE DURING ' hHIS REPORTING PERI bD).

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--

MONTHLY TOTAL 0 ..

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-------·-- -··- -··---· .... -7-

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'. ··-·--·---'

JULi' 1978 ------ ···- ··-·- ··-.-------·-··----------·· ·-·- ------------·---

D~ET NO 50-280 UNIT SURRY : D_AT_E_.8_~1- - 7 8

COMPLETED BY 0 J COSTELLO

AVERAGE DAILY POWER LEVEL (NWE-llET)

AVERAGE DAILY POWER LEV~~

DAY

..

.J.

----------- - ····· - ·-··--···. -- ----- --- ----------·-------2

3

. Li

5

6

7

----- -~ '·8 _____ _

DAY ~/.J'iiE-1.'ET)

17 7 3 6. LI.

·------- ---18 736.2

19 733.9 ~------------'-- --

20 ·731.9

21 726.5

22 713.8

23 720.5

.. ·-:·

------··--···--··----- ----~---------------~~5 ________ 2_5 __________ 7_25.0 __ _

10 502. 8

11 702.0

12 ___ --------- ______ J_2)_. ~---

13 --:-------------------

.. lJ .J..

7 2 5. 7

26 721.1

27 7 2 5. 5

7.~-- 7 2 5~·~5 ___ _

29 724.9

30 723.0

.. -_____ .J. ~ . ------- ------- __ 7__3.lf .• _~ __________ 3_1 ___________ 7'-'2=-3~·-~-----·

16 734.9

DA:LY UNIT POWER LEVEL FORM INSTRUCTIONS ------ ------- -- - ------------------·---- ON TH:S FORM, LIST THE AVERAGE DAILY UNIT POWER LEVEL fN M~E-NET FOR EACH DAY ~··

·THE REPORTING MONTH. THESE FIGURES WILL BE USED TO PLOT A GRAPH FOR EACH REPOET____ :NG UONT b.'. NOTE TH AT BY . USING l.f AXIYU!L DEPENDABLE._ .CAPAC IT J_FOR_']' l::i E __ N E'f __ E LE_C T_RIC f..I.

EATING OF THE UNIT, THERE MAY BE OCCASIONS WHEN THE DAILY AVERAGE POWER EXCEEDS .1 THE 100 °/ 0 LINE (OR THE RESTRICTED POWER LEVEL LINE). IN SUCH C~SES, THE AVERJC3

____ .DAI LY - u HIT .. PO'rl ER ... OUTPUT __ 5_H E E_T__ s HOU LD __ B E_E_Q_OT_lLO_T__E;_ D_T.o_:__E__x_E_L_/) I {l__:_T lf_E__.AE.r.A.E.E i.''l' A.HQ,~~ JJ_,_~ I

----·--------·· ·-·-·-- - .. ·------- .. -·-----·----------- - ·----- -- ---.- -- ------------------ _., ____ _.-.._ __________ _

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I

. . -----· -·-·. .. -- . --·.:.:a.:.·-···----·----~-------------·----·

• - ·--··- _ -·- __ ·-· . -· __ -·--------______________________ DATE .. __ ~--:.1~ P _________ _ COMPLETED BY Q J COSTELLO

-- BLE..l~ -~l-.J.!..b'-'!' J:.Q.:./f.B L:;'fcL -----· _______________ _

- ~:OfTE: JULY 1978

AVERAGE DAILY POWER LEVEL. (J.f';/"E-NET)

·-----Avt:fiGE DAILY-POWER-LE°li~ DAY DAY (M~E-NET)

71+2.2 17

···---· -- --------- ---·------------------·'----,.., "'- 744. 0 ..;. 18

- ________________ 3 ------ -· ... ?.4 ~---~ - -----------~-9~--

u 737.0 20

·-- -- --------------·-- -------·---------------·--·-------s 7 3 3. 8 21

- -~ ------- ------------- _______ .. ? 1;3_,,_J .. __ _

7 18.2 23

. ---·-··-·--- -·------··~ __ ..:_ __ -· ---------------8 24

- -·------------ --- ---- ···-·---~ ----------------·----·---- ---- ____________ --1_~------- ----

10 26

11 27

12 28

13 29

- -------- -- ------------·~-ii-·-----------------

.L . 30

15 31 ----- - ·--- ----- ··-· ------ -- - - - -·- ---·- ---

16

. -- -----------------------------------------------.·

D~ILY URIT POWER LEVEL FORM INSTRUCTIONS -- ------····--· ------------------------

-- ON TE!S FORM, LIST THE AVERAGE DAILY UNIT POWER LEVEL IN M~E-NET FOR EACH DAY I~

"THE REPORTING MONTH. THESE FIGURES WILL BE USED TO PLOT A GRAPH FOR EACH REPORTING !-:'JNI'il. NOTE 'I'HJ.T BY USING. ~1AXIJ.1UJJ DEPENDABLE CAPACITY joR_ THE _.NET __ ELECT.RIC AL RATING OF TEE U~IT, THERE 0AY BE OCCASIORS WHEN THE DAILY AVERAGE POWER EXCEEDS THE 100 °/ 0 LINS (OR THE RESTRICTED PdWER LEVEL LINE). IN SUCH CASES. THE AVER~G~

- .. - .. Dh:::LY. .UNIT POw ER OUTPUT s ii EE1'_.SH OU LD __ BE __ F.OOJ'..NOTE_D_T_O_EXP..LAI_!L_X.li E ... AP..EARS..NT_AnO:'~ I I.,!

. - -"!"\f.~·~

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-9-y OF OPERATING EXPERIENCE

JULY, 1978

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

UNIT 1

July 1

July 2

July 4

July 5

July 6

July 8

July 9

This report begins with the unit in a cold shutdown ·Condition. Primary and secondary maintenance in progress.

At 2245 the turbine was placed on turning gear following major overhaul.

At 2230 the unit was >350°F for normal plant recovery.

At 1630 Rod Drop Testing (PT-7) was satisfactorily completed.

At 1025 the reactor was taken critical. At 1645 a turbine roll-up was completed for balance testing. The reactor power was reduced to lo-7 amps Intermediate Range and Lo Power Physics Testing begun.

At 0500 rod K-4 dropped from a blown fuse. At 1045 the rod was retrieved.

At 1200 Lo Power Physics Testing was completed and at 1330 the · .... generator was paralleled to the system and power increase begun.

July 11 - At 0518 the reactor power was at 98% running FQ maps. At 1815 the unit was at 100% power. For the next 3 days slight power changes (<1% power) were made as required by FQ surveillance monitoring.

July 23 - At 2000 a rampdown was commenced due to river temperature greater than 87°F. At 2102 the power was at 90% and the river temperature returned to within specification. At 2210 the unit was returned to 100%.

July 25 - At 1340 a rampdown was connnenced due to loss of required heat tracing OU a eves system boric acid line. At 1356 at 98.1% power the circuit was returned to normal and at 1405 the unit was returned to 100% power. At 1525 another rampdown was required due to a failure of required heat tracing circuit. At 1630 at 94% power the circuit was returned to service and the unit returned to 100% at 1730.

July 26 - At 1517 a rampdown was commenced due to river temperature greater than 87°F. At 1656 the power was at 92% and the river temperature returned to within specification. At 1805 the unit was returned to 100%.

July 31 - At 1940 a rampdown was connnenced due to river temperature greater than 87°F. At 2000 the power was at 98% and the river temperature returned to within specification. At 2015 the unit was returned to 100%. This report ends with the unit at 100% power.

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UNIT 2

July 1

July 6

July 7

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1-!MARY OF OPERATING EXPERIENCE e (CONTINUED)

This report begins with the unit at 100% power.

At 2100 a unit rampdown was begun for ECCS Pump Modification. At 2400 the unit was at 44%.

At 0400 the output breakers were opened and at 0405 the reactor was shutdown. At 1130 the unit was <350°/450 PSIG. At 1600 the unit was in a cold shutdown condition and primary maintenance began.

July 24 - At 1105 Filling and Venting Operations for the primary were commenced.

July 27 - At 0700 "C" RCP Motor would not start due to a ground in the motor. Plant cooldown was begun to replace the RCP motor.

July 30 - At 0833 the RCP motor was replaced and a unit recovery begun. At 2145 the unit was >350°F.

July 31 - At 0820 a plant cooldown was commenced to repair several problems. At 1243 the unit was <350°F. At 2252 the unit was taken >350°F after required repairs had been completed. This

_report ends with the plant heating up as part of a normal plant recovery.

