ML19095A383
| ML19095A383 | |
| Person / Time | |
|---|---|
| Site: | Surry  |
| Issue date: | 08/01/1978 |
| From: | Virginia Electric & Power Co (VEPCO) |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| Download: ML19095A383 (47) | |
Text
VIRGINIA ELECTRIC Al'l"D POWER COMPANY SURRY POWER STATION MONTHLY OPERATING REPORT REPORT NO. 78-07 JULY, 1978
. __ ~
Superintendent-Station Operations APPROVED:
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'MANAGER
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CONTENTS Sect;ion Operating Data Report - Unit 111 1 Operating Data Report - Unit 112 2 Unit Shutdowns and Power Reductions - Unit ffl 3 Unit Shutdowns and Power Reductions - Unit 112 4 Load Reductions Due to Environmental Restrictions - Unit Ill 5 Load Reductions Due to Environmental Restrictions - Unit 1/2 6 Average Daily Unit Power Level - Unit Ill 7 Average Daily Unit Power Level - Unit 112 8 Summary of Operating Experience 9 Amendments to Facility License or Technical Specifications 11 Facility Changes Requiring NRG Approval 13 Facility Changes That Did Not Require NRG Approval 13 Tests and Experiments Requiring N~C Approval 14 Tests and Experiments That Did Not Require NRC Approval 14 Other Changes, Tests and Experiments 15 Chemistry Report 16 Description of All Instances Where Thermal Discharge Limits 17 Were Exceeded Fuel Handling 18 Procedure Revisions That Changed the Operating Mode Described In 21 The FSAR Description of Periodic Tests Which Were Not Completed Within The 22 Time Limits Specified in Technical Specifications Inservice Inspection 23 Reportable Occurrences Pertaining to Any Outage or Power 25 Reductions Maintenance of Safety Related Systems During Outage or Reduced 26 Power Periods - Unit Ill - Mechanical Maintenance Maintenance of Safety Related Systems During Outage or Reduced. 28 Power Periods - Unit 112 - Nechanical Maintenance
-ii-Section
(
Maintenance of Safety Related Systems During Outage or Reduced 31 Power Periods - Unit Ill - Electi;ical Maintemance Maintenance of Safety Rela.ted Systems During Outage or Reduced 33
~ower Periods - Unit #2 - Electrical Maintenance Maintenance of Safety Related Systems During Outage or Reduced 35 Power Periods - Unit #1 - InstrUIDent Maintenance Maintenance of Safety Related Systems During Outage or Reduced 37 Power Periods - Unit #2 InstrUIDent Maintenance Health Physics Sunnnary 39 Report of Effluent Release D.ata 40 Sensitivity Data 43 Procedure Deviations Reviewed by Station Nuclear S.afety and 44 Operating Committee After Time Limit Specified in T.S.
/
REPQ RT COMPL~TED EY O.J. COSTELLO ST'ri'JUS TELEPHONE 80U-357-318u 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
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- 0 s-o-st-:v---tr s-rs;.-:-tJ--....--~
- 12. HUU3E2 O? HOURS EEACTOR WiS CR7TICAL 613,6 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
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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.J*L~~--
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- 18. fiET ELECTRICAL EYERGY GEYERATED iMWH) 381029.0 2il38356;0 22705920.0
- 19. UNIT SEEV:CE FACtOR 63 . 0 o/c 54.6 o/o
---2-0 ~--UI*l:~r" /. . F A:L/..3: LITY--F'ACTOP. /-2-.**c,-Of-o--6-~.-iJ-O)o----OlI;-:6-c7--o- *---**
- 21. UN:T CA?AC:TY FACTOR (US:NG UDC NET) 56.1 o/o 61,8 o/o 59.5 o/o
- 22. U[IT CA?ACIIY FACTOR (US:NG DER NET) 52,3 o/o 58.3 c/o 56.2 o/o
---2-3-~--i'i/:-T--FO?.C E D--o-o*T-;:,,,*G-~-R A'i'"E -----0-:rs--01 o u-:O o / o -:;:;-: 0- c - ; * -
sau~~o~;s SCEEDULED OVER *vEXT s 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
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- ~:T:AL c~:T:CAL:TY
