ML19105A303
| ML19105A303 | |
| Person / Time | |
|---|---|
| Site: | Surry  |
| 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: ML19105A303 (46) | |
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VIRGINIA ELECTRIC AND POWER COMPANY RICHHOND,VIlilGI::iiIA 23261 ~, l. A. ~ f Uld. &6!1~ 1'1Nat~~ lod..&1 U.. }li
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~) VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION MONTHLY OPERATING REPORT REPORT NO. 78-08 AUGUST, 1978 C)&;..~ Superintendent-Station Operations APPROVED: 15~ I MANAGER
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'I.'. Sectlon Operating Data Report - Unit f.!l 1 Operating Data Report - Unit t/2 2 Unit Shutdowns and Power Reductions - Unit lfl 3 Unit Shutdowns and Power Reductions - Unit 112 4 Load Reductions Due to Environmental Restrictions - Unit #1 5 Load Reductions Due to Environmental Restrictions Unit /12 6 Average Daily Unit Power Level - Unit #1 7 Average Daily Unit Power Level - Unit #2 8 Summary of Operating Experience 9 Amendments to Facility License or Technical Specifications 11 Facility Changes Requiring NRG Approval 12 Facility Changes That Did Not Require NRC Approval 12 Tests and Experiments Requiring NRG Approval 14 Tests and Experiments That Did Not Require NRG ~pproval 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 24 Reductions Maintenance of Safety Related Systems During Outage or Reduced 25 Power Periods - Unit #1 - Mechanical Maintenance Maintenance of Safety Related Systems During Outage or Reduced 27 Power Periods - Unit /.12 - Mechanical Maintenance
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~iaintenance of Safety Related Systems During Outage or Reduced 29 Power Periods - Unit #1 - Electrical Maintenance Maintenance of Safety Related Systems During Outage or Reduced 31 Power Periods - Unit fJ2 - Electrical Naintenance Maintenance of Safety Related Systems During Outage or Reduced 33 Power Periods - Unit #1 - Instrument Maintenance Maintenance of Safety Related Systems During Outage or Reduced 35 Power Periods - Unit f.12 - Instrument 11aintenance Health Physics Summary 37 Report of Effluent Release Data 38 Sensitivity Data 41 Procedure Deviations Reviewed by Station Nuclear Safety and 42 Operating Committee After Time~ Limi.t Specified in T. S.
0PE.r::AT IJG-TA REPORT DOCKET NO. 50-280 DATE 05 SEP 78 COMPLETED BY O.J. COSTELLO TELEPHONE 804-357-3184 OPERATING STATUS
- 1. Ul,'IT NAN? SUP.RY U!iIT 1
- 2. RE?O?.TING FEP.IOD 0001 780801 - 2400 780831
~. LICENSED TaERMAL PO¥ER (MWT) 2441 1------------------------1
- 4. NA~EPLATE RATING (GROSS MWE) 847.5 !NOTES i
~. DESIGN ELECTRICAL RATING (NET MWE) 822 i I 6, MAXIMUM DEPENDABLE CAPACITY (GROSS AWE) 811 I I
- 7. MAXIMUM DEPENDA3LS CAPACITY (NET MWE) 77 S [ _ _ _ _ _ _ _ _ _ _:_______ I
- 8. IF CHANGES OCCUR IN CAPACITY RATINGS NIA (ITEMS 3 THROUGH.7) SINCE LAST REPORT, GIVE REASONS
- 9. POWER LEVEL TO WHICH RESTRICTED, IF ANY N/A (NET Mi./E)
- 10. REASONS FOR RESTRICTIONS, IF ANY N/A THIS MONTH YR-TO-DATE CUMULATIVE
- 11. HOURS IN REPORTING PERIOD 7~4.0 5831.D 49895.0
- 12. llUMBER OF HOURS REACTOR WAS CRITICAL 736.1 4016.7 33333.6
- 13. REACTOR RESERVE SHUTDOWN HOURS 0.0 0.0 0.0