-11-

AMENDMENTS TO FACILITY LICENSE OR TECHNICAL SPECIFICATIONS

JULY, '1978

The Nuclear Regulatory Commission issued an order June 23, 1978 which modifies Surry Unit No. 1 operating license. The order results from the NRC Staff's review of the .Steam Generator Repair Program. Of significance, the order limits 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 perform an inspection of the steam generators within six equivalent months of operation from the date of this Order. Nuclear Regulatory Commission approval shall be obtained before resuming power operation following this inspection, Equivalent operation is defined as operation with the reactor coolant at or above 350°F.

2. Leakage from the reactor coolant system to the secondary system through the steam generator tubes shall be limited to 0.3 gpm per steam generator, as described in the NRC Safety Evalaution of Hay 6, 1977. With any steam generator tube leakage greater than this limit the reactor shall be brought to the cold shutdown condition within 24 hours. Nuclear Regu- , latory Commission approval shall be obtained befor~ resuming reactor operation.

3. Reactor operation will be terminated if reactor coolant leakage which is attributable to two or more steam generator tubes occurs during a 20 day period. Nuclear Regulatory Commission approval shall be obtained before resuming reactor operation.

4. The concentration of radioiodine in the reactor coolant shall be limited to 1 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 May 6, 1977 Order and shall remain in effect for six equivalent months of operation from the date of this Order.

The Nuclear Regulatory Commission issued an order June 29, 1978 which modifies Surry Unit Nos. 1 and 2 operating license. The order results from the NRC Staff's review of the net positive suction head requirements of the containment recirculation spray pumps. Of significance, the order revises the maximum service water temperature limit previously specified in the January 10, 1978 order.

Maximum Service Water Temperature 87°F

Containment Temperature 100°F - 125°F

-12-

.AMENDMENTS TO ILITY LICENSE OR TECHNICAL SPF' ICATIONS (CDNTINUED)

Containment Air Partial Maximum Pressur:.e

}linimum Refueling Water Storage Tank Volume

Outside Recirculation Spray Pump Flowrate

9.2 PSI.A at 87°F service water temperature and 45°F RWST temperature. This value will vary in a manner similar to existing Technical Specification 3.8.

385,200 gallons

2250 gpm

The Nuclear Regulatory Commission issued Amendment Nos. 42 and 41 June 30, 1978 to the Operating License for the Surry Power Station. Unit Nos. 1 and 2, respectively. The changes are the result of our request to reload Surry 1 for cycle 5 operation. Of significance are the following changes:

1. Reduction of axial flux difference to a + 5% band.

2. Decrease of control rod insertion limits.

In addition, the NRC issued specific exemption from the requirements of 10 CFR 50.46(a)(l). The exemption results from our request and is related to the NRC's Staff review of Westinghouse LOCA Evalua~ tion Model. The exemption places the following requirements on the operation of Surry Unit No. 1:

(1)

(2)

Unit further authorization by the Commission, the Technical Specification limit for total nuclear peaking factor (FQ) for the facility shall be limited to 1.94.

~linimum accumulator water volume shall be decreased to 975 ft.3 as specified in the May 26, 1978 letter from VEPCO.

This exemption will be terminated by the Staff upon completion of its review of the evaluation .model used by the licensee.

-·~·~

~ FACILITY CHANGES REQUIRING • W NRC APPROVAL -

JULY, 1978

There were none during this reporting period.

FACILITY CHANGES THAT DID NOT REQUIRE NRC APPROVAL

JULY, 1978

Design Change Unit

1.

2.

DC-78-01 Replacement of Sample System Trip Valves Description - Operating parameters have disclosed that the initially installed valves (TV-SS-lOOA/B, 200A/B, 201A/B, 202A/B, 206A/B) were not effective and had a history of con~ tinual failure. New valves capable of operating within existing conditions:. have been installed.

Summary of Safety Evaluation

Since the replacement valves are virtually the same as those initially installed (except for having broader operating ranges) no accident analysis previously made has been altered less conservatively and the possibilities for different acci~

.-dents or malfunctions have not been created.

Conclusion

The margin for safety as defined in Technical Specifications has not been reduced.

DC-77-08 Overpressure Mitigating System Description - The containment instrument air system header to the power operated relief valves (PORV) were modified with the addition of a solenoid valve and a backup high pressure air supply in the line to each relief valve. Two existing RCS transmitters have been used to provide high pressure alarms and to control the PORV's. Two keylock switches were installed

2

2

in the main control board vertical section to permit administrative control of the system at the appropriate point during cooldown or heattip.

Summary of Safety Evaluation

No margin of safety defined in the basis for any Technical Specification has been reduced, no potential accid·ent or malfunction different from those previously evaluated have been created, and no consequences of accidents previously postulated have been increased in magnitude.

Conclusion

This design change neither constitutes an unreviewed safety question nor alters the basis of any Technical Specification.

. , -.

-14-¢.sTs AND EXPERIMENTS REQUIRING. • NRC APPROVAL.

JULY, 1978

There were none during t'his reporting period.

TESTS M'D EXPERIMENTS THAT DID NOT REQUIRE NRG APPROVAL

JULY, 1978


_····~r

-15-CHANGES, TESTS AND EXPERIMENT

JULY, 1978


··~F~~ -·<

'·

~-I . .

PRIMA.RY COOLANT ANALYSIS

Gross Radioact., µCi/ml

Suspended Solids, ppm

Gross Tritium, µCi/ml

Iodine-131, µCi/ml

I-131/I-133

Hydrogen, cc/kg

Lithium, ppm

Boron-10, ppm +

Oxygen-16, ppm

Chloride, ppm

pH @ 25°C

-16-

• SURRY POWER STATION

CHEHISTRY REPORT

JULY , 19~

T.S.6.6.A.ll

UNIT NO. 1

MAXIMUM MINIMUM AVERAGE

3.61E-l 3.32E-3 178E-l

0.4 o.o 0.1

1. 06E-l 4.14E-2 6.94E-2

2. 72E-3 2.98E-4 1. 63E-3

0.1878 0.0838 0.1294

42.2 20.6 33.5

2.00 0.10* 1.15

451.2 158.4 226.2**

0.000 0.000 0.000

0.07 0.05 0.05

7.02 4.68 6.20

+ Boron-10 Total Boron x 0.196

NON-RADIOACTIVE CHEMICAL RELEASES, POUNDS

T.S. 4.13.A.8

Phosphate o.o Boron

Sulfate 1112 Chromate

50% NaOH HOO Chlorine

Remarks: * Unit at cold shutdown.

UNIT NO.

MAXIMUM MINIMUM

2.21E-l 4.32E-3

2.0 0.1

1. 39E-l 3.47E-2

5.24E-4 . 2. 32E-4

o. 1174 0.0502

37.5 0.0*

2.00 0.30

459.2 67.0

2.500 0.000

0.09 0.05

6.88 5.78

957

0.01

0.0

*,~ Ave. does not include boron values run during physics testing.

2 I I

AVERAGE ;

!

8.68E-2 I 0.2 !

I

8.45E-2 I I

4.02E-4 I 0.0973 I

; I t

4.1 ! I

.I

I 1.26 I t

303.2 I 0.267

I

I

0.05

6.19

')

• -17..:- 9 DESCRIPTION OF ALL INSTANC_ES WHERE -

THERMAL DISCHARGE LIHITS WERE EXCEEDED

JULY, 1978

On 07/09/78 Unit 1 was returned to service resulting in,a change in river temperature greater than 3°F/hr. during the initial loading. There were no reported instances of significant adverse environmental impact.

-:18-

• FUEL HANDLING

JULY, 1978

On 07/11/78 an audit was conducted of the fuel assembly physical inventory of the new and spent fuel storage areas. This annual inventory was conducted in accordance with Administrative Procedure No. 32. No discrepancies were discovered during the performance of the physical inventory. No other fuel handling was done during this month.

-··---~r I

' -----' I -19-

1 UNIT II . " I • FUEL HANDLING e ... ,

197S -JULY, -' --

,DN:E ' NO OF ANS.I NO. NEW OR SPE~iT FUEL ' .. s~:??ED/RECEIVED ASSEMBLIES PER SHIPMENT INITIAL ENRICHHENT SHIPPING CASK ACTIVITY.I..::

- 1· I ..

' I -·

(NONE DURING TH ~ REPtlRTING PERIOD). ~ I ' I -

I I I ..

- I - -

-

I -··

-- I ! -.

I L I -·-

I -·

_.

' .,

-· --'

--

--·

I -----

I ---· ''°--·- I ' _ ... \

--~~·~

D.!.TE I r;o OF ' I •

SHI??.~J / RE.C EIV"E-D I ASSE.MBLlES PER .