=~IT:AL [LgcrR:c:TY
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0 PER t. T .:-1.:.;A~ A REPORT DOCKET llO. 50-281
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- 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 cn.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 NIA
-*--:n*-:-*- BGUF.S :N* ?.'EPORTING-PEIC'OD. /1!4. u :iut! 7*:-v----i.rti*u-3r.D---
12 NUMBER.OF HOYRS REACTOR WAS CRITICAL 148. 1 3860.6 30273.4
- 13. REACTOR RESERVE SHUTDOWN HOURS 0.0 0.0 0.0
-**-*-1u * .. HCU?.S -G5FER ATOR- O!i=tiliE ______ . - - - - - -i-1.rB . .~--~::SB
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- 15. UHIT RESERVE SHUTDOWN HOURS o. o o.o 0.0
- 16. GRQSS THERMAL ENERGY GENEEATED (M~E) 351672.0 935U683.0 69064917.D
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~* 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 ~ .. - UiCT AV'"J.I LASI iIT'F.? fi.cj'(iR_____ r-fg *:9-;,7-c--7 5 :*7-*0 ; o .... -.. t*u*: 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.: Ai'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
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DOCKET NO. 50-:-280 UNIT SHUTDOWNS AND POWEil JtEPUCilONS Surry l UNIT NAME DATE 8-1 COMrLETED llV o. J. co.:t*:!l1o ilEPORT MONTI! July 1978 TELEI llONE (804) J57-3I84
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6 78-1 780701 s *2os.s c 1 Unit shutdown at beginning of period.
~ Turbine repairs in progress.
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F: Forced
- S: Scheduled
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A-Equipment f-ailure (Explain) 3 Method:
- I-Manual 4
Exhibit G
- Instructions for Preparnllun of Data .
D-Maintemince or Test* 2-Manual Scram. Entry* Sheets for l.ktnsec
(l~cfucling 3-Aulomallc Scram. Event Report (LER) File lNUREG-
. D-llcgulatory Restriction 4-0lhcr (Explain) 0161)
E-Opcrator Training & License Examination F-/\drninistrali'ic
- s G-Opcralional Error (Explain) Exhibil I *Same Souri:t (IJ/77) 11-0lhcr (Expl:1in)
DOCKET NO. 50-:-281 UNIT SHUTDOWNS AND FOWER REJ)UC:TIONS Surry 2 UNIT NAME DATE 8-1 COMl'LETEO DY o. J. Co~tello RErORT MONTI I July 1978 TELEl llONE (804) 357-3184
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78-4 780707 s 596 H 1 ECS Pump Modifications.
Shutdown at the end of this report period~
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, 3 4 F: Forc:cd
- Reason: Method: Exhibit G
- lnstrudlons S: Scheduled A*f:quipmenl Failure (Explain) I-Manual for Preparation of Oa13 ..
0-Mainlehancc or Tc:it 2-Manual Scra1n. Entry Sheets for Licensee.
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C'-Rcfucling . 3-Aulunrnllc Scram. Event Report (lERl File (NUREG* h>
. ().J{cgulatory Restriction . 4-0thcr (Explain) 0161) I N
E-Opcralor Training & License Examination I . 00 r-Ad111i II isl rat i*1c s I
-...i G*Ppcrational Error (Explain) Exhibit I *Same Snuri:t
. (lJ/77) ll*Othcr (Explain)
LOAD REDUCTIONS DUE TO ENVIRONMENTAL RESTRICTIONS UNIT NO. 1 MONTH: JULY, 1978
., I DATE Til1E HOURS LOAD 2 MW REDUCTIONS 2 MW
-MWH REASON I' (NONE DURING THIS REPORTING P!RIOD).
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II MONTHLY TOTAL 0
LOAD REDUCTIONS DUE TO ENVIRONMENTAL RESTRICTIONS
. UNIT NO. 2 MONTH: JULY, 1978
- .,l DATE Til1E HOURS LOAD 2 MW REDUCTIONS 2 H.W MWH REASON
- I
(~ONE DURING ' hHIS REPORTING PERI bD).
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I 1-MONTHLY TOTAL 0 ..
D~ET NO 50-280 UNIT SURRY :
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D_AT_E_.8_~1- - 7 8
' COMPLETED BY 0 J COSTELLO JULi' 1978 AVERAGE DAILY POWER LEVEL AVERAGE DAILY POWER LEV~~
DAY (NWE-llET) DAY ~/.J'iiE-1.'ET)
.J. 17 7 3 6. LI.
