ML19095A381

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Submit Operating Report for Month of August 1978
ML19095A381
Person / Time
Site: Surry  Dominion icon.png
Issue date: 09/13/1978
From: Stallings C
Virginia Electric & Power Co (VEPCO)
To: Hartfield R
Office of Nuclear Reactor Regulation
References
Serial No. 319
Download: ML19095A381 (46)
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VIRGTNIA. RLECTRIC AND PowER CoMPA,N:Y~?. * *

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VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION MONTHLY OPERATING REPORT REPORT NO.

78-08 AUGUST, 1978 C)g.~

Superintendent-Station Operations APPROVED:

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7D MANAGER

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-i-cmrrn:r."'Ts Section Operating Data Report - Unit #1 Operating Data Report - Unit f/2 Unit Shutdowns and Power Reductions - Unit Ill Unit Shutdowns and Power Reductions - Unit ff 2 Load Reductions Due to Environmental Restrictions Unit Ill Load Reductions Due to Environmental Restrictions - Unit 112 Average Daily Unit Power Level - Unit #1 Average Daily Unit Power Level - Unit #2 Summary of Operating Experience Amendments to Facility License or Technical Specifications Facility Changes Requiring NRC Approval Facility Changes That Did Not Require NRC Approval Tests and Experiments Requiring NRC 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 lnservice Inspection Reportable Occurrences Pertaining to Any Outage or Power Reductions Maintenance of Safety Related Systems During Outage or Reduced Power Periods - Unit #1 - Mechanical Maintenance Maintenance of Safety Related Systems During Outage or Reduced Power Periods - Unit f,!2 - Mechanical Maintenance 1

2 3

4 5

6 7

8 9

11 12 12 14 14 15 16 17 18 21 22 23 24 25 27

1

-ii-Section Maintenance of Safety Related Systems During Outage or Reduced Power Periods - Unit #1 - Electrical Maintenance Maintenance of Safety Related Systems During Outage or Reduced Power Periods - Unit /)2 - Electrical Naintenance Maintenance of Safety Related Systems During Outage or Reduced Power Periods - Unit #1 - Instrument Maintenance Maintenance of Safety Related Systems During Outage or Reduced Power Periods - Unit /)2 -

Instrument 11aintenance Health Physics Summary Report of Effluent Release Data Sensitivity Data Procedure Deviations Reviewed by Station Nuclear Safety and Operating Committee After Time-Limi.t Specified in T. s.

29 31 33 35 37 38 41 42

,, 0PE RAT I JG.TA REPORT DOCKET NO. 50-280 DATE 05 SEP 78 COMPLETED BY O.J. COSTELLO TELEPHONE 804-357-3184 OPERATING STATUS

1. U NIJ' NAME
2. REPORTING PERIOD
3. LICENSED THERMAL POWER (MWT)
4. NAMEPLATE RATING (GROSS MWE)
5. DESIGN ELECTRICAL RATING (NET MWE)
6. MAXIMUM DEPENDABLE CAPACITY (GROSS ~WE)
7. MAXIMUM DEPENDABLE CAPACITY (NET MWE)
8. IF CHANGES OCCUR IN CAPACITY RATINGS (ITEMS 3 THROUGH 7) SINCE LAST REPORT, GIVE REASONS SURRY UNIT 1 0001 780801 -

2400 780831 2441,------------------------1 847.5 INOTES I

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I 77 5 I

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9. POWER LEVEL TO WHICH RESTRICTED, IF ARY N/A (NET Mf./E)
10. REASONS FOR RESTRICTIONS, IF ANY NIA
11.
12.
13.
14.
15.

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17.
18.
19.
20.
21.
22.
23.
24.

HOURS IN REPORTING PERIOD NUMBER OF HOURS REACTOR WAS CRITICAL REACTOR RESERVE SHUTDOWN HOURS HOURS GENERATOR ON-LINE UNIT RESERVE SHUTDOWN HOURS GROSS THERMAL ENERGY GENERATED (MWH)

GROSS ELECTRICAL ENERGY GENERATED (MWH)

NET ELECTRICAL ENERGY GENERATED (MWH)

UNIT SERVICE FACTOR UNIT AVAILABILITY FACTOR UNIT CAPACITY FACTOR (USING MDC NET)

UNIT CAPACITY FACTOR (USING DER NET)

UNIT FORCED OUTAGE RATE SHUTDOWNS.SCHEDULED OVER NEXT 6 MOIJHS (TYPE.DATE.AND DURATION OF EACH)

THIS MONTH YR-TO-DATE CUMULATIVE 744.0 5831.0 49895.0 736.1 4016.7 33333.6 o.o 0.0 0.0 733.0 3938.0 32503.2 o.o 0.0 0.0 1772814.0 9530217.0 74671213.0 558250.0 3121800.0 24481643.0 530078.0 2968434.0 23235998.0 98.5 olo 67,5 olo 65.1 olo 98,5 olo 67,5 o/o 65.1 olo 91.9 olo 65.7 o/o 60.1 olo 86.7 olo 61.9 olo 56.7 o/o 1.5 o/o 0.2 o/o 16.3 o/o SNUBBER INSPECTION 9/18/78-1 WEEK -

STEAM GENERATOR INSPECTION 1/9/79 -

6 wEEKS

25. IF SHUT DOWN AT END OF REPORT PERIOD, NIA ESTIMATE DATE OF STARTUP
26. UNITS IN TEST STATUS (PRIOR TO COMMERCIAL OPERATION)