'

(NONE

I

' r ! I I -

.

- --- -

' -::zu.:... UNIT 11 2

FUEL H.AlmL DiG JULY, 1978

A:.'\iSI

• HO.

SHIPt1ENT. INITIAL ENRI CillfENT

I

DURING THIS REPORING PERIOD).

I

I - -

-·

'T'r'"TT d.t:..W OR S?:::~iT FUEL

SHIPPING CASK AC'l"IVITY L::.:---.-

···-

I --

--_,

--

I I

~-

I ..

I ,....~--

-·-

--·····

I

---

---

I --

-···

I --

I ...... -w.·~

-- r -- -

No. --· Unit

OP-1.1 2

OP-1. 2 2

OP-3.3 2

OP-3.4 2

PR-URE REVISIONS THAT CHANGED THE oP4JrnG MODE DESCRIBED IN THE FSA!

JULY, 1978

Title

Unit Startup Operation (CSD to 230°F)

Unit Startup Operation (230°F to 350/450)

Unit Shutdown Operation 350/450 to CSD)

Unit Shutdown Operation (Solid Plant Operation)

Change

Update to reflect installation of Overpressure Mitigating System




Note: Refer to Safety Analysis for Design Change 77-08.

-·..--~'t'";'"'

1

-22-

DESCR~ION OF PERIODIC TESTS WHICH WE~NOT COMPLETED WITHIN THE TIME LIMITS

SPECIFIED IN TECHNICAL SPECIFICATIONS

JULY, 1978


-23-INSERVI CE INSPECTION

JULY, 1978

~isual inspections were performed on the s'ensitized piping, Unit ifl, during PT-11 and PT-18.5. No reportable indications were follild in this inspection.

An eddy current, gaging inspection was performed in Unit /12 A,B and C Steam Generators. Testing was done in accordance with .VEPCO procedure NDT-14.1. The eddy current inspection was performed at 100 KHZ and 400 KHZ using .650, .610 and .540 probes. The number of tubes recommended by Westinghouse to be plugged per gaging criteria are:

A S/G B S/G C S/G

36 21 17

Tube plugging was completed July 28, 1978. No reportable indications were detected as a result of this inspection.

Df,' IT= f//JT

li'E1'SF,ft'V vr SYS COMP

07/22/78 RC SG 07 /'J.U/7~ RC SG 07 f2q /78 RC SG

IJF.l'T TOT II[,

..

y ...

m!TT 2-JUf,Y 1'l7~

lNlliNTt:NllNCr: OF :Jllff':TY llEf,/ITf:/J SYSTEMS DU!iING OIJT/IGE: Ofi mmucr~·u /'01~/\R l't::liJOIJ:;)

NllRKNO SUUM/IRY

2-r.c-r::-2c /i:/JDY CUliRC:NT+R[\'l'll[I? !IS Nli'Cl·:ss 2-RC-E-2/i ' f,'/)/JY curmrmr+RF.l'llTR AS Nr:cF:SSllRY 2-m;-11-211 IW/JY CUR/i'/\°N7'+RflPllrn /IS NECc'SS

WKl'li'liF

EDDY CUR//t::NT PWGE/J+CWSIW OUT E1' ·rr.srt:TJ 11/VTJ l'WGGl::O 1'U/Jf\'S li'T TUllli'S ANIJ E'fJJGr;gu !IS fjf·:Qu.rnw

u /.fR

2 ao1os1s2q 2 1!07051522 2 ~07051523

TOTIN NT/.!

302 35!i 337

'!95

I

"" J:'-1

-25- . RE.erABLE OCCURRENCES PERTAINING T.

ANY OUTAGE OR POWER REDUCTIONS

JULY, .1978


··~·"'". __ t_"

-26-

'

Maintenance of Safety Related Systems During Outage or Reduced Power Periods

UNIT 1/1

Mechanical Maintenance

11 .. - v1;·p r=.~1.•:c" .. ,

U/117' 1-JULY 1970 • {!.fA T/11'1!.'NArtCe m· SAFr:1'Y 11/o:LA'l'f.:V SYS1'/.;MS VUllTNG OUTAGli 011 Ji&IJUa:v l'lMt:.'11 n;urovs>

J.'li1'S/o.:tcV D'I SYS COi'll' M11111!NO SUftl.'IAUY J{K/'11/i'F u NI/ 1'0'ft:MN1'11

07 /01 /7J!. I/SS SNUIJ/Jl!.'H Wfl'IHISS-1 NO /o:l-'11 Se'Af, IN flF:Sll/IVOfR VI/ VAf,Vl:.' UL 111-:l-'LACb'V S/IUUUB'US 1 B0525130q 13

07 /0l/7P. I/SS SllU!JUl!.'I/ 1 ~f1/H/5'S-12 Ll!.'AKr:t.'·-FWTV l.01{ (A1' ACC/'.'l'l'AfJUS LTMl A/}f)/.;/J fWTD NO Lli'JIKS N01'/W 1 805251309 1q

07/01/7J!. Cl/ HOV NOV-1'275U M01'0f( V/WIIfJG OVl!.'HWAD JNSl'f:l'1'1~·u VALVc' 1 805300000 37

07 /0l /7'13 HSS 51/UIJIJl;;Jl 8T-'1£i Rf.'MOV~: ANIJ INl'/.;CT SNUIJU/.;U w rm1m+ s1.;'l'• /!lil NS'/' ALL/'.'/) SNUUfJJ::){ 1 IJOb:.!'l'n•tS u.o 07/01/713 liC VAI.V1'.: 1-CV 1556(] !'AC/l.lrlli [,!;'AK AVJIJS1'c'IJ l'ACKING 1 P.Ofi.l00531 I)

07 /Ol./7ll !/SS SNU/llJF:R 1 ·/IC-l/.','S-101 l<f<:Slll1'VOTH MOIJN1'1'/J ON ST/JI\ NO SUl'Oli'T SW A/-'/'B'/) llN/Jli• lll>l'OST1' IUNf;IJ V 1'1'11' UllACK 1. UOSl.513011 22 07 /0'2/7ll I/SS S.VIJUU~ll 1-ST-F/SS-20 [,/:'AK A'/' '/'IJl/11'11/l S~Al.•NO'f U/UiASE/J RliCI!.' Mi/JUT/."/' ST-'20 I{ f1'1/ f,'P MA'l'f:llI Af, 1 (105251314 154

07 /0"2/70 u:;s S//UIJUeH I/SS 111-.'SEl<VOJ h' N01' SU l'L'0/11'1!.'IJ UY Uf!ACK!:.'1' /it:l'OSI1'JONIW SNIJ/JJJbR C0/1'Hl~CTr..Y 1 ~or,2•11 11 1 15 22

07 /Oj/78 118 fVN/' 1·-RS-I'-lA l:'l.Jl.L PiJ/.Jf' mu JNlil'/.;C'l'TON CU.'111/B'/J f'Uf.tf'+R8Nr.'W/i'D WO/It/ 1-'AUTS 1 805110 1J45 127fi

07/0:J/7~ I/SS SN/JliUflR llfl:'V-/ISS-4 NO !:.PH Sl·.'11 L IN f..'b'Sll'/!VOTll OR VA/,V/;' BL VOTIJ 1 ll05'2!il'.l00 0 ) 07 /03/78 I/SS SNUUIJc'R !/J:'l'V-11ss-a NO E.'l'l? Sf<:A L rn m:sr:11vorn OR VALVI> ni VOTIJ 1 t105'l51301 0

011o:i;n HSS Si'IUl!Ut:R Wfl'U·/ISS-9 NO Eif'R St;A[, TN Rt.'Sl;'fi'VOlll OR VALVE BL voro 1 005251302 0 e {17/03/711 I/SS SNUUBl::ll WFL'V-llSS-15 NO erR S/o.'AL lN /1HS@VOill OR VALV/<: BL vorv 1 805251303 0

07 /03/7l\ I/SS SNU/i/31!,'/I 1-S//P-l/SS-38 OTL U.'VffL /JliWW SUl'l:'/,Y DTNI!.' llEWCATt;D RESERVOIR 1 805251305 qa

07 /03 /78 HSS S/IUUIJeH 1-SIJP-IJSS-58 RF:Se'/,'VOrF/+VALVf.: BLOCK NOT SUI'/'0111'&'/J W/;'[./)l'V ugst:llVOrR-VLV BLK SUPl'ORT 1 805'.l51J0ti 57

07 /03/?fJ I/SS SNUU/lef! WFl'/J-//SS-16 l:'U /,/,Y COf.Jl'liESSf.'V INS'I'ALLIW S/IOUTF:U /IOV Em 1 805251307 57

07/03/78 //SS SllU/if3t:R 1 ··SI-//SS-25 NO'/' GR/iASW Rt:C8N1'LY ·S//M'1' VTR1'Y VOTO 1 005251311 0

07 /03/713 ·uss SNUU/Jell 1-SI-//SS-26 N01' GRb'11SIW llli'C£N1'J,Y--S/JA/o'1' /JIR'I'Y vorv 1 B05'.l51313 0

.07/03/78 //SS SNU/3Ur:R VAFITOUS l''/,R SNIJU/Jb'RS-Af,L f,/~11/J+Sl/Af1'S VIllTY 1'T!il/Tl:.'NSIJ PACKING /WT 1 805'151315 57 )

07 /0'.l/70 Cl/ PUl·IP 1-Cl/-P-2A Wi':Hf.fAf, OVEHWAD TN PAST SE'l:.'E/J Rli'Pf,ACt:/J PUMP 1 006261530 q I N

07 /O'.J/7P. iiS l'J I'! NG Sll-RS·-38 /.ITSA/,TGNt:U •OV l!.'llW11Dl:.'/J STUATGl/T8NED SP/IING //AIJGSR 1 80li27141fi 2'' "-!