736.2 2 18 3 19 733.9
~------------'-- --
. Li 20 *731.9 5 21 726.5 6 22 713.8 7 23 720.5
-~ '*8_____ _
**--***--**----- ----~---------------~~5_ _ _ _ _ _ _ _2_5_ _ _ _ _ _ _ _ _ _7_25.0_ __
10 502. 8 26 721.1 11 702.0 27 7 2 5. 5 12 ___ --------- ______ J_2)_. ~--- 7.~-- 7 2 5~*~5_ _ __
13 7 2 5. 7 29 724.9
--:------------------- .. lJ
.J.. 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__ NE'f__ ELE_C T_RIC f..I.
EATING OF THE UNIT, THERE MAY BE OCCASIONS WHEN THE DAILY AVERAGE POWER EXCEEDS .
THE 100 °/ LINE (OR THE RESTRICTED POWER LEVEL LINE). IN SUCH C~SES, THE AVERJC3 0 1
____ .DAI LY - uHIT .. PO'rl ER ... OUTPUT__ 5_H EE_T__ s HOU LD__ BE_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 I
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. -----* -*-*. .. -- . --*.:.: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. *-----Avt:fiGE DAILY-POWER-LE°li~
DAY (J.f';/"E-NET) 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 __-* ---------------
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- -*------------ --- ---- ***-*---~ ----------------*----*---- ---- ____________ --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 REPORT-ING !-:'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.,!
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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 sig-nificant non-load related incidents.
UNIT 1 July 1 This report begins with the unit in a cold shutdown *Condition.
Primary and secondary maintenance in progress.
July 2 At 2245 the turbine was placed on turning gear following major overhaul.
July 4 At 2230 the unit was >350°F for normal plant recovery.
July 5 At 1630 Rod Drop Testing (PT-7) was satisfactorily completed.
July 6 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.
July 8 At 0500 rod K-4 dropped from a blown fuse. At 1045 the rod was retrieved.
July 9 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 re-quired 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.
- .,_.;:;.:~~:r
1-!MARY OF OPERATING EXPERIENCE e (CONTINUED)
UNIT 2 July 1 This report begins with the unit at 100% power.
July 6 At 2100 a unit rampdown was begun for ECCS Pump Modification.
At 2400 the unit was at 44%.
July 7 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.
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 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. 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 signi-ficance, 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
.AMENDMENTS TO ILITY LICENSE OR TECHNICAL SPF' ICATIONS (CDNTINUED)
Containment Air Partial 9.2 PSI.A at 87°F Maximum Pressur:.e service water temper-ature and 45°F RWST temperature. This value will vary in a manner similar to existing Technical Specification 3.8.
}linimum Refueling Water 385,200 gallons Storage Tank Volume Outside Recirculation Spray 2250 gpm Pump Flowrate 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 require-ments 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) 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.
(2) ~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. DC-78-01 Replacement of Sample System Trip Valves 2 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.
- 2. DC-77-08 Overpressure Mitigating System 2 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 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 mal-function different from those previously evaluated have been cre-ated, 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.
¢.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 There were none during this reporting period.
_****~r
CHANGES, TESTS AND EXPERIMENT JULY, 1978 There were none during this reporting period.
- ~F~~ -*<-
~- . .
- SURRY POWER STATION CHEHISTRY REPORT JULY , 19~
T.S.6.6.A.ll PRIMA.RY COOLANT ANALYSIS UNIT NO. 1 UNIT NO. 2 II MAXIMUM MINIMUM AVERAGE MAXIMUM MINIMUM AVERAGE ;
Gross Radioact., µCi/ml 3.61E-l 3.32E-3 178E-l 2.21E-l 4.32E-3 8.68E-2 I
o.o Suspended Solids, ppm 0.4 0.1 2.0 0.1 0.2
!I Gross Tritium, µCi/ml 1. 06E-l 4.14E-2 6.94E-2 1. 39E-l 3.47E-2 8.45E-2 II Iodine-131, µCi/ml 2. 72E-3 2.98E-4 1. 63E-3 5.24E-4 . 2. 32E-4 4.02E-4 I
I-131/I-133 0.1878 0.0838 0.1294 o. 1174 0.0502 0.0973 I I
t Hydrogen, cc/kg 42.2 20.6 33.5 37.5 0.0* 4.1 !