INITIAL CRITICALITY INITIAL ELECTRICITY COMMERCIAL OPERATION FORECAST ACHIEVED

~ 0 PER AT ING.*

A REPORT DOCKET NO. 50-281 DATE 05 SEP 78 COMPLETED BY O.J. COSTELLO TELEPHONE 804-357-3184 OPERATING STATUS

1. UNIT NAME
2. REPORTING PERIOD
3. LICENSED THERMAL POWER (MWT)
4. NAMEPLATE RATING (GROSS MWE)
5. DESIGN ELECTRICAL RATING (NET MWE)
6. MAXIMUM DEPENDABLE CAPACITY (GROSS MWE)
7. MAXIMU~ DEPENDABLE CAPACITY (NET M~E).

B. IF CHANGES OCCUR IN CAPACITY RATINGS (ITEMS 3 THROUGH~) SINCE LAST REPORT. GIVE REASONS SURRY UNIT 2 0001 780801 -

2400 780831 2441 847.5 !NOTES I

822 I

I 811 I

I 775

'~---------------* _______ I NI A

9. POWER LEVEL TO WHICH RESTRICTED, IF ANY N/A (NET /.1WE)

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10. REASONS FOR RESTRICTIONS, IF ANY N/A
11. HOURS IN REPORTING PERIOD
12. NUMBER OF HOURS REACTOR WAS CRITICAL
13. REACTOR RESERVE SHUTDOWN HOURS
14. HOURS GENERATOR ON-LINE
15. UNIT RESERVE SHUTDOWN HOURS
16. GROSS THERMAL ENERGY GENERATED (MWH)
17. GROSS ELECTRICAL ENERGY GENERATED (MWH)
18. RET ELECTRICAL ENERGY GENERATED (MWH)
19. UNIT SERVICE FACTOR
20. UNIT AVAILABILITY FACTOR
21. UNIT CAPACITY FACTOR (USING MDC NET)

.22. UNIT CAPACITY FACTOR (USING DER NET)

23. UNIT FORCED OUTAGE RATE
24. SHUTDOWNS SCHEDULED OVER NEXT 6 MONTHS (TYPE,DATE,AND DURATION OF EACH)

THIS MONTH YR-TO-DATE CUMULATIVE 744.0 5831.0 46775.0 729.8 4590.4 31003.2 0.0 0.0 0.0 727.3.

4577.4 30506.3 0.0 0.0 0.0 1751893.0 11106576.0 70816810.0 553485.0 3592175.0 23159569.0 524109.0 3412120.0 21965237.0 97.8 o/o 78.5 o/o 65.2 o/o 97.8 o/o 78.5 o/o 65.2 o/o 90.9 o/o 75.5 o/o 60.6 o/o 85.7 o/o 71.2 o/o 57.1 o/o 0.0

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2.9 o/o 22.8 o/o SNUBBER INSPECTION 10/12/78-1 WEEK REFUELING 12/25/78-6 WEEKS

25. IF SHUT DOWN AT END OF REPORT PERIOD, N/A ESTIMATE DATE OF STARTUP
26. UNITS IN TEST STATUS (PRIOR TO COMMERCIAL OPERATION)

INITIAL CRITICALITY INITIAL ELECTRICITY COMMERCIAL OPERATION FORECAST ACHIEVED

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Date 78-2 780814 78-3 780814 78-4 7808:l'9 F: Forced S: Schtdulcd (IJ/77)

UNIT SHUTDOWNS AND POWER REPUCOONS REPORT MON*nr Aug. 1978 F

1.6 H

3 F

4.9 G

1 F

4.5 G

3 Reason:

A-Equipment Failure (Explain)

D-Maintcnance or Test

(-Refueling Licensee Even I Repott #

. D-Rcgulatory Reslrktlon E*Opcralor Training & License Examination F.J\\ ti mi 11 i~I rn I i*1c G-Opcral Iona I Error (Explain) 1 l*Olhcr (Explain) 3 Method:

I-Manual 2-Manual Scnim.

3-Aulomatic Scram.

4-0thcr (Explain)

(1)

(2)

DOCKET NO.

UNIT NAME DATE COMPLETED llY TELE( llONI!

50-280 Surry Unit 1 9-1-78 O. J. Costello (804) 357-3184 C:1usc & Con rel Ive

  • Ac.:11011 10 Prcvc111 Rec11rrcr11:e Electrical short caused by correc-tive maintenance on relay during lc;g:i_c testing, Opera tor. manually tripped unit.

(3) Turbine runback resulting.from spik~ on electric~l system and resultant over boration.

4 Exhibit G - Instructions for Prcp:iratlon of Dal:i Entry Sheets for Licensee Event Rcporl (LEIO filr (NUREG-D161l 5

Exhibit I - Sam~ S1111r~~

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Date 78_;.4 780801 78-5 780814 Q

F: Forced

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UNIT SHUTDOWNS AND POWER REPUCTIONS 4

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REPORT MONTI('. Aug. 197JL

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A-Equipment failure (Explain)

D-Maintenancc or Test f-Rcrucling Licensee Event Repotl #

78-029/03L-0

. D-Rcgulatory Restriction E-Opcr:itor Training & License Examinallun F-Ad min ist ra I i*1c G-Opcrational Errnr (Explain)

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OOCKETNO.