- 14. HOURS GENERATOR ON-LINE 733.0 3938.0 32503.2
- 15. UYIT RESERVE SHUTDOWN HOURS 0.0 0.0 0.0
- 16. GROSS THERMAL ENERGY GENERATED (MWH) 1772814.0 9530217.0 74671213.0
- 17. GROSS ELECTRICAL ENERGY GENERATED (MWH) 558250.0 3121800.0 24481643.D
- 18. NET ELECTRICAL ENERGY GENERATED (MWH) 530078.0 2968434.0 23235998,0
- 19. UNIT SERVICE FACTOR 98,5 o/o 67.5 olo 65.1 o/o
- 20. UNIT AVAILABILITY FACTOR 98,5 o/o 67.S o/o 65.1 olo
- 21. UNIT CAPACITY FACTOR (USING MDC NET) 91.9 olo 65.7 olo 60.1 o/o
- 22. UNIT CAPACITY FACTOR (USING DER NET) 86.7 olo 61.9 olo 56,7 o/o
- 23. UNIT FORCED OUTAGE RATE 1,5 olo 0.2 olo 16,3 o/o
- 24. SHUTDOWNS.SCHEDULED OVER NEXT 6 MOKfHS SNUBBER INSPECTION 9118/78-(TYPE,DATE,AND DURATION OF EACH) 1 WEEK - STEAM GENERATOR INSPECTION 1/9/79 - 6 WEEKS
- 25. IF SHUT DOWN AT END OF REPORT PERIOD, NIA ESTINATE DATE OF STARTUP 26, UNITS IN TEST STATUS FORECAST ACHIEVED (PRIOR TO COMM~RCIAL OPERATION)
INITIAL C~ITICALITY INITIAL ELECTRICITY COMMERCIAL OPERATION
,. OPERATING ~A REPORT e DOCKET NO. 50-281 DATE 05 SEP 78 COMPLETED BY O.J. COSTELLO TELEPHONE 80~-357-318~
O?ERATING STATUS
- 1. UNIT NAl1E SURRY UNIT 2
- 2. REPORTING PERIOD 0001 780801 - 2~00 ?80831
~. LICEKSED THERMAL POWER (MWT) 2~~1 ,------------------------1 ~. NA~E?LATE RATING (GROSS MWE) 847.5 !NOTES I S. DESIGN ELECTRICAL EATING (NET MWE) s2 2 I I
- 6. MAXIMUM DEPENDABLE CAPACITY (GROSS MWE) s11 I I I
- 7.
8.
/.i!:XI!.Wf.~ DEPENDAELE CAPACITY (NET !1w'E).
IF CHANGES OCCUR IN CAPACITY RATINGS 775 NIA ~-------------~------' 1 (ITEMS 3 THROUGH 7) SINCE LAST REPORT, GIVE REASONS
- 9. POWER LEVEL TO WHICH RESTRICTED, IF ANY N/A (NET !.JWE) I
- 10. REASONS FOR RESTRICTIONS, IF ANY N/A THIS MONTH YR-TO-DATE CUMULATIVE
- 11. HOURS IN REPORTING PERIOD 744.0 5831.0 46775.0
- 12. NUUBER OF HOURS REACTOR WAS CRITICAL 729.8 l.i-590.4 31003.2
- 13. REACTOR RESERVE SHUTDOWN HOURS 0.0 0. 0 0.0 HOURS GENERATOR ON-LINE 727.3 4577.4 30506.3
- 15. UNIT RESERVE SHUTDOWN HOURS 0.0 0. 0 0.0
- 16. GROSS THERMAL ENERGY GENERATED (MWH) 1751893.0 11106576.0 ?0816810.0
- 17. GROSS ELECTRICAL ENERGY GENERATED (MWH) 553485.0 3592175.0 23159569.0
- 18. NET ELECTRICAL ENERGY GENERATED (MWH) 524109.0 3412120.0 21965237.0
- 19. UNIT SERVICE FACTOR 9 7. 8 o/o 78.5 o/o 65.2 o/o
- 20. UNIT AVAILABILITY FACTOR 97.8 o / o 78.5 o/o 65.2 o / a
- 21. UNIT CAPACITY FACTOR (USING MDC NET) 90.9 o/o 7 5. 5 o/o 60.6 o/o
- 22. UNIT CAPACITY FACTOR (USING DER NET) 8 5. 7 o/o 71. 2 o/o 5 7 .1 o/o
- 23. UNIT FORCED OUTAGE RATE 0. 0 .- 2. 9 o/o 22.8 o/o 2 !.j.. SHUTDOWNS SCHEDULED OVER NEXT 6 MONTHS SNUBBER INSPECTION 10/12i78-(TYPE,DATE,AND DURATION OF EACH) 1 WEEK REFUcLING 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 FORECAST ACHIEVED (PRIOR TO COMMZRCIAL OPERATION)
IllITIAL CRITICALITY INITIAL ELECTRICITY COMMERCIAL OPERATION
50-280 l>OCKET NO. UNIT SHUTDOWNS AND rowEn REPUCTlONS UNIT NAME Surry Unit I DATE 9-1-/8 COW'LETEI> IIY 0. J. Costello REPORT MoN*nr Aug. 1978 TELEI JIONE (804) 357-3184. 1...... I "L ...c:: -
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.. (1) Electrical short caused by correc-78-2 780814 F 1.6 H 3 78-3 780814 F 4.9 G 1 tlve maintenance on relay durlng log:ic testing.