I
.I I
Lithium, ppm 2.00 0.10* 1.15 2.00 0.30 I 1.26 t
Boron-10, ppm + 451.2 158.4 226.2** 459.2 67.0 303.2 I I
Oxygen-16, ppm 0.000 0.000 0.000 2.500 0.000 0.267 I
Chloride, ppm 0.07 0.05 0.05 0.09 0.05 0.05 pH @ 25°C 7.02 4.68 6.20 6.88 5.78 6.19
+ Boron-10 Total Boron x 0.196 NON-RADIOACTIVE CHEMICAL RELEASES, POUNDS T.S. 4.13.A.8 Phosphate o.o Boron 957 Sulfate 1112 Chromate 0.01 50% NaOH Chlorine 0.0 HOO Remarks:
- Unit at cold shutdown.
- ,~ Ave. does not include boron values run during physics testing.
- -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 inven-tory 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
. ' UNIT
' I I II 1 FUEL HANDLING
-JULY, 197S e --
,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 -*
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UNIT 11 2 FUEL H.AlmL DiG JULY, 1978 D.!.TE
' I
- SHI??.~J / RE.C EIV"E-D I r;o OF ASSE.MBLlES PER SHIPt1ENT.
A:.'\iSI HO. d.t:..W OR S?:::~iT FUEL
'T'r'"TT I. INITIAL ENRI CillfENT SHIPPING CASK AC'l"IVITY L::.:-
I
' I --
(NONE DURING THIS REPORING PERIOD).
I I
I ~-
I ..
,....~--
I I -*-
I I --
I I -
I --
I I
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PR-URE REVISIONS THAT CHANGED THE oP4JrnG MODE DESCRIBED IN THE FSA!
JULY, 1978 No. Unit Title Change OP-1.1 2 Unit Startup Operation Update to reflect in-(CSD to 230°F) stallation of Overpressure Mitigating System OP-1. 2 2 Unit Startup Operation Update to reflect in-(230°F to 350/450) stallation of Overpressure Mitigating System OP-3.3 2 Unit Shutdown Operation Update to reflect 350/450 to CSD) installation of Overpressure Mitigating System OP-3.4 2 Unit Shutdown Operation Update to reflect in-(Solid Plant Operation) stallation of Overpressure Mitigating System Note: Refer to Safety Analysis for Design Change 77-08.
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1
DESCR~ION OF PERIODIC TESTS WHICH WE~NOT COMPLETED WITHIN THE TIME LIMITS SPECIFIED IN TECHNICAL SPECIFICATIONS JULY, 1978 There were none during this reporting period.
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.
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li'E1'SF,ft'V vr SYS COMP NllRKNO SUUM/IRY WKl'li'liF u /.fR TOTIN NT/.!
07/22/78 RC SG 2-r.c-r::-2c /i:/JDY CUliRC:NT+R[\'l'll[I? !IS Nli'Cl*:ss EDDY CUR//t::NT PWGE/J+CWSIW OUT 2 ao1os1s2q 302 07 /'J.U/7~ RC SG 2-RC-E-2/i ' f,'/)/JY curmrmr+RF.l'llTR AS Nr:cF:SSllRY E1' *rr.srt:TJ 11/VTJ l'WGGl::O 1'U/Jf\'S 2 1!07051522 35!i 07 f2q /78 RC SG 2-m;-11-211 IW/JY CUR/i'/\°N7'+RflPllrn /IS NECc'SS li'T TUllli'S ANIJ E'fJJGr;gu !IS fjf*:Qu.rnw 2 ~07051523 337 IJF.l'T TOT II[, '!95 I
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RE.erABLE OCCURRENCES PERTAINING T .
ANY OUTAGE OR POWER REDUCTIONS JULY, .1978 There were none during this reporting period.
- ~*"'".
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Maintenance of Safety Related Systems During Outage or Reduced Power Periods UNIT 1/1 Mechanical Maintenance
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Uaintenance of Safety Related Systems .During Outage or Reduced Power Periods UNIT 112 Mechanical Maintenance
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7 e 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 VllDVI': 2 P.072 1! 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 1 1t 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 ll5 '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 fl 11
- y.**
Df'.1'T=m:c11 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)
S/Jf.:/o!Ali'.Y Wlf.P/*,'/W 11 Mil 7'01' /}.{ !tl'f.!