07 /0.l /711 Cl/ l'U/.11-' 1-Ci/·- ... -2A l'Ul-1/-' NOLSY+l-Cll-P-W Sl!:AL Ll!.'AKTNG l!b'PE,ACSV PU/.JP 1 {106300 1115 9 I

07/05/711 /i'S l'!l'IilG 1-US-11 INSTALf,+/i/','/.JOVE fU;flS /:'OJ! PT lfi.4 IN::i1'Af,L-/IEMOVE l"/,A,VG/!.'S 1 802171055 102'1

07 /05/7B cs PIPTNG 1·-CS·-13 INS1'ALL+ftb'/./OV/i' Sl'EC FUlN FOR l'f16. q I NS'l'Af,LW-f1't::'of0~' t:D f'LAl/GF:S 1 002171106 10'2'l l.J7/0S/7P. Cli l'l l'UJ(i 1-CS-'24 INS'/'11 [,/, + /,'J,'f10V E Sl'J;C f'f,A//Gl!.'!J fO[{ l-"f 1 1 NS'l'ALLl!.'V+Hli'NOV B/J f'l,ANGl!.'S 1 002171107 102')

07 /0S/7~ us IVl·ll' 1-/IS-1'··28 h'/-:NOVf: l'IJl·ll' f'OR Sl/Jllo"I' M'l-'AIH l'Uf.11' /U·.'PAIU COMl'Lf."1'1!.'U 1 B051515'.J8 120U

07 /05/78 I/SS Sl/U IJ/JBf! fo'UIJC'I' u:sr 10 SNU/l!Jb'f!S CQ.11l'J,f.'1'B'V t'llNC'/'IO//Af, 7'11'S7' 1 80£;031000 7G'.l

07 /OS/7fl Cl/ l'U/oll' 1-Cl/·-P-28 /JlSC!IAli'Gli' fLANfiE f,t:/lh.INri 11!:.'PE,AC/:,'{) f'l,ANGl' ' 1 eOfi'2'J'lj 110 1:l5 07 /0S/?ll /JS 11111'(,'IJ Cl,/i'.1N l'ATN'f OFF VRTNri AlllJS/;'A1' ING CU'llNED 0 IWIGS-111.;t'LACE:D 2'WO 0 RINGS 1 J!.07010 1145 107

07 /05/70 BS l/1ITCll Ti{() OLAl/KlW FLANGt:s II.WI:: Alli u:AKS f1!':LACt:V GASKf..'l'S 1 001010'!'16 107

07/US/?B HS llM'Cl/ IN!lt'd /JOO/I l{INVOW Of/ l'ERSONN!:.'L l/llTC/J m:l!LACW GASK1'.''f 1 B07010'.l117 107

07/05/78 !JS llA1'Cll f.'1iVILIZltiG VA/,VB' 11ANV£,l:.' SI/AF-I' 111'.'l'LACt::v 0 RTNGS 1 80701 o)'Jlt u 107

07 /05/?ll [)5 llATCtl Rt-:l'A [// ATH W.1KS COl-ll'U.'1'80 UNUl'/I llNO'fl/SR /.IU 1 807030005 61 • 07/0S/7B 1C TT/.J/IL!:.' U-1 Lr::AKLNU A1' S8AL 'l'A/IW 7'IGl/1'E/lt:U f'I1'1'ING 1 807031150 56

u7 /0S/70 Ft'C VALVE 1-RC-~5 PACKTNG Lf.'AK TIGIJ'/'/;'N AVJUsnv l'ACKJNG 1 8070'.Jl'.lOO 5b

07 /05/711 liL' VA/,V/;' u:V-1%0A SNA LL 130/JY 1'0 fJOllNl!.'1' LEAK Tiri/11'1','NTW CWSU/iB S7'U/JS 1 807031205 fi3

07 /05/7B Cl/ l'U/.IP 1--Cll-P-211 ALTGN l'Ul·ll' AllU ftf01'0R [(f;ALrGNf;V /:'U/.11' TO MO'I'Oll 1 0010111000 2'1

07 /05/711 Cl/ VALV!:.' 1-Cl/-04 f<f;'Pf,/l(,'/i,' {)[ Al'lll!/IGM R6'1'l,llCl!.'JJ IJI Ai'llllAGl.f 1 B0'70510UO 3

07/05/78 Cl/ VAi.VF: · 1-C//-365 JJI,ANK Fl.ANG~: NTSSING INS'l'Al,Lf':D DLAllK 1 l\07052100 2

07/0fi/7B cc /IX 1-CC-S-lA Cf.t.'AN Ii;./ SWI!.' CLl'.'MIW Sf{ SIU/:: 1 80(i'.l51'l:!•t 1 07 /Oti/70 cc /IX l·CC f:-i.IJ CLf.'/IN SW STDI!: Cf,/l'llNIW S1/ STDE 1 801i'.l51 q·15 1

07 /Qt;/7ll F:f: COi-1/'R/ISS 1 Hf;'l'ATN m:iu:1-· N0.1 AC " LAPl'c'/J 11/J SPAC6'/l+REPLAC!:.'U VADV/<: 1 801i:?Ul130 03

07 /(Jti/711 MS VA/,Vl:.' 1·-,l/S-18 LEAK ON Si/AGWCK Fr1'1'[NG UJ:.'l' Ar 11/W J:'l1'1' T NG-S'l'OPl'l!.'U LEAK 1 807050750 10

01101;/n I/SS SNU/JUER 1- /11/-1/SS-10 All! [N m~·st:UVOTll-VAf,Vg IJLOCK COtlNEC1' HtPLACf,'/J SNUUlif,'f{ 1 B070h1115 'l

I;~ I•

,j

-28-

Uaintenance of Safety Related Systems .During Outage or Reduced Power Periods

UNIT 112

Mechanical Maintenance

m;vr=m:cll

UNIT 2-J~r,y 1978 ,•

(MliTNTl::NllNCF, OP SM'F.TY R/\[,/i'/'F:D SYS1'1•:,1rs !JU/UNG OUT/iU/{ Oii Ht:IJ/Jl'l::!J l'OWlm Pl':fi'TODS)

RE'!SERVDT SYS COMP MARl<NO SUNNAHY WKPt:IW u f.IH TOTWNTN

07 /10/7?. RC SG 2-RC-f:-28 TNsn:c·r r. IN. 1/AN!Jl!OC,F:S COf.IPU;TIW. 2 !10705151? 7 07 /11 /7.f1 !Ill f'UU!' R,\f-25q vm:s r/OT i'UMl'-T!ITPS Otl OVERWATJ !IF.l'l.ACf:IJ 1Jf:l,T-M1'R WTlllW WRONG 2 l!070fi1001 l3 IJ7/12/7f1 R/./ l'IJl·IP ll:'l-25q vo1~·s NOT Wf.11' NO l'llODU\N PO/JN/J 2 ll07111U2Q 1 07 /13/78 CV VAC.VE 2-CV-1 LSAKS TJ/l/IJ VOT/J 2 f1%120711Q 0 07 /1.) /7 f1 STJ VAT.Vi\ l..CV-SIJ·-2008 UO/IY TO /JON.Vl•,'1' Wiii( vorn 2 fJor.2211n 0 07 /1'•/70 RC VALVf; ?.·-li'C-1?. l'//r.KTNG [,f,'//K li't.'l'ACKIW V Af,V!·: 2 ltor;osoooo 11