UNIT NAME IJi\\TE COMPLETED BY TELEt llONE

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50-281 Surry 2 9-1-78 O. J. Costello (804) 357-3184 *-

Cause&. Correcllvc Action lo Prevent Rcc11rrc11cc ECCS pump modification shutdown at start of month.

Unit Load*Reduced >,20% as a result of river water inlet temperl!lture greater than specification.

Unit. was not shut down *.

4 5

Exhibit G

  • Inst met Ions for Prcparnllon of Dat:i.

Entry Sh eels for Licensee Event Report (LERl File (NUREG-

. 0161)

Exhibit I

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  • ,, LOAD REDUCTIONS DUE TO ENVIRONMENTAL RESTRICTIONS UNIT NO. 1 MONTH: AUGUST, 1978
  • i DATE Til1E HOURS LOAD, MW REDUCTIONS 2 MW MWR REASON NONE DURUG THIS REPORTING Pl RIOD.

MONTHLY TOTAL 0

  • LOAD REDUCTIONS DUE TO ENVIRONMENTAL RESTRICTIONS UNIT NO. 2 MONTH: AUGUST, 1978

! I TIHE DATE HOURS LOAD, MW REDUCTIONSi MW MWH REASON I

I NONE DURJ NG THIS REPORTING 'ERIOD.

I MONTHLY TOTAL I 0

-- -- _[_ __ _

!:J.ON'[_fl:

AUGUST DAY 1

2 3

4 5

6 7

8 9

10 11 i2 13 14 15 16

    • 1978 AV~RAGE DAILY POWER LEVEL.

U.fllE-NET) 728.0 7 31. 8 726.1 7'3 4. 8 735.2 733.0 732.7 731. 8 731. 3 731.5 733.5 735.0 733.8 430.8 668.8 729.0 DAILY UNIT POWER LEVEL FORM INSTRUCTIONS DOCK.ET NO UNIT DATE COMPLETED BY AVERAGE DAY 17 18 19 20 21 22 23 24 25 26 27 28 29 30 31 so..:.2so SURRY I 9-1-78 0 J COSTELLO DAILY POWER (MWE-NET) 728~7 728.'+

728.6 723.9 732.5 730.4 73 1-L 1 727.3 73i+.O 732.5 733.0 730.'+

517.1 72'+.6 73lf.1 LEVEL ON THIS FORM. LIST THE AVERAGE DAILY UNIT POWER LEVEL IN MWE-NET FOR EACH DAY IN THE REPORTING MONTH. THESE FIGURES WILL BE USED TO PLOT A GRAPH FOR EACH REPORT-ING MONTH. NOTE THAT BY USING MAXIMUM DEPENDABLE CAPACITY FOR THE NET ELECTRICAL RATING OF THE UNIT, THERE MAY BE OCCASIONS WHEN THE DAILY AVERAGE POWER EXCEEDS THE 100 o/o LINE (OR THE RESTRICTED POWER LEVEL LINE). IN SUCH CASES, THE AVERAGE DAILY UNIT POWER OUTPUT SHEET SHOULD BE FOOTNOTED TO EXPLAIN THE APPARENT ANOMALY.

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AUGUST 1978 AVERAGE DAILY POWER LEVEL DAY (Mii'E-NET) 1 70.8 2

606.5 3

733.0 4

7*1a. 2 5

739,6 6

733.6 7

717.2 8

733.9 9

736.1 10 739.0 11 739.B 12 739.3 13 738.0 14 693.2 15 728.4 16 726.7 DAILY UNIT POWER LEVEL FORM INSTRUCTIONS DOCKET NO 50-281 UNIT SURRY II DATE 9-1-78 COMPLETED BY 0 J COSTELLO AVERAGE DAILY PO'dER DAY U1WE-NET) 17 722.7 18 725.6 19 727.2 20 726.5 21 727.6 22 729.6 23 729 1 24 732.1 25 728.3 26 7 31.1 27 735.7 28 730.0 29 730.3 30 733.9 31 735.0 LEVEL ON THIS FORM, LIST THE AVERAGE DAILY UNIT POWER LEVEL IN MWE-NET FOR EACH DAY IN THE REPORTING MONTH. THESE FIGURES WILL BE USED TO PLOT A GRAPH FOR EACH REPORT-ING MONTH. NOTE THAT BY USING MAXIMUM DEPENDABLE CAPACITY FOR THE NET ELECTRICAL RATING OF THE UNIT, THERE MAY BE OCCASIONS WHEN THE DAILY AVERAGE POWER EXCEEDS THE 100 °/ 0 LINE (OR THE RESTRICTED POWER LEVEL LINE). IN SUCH CASES, THE AVERAGE DAILY UNIT POWER OUTPUT SHEET SHOULD BE FOOTNOTED TO EXPLAIN THE APPARENT ANOMALY.

  • ' ~y OF OPERATING EXPERIENCE ~

AUGUST, 1978 Listed below in chronological sequence by unit is a summary of operating experiences for this month which required load reductions or resulted in sign-ificant non-load related incidents.

UNIT 1 August 1 This report period begins with the unit at 100% power.

August 10 -

At 2325 power was reduced to 90% to-perform Power Coefficient Testing (PT-28.12).

At 2355 the unit was returned to 100%.

August 14 -

At 1251 the reactor was automatically tripped during Protection Logic Testing.

At 1332 the reactor was taken critical and at 1425 the system was paralleled to the system.