(2) Operator. manually tripped unit. e 78-l, 780819 F ,l. 5 G 3 (3) Turbine nm back resulting.from
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50-281 DOCKET NO. UNIT SHUTDOWNS AND POWER REJ)UCT10NS UNIT NAME
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78-5 7808111 F 7.3 D 4 78-029/0JL-0 Unit Load-Reduced > .20% as a result of river water inlet temper~ture
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e LOAD REDUCTIONS DUE TO ENVIRONMENTAL RESTRICTIONS UNIT NO. 1 MONTH: AUGUST, 1978 DATE l1n.1E I HOlJRS LOAD, MW REDUCTIONS , MW REASON NONE DURH G THIS REPORTING PJ RIOD. I _ I _ _ _ _ _ _ _ . _ _ _ _- , - - ,_ _ ! ____) MONTB:LY TOTAL l o I
e LOAD REDUCTIONS DUE TO ENVIRONMENTAL RESTRICTIONS UNIT NO. 2 MONTH: AUGUST, 1978 I I I I DATE
- - I TI!1E HOURS LOAD, MW REDUCTIONS , MW I I -MWH I REASOK l
I I I NONE DURJ NG THIS REPORTING bERIOD. I I I i II I I I I I ! MONTHLY TOT.Al. I I i i 0 I
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DOCK.ET llO UNIT DATE 50-280 SURRY I 9-1-78 0 J COSTELLO l.EE.Be..Qt: I2..1LL.l. !l.lil.X !:.Q'il.E..B. LE.UL. !:J_ 0 NX.il. : .4UGUST 1978 AVERAGE DAILY POWER LEVEL AVERAGE DAILY POWER LEVEL DAY (MWE-NET) DAY OJWE-NET)
.I. 728.0 17 7 2 S. 7 2 7 31. 8 18 728.'+
3 726.1 19 728.6
'+ 73'+.8 20 723.9 s 735.2 21 732.5 6 733.0 22 730.'+
7 732.7 23 73'+.1 8 7 31. 8 2 '+ 727.3 9 731. 3 25 73-4-.0 10 731. 5 26 7 3 2. 5 11 733.S 27 733.0 12 735.0 28 730.4 13 733.8 29 517.1 1'+ 430.8 30 724.6 15 668.8 31 734.1 16 729.0 DAILY UNIT POWER LEVEL FORM INSTRUCTIONS ON THIS FORM, LIST THE AVERAGE DAILY UNIT POWER LEVEL IN M~E-NET FOR EACH DAY IN THE REPORTING MONTE. THESE FIGURES wILL BE USED TO PLOT A GRAPH FOR EACH REPORT-ING MONTH. NOTE THAT BY USING MAXIMUM DEPENDABLE CAPACITY FOR TEE NET ELECTRICAL RATING OF THE UNIT, THERE MAY BE OCCASIOUS WHEN THE DAILY AVERAGE POWER EXCEEDS THE 100 o/o LINE (OR THE RESTRICTED POWER LEVEL LINE). IR SUCH CASES, THE AVERAGE DAILY UNIT POWER OUTPUT SHEET SHOULD BE FOOTNOTED TO EXPLAIN THE APPARENT ANOMALY.