07/1"/7R. Clf VM,VS 1-Cll-911 llE.'Pf,AC!\ DON!lli'T Ul·:Pr,AC!;'/J /lOf/Nfi"T /. B070'l13:15 2 07 /1 1• /7 f1 cs VA/,Vt: 2-CS-57 SrnllN U.'111( VOTIJ 2 u0111oi;11 0 07/15/713 SV 1!ll'TNtJ /,C-SV-201D S'J'N f,EAJ< Ul'lWll f[,A/IGE li'f\'l'11i:JllW f'l.llliGP, [,f:AK 2 (10703115 q

07 /15/7~ Sll PTPWG u:-su-2ooc S'J'l.1 U.'AK Wi,JJ•:!i.' fl,llf/Ut: r.l'.·r11rmw n,11Nr;r; /,fW( 2 8070311f. q

07 /15/7f3 CH VAT,V E 1'V-?.88QA /ilJ,JUS1' PACl<.TNG OR m:PACK AS NECESSAR AfJ-JUST/iU PACKINU 2 l.lOf•Of>0'.121 3

07 /15/78 Clf v A!,VF: 2·C//-27~ m:f'ACK·· 11' Lli'AKS A/J.JIJS'l't,/J f'ACKING 2 t1or;oo1sn 3 07 /15/71.l Cl! VllLVE 2·-C//-20 l.l VAf,VE /JffflCUT.i' 1'0 OPF,'RATE lil','l'LllCE:U IJONNfiT 2 ~07011521 3

07/15/7!! Cl/ VAT.VP, 2-Clf-210 BOVY TO /l(}NflllT G/JSKW/' UiAK tiGll'l'b'Nrm cwsur.w rJoc,rs 2 1.107011522 3 07 /15/70 cs l'Il'ING i-cs-211 INSTAU,/fir.'.'IOVI~· ff,11//GfiS INS1'A/,UW fl,11NG8S FOR VALVt: 1'F.S'f 2 ll0701;13011 122 07/l5/7f1 cs VAC,Vt: 2-CS-57 U.'/JKS '1'1/f\OIJGI/ INSTllDUW Nii:; V/l[,VE 2 l•070'l'.l3:H (I~

07/15/7f1 C'" ~· :-wv NOV-CS-201C INS/'fl'(,"T-m:l'AT.ll AS Nt:Cl:.'SSARY ... VlSASSfiNIJ/./•.'/J VAf,Vf;'+CLEANEV 2 ~07100 1)115 qe 07 /15/713 cs l/OV NOV-CS-201D INSl'l!:CT-fi'!\'l'AlR AS m;ct:SS/JliY DTSllSSf;'Nl!LIW+CU:ANED 2 807100'!46 98 I 07/1P./7e ,.~ FU/IP 2-ST-l!-18 OVW!f'1/J£ + lNSl' I-VI.fl' INSP5CTW PUN!! S/11' 2 £107051512 210 ·N ,;~

07 /1?/7 ~ !IC SG 2-r.c-t:-1A ANN/JtJJS NEAS/JR[','NP.N1' ·· 1'00K ANNUWS /.Jf:l1SIJ11f."Mf:.'N1' 2 fJ0712111•0 1..)2 '° ·I 07 /l 9/71.l Cl/ VAf,Vf;' 2-C/I 305 m;Pl!CK-l'ACKING rs Uf!lPPifiG /lU,/IJSTEIJ N1CJ<TNG 2 ll0fl0fi05:l2 q

07/1q{78 USS Sl/U/Jf3ER 2-Sl-f!SS-25 Rfo:iiU T W lolT1'1/ EP NAl'EfiI AL mmun1· r-111·u El' NllTr:tt'IAL 2 !107111-)0'.l 170 07/20/7~ SD v111,ve 2-SIJ-5lfi BOUY 7'0 /JOfif/lff L811K fJllN VC,V BY·LCV-S Nl\f'Aifif,'I) fJOUY /J(}Ng·r UiAK 2 !l01il11Q101 lfill 07/21/7(l TIS PUMP 2-l/S-P-211 ov;;:m111ur, + I/IS/' PU/.11' l'Wll' OV!'.'Rl/llU[,F,:J 2 007051510 3111,

07 /2?./713 /IC sr; 2-/i'C-c-2C fll·."NOVt:/ TNSTAf,f, l'lllM /.Ill Ni./ MS m·:,110VW+fi'P.IN.'i1'M,/£D f.!Ar'JWMS 2 l!-07051517 2% 07 /2:1/7P. /IC VA!,Vf: PCV-24550 U:AKS Tl/Tt/J·-DTSCONNECTHD l//flJIJTf;/' VADV!•.' 2 f.1011100935 127 07 /'2:t/70 !IC SG 2-ur.-r1·-w !IF,!·!OV P. / WS1'Af,f, P!ITN NANlv AYS !11'.'!IOV IW/ R/1· 1 NS'f'Af,UW 1111/M 11YS 2 (l07051515 357

01/n/78 /!SS SNIJ/JlJER 'J.-51/£'-/ISS-10 NO El' .'il\'Af, /.fllTt::liT Af, 10 lN. m:;uuTJ;I' SNU/l/J{;"I/ rn'l'I/ [','/l MllTC!ITAC, 2 ll071ll1010 11:.1 07 /'23/71!- I/SS Sl/UlJf3/o:R 2-Slfl'--l!SS-1?. NO ,.,.,, SP.Al. Mll'l'l!:Rr Ar, llTN •. !llWUT/,'/' SN//ll/Jl-:ll llT'rl/ P.l' MA1'1'.'lilA/, 2 8071£11015 55 07/2"/70 RS l'IJ/oll' 2-flS-l'-?.U OV/o:/i'/111/J[, + I N~W f'IJ/.lf' 1'111·11' OV/iJ!lllAIJT.W ANIJ TNSl'/•:C'l'W 2 !•070!il511 010

07/2"/7P. li'C SG 2-fiC··l;"-/.A R/'.'NOVl'.'/TNS'/'J1l,f, Pf/TM MAWAYS C0/1£'/E'/'t:IJ TllS'f 11[.[,[NG MANi./ AY S 2 001os1s1r; 35g e 07 /'21J /79 Cl/ V Af,Vf. u:v-20 r.011 l'llCKTNll /,P,/i/(-11/MIJST A/J.J1J:;r1-:v l'llCKTNG 2 l-!07'.llllq35 5 07/2q17p. li'C VA!,V!;' FCV-:1'155/1 BOUY 'l'O fJONNl•,'1' [,f,'llK lJO/JY TO /jONNr.'/' IJ0[,1'5 TTGl/TEN~:v 2 ll07211151fi 7 07/25/7P. SI V A!,VP, f/CV-2f.l5:1c l'liCKJNG WAK A/J,JUS1't!J l'ACKT.VG 2' (10711.122:11 11 07/25/7P. s~ .. I' Af,Vt: 2-s1-1as PACK!N!i [,EllK AlJ.l E'ACKI/l!J 2 1107182/.J<J 11 07 /25/7P. ST V ///,Vt: l/CV-'28538 l'ACK ING T.l'.'Al( A/J,J l'llCKING 2 !1071ll22110 11 07/25/78 !Iii NOV NOV 2700 f1'l\l'ACK //f,'£'/iCKli/J V llDVI': 2 P.0721! 10.30 s 07 /21i/7P. RC l'IJ/.ll' 2-/i'C-l'-18 RF,PAJll SP.A/,S f!l;'l'f,11CP:D Sli"ll/,S ?. 007051513 304 07 /'2fi/7P. R" ,, PJl'PIG r.'S-S/f-n I/.11'/IOl'f;fif,Y SI'S' SPRING //lil!GE!I INS1'f11,[,W Sl'li'TNG llA/'!Gl;'/1' flOV+Sf\1' 2 !107111:117 3 07 /21;17p Iii co•1n12:ss 2-lA-C-2A llfl/JIJ l UJ CONl'lll::SS0/1 u1-:nu r ur lll!:11u+ 1'rs·1·0N 2 !107120717 350 07 /";.r./7!1 IA co:-:1 ·11r\·8s '2-Tk-C·-28 111wu r w co11P1i1·:ssou Ur.'lJl/ll/l' llf·:111J+I' TS 'l'O N 2 ll071'2071P 350 07 /'J.r;{7~ sr VA/,VE 2.-ST-113 l'llCI< rm; f,fo.'AK llVJ /'/1(.'KTNG 2 oo71~n::1l:l 15