Hf."l'Ser.v /J'f SYS CON!' MA/lliNO 07 /27 /7~ 2-RS-P *1/J 81111 ORTNG ON Rf:GU[,A7'0R 1{ATf.R rllAP /1F:/'[,ACIW <JriTNG 2 ll071:l.O!il 'I 3<J:l.
RS l'UMl' TTGll'rf.'Nff/J fJ()f,1'S Of/ SCHl*,'/iNS 2 007170lll5 '.J<Jlf 011-n 11.0 [l,'j ~WIP llfmtJ(,1' SCfi'F.~.'NS TN f;'/,llCf:
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 l!IJ71!l10lfi 10 11 07 /'27 /7f'. i/SS Sf/U /J/Jflfl NO l'l' St.'llL !.JA'l't:RI /il, El TN. RF.l'f,ACTW lff/'// fl/-'// fllWIJIL1'-0f/S 2 {1071lt1017 1011 07 /27/7f'. I/SS 511/JIJB&R 2-SllP -/ISS-P NO fll*' SF.AL NllTr::RI AL 10IN, WW/JILT Sfl//Ulll'ft' WIT/I fll'R f.IA'rt:RIAL 2 l1071lll010 1oq 07 /27 /7!1 //:JS SNUTJ/l&R 2-Sf/l'-llSS-9 2-l/SS-170 Rl!.'1'11 TH S.VU /lflf.11 /if,'l'/IIr!f.'D SA'/J/Jf!r::R 2 0012120113 130 07 /27 /?ll //SS Sll/J/J/Jm
/it:PAU1'fo.'fJ /JO/JY TO RO.V/lr,'1' T,l\AK 2 P0721123j0 111 07 /1.7 /'I~ RC I' A/,VS 1'CV21* SSA /!OTJY *ro UO!INf.1' 1,SllK INS1'ALC,f,'IJ/ l//;'NOl'IW fjG Tl~N'l'S 2 ll0705151 If 528
()1 /'l.P/7? as TENTS INS1'11[,[,/R/\'l*JOVS SG TEN7'S 01'/\'NfW llNIX:WSf.IJ //A1'C// 2 ll0727105ll 1'.J.
07 /30/7f'. liS I/ATC/I Of'l?N+/IP.CWSP. t::C.JUTl'/.lfiN1' llA1'CI/
CUO:AN/*.'/J t l1'l\G/1'EAS/m 0 RINGS 2 ll07J012'25 3 07 /:l(J/7!1 as I/ATC/I /IF:PATR f,'/.ft:fi'G I/ATC// WC/I. Nr1'C/IANTSM 2 l\07271025 75 07 /31/7? li'C l'NPflTR 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 Sfl/lf, LP.AK BAU ON B ff.IMP SE'A£ LF;M<. m;PAil/lW 2 f!07j01525 2'.l 07 /31 /7? SI T'U/f P 2-ST-P-1B 2-/i'C-13B PACKTNG Ll\1111. /i'fll'ACll.F:/J VAT,VJ-:+RF.PLACl::V GT,/IND STUDS 2 807310150 10 07 /31/7!1 RC VALVS fill30 DffT TOTAL I
l.J
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- "ii ..
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- ~
Maintenance of Safety Related Systems During Outage or Reduced Power Periods UNIT Ill Electrical Maintenance
Dr:T-T=f.U'C 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)
!I 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 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 07/0f./7?
07 /0f./7£'.