DO,ET NO 50-281 UNIT SURRY II DATE 9-1-78 COMPLETED BY 0 J COSTELLO !j_Q!J. T .=i : AUGUST 1978 AVERAGE DAILY POWSR LEVEL AVERAGE DAILY PO'dER LEVEL DAY (Mii'E-NET) DAY t/.fWE-NET) 1 7 0. 8 17 722.7 2 606,5 18 725.6 3 733.0 19 727.2 4 718. 2 20 726.5 5 739.6 21 727.6 6 733.6 22 729.6 7 717.2 23 729 1 8 733.9 2 '+ 732.1 9 736.1 25 728.3 10 73g,o ' 26 731.1 11 739,8 27 73*5. 7 12 739.3 28 730.0 13 738.0 29 730.3 14 693.2 30 733.9 15 728.4 31 735.0 16 726.7 DAILY UNIT POWER LEVEL FORM INSTRUCTIONS ON THIS FORM, LIST TEE AVERAGE DAILY UNIT POWER LEVEL IN M~E-NET FOR EACE 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 R~TING OF THE UKIT, THERE MAY BE OCCASIONS ~HEN THE D~ILY AVERAGE POWER EXCEEDS THE 100 o/o LINE (OR THE RESTRICTED POWER LEVEL LINE). I~ SUCH CASES, TEE AVERAGE DAILY UNIT POWER OUTPUT SHEET SHOULD BE FOOTNOTED TO EXPLAIN TdE APPARENT ANOMALY.
-~-
SUMMARY
OF OPERATING EXPERIENCE e AUGUST, 1978 e
- t. I 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 system. 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 hours power was changed about 1% until the F0 surveillance allowed 100% power operatic~. At 1500 the reactor atta:ined 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 Fater.was pumped inco 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 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 beguu. At 2400 the unit was at 48~~ power. August 2 At 1000 the unit was at 100% power.
11MARY OF OPERATING EXPERIENCE
.. (CONTINUED) ~
l UNIT 2 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.
AME:NDHENTS TO CILITY LICENSE OR TECHNICAL SPEr.IFICATIONS 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: The facility shall be operated within the following limits: Maximum Service Water Temperature 90°F Containment Temperature Allowable 100°F - 125°F Range Containment Air Partial Maximum Pressure
- 1. For Service Water Temperature :3_87°F Air partial pressure shall be m~intained in accordance with Figure 3.F.2
- 2. For Service Water Temperature >87° Air partial pressure shall be maintained in accordance with Figure 3.F.l Minimum Refueling Water Storage 385,200 gallons Tank Volume Outside Recirculation Spray Pump 2250 gpm Flow Rate
~ACILITY CHANGES REQUIRING NRC APPROVAL AUGUST, 1978 L
There were none during this reporting period. FACILITY CHANGES THAT DID NOT REQUIRE NRC APPROVAL AUGUST, 1978 Design Change 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.
Summarv of Safetv Evaluation This design change in no way affected the operation of the Emergency Diesel Generators and as such was considered non-safety related.
i .... FACILITY CHANGES THAT
~ID NOT REQUIRE NRC APPROVAL (CONTINUED) e AUGUST, 1978 Design Change Unit
- 4. DC-78-S23 - Snubbers - LHSI, *Feedwater, and Steam Generator 2 Blowdown System Descrintion - 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 was 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. Summarv of Safetv 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 Specifications is not reduced. Conclusion This design change does not constitute an unreviewed safety question
- 5. DC-78-S24 Fire Protection Piping System-Personnel Change 1,2 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 create an unreviewed safety question.
TESTS AlID EXPERIMENTS REQUIRING e NRC APPROVAL AUGUST, 1978 e There were none during this reporing period. TESTS Alsi'D EXPERIMENTS THAT DID NOT REQUIRE NRC APPROVAL AUGUST, 1978 There were none during this reporting period.
-D-OTH-CHANGES, TESTS AND EXPERIMENTSe AUGUST, 1978 There were none during this reporting period.