07/2G/71.l RS IJllTCll RP.l'Arn !Nl/fo,'1/ DOOR f>/.f/',"/iG I/ATC// !ll;'W/lf:U Ofi'JNGS+l<f'.'l'/,/iCfiU GASl<fo."'/'S 2 ~07:l5lll 'l5 B

07 /27 /7~ RS l'Tl'tNG llS·-S/1-511 INIHOl'l·.'li/,Y SI•:'/' Sl'llT.NG ll11NUfm A/i.J/JS'f'l:'IJ //l!NUl\°11 1'0 2:1:.10 2 !•01111ns 11t

07 /27 /7£1 us l'Tl'I//,'; llS-Slf·-ftO I/.fl'/10/'f.'/lf,Y .'i/iT Sl'fllNU 11/ING/\R A/JJIJS'l'fW l/llN!ll\'/i TO ti50 2 ~07111.llfi 24 (.... 07 /27 /78 /IS l'lriNt; 1,·s-su-q11 lMI'hOl'l•,'/if,Y Sl1"1' SCfrT Nr; /IAf/ril·.'11 AIJ,JIJ,)T/<,'U l/llNr;f,H TO l''l5 '2 ~07111:.t~ 24

07 /27 /7!1 NS l'Tl'TNG llS-Slf-'Jli If.l/'ii'Ol'l::JnY sr-:T Sl'llT,vr; !/llNUf:ll 11/J.JU:i'l'W llANGMI 1'0 n'l7 2 l107111Jl'l 211

11 " fl

Df'.1'T=m:c11

Hf."l'Ser.v /J'f SYS CON!'

07 /27 /7~ RS l'UMl' 011-n 11.0 [l,'j ~WIP

07 /'27 /7f'. i/SS Sf/U /J/Jflfl 07 /27/7f'. I/SS 511/JIJB&R 07 /27 /7!1 //:JS SNUTJ/l&R 07 /27 /?ll //SS Sll/J/J/Jm 07 /1.7 /'I~ RC I' A/,VS ()1 /'l.P/7? as TENTS 07 /30/7f'. liS I/ATC/I 07 /:l(J/7!1 as I/ATC/I 07 /31/7? li'C l'NPflTR 07 /31 /7? SI T'U/f P 07 /31/7!1 RC VALVS

DffT TOTAL

.; •"ii .. l ;~

·y.··

UNT'I' 2-,JU.J,Y 1 'l7ll (MATNTENANCF. Of' SAF!';'/'Y /ll•.'[,A'/'8/J SYSTP.'l·/S /J/JUJNG OUTAl;F, 011 RIWUCf.'/J /'OWl-:rl l'F.'/l'TO/JS)

MA/lliNO S/Jf.:/o!Ali'.Y Wlf.P/•,'/W

2-RS-P ·1/J 81111 ORTNG ON Rf:GU[,A7'0R 1{ATf.R rllAP /1F:/'[,ACIW <JriTNG llfmtJ(,1' SCfi'F.~.'NS TN f;'/,llCf: TTGll'rf.'Nff/J fJ()f,1'S Of/ SCHl·,'/iNS

2-Sl/P-l/SS-1 NO f.l' Sf;'tlf, Mll'n'J.'Illf, IJTN. lif.'PLllC/~.'/) WI1'1/ /1'P/I mmurr;r ONS

2-SllP -/ISS-P NO l'l' St.'llL !.JA'l't:RI /il, El TN. RF.l'f,ACTW lff/'// fl/-'// fllWIJIL1'-0f/S

2-Sf/l'-llSS-9 NO fll·' SF.AL NllTr::RI AL 10IN, WW/JILT Sfl//Ulll'ft' WIT/I fll'R f.IA'rt:RIAL

2-l/SS-170 Rl!.'1'11 TH S.VU /lflf.11 /if,'l'/IIr!f.'D SA'/J/Jf!r::R

1'CV21• SSA /!OTJY ·ro UO!INf.1' 1,SllK /it:PAU1'fo.'fJ /JO/JY TO RO.V/lr,'1' T,l\AK INS1'11[,[,/R/\'l•JOVS SG TEN7'S INS1'ALC,f,'IJ/ l//;'NOl'IW fjG Tl~N'l'S

Of'l?N+/IP.CWSP. t::C.JUTl'/.lfiN1' llA1'CI/ 01'/\'NfW llNIX:WSf.IJ //A1'C//

/IF:PATR f,'/.ft:fi'G I/ATC// WC/I. Nr1'C/IANTSM CUO:AN/•.'/J t l1'l\G/1'EAS/m 0 RINGS

2-RC-P-1C DISCON Nl\CT I m;corJNECT c l'LING+l'I PI NG . m:NOV6U+Rl•,'l'[.t1CEV fi'CP /.!01'0R

2-ST-P-1B Sfl/lf, LP.AK BAU ON B ff.IMP SE'A£ LF;M<. m;PAil/lW

2-/i'C-13B PACKTNG Ll\1111. /i'fll'ACll.F:/J VAT,VJ-:+RF.PLACl::V GT,/IND STUDS

11 Mil

2 ll071:l.O!il 'I 2 007170lll5 2 l!IJ71!l10lfi 2 {1071lt1017 2 l1071lll010 2 0012120113 2 P0721123j0 2 ll0705151 If 2 ll0727105ll 2 ll07J012'25 2 l\07271025 2 f!07j01525 2 807310150

7'01' /}.{ !tl'f.!

3<J:l. '.J<Jlf

1011 1011 1oq 130

111 528

1'.J. 3

75 2'.l 10

fill30

·"

I l.J

?

-31-


UNIT Ill

Electrical Maintenance

Dr:T-T=f.U'C

• -

!I Uf/T'/' l··JULY l<J70

(NAIN1'F.NANCES OF SAFf:''l'Y rrr.;f,A'l'TW SY51'f:'MS" DUUiNG OU1'AGt: OR RP./JUC~:1j f'(J:.l/·:u l'/\li[(JTJS)

RF·:TSF.TiV rrr SYS CO.'IP MAl1'KNO SU/.IMAl?Y Wlll'/~'/1'F u f.tR 1'01'WN1'"1

07 /01/7ll RI/ l'.'•W trI'fl 1··W/-P··1A INS!:' Mr.'l\+Cl/Ar/Gf. OTL j COM/>C.f:1't:IJ f.NP-P··W-2£1 1 BOU1!10e23 3f.5 07/02/7P. Cl/ TIT 1-Cl/·P 2lJ W TiSMl' PAl/T:,'[, ~ Cl<.'/' 2fi vom 1 £l0ri220<Jll7 0 07 /02/7B GW flfl"CQrtn 1A DO/IS N07' CON7'1/0[, l'fiOP/-:Uf,Y TNS'l'Af,[,!W Nt:W SC/i' CON'!' CA[, TeST SA'l' 1 P.01;2r.1us!1 101l 07 /02/7!1 RC P7.R !IT/i W!r Kio/ 11/JJ AND 'l'f:'liTt:D 1 BOf.271500 75

I 07 /02/7£'. RI! f.IOV MOV-Rl/··100 Sf:.'7' 'l'OR(JUf. + I.Tf.:ITS . Hl'.'S/i,"'l' ·romJUf, AND f,Tf.JITS FOR l:T lfi. q 1 P.Oli/.(l0<Jllfi fi<J 07/02/7B RS NOV llOV-RS-1Sfi8 Sf::T 'l'Oli'(JUF:+DTMTT SltT'l'Cl/l•:S SE1' DT.MT'l' Sio/[1'Cllll'S Clll\CKF:fJ TOf1QUF. 1 £10fi2llJ 527 P.O 07 /0'l/7P. Cl/ /IT 1-C/l··P-2A DT.SCOf/NECT+l\/\CONNf,'(,"f 1/11/lT Tl?llCT.NG Rf.MOL' t:U+ R/\'fDACIW 111•:/l n:RS+T///o: flMOS 1 [l07021h00 us 07/05/7!1 RC PHP NTR 1-/IC-l'-lC orsc I m·:coNN cu11N1;r:,· on DISCOf/li'•Rfi'CONN CllllNGC:V on 1 (l(lUJ ll0llf)J 1Sq2 011os/1e f",o/ V 11/,V/i' FCV-1 1l1B J NS'/'tt/,[, Nf,'W SO/,f,'fl(}iD @'Pr,11cr::o sou:.von1 v M,V/': 1 l.l0621i1015 1'!5 e 07/0f./7? RC m:NT Nr:V 1-RC-l'-1C l-'OSS!/JLI'.,' 8/lf) TN DIC AT TON 7'E:S1'f,'f) Brmnl'Y NW Af)/l SYSTf:N 1 l.l030'Jn~30 'Ill 'I 07 /0f./7£'. FW ft!OV 110V·N-1S1B Ullf:AKr:I? lo/[[,[, /JOT h'F.SF.T + VALV/': R/i,'l'AIRW -Tl'STr::D SAT 1 l.l0ft302330 fjlJ