At 1502 the turbine was manually tripped which resulted in an automatic reactor trip.

This trip was the result of operator error when he overreacted to an inappropriate aside comment regarding reactor trip.

The reactor startup was pro-hibited by service water temperature greater than 87°F until 1857, when the reactor was taken critical and at 1958 the turbine was paral-leled* to the syst~~. A power increase was begun.

At 2400 the unit was at 65% power.

August 15 -

At 0610 the unit was at 97% and for about 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> power was changed about 1% until the F0 surveillance allowed 100% power operatio~. At 1500 the reactor attiHned 100% power.

August 29 -

At 1100 a runback of the unit to 70% occurred from a spike on the

-~lectric Control $ystem.

The unit was stabilized and a recovery begun at 1105.

At 1140 with the unit at 94% approximately 200 gallons of borated water.was pumped in~o the RCS.

This was.the result of the emergency borate admission valve being inadvertently opened during.the first casualty.

This condition went unnoticed until a manual boration was attempted during the normal recovery.

The result of the boron addition was a rapid drop in average temperature and a reactor trip on Low RCS Pressure at 1227.

At 1545 the reactor was taken critical.

At 1657 the turbine was paralleled to the system *.

A load increase was begun.

At 2130 the unit was returned to 100%.

power.

August 31 -

This report ends with the unit at 100% power.

UNIT 2 August 1 August 2 This report period begins with the unit heating up as part of a normal recovery.

At 0515 the RCS was at hot shutdown condition and at 0655 PT-11 (Overpressure Test) was completed.

At 1410 the reactor was taken critical and at 1640 the turbine was paralleled to the system.

A power increase was begun.

At 2400 the unit was at 48% power.

At 1000 the unit was at 100% power.

UNIT 2

~ -1MARY OF OPERATING EXPERIENCE (CONTINUED)

August 14 -

At 1510 a rampdown was commenced due to river temperature greater than 87°F.

At 1830 the power was at 62% and a change to the river temperature specification was received via Telecon from NRG Licensing, a load increase was commenced.

At 2235 the unit was returned to 100%.

August 31 -

This report period ends with the unit at 100% power.

AMENDHENTS T.CILITY LICENSE OR TECHNICAL SP-FICATIONS AUGUST, 1978 On August 14, 1978, the Nuclear Regulatory Commission issued Amendments No. 43 and 42 to the Operating License for the Surry Power Station Unit Nos. 1 and 2.

This amendment which specifies license conditions results from our request to operate with a service water temperature above 87°F.

These interim conditions will ensure adequate net positive suction head to the recirculation spray and.low head safety injection pumps, in the event of a loss of coolant accident.

Of sig-nificance, the staff has imposed the following limitations:

1.
2.

The facility shall be operated within the following limits:

Maximum Service Water Temperature Containment Temperature Allowable Range Containment Air Partial Maximum Pressu:re For Service Water Temperature :5._87°F For Service Water Temperature >87° Minimum Refueling Water Storage Tank Volume Outside Recirculation Spray Pump Flow Rate 90°F 100°F 125°F Air partial pressure shall be m~intained in accordance with Figure 3cF.2 Air partial pressure shall be maintained in accordance with Figure 3.F.1 385,200 gallons 2250 gpm

  • ' 9£AcILITY CHANGES REQUIRING NRC APPROVAL AUGUST, 1978 There were none during this reporting period.

Design Change FACILITY.CHANGES THAT DID NOT REQUIRE NRC APPROVAL AUGUST, 1978 Unit

1.

DC-78-Sl6 - Auxiliary Building Ventilation Test Holes 1,2 Description - Forty-nine (49) instrument test holes were in-stalled to permit the use of portable test equipment to measure air velocity and static pressure during the design, testing, and operational stages of NRC imposed modifications.

Summary of Safety Evaluation This change to the Auxiliary Building Ventilation System will have no effect on station operations or the functioning of safety related equipment since the original design basis criteria are maintained.

Conclusion This design change does not constitute an unreviewed safety question.

2.

DC-78 Telephone Computer Room Ventilation N/A Description - With the replacement of the PBX telephone system by the ROLM system which utilizes two computers, a need for im-proved ventilation was created.

This design change encompassed directing the flow of cooled air from a nearby duct into this space lowering the temperature approximately 15°F.

Summary of Safety Evaluation All work involved with this design change was non-safety related.

3.

DC-78 Emergency Diesel Generators 1,2 Description - Pressure control switches were so mounted that vibration was causing premature failure.

To rectify this the switches were removed from the base plate and relocated on an adjacent cement wall.

Summary of Safety Evaluation This design change in no way affected the operation of the Emergency Diesel Generators and as such was considered non-safety related.

Design Change FACILITY CHANGES THAT DID NOT REQUIRE NRC APPROVAL (CONTINUED)

AUGUST, 1978 Unit

4.

DC-78-S23 Snubbers - LHSI, *Feedwater, and Steam Generator 2

Blowdown System Descriution -

LHSI snubber was discovered to be fully extended during an inspection.

To enable this snubber to have free travel, two one inch shim plates were installed between the pipe attachment and the suppressor.

A feedwater system snubber Mas found fully contracted during cold shutdown conditions.

To assure no undue stresses were imposed the rod end was changed from a 4 inch to a 2 inch attachment assur-ing proper_ functioning during all phases of operation.

To correct deficiencies noted in the steam generator blowdown system one guide, two lateral/vertical restraints, and one strut were installed.