f",o/
RC FW V11/,V/i' m:NT Nr:V ft!OV FCV-1 1l1B 1-RC-l'-1C 110V*N-1S1B J NS'/'tt/,[, Nf,'W SO/,f,'fl(}iD l-'OSS!/JLI'.,' 8/lf) TN DIC AT TON Ullf:AKr:I? lo/((,[, /JOT h'F.SF.T + VALV/':
@'Pr,11cr::o sou:.von1 v R/i,'l'AIRW -Tl'STr::D SAT M,V/':
7'E:S1'f,'f) Brmnl'Y NW Af)/l SYSTf:N 1
1 1
l.l0621i1015 l.l030'Jn~30 l.l0ft302330 1'!5
'Ill fjlJ e 'I 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
3G03 N D/WJ' TOT/if, I
- ..... -.J j * ,,
I
Maintenance of Safety Related Systems During Outage or Reduced Power Periods 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 rmv-2sq1. lvTT.,f, NOT Ol'f.N com*r,F:Ttm. liMl'-C-NOV*-1~ TBST SAT 2 !!070701.'50 31 07/08/7P. liC /.IOV 07 /12/71! RC V/if,V~; l'CV-2'l5fi wnr, NOT Ol'F.N Tf~S7'/SIJ VAf,VE*-7'1':5T£/J SAT 2 P.07072'.)110 e SfiT f,TMI'/'f.*TSS'f!i'D 2 0011:111100 bb fJ7 /1S/7e cs NOV MOV-CS-20AC ST-,'T C,P.1l7' SirT'/'Cf{fiS Sl':T f,TNTTS*1't::S'/'8/J 2 {l07131h01 bb
- J7 /15/7P. cs NOV MOV-CS-20AD Sfff [,I!f[1' S'dITCl/!IS 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 /17 /7f'. Cl/ /IT 07 /H/71! Cl/ /IT l'N/,8-CKTB W:V /11,/rR!I CllT::CKW CIJ/ili'!IN'I' 2 l!071fi1200 112 CllllCKl*."IJ C/Jf1'lifiN'l' 2 B071fl1201 b'i
- 07 /H/71.' Cll li1' l'NDP.-CKTb JIT/W /rf,Af/M
( 2-IA-C-2A COMPTIT~SSOR /JOE.'S NO'/' START IN AUTO CllP.CKlW c rncur*r 2 (10fi301ll00 215 0111*i11e IA CONT 2 eo1os1:in 2ll3 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 p.071q1320 7 07 /20/78 Cl/ /IT PND-10 crncurr s [/Jr.I TENl' 7'F:S1'EIJ SA1'
( CIHCUIT fl Wlo/ 'l'E:l*ll'ERATURF. 1'ES7'F.'IJ SA'/' 2 0071'!1321 6 07 /':.0/7('. Cll /IT l'N[, 10 CI/ICU l'l' 5 Wlr TF:Ml' 7'SS'l'l'.'D SAT 2 8071 <J1325 7 01120/n Cl/ HT PN[, 11 COMl'f,f,'TS/J EMP-C-EP/1-12 2 007051320 ~01 07 /'J.U /70 RS I'fo!P f.fTR 2-US-l'-2A DISC/Rl\CONN FOR MSCllS 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'}
1i;n Df.n' TO'I'AL
Maintenance of Safety Related Systems During Outage or Reduced Power Periods UNIT t/l Instrument Maintenance
I VE"IT=msr 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) m:rs1mv 1rr SYS C0111' /.ftlRKflO SUNl//l.llY /} MR TO'l'WNT.11 07/03/7P BR lf/S1' f,I-UR*-114 DtllJ TN/JTC/l.TWN**C/l.L-CllFICK ST::NSTNG [,[N /J/JTL.T /lf.'l't,'/l.Tr:R+C//TiCKlW XMTTU:R 1 {l0fi2~0l110 fi 07/05/7'(1 us INST l'I-1-tir.B INDIC/J1'f:S lQOO WS WllfiN 300WS /l.CTU/I. R81'I,/l.Cr::D OSCJ f,f,ATOR*-tl!Jl' 1 !l07050fi30 5 07/07/70 E:l'CR f1PL G13 OUT Of tlf,IGNMS.VT W/ D/Jl/K /JLIGNIW Wl'l'll n 5.2 1 B070fi01i00 1 07 /07 /7P. SPCR Ii PI N'l OUT OF tlLrGNNf,'NT 'ti/ U/l.f/K 11LTGN8/J IJ/Jl?TNG Pl' S. 2 1 B070fi0ti0l 1 07 /07 /78 E'l'CR Rl'L G3 OUT OF ALWN!IE'NT W/ D/l.Nl{ /J'[,T.NGc'D DIJlliflG Pf S. 2 1 !l070fi0fi02 1
/)f.Pf T01'11[,
lb I
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I
.I11
'11
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Maintenance of Safety Related Systems During Outage or Reduced Power Periods UHIT /12 Instrument Maintenance