01 /Ofi/7e R:i NOV /.:OV-//S 151l8 STJT 'l'OR(JUE S1¥T'l'Cll 7'0 MAX Sf,'T 1'0111JUF,' SI./ ·rr::sr SAT 1 {107021545 104 07 /Of./711 cs VADVE: f·IOV-CS·l.0111 Sf,''l' f.T.MT'I' :NT1'CllF:S S/.'7' [,TNT.TS 1 {1070215411 118 07 /0fi/7? CV V/lf,Vf\' l/CV-CV-100 l/CV-CV-100 Ii[[,[, NO'l' GO SI/UT vow 1 (107031501 .0 07/10/7£'. - fl{ NO>' MOV-W·151D DTSCONN/i'CT-fll>"COflllfiCT f'OR MF.CllS D[SCON.'it:CTF./J··RfICONflfi,'C1'fW 'l'E:S7' SAT 1 OOf.1315 111 (iif,

07 /10/7!1 f,P/JC D/IS lB N£Gll1'TVt,' GROUND Cf,/\AR/W GllOUN/J 1 ll0fi2511133 67 07 /10/7P. VS CONT 1-VS-li'-4C GRE/','N LTGllT f,T'J' Wlili'N UNIT Ol'f.RATING nlfi'Efl Jllf.IMf.'/J NATN [,[flf,' CON1'ACTO/i 2M 1 B070~11.l25 57 I

w D/WJ' TOT /if, 3G03 N

I

:..... -.J

ij .I

• ,,

·-------- -

-33-


UNIT /12

Electrical Maintenance

Dt;PJ'=!SC,F.C

UNIT 2-JUT.Y 1q7(l

lNATNTISNANCI': OF SAFf.TY Rf.f,AT/W SYS1'F:NS D/JUING OUTAG~; OR ww11cE1J ro11r-,'R nmwns>

RF.TSf:T/Vtrr SYS COMI' l.fARKNO SUN/I ARY WKPHHF u f.11/ T01' /JI/ NT.'f

07/08/7P. liC /.IOV rmv-2sq1. lvTT.,f, NOT Ol'f.N com•r,F:Ttm. liMl'-C-NOV·-1~ TBST SAT 2 !!070701.'50 31

07 /12/71! RC V /if,V~; l'CV-2'l5fi wnr, NOT Ol'F.N Tf~S7'/SIJ V Af,VE·-7'1':5T£/J SAT 2 P.07072'.)110 e fJ7 /1S/7e cs NOV MOV-CS-20AC ST-,'T C,P.1l7' SirT'/'Cf{fiS SfiT f,TMI'/'f.•TSS'f!i'D 2 0011:111100 bb

·J7 /15/7P. cs NOV MOV-CS-20AD Sfff [,I!f[1' S'dITCl/!IS Sl':T f,TNTTS•1't::S'/'8/J 2 {l07131h01 bb

07 /17 /7f'. Cl/ /IT l'f/[,I! -C KT-b fi'l•.'PC,ACE Wlv UMTT Tlll':TiMOSTAT Rb'l'DACfi/J Tllf:liMOU'l'AT [,() f,Tf.IJT 2 ll071707:10 (l

07 /H/71! Cl/ /IT l'N/,8-CKTB W:V /11,/rR!I CllT::CKW CIJ/ili'!IN'I' 2 l!071fi1200 112

· 07 /H/71.' Cll li1' l'NDP.-CKTb JIT/W /rf,Af/M CllllCKl·."IJ C/Jf1'lifiN'l' 2 B071fl1201 b'i

( 0111•i11e IA CONT 2-IA-C-2A COMPTIT~SSOR /JOE.'S NO'/' START IN AUTO CllP.CKlW c rncur·r 2 (10fi301ll00 215

0711 'l/78 ST l'MT' ~rrr. 2-sr-·r-rn Di SC/ Tif;'CONN FOR f.lliCTIS COMl'C,lff/SIJ EMP··C-b'l'C,-12 2 eo1os1:in 2ll3

07 /20/78 Cl/ /IT PND-10 crncurr s [/Jr.I TENl' 7'F:S1'EIJ SA1' 2 p.071q1320 7 ( 07 /':.0/7('. Cll /IT l'N[, 10 CIHCUIT fl Wlo/ 'l'E:l·ll'ERATURF. 1'ES7'F.'IJ SA'/' 2 0071'!1321 6

01120/n Cl/ HT PN[, 11 CI/ICU l'l' 5 Wlr TF:Ml' 7'SS'l'l'.'D SAT 2 8071 <J1325 7

07 /'J.U /70 RS I'fo!P f.fTR 2-US-l'-2A DISC/Rl\CONN FOR MSCllS COMl'f,f,'TS/J EMP-C-EP/1-12 2 007051320 ~01

07 /211 /713 RS Pf.IP MTR 2-RS-P-28 DTSC / fll·:CONN FOR Mf,'CllS DlSC•Rl~COllNECTEIJ CllANGIW on 2 !107051:121 3<J'}

Df.n' TO'I'AL 1i;n

-35-


UNIT t/l

Instrument Maintenance

., ... '11 '~

VE"IT=msr

m:rs1mv 1rr

07/03/7P 07/05/7'(1 07/07/70 07 /07 /7P. 07 /07 /78

/)f.Pf T01'11[,

SYS C0111'

BR lf/S1' us INST E:l'CR f1PL SPCR Ii PI E'l'CR Rl'L

UNI'I' 1-JUT,Y l'l7l1 l/.1/1.TNTSN/l.NCS Of:' S/l.f'fl'TY R1·:1,11rr:;v srs·rt:f.JS .DUUJNG OUTl1Gf,' or. fi'/\'/)/JCI:..'/) PVllE.''1' l'SRlOIJS)

/.ftlRKflO

f,I-UR·-114 l'I-1-tir.B G13 N'l G3

SUNl//l.llY

DtllJ TN/JTC/l.TWN··C/l.L-CllFICK ST::NSTNG [,[N

INDIC/J1'f:S lQOO WS WllfiN 300WS /l.CTU/I. OUT Of tlf,IGNMS.VT W/ D/Jl/K OUT OF tlLrGNNf,'NT 'ti/ U/l.f/K OUT OF ALWN!IE'NT W/ D/l.Nl{

/J/JTL.T /lf.'l't,'/l.Tr:R+C//TiCKlW XMTTU:R R81'I,/l.Cr::D OSCJ f,f,ATOR·-tl!Jl' /JLIGNIW Wl'l'll n 5.2 11LTGN8/J IJ/Jl?TNG Pl' S. 2 /J'[,T.NGc'D DIJlliflG Pf S. 2

,,., •'·

/} MR TO'l'WNT.11

1 {l0fi2~0l110 fi 1 !l07050fi30 5 1 B070fi01i00 1 1 B070fi0ti0l 1 1 !l070fi0fi02 1

lb

I w 0\ I

. I I

.I 11

,,

-37-


UHIT /12

Instrument Maintenance

DF:lT=TNST

· lilTSF:f/VDT SYS CONl'

07 /13/71) IC lNST IJ7 /U/78 cs iNST 01/D17 e cs TNS1' 01121 /7e TA l'TPING 07 /'J.1 /'lf!. /:,'/'CR Iii'[ 01121ne IA VA/,VE 07 /21/70 ST ;:1s1·

VF.VF TOTAL

..

UNTT 2-JULY 1q79 WATNTE:NAl1Ct: OF SAFF:7'Y R!i/,AT/;'/) SYSTENS ·vuRTNG OUTAGr: OR /1WIJIJCf,'/} l'0:-11\R PF,'/1'10/JS)

MA//iil/O SU/.JMA/IY u MR 7'0'/'W.VT,11

RF,'COR/Jf\RS FOR l'EN Cl/ARTS DO NOJ' BYl'ASSIJTJ lJEP/\(,'7'IV/:,' 'flllf.JIJC,F.S 2 ll07011f>55 2:1 2-CS-GA-130A GAUtJf,' IMl'l\Ol'IW m:AIJTNG CllfiCf\1-:V S/11' 2 l'071?.C!IJ1q 2fi 2-CS-GA-131A GAUGfi: lfo/l'flOl'f,'fl flF:AIJlNG CllF.Cl<lW SA'/' 2 ~071'10020 21i l'CV-2'• Sfi AJH f,P.AK ON /,lNfi 'fO VA/,Vf:: llb'l'A.rurm m:n·n PACli 2 (1071101100 tiP 010 NO r.·uv BOTTOM f,TG/17' ATJJ118'J'f,'V HOU UOT1'011 IJTS1'AlJLF. Sf~1'POIN 2 8071920;)0 22

REMF.F V Af,VF: Lf;111<S nx1m mmur,Amn~c1ll1cK1w FO{( f,l\AKS 2 sono1 so11 i;

PT 021 NO PRESSURF: TNDICATTW Rlil'LACf,'[) ,Jl'OWP.11 S/Jl'l'/,Y 2 !107201 q:-is J

1511

I w CP I

_3-9::.. HEALTH PHYSICS

JULY 1. ~9_7_8

.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.