Summary of Safety Evaluation This modification which supports a pipe stress review does not increase the probability of. occurrence or the consequences of an accident previously postulated.It does not increase the possiblity for an accident or malfunction of a different type from those eval-uated and the margin of safety defined in Technical Specifi~ations is not reduced.

Conclusion This design change does not constitute an unreviewed safety question

5.

DC-78-S24 Fire Protection Piping System-Personnel Change Decontamination.Building Description - This fire protection piping was installed to service *the new Personnel Change and Decontamination Building.

The seismic criteria of the original piping was met* and is in accordance with NFPA and Class 1 earthquake criteria.

Summary of Safety Evaluation The installation of this fire protection piping does not increase the probability of occurrence or the consequences of an accident of equipment important to safety which was previously evaluated, create the possibility for an accident or malfunction of a different type than previously addressed, or reduce the margin of safety as defined in Technical Specifications.

Conclusion This design change does not c~eate an unreviewed safety question.

1,2

,. -STS AND EXPERIMENTS REQUIRING &

NRG AP PROV.AL AUGUST, 1978 There were none during this reporing period.

J TESTS Ah"D EXPERIMENTS THAT DID NOT REQUIRE NRG APPROVAL AUGUST, 1978 There were none during this reporting period.

)' 0T~ CHANGES, TESTS Al\\TD EXPERIMEN~

AUGUST, 1978 There were none during this reporting period.

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  • SURRY POWER STATION CHEHISTRY REPORT
AUGUST, 19 78 T.S.6.6.A.ll PRIMARY COOLA.i.~T UNIT NO. l UNIT NO.

ANALYSIS I

MAXIM:UH MINIMUM AVERAGE MAXIMUM MINIMUM Gross Radioact., µCi/ml.1 3.67E-l I 1. 68E-l 2.63E-l 2.39E-l l.21E-l Suspended Solids, ppm 0.2 0.1 0.1 0.2 0.1 Gross.Tritium, µCi/ml 2.02E-l l.35E-l l.61E-l

1. 85E-l 3.04E-2 Iodine-131, µCi/ml 2.58E-2
9. 48E-4 3.09E-3 4.88E-4 l.41E-4 I-131/1-133 0.1943
o. 0677 0.1434 0.1659 0.0298 Hydrogen, cc/kg 49ol 26.9 38.8 47.8 11.3 Lithium, ppm 2.68 2.10 2.38 0.95 0.53 Boron-10, ppm +

169.3 149.7 155.4 217.6 55.7 Oxygen-16, ppm 0.000 0.000 0.000 a.oao o.aaa Chloride, ppm a.a5 0.05 a.as o.as 0.05 pH @ 25°C 7.03 6.75 6.91 7.15 6.59

+ Boron-la = Total Boron x 0.196 Phosphate Sulfate saz NaOH o.o 278 350 NON-RADIOACTIVE CHEMICAL RELEASES, POUNDS T.S. 4.13.A.8 Boron 65a Chromate __

o-'-._o_a,s _____ _

Chlorine --=0-=-*..;;..0 _____ _

2 AVERAGE l.67E-l 0.1 l.07E-l 3.08E-4 0.0871 30.l 0.83 67.4 o.oaa o.as 7.a2 CRIPTION OF ALL INSTANCES WHE TH DISCHARGE LIMITS WERE EXCEE AUGUST, 1978 On August 14, 1978 and August 29, 1978, Unit 1 tripped resulting in a change in river temperature greater than 3°F/hr.

Due to impairment to the circulating water system on the following days the thermal discharge limits were exceeded as noted.

August 2, 1978 Exceeded 15°F /lT across station August 3, 1978 Exceeded 17.5°F /lT across station August 4, 1978 Exceeded 17.5°F /lT across station August 5, 1978 Exceeded 15°F bT across station August 6, 1978 Exceeded 15°F 6,T across station August 7, 1978 Exceeded 15°F 6.T across stat.ion August 8, 1978 Exceeded 15°F 6.T across station August 9, 1978 Exceeded 15°F 6.T across station August 10, 1978 Exceeded 15°F /lT across station August 11, 1978 Exceeded 15°F /lT across st.a:tion August 12, 1978 Exceeded 15°F /:..T across station August 13, 1978 Exceeded 15°F l::,T across station August 14' 1978 Exceeded 15°F b.T across station August 15, 1978 Exceeded 15°F /lT across station August 16, 1978 Exceeded 15°F /lT across station August 16, 1978 Exceeded 103°F at groin August 17, 1978 Exceeded 15 °F t:r across station August 17, 1978 Exceeded 103°F at groin August 18, 1978 Exceeded 15°F f..T across station August 18, 1978 Exceeded 103°F at groin August 19, 1978 Exceeded 15°F /lT across station August 19, 1978 Exceeded 103°F at groin August 20, 1978 Exceeded 15°F /lT across station August 20, 1978 Exceeded 103°F at groin August 21, 1978 Exceeded l5°F f..T across station August 22, 1978 Exceeded 15°F 6.T across station August 23, 1978 Exceeded 15°F l:iT across station August 24, 1978 Exceeded 15°F /lT across station August 25, 1978 Exceeded 15°F /lT across station August 26, 1978 Exceeded 15°F /lT across station August 27, 1978 Exceeded 15°F /lT across station August 28, 1978 Exceeded l5°F /lT across station August 29, 1978 Exceeded 17.5°F /lT across station August 30, 1978 Exceeded 15°F /lT across station August 31, 1978 Exceeded 15°F /lT across station These /lT excursions as well as the high discharge.temperatures were allowable under Technical Specifications 4.14.B.1 or 2.