DF:lT=TNST 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)
- lilTSF:f/VDT SYS CONl' MA//iil/O SU/.JMA/IY u MR 7'0'/'W.VT,11 07 /13/71) IC lNST 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 IJ7 /U/78 cs iNST 2-CS-GA-130A GAUtJf,' IMl'l\Ol'IW m:AIJTNG CllfiCf\1-:V S/11' 2 l'071?.C!IJ1q 2fi 01/D17 e cs TNS1' 2-CS-GA-131A GAUGfi: lfo/l'flOl'f,'fl flF:AIJlNG CllF.Cl<lW SA'/' 2 ~071'10020 21i 01121 /7e TA l'TPING l'CV-2'* Sfi AJH f,P.AK ON /,lNfi 'fO VA/,Vf:: llb'l'A.rurm m:n*n PACli 2 (1071101100 tiP 07 /'J.1 /'lf!. /:,'/'CR Iii'[ 010 NO r.*uv BOTTOM f,TG/17' ATJJ118'J'f,'V HOU UOT1'011 IJTS1'AlJLF. Sf~1'POIN 2 8071920;)0 22 01121ne IA VA/,VE REMF.F VAf,VF: Lf;111
ha Radloactivitv (a) Total Ri.!leased Curies 2.04E-5 (b) Avg. Concentration He leased pCi/ml .1. lUE-lJ
- 5. VoL of Li<Juid to Disch. Canal Liter*s 3.90E+7 I
- 6. Vol. of IJJ lutiOn \foter Liters l.85E+ll
7.52E-5 I-132 8 x JO G
- ---- ~
1-133 l x 10-*
- I-1311 2 x 1o-=* 1i
-:J.7lilF5
-~
I-135 4 x io-*
Cs-lJt, 9 x 10-T 3.JSE-2 Cs-136 6 x 10-*
Cs-137 2 x 10-,
8.27E-2 Cs-138 -
- Hli-88 - *
~
- ~-------'------------------*-**--- *-**-** -*-**
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 10CFR20 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 I
- 5. Total l'artlculate Gross Alpha ~
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 c .. -118 Co-58
1. 09E-5 j~SrH-
- ---:;-:-BE"=-~
Co-60 -~:4GE=q-H11-S!J 2.47E-5
.* Fc-59 *
- -- -- - ----- ... Hl>-~8 .. --- - .. ----- -*----*- o~*
... *-* .. -* -- .. **--* *--- ----* - - --- ---- .. --*--- --- ****- -----* - .. ---- ---a . - *---* --
f
'~
REPORT OF RADIOACl'IVE EFFLUENTS PAGE 3 FACILITY: Surry Power Station YEAR:_~l~9~7~B_ __
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 l.61E-7 1-132
- I-133 5.55E-8 1-135 *
(c) Cases Xe-133 ---:r:lbE+l Xe-133m 3.90E-6 Xe:-135 4.0BE-1 Kr-85m
- Kr-85 Kr-87 Kr-88 Ar-41 l.25E+U 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_lv_i_t~y____
- __ Cu r.i es (c) Date of Shipment and llarnwell, Dlsoositlou 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
...* I.* '**
- SENSITIVITY DATA
... , .. *l. Mini-num Detectable Activity
/ ' ... *~ ..
a~ Gross Alpha; 5.27E-9 µCi/ml
- b. Tritium; 4.0E~6 µCi/ml
- c. Strontium-89; less than 3.0E+l pCi per total filter composite.
- d. Strontium-90; less than 2.0E+-0 pCi per total filter composite.
- e. C02-14; less than 7.0E-10 µCi/ml.
- f. Strontium-89; less than 9.0E-9 µCi/ml.
- g. Strontium-90; less tha~ 8.0E-10 µCi/ml.
- 2.
- Multichannel Analyzer - GeLi
\
Ar-41 1. 6E-7 1~134 l.lE-7 .
I-132 l.OE-7 Na-24 l.7E-7 I-133 6.9E-8 I-135 4.5E-7 Kr-85 l.36E-5 Kr-88 5.SE-8 Kr-87 5.3E-8
- b. Radioiodines I-131 2.3E-6 I-133 3.lE-6 I-132 4. TE-6 I-134 4.8E-6 I-135 2.0E-5
(
.\-,
.. 1
.... _,)
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.