Facility: Surry Power Statlon

I. J.IQUllJ RELEASES

l. Gro.is Radioactlvitl:'. (py) (a) Total Release (b ~ Avi;. Concentration. Released (c) Maximum Concentration Released

2. 'fritJum (a) Total Released (b) Avg. Concentration Released

] . !J !!mo l ved Noh le Ca~ea (a) Total lie lease (b ~ Avt;. Concentrution Released

4. Gro8.s Alr>ha Radloactivitv (a) Total Ri.!leased (b) Avg. Concentration He leased

5. VoL of Li<Juid to Disch. Canal 6. Vol. of IJJ lutiOn \foter 7. Isotopes He leased MPC pCi/ml

7 I-131 ) x 10 I-132 8 x JO G

1-133 l x 10-• I-1311 2 x 1 o-=• I-135 4 x io-• Cs-lJt, 9 x 10-T

Cs-136 6 x 10-•

Cs-137 2 x 10-, Cs-138 -Cu-57 4 x 10-~

Co-Sil 9 x 10 , Co-60 3 x 10 ,

Mn-54 1 x 10-~

Na-24 3 x 10-5 Cr-51 2 x 10-' Fc-59 5 x 10 ·S

Nb-95 1 x 10 '• Ba-l.a-140 2 x rn-s Hli-88 -

.UlHTS

Curies pCilml pCi/ml

Curies pCi/ml

Curl.es pCihnl

Curies pCi/ml

Liter·s Liters Curies -----

·----

-----

----

~

HEl'ORT OF RAllIOACTIVE EF11LUENTS

DOCKET: 50-280 and 50-281

·----- -- ...

JULY

l.99E-l l.07E 9 1. 95E-9

l.13E+2 6.llE-7

---zt:T?E-z -Z:-Z5E=IU--

2.04E-5 .1. lUE-lJ

3.90E+7 l.85E+ll

7.52E-5 ~

* 1i

-:J.7lilF5 3.JSE-2

* 8.27E-2

* 3.95E-4 5.33E-l 3.62E-l l.OSE-2 7. 74E-l1

-l1.13E-2 4.44E-4 G.lJE-3

* *

--

-

PAGE l

YEAR: 1978

- -

I

I

-~

·~-------'------------------·-··--- ·-··-·· -·-··

REPOHT 011 RADIOAC1'IVE EF17LUEtffS PAGE 2 FACILITY: ·surry Power Station

DOCKET: 50-2110 and 50-281 YEAR: 1978

L / LIQUID RELEASES (CON'T) - -- -·· --- - --- ··- ... - --- . ~

-· - ·= -· - --- - --- -- .. -· .. - - ·UUITS JULY .'f.OTl\h. ___ }: E;rror

7. Isotopes Released pMPC Ci/ml r. .. ries Ce-llil 9 x io-" * Ce-144 1 x 10- 0 2.79E-4 Xe-133 J x 10-• 2.28E-2 Xe-135 J x 10-b 4.09E-3 Ar-41 J x JO " 6.56E-5 Sr-89 3 x 10-•

Sr-90 3 x 10-

C-14 8 x 10-•

8. Percent of lOCFR20 Percent l.90E-2

II. A!l{!!OltNE RELEASES

l. Tot a 1 Noble Gase~ Curies 3.92E+l 2. Total Halogens Cur:les 2.16E-7

-3. 'l'uta l Particulate Gross Rad lo-_____ actlvl~lJ.frrl. Cu!:_ies _ 2.80E-3 4. Total Tri ti um Cur!l!S L6JE+l 5. Total l'artlculate Gross Alpha

I ~

Ha<lioactivlty Curies 2.91.E-5 ...... I

6. Haximum Noble Gas Release Rate •1Ci/sec l.06E+3

7. Percent of Applicable Limit for Techn!c.:a l S1>ecificatlons (a 2 Noble Gases Percent 2.99E-2 (l>) llaloi;ens Percent l.BOE-6 (c) Particulates Percent 6.93E-2

8. 1 sotopes Released: Cud es (a) Particulates

C,;-1 '.llt 2.110E-6 -Ci;-135 * C:;-117 1. 09E-5 c .. -118 ---- j~SrH-Co-58 ·---:;-:-BE"=-~

Co-60 -~:4GE=q-

H11-S!J 2.47E-5 Fc-59 * Hl>-~8 * - -- -- - ----- ... .. --- - .. ----- -·----·- o~· ... -· .. -· -- .. ··--· ·--- ----· - - --- ---- .. --·--- --- ····- -----· - .. ---- ---a . - ·---· --

.·

... - ....... __________ .. ,,,_ ·----.. ---·----------------------------------- -"·-·-····- ...

REPORT OF RADIOACl'IVE EFFLUENTS FACILITY: Surry Power Station

DOCKET: 50-280 and 50-281

II. AIRllORNE RELEASES (CON'T) UNITS . x .JUl,Y

8. Isotopes Released (con 1 t) Curies (b) llalo((ens

I-131 1-132 I-133

1-135 (c) Cases

Xe-133 Xe-133m Xe:-135 Kr-85m Kr-85 Kr-87 Kr-88 Ar-41

III. SOLID RADl OACTIVE WASTE DISPOSAL 1. (a) Total Amount Solid Waste

Packaned FT 3

, ____ (~b~) __ l_cs_·. t_l_11_1a_t_e_d_'_fo_t_a_l_A_c_t_l v_i_t~y ____ • __ Cu r.i es (c) Date of Shipment and

Dlsoositlou

l.61E-7

* 5.55E-8

* *

---:r:lbE+l 3.90E-6 4.0BE-1

* * *

l.25E+U

llarnwell, s.c.

7-6-78 7-9-78 7-15-78 7.:.17-78 7-22-78 7-22-78 7-25-78 7-27-78 7-27-78 7-Jl-78

PAGE 3

YEAR:_~l~9~7~B __ _

f

'~

• I.• ...

/

( .\-,

.. 1

.... _,)

'·· * SENSITIVITY DATA

... , .. •l. Mini-num Detectable Activity ' ... ·~ ..

\

a~

b. c. d. e. f. g.

Gross Alpha; 5.27E-9 µCi/ml Tritium; 4.0E~6 µCi/ml Strontium-89; less than 3.0E+l pCi per total filter composite. Strontium-90; less than 2.0E+-0 pCi per total filter composite. C02-14; less than 7.0E-10 µCi/ml. Strontium-89; less than 9.0E-9 µCi/ml. Strontium-90; less tha~ 8.0E-10 µCi/ml.

2. · Multichannel Analyzer - GeLi

a. Liquid and/or Radiogases - lOOcc

Ba-La-140 I-131 Xe-133 Xe-135 Cs-137 Cs-134 Co-60 Co-58 Cr-51 Mn-54 Fe-59 Ar-41 1~134

I-132 Na-24 I-133 I-135 Kr-85 Kr-88 Kr-87 ·Kr-85m. Xe-138 Xe-135m Xe-133m Rh-88

· b. Radioiodines

I-131 I-133 I-132 I-134 I-135

2.0E-7 5.lE-8 5.4E-8 2.9E-8 9.2E-8 7.2E-8 l.5E-7 9.BE-8 3.8E-7 l.OE-7 2.4E-7 1. 6E-7 l.lE-7 . l.OE-7 l.7E-7 6.9E-8 4.5E-7 l.36E-5 5.SE-8 5.3E-8 2.3E-7 4. 7E;...9 5.8E-8 1. 7E-7 8.SE-7

2.3E-6 3.lE-6 4. TE-6 4.8E-6 2.0E-5

-44-EVIATIONS REVIEWED BY STATION l\11 CLEAR

SAFETY AJ. - OPERATING COMMITTEE AFTER TH IT SPECIFIED IN TECHNICAL SPECIFICATI0,0

JULY, 1978

There were none during this reporting.peri6d.

VIRGINIA ELECTRIC Al'lD POWER COMPANY

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