There were no reported instances of significant adverse environmental impact.

FUEL HANDLING AUGUST, 1978 On 08-29-78 an audit was conducted of the fuel assembly annual account-ability audit of our SNM accountability records and procedures.

No significant discrepancies were discovered during this audit.

No fuel handling was done during this month.

DATE SHIPPED/RECEIVED I

I I

I l

I I

NO OF UNIT /fl FUEL ::_~umLING AUGUST, 1978

! i ANSI HO.

ASSEMBLIES PER SHIPMENT I

INITIAL ENRICID1ENT I

I

! I I

I I

NONE DURiNG THIS REPORTING PERIODj I

I I I

  • 1 I

I

  • ~ '

I I

I I

I NEW OR SPE~iT FUEL SHIPPING CASK ACTIVITY LE~

~

SHIPPED/RECEIVED

\\

l.l,r--

UNIT if L FUEL HANDLING AUGUST, 1978 ANSI NO.

NO OF ASSEMBLIES PER SHIPMENT INITIAL ENRICH11ENT 1--l'EW OR SPENT FUEL SHIPPING CASK ACTIVITY LEVEL NONE Dl RING THIS REPORTING PERI< n.

I

~!

PR~URE REVISIONS THAT CHANGED THiii OPERATING MODE DESCRIBED IN THE FSAR AUGUST, 1978 There were none during this reporting period.

DESC ION OF PERIODIC TESTS WHICH WE MPLETED WITHIN THE TIME LIMITS SPECIFIED IN TECHNICAL SPECIFICATIONS.

AUGUST, 1978 The following Periodic Tests were not completed within the time liLJ.its specified in the Technical Specifications.

PT-14.1 PT-24.2 Main Steam Line Trip Valve 3° stroke was not completed on Unit 1.

See Licensee Event Report 78-027-03-L-0.for further information.

High Pressure C02 System was not completed on scheduled date for Unit 1.

See Station Deviation 78-116 for more information.

PT-28.4 The T+480 axial flux distribution surveillance for Unit 2, was inadvertantly missed on 08-15-78.

This was the last in the transient series which began at 2140 hours0.0248 days <br />0.594 hours <br />0.00354 weeks <br />8.1427e-4 months <br /> on 08-14-78.

A scheduled Fq Surveillance was performed satisfactorily 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> and 20 minutes after this PT was missed *.

PT-49 On August 31, 1978, it was discovered.that a census of animals producing milk for human consumption, required per Technical Specification 4.9.2F at the beginning and at the middle of the grazing season, was not performed.

Until August, 1978

!,
*/:there was no procedure for conducting such a census, however, a procedure to perform the census now exists and will be utilized.

.. INSERVICE INSPECTION AUGUST, 1978 NONE DURING THIS REPORTING PERIOD.

\\

,. R~TABLE OCCURRENCES PERTAINING ~

A1TY OUTAGE OR POWER REDUCTIONS AUGUST, 1978 There were no reportable occurrences pertaining to any outage or power reductions for the month of August.

Maintenance of Safety Related Systems During Outage or Reduced.Power*Periods UNIT Ill Mechanical Maintenance

11/*:7'.<:lifi\\' ll'T' SYS C0/11' 011/1'1/'ln CV on/1 111711 cv on/n/7n 1m

/J/W/' 1'0T/ll, 1'111*11' V/l/,VE V J1r,VE UNIT 1 llUGIJST H7R 1 N/11 N1'TmllrVCl*: OF SAFr:TY RF.f,ATED SYS7'F./.IS DURING O/JTAr.F. OR ll/WUCT!:D l'OWETI l'f:T!lO/J.J)

MA/1KNO 1-CV-l'-1/1.

1-CV-21l 1-nR-20:1 S/Jf.INARY DOF,S NOT l'CJMT' C/ll':CK AND RF.Pf,ACED JF NF.lWF.D V 11f,V E DODY LEllKlNG lrKl'l~/IF vo.m Rli'Pf.ACEIJ Dl/l.Pf/RllGN REN!i:WED v 111,vr. nONNf;T1'+Dl lll'llR/J(;M

.. **-* **---*.. ****-- ****----**----**** -~. -,,... *-****--*-*-**---- **--** *- *---*-- -**

1 :mr* 111 * :12: 11A 1w 1w;r-: 2

//

NII 7'07'/MNTM 1

A0771ll'.l15 t

ROR120110 t

non2 111n:10 0

sr; 17

'15

)

I

~ )

I Maintenance of Safety Related Systems During Outage or Reduced Power.Periods UNIT {/2 Mechanical: 'Maintenance

\\..

j CJF:f1'~,11F.CT/

RP.TSF.TIVV1' SYS CONT' on/01/7n CTI on/Ol/'fn sz

/JF.r'T' 7'0'/'/il, l'lPlNG V /IT.VF,'

  • 1 UNIT 2*AUGUST 1q7R -

CMAlNTf.'NANCE OF SAnrrr RliLATFW SYSTEMS DURING OUTAGF: OR REIJUCFID l'OIJER PERIODS)

HARKNO 2-CTl-P-W 2-SI-R?.

SUMMARY

fJKl'F.RP

. VOW sr-:r* 1n

  • 12:52 l'M I'M!': 2

(/

rm 1*o*nxvN1*11 2

IJ071'l17'16 2

R0'7271020 113 0

  • 13 I NI OJ I

., Maintenance of Safety.Related Systems During Outage*or*Reduced Power Periods UNIT /11 Electrical Maintenance Electrical Maintenance Unit Ill There was none during this reporting period.

,. Maintenance of Safety Related Systems During Outage or Reduced Power Periods UNIT //2 Electrical Maintenance

~ Electrical Maintenance Unit #2 There was.none during this reporting period.

Maintenance of Safety Related Systems During Outage or.Reduced Power Periods UNIT f/l Instrument Maintenance

.. Instrument Maintenance Unit ill There was none during this reporting period.

  • " Maintenance of Safety Related Systems During Outage or Reduced Power.Periods UNIT /!2 Instrument Maintenance
i. :

I

. I J

I RF.TSF:RV/l1' SYS COM1' on/0117n Cl/

lNST 1Jfi/01/1n RC ii AT.Vt mwr rorM, 1 ::,.;p 7R

  • 1?.: 52 /'M 1'AGF. 1 UNIT 2-AUGUST 197R (MAlNTF.'NANCf. OF SMf:TY mnATEIJ SJSTf.NS DURING OUTAGE OR REDUCTW l'OWllR Pf.'RlOTJS)

MARI< NO SUNN/I.RY Wl<f'SRP Tl Nfl 1'0'T'/ll{N1'M Pl-2151 C/l.LIDRATR 011 T?El'C.ACE /l.S NF.CESS/l.R'i CALIDRATF.D G/l.UGF.

?.

no12s11100 9r,

/'Cil-:2'155/i vor.s uooUtAtP. Pnorentr Cl/RCK@ S1'liO'KF.+STARTJNG l'O.JNT-SAT 2

non101s 1l 1!i 112

... **-* ----*----**-*** --**----**-*h<-*--** -... *-**...,. --* -* -.!. *-----

............. -... -~

I w C]\\

I HEALTH PHYSICS AUGUST, '1978 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.

.:.~

sza n>i e;u s*:.m** P  :!& o; a* r

  • --*. --*-"~-*-... *--*-**---*--*- *~.

REPOR'r OF RAllIOACTIVE EFFLUENTS PAGE 1 Facility:

Surry Power Station DOCKET:

50-280 and 50-281 YEAR: 1978

=*

~

I.

LI<lUlll RELEASES

,-**ffin:TS JULY AUGUST H

l.

Gross Rad1oac£_Jvi t):'. <ilr2 H

(a)

Total Release Curies l.99E-l 2.0SE-1 (b)

Avg." Concentration Released pCi/ml l.07E-9 B. 78E-10 (c)

Maximum Concentt*ation Released

µCi/ml l.95E-9

1. 4 7E-9
2.

Tri t1 urn (a)

Total Released Curies l.13E+2 l.41E+l (b)

Av!l. Concentration Released pCi/ml b.llE-7 6.04E-8

3.

Dissolved Noh le G1wes (u)

'l'otul Ile lease Curies 4.17E-2

1. 39E-l (li 2 Avg. Concentration Released

µCi./ ml

-Z.-:!51'-.1.U 5.95E-10

4.

Gross Alpha lladiouctivit):'.

(a)

Total Released Curies 2.04E-5 4.36E-6 (b~

Avg. Cone en t ration Released jiCi/ml l.lOE 1.86E-14

5.

Vol. of Liquid to Disch. Canal Liters 3.90E+7 3.64E+7 I

6.

Vol. of D llution Water J.:lters l.85E+ll 2.34E+ll w

CX)

7.

1:rntopes Released H~1Ci/ml Curies I

I-131 3 x 10-7.52E-5 6.08E-4 I-132 8 x 10 6 1-133

] x io-6 r.*tt7E-'l\\

I-1311 2 x 10 *

'I<

I-135 4 x 10-*

J,/4E-!>

Cs-134 9 x 10"-'"C" 3.lSE-2 L64E-1 C,;-136 6 x 10-5 Cs-137 2 x 10,

B.27E-2

z. lJE.. l Cs-138 Co-57 4 x 10--

3.95E-4

  • 4.03E-5 Co-58 9 x Jo-*

5.33E-l l,54E-l Co-60 3 x JQ-5 3.62E-l l.llE-1 Mn-54 1 x io-11 1.05E-2

  • 4.21E-3 Na-211 3 x }Q-o
7. 74E-4 3.69E-2 Cr-51 2 x 10- 3 4.13E-2 3.18£-3 Fe-59 5 x 10->

l1.l14E-4 Nb-95 1 x ]Q-11 6.l3E-3 3.68E-4 lla-I.a-ll1U 2 x 10-s 3.T4E....:5 Rb-88

REPORT OF RAIHOACTIVE EFFLUENTS PAGE 2 FACILITY:

Surry l'ower Station DOCKET: 50-280 and 50-281 YEAR:

1978

~

-1 I.

LIQUID REI.EASES (CON'T)

-~

" -ca I ml

" ll!!!1'S JU)'.,Y AU.GVSL.

..TOTA}._

+/- Egor_

].

Isotopes Heleased uMl'C C:11ries Ce-141 9 x 10-"

Ce-ll14 l" x 10-"

2.79E-4 Xe-133 3 x lO-"

Z.28E-2 4.96E-2 Xe-135 3 x io- 0 4.09E-3 l.93E-2 AL"-41 3 x io-"

6.56E-5 l.40E-4 Sr-89 3 x 10-0 Sr-90 3 x 10-C-14 8 x io-*

B.

Percent of 10CFR20 Percent l.90E-2 3.74E-2

11.

AI!(JlOHNE REI.EASES

1.

'J'otal Noble GaseH Curies 3.92E+l l.41E+l

2.

Total Halogens Cnries 2.16E-7 2.79E-5 3,

Total Particulate Gross Radio-activit):'. ((3y)

Curies 2.BOE-3

5. 71E-5 T

Total Tritium Curies l.63E+l 2a34E+l 5,

Total Particulate Gross Alpha Rudioactivl.t:z:

Curies 2.91E-5 3.71E-6

6.

Maximum Noble Gas Release Rate pClLsec l.06E+3 l..?9E+l

7.

Percent of Appllcable Limit for Technlcal Speciflcations

{a2 Noble Gus es l'ercent 2.99E-2 1.17E-2 (b)

Ila lo gens Percent l.80E-6 2.99E-6 (c)

Particn]ates Percent 6.93E-2 6.07E-4

8.

Isotopes Released:

Curles (a)

Particulutes Cs-1311 2.40E-6 l.OlE-10 Cs-135 Cs-137 l.09E-5 4.47E-6 Cs-138

'.l. Z1SE-S 2.llE-5 Co-58

.J *.l\\IE-3 3.74E-5 Co-60 9":?ibTI::q-l.23E-5 Mn-st, 2.47E-5

,~

Fe-59 mi.::-Uii

-~.;.;;.:...o::.----.. -*--**.--**-

~-***--* ***- -** -***------*-*-

I w I

FACILITY:

Surry Power Station II.

AlRllORNE RELEASES (CON'T)

~ _. ----***--...

8.

Isotopes Released (con't)

III.

1.

(b)

Ila lo gens I-133 I-134 I-135

( c)

Gases Xe-133 Xe-133111 Xe-135 Kr-85m Kr-85 Kr-87 Kr-88 Ar-41 SOLID RADIOACTIVE WASTE DISPOSAL (u)

Total Amount Solid Waste Packaged (b)

Estimated Total Activity (c)

Date of Shipment and Disoosition

---**---"-----~-----;.. ___ _,_-...: __

Rl~l'ORT 01~ RADIOACTIVE JffFLUENTS DOCKET; 50-280 and 50-281

.!J!llTS

_. JUT"Y Curies 1.61E-7 5.55E-8 3.76E+l 3,90E-6 4.08E 1 l.2::>i;-ru FT 3

.3.25E+3 Curles

~.l~E+l

Barnwell, 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 7-31-78

-* AJlGUS'J:_.

2.67E-5 l.15E-6 l.21E+l

1. 72E+O 9.14E-2 9.44E-4 3.'09E+J 9.23E+O
Barnwell, s.c.

8-2-78 8-li-78 8-7-78 8-15-78 8-25-78 PAGE 3 YEAR: _ _.).""'9'"'"7;.8 ___ _

I f

~ '). ~,\\

\\

.c

.---'I,,

  • .. *_)
l.

}f.i.::i.i=!-..:::J. Detectaole Activity

~.

Gross Alpha; 5.27E-9

µCi/!J.l

b.

Tritium.; 4.0E-6 µCf/ml

c.

Stronti~89; less than 3.0E+l pCi per total

d.

Stronti~90; less than 2:0E+o pCi per total

e.

co,-14; less than 7.0E-10 µCi/ml.

=*

St;onti~89; less than 9.0E-9 µCi/ml..

g.

St=ont:ium-90; less than 8.0E-10 µC:L/ml.

2.
  • Hult:ich.a.nne.l.Analyzer -

GeLi

a.

Liouid. and/ or R.adiogases -

lOOcc

b.

Ba-La-140 I-1.31 Xe-133 Xe-135 Cs-137 Cs-l34 Co-60

.Co-58 Cr-51 Mn-54 Fe-59 Ar-41 I".""'134

. I-132..

Na-24 I-133 I-135.

Kr-85 Kr-88 KI-87 *..

  • Xe-135m Xe-133m llli-88 Rzdioiodines.

I-131.

I-133 I-132 I-1.34 I-135 2.. 0E-7 5.lE-8 5.4E-8 2.9E-8 9.2E-8 7.2E-8 1.5E-7 9.. SE-8 3.8E-7 l.OE-7 2.4E-7 1.6E-7

.l.lE-7 :;..

1.0E-7 l.7E-7 6.9E-:-8

5.SE-8 5.3E-8 2.3E-7*

. 4. 7£-9

    • 2.:3E-6 3.. lE-6.-
4. 7B-6.

4.. SE-:6 2.0E-5 filter CO~?OS~=e.

filter conpos:Lte.

~.:.. *:::. *.. : '

~...

~ :.;.** ~,...~.. *..

  • ./*,*-::.
-
:~.;..

"'.; ~~:.

~-

_;=-*.... *. ~.... *.

".... PROCEDU~EVIATIONS REVIEWED BY STATION ~LEAR SAFETY AND OPERATING COMMITTEE AFTER TIME LH1ITS SPECIFIED' IN TEC!Il~ICAL SPECIFICATIONS AUGUST, 1978 There were none during this reporting period.

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