- SURRY POWER STATION e CHEHISTRY REPORT
'- AUGUST, 19 78 T.S.6.6.A.11 PRIM.UY COOLAl'-rr UNIT NO. 1 UNIT NO. 2 ANALYSIS MAXIMUM MINIMUM AVERAGE MAXIMUM MINIMUM AVERAGE Gross Radioact., µCi/ml
-1 3.67E-1 I 1.68E-l 2.63E-l 2.39E-l l.21E-1 l.67E-l Suspended Solids, ppm 0.2 0.1 0.1. 0.2 0.1 0.1 Gross.Tritium., µCi/ml 2.02E-1 l.35E-1 l.61E-l 1.85E-1 3.04E-2 l.07E-1 Iodine-131, µCi/ml 2.58E-2 9.48E-4 3.09E-3 4.88E-4 1.41E-4 3.08E-4 I-131/I-133 0.1943 0.0677 0.1434 0.1659 0.0298 0.0871 Hydrogen, cc/kg 49ol 26.9 38.8 47.8 11.3 30.1 Lithium, ppm 2.68 2.10 2.38 0.95 0.53 0.83 Boron-10, ppm+ 169.3 149.7 155.4 - 217.6 55.7 67.4 Oxygen-16, ppm 0.000 0.000 0.000 0.000 0.000 0.000 Chloride, ppm 0.05 0.05 o.os 0.05 0.05 0.05 i pH@ 25°C 7.03 6.75 6.91 7.15 6.59 7.02
+ Boron-10 = Total Boron x 0.196 NON-RADIOACTIVE CHEMICAL RELEASES, POUNDS - . T.S. 4 .13 .A.8
-Phosphate 0.0 Boron 650 Sulfate 278 Chromate 0.005 50% Na.OH 350 Chlorine o.o-
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Remarks:
DESCRIPTION OF ALL INSTANCES WHERE THE~ DISCHARGE LIMITS WERE EXCEE11 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 -,
? 1978 Exceeded 15°F ~T 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 6T across station August 6, 1978 Exceeded 15°F ~T across station August 7, 1978 Exceeded l5°F lT across station August 8, 1978 Exceeded l5°F lT across station August 9, 1978 Exceeded 15°F ~T across station August 10, 1978 Exceeded 15°F lT across station August 11, 1978 Exceeded 15°F ~T across station August 12, 1978 Exceeded 15°F lT across station August 13, 1978 Exceeded 15°F lT across station August 14, 1978 Exceeded 15°F ~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 6T across station August 17, 1978 Exceeded 103°F at groin August 18, 1978 Exceeded 15°F ~T across station August 18, 1978 Exceeded 103°F at groin August 19, 1978 Exceeded l5°F 6T across station August 19, 1978 Exceeded 103°F at groin August 20, 1978 Exceeded 15°F 6T across station August 20, 1978 Exceeded l03°F at groin August 21, 1978 Exceeded 15°F lT across station August 22, 1978 Exceeded 15°F lT across station August 23, 1978 Exceeded 15°F ~T 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 ~T across station August 27, 1978 Exceeded l5°F lT across station August 28, 1978 Exceeded 15°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 e AUGUST, 1978 e 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 ~onth.
UNIT ftl DATE SHIPP:'.D/R.Et:SIVED NO OF e FEEL ::_:_:~WLING ASSEMBLIES PER SHIPME.:.'l'T AUGUST, 1978 i I I A.~SI NO.* INITIAL ENRICHMENT
- NE'..i OR SPE:IT FUEL SHIPPING CASK ACTIVITY LE I
I I I I I l I I I I
! j I NONE DURiNG THIS REPORTING PERionJ I I I
I I I I I'
*I I
I I -' I I I' ' l I ' I I I . - I I I I I I I I I II I I I I I I I I Ii .. -** .... - - -* II . - . *- - -- -- -- . ... -**
FTJEL HANDLING AUGUST
- 1 9 78 DATE NO OF ANSI NO.
I NEW OR SPEI1T FUEL
- HIPPED/P...ECF;IVED , ASSEMBLIES PER SHIPMENT
. INITIAL ENRICIDiENT . SHIPPING CASK ACTIVITY LEVE I
I NONE DJRING THIS REPORTING PERF T'l. I .. I .,
. ~-: . :'
CHANGED THE IN THE FSAI AUGUST, 1978 There were none during this reporting period.
DESCRIP.TION OF PERIODIC TESTS WHICH WERE NOT LETED WITHIN THE TIME LIMITS IN TECHNICAL SPECIFICATIO AUGUST, 1978 The following Periodic Tests were not completed within the time liraits specified in the Technical Specifications. PT-14.i 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. PT-24.2 High Pressure CO2 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 hours on 08-14-78. A scheduled Fq Surveillance was performed sat*isfactorily 2 hours 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.
\
TABLE OCCURRENCES PERTAINING
~NY OUTAGE OR POWER REDUCTIONS AUGUST, 1978 There ~ere no reportable occurrences pertaining to any outage or power reductions for the month of August.
Haintenance of Safety Related Systems During Outage or Reduced*Power*Periods UNIT /fl Mechanical Maintenance
l
,,,.;rr =m:c 11 1 :,f*,'/' 711
- l 71 11R /'M /'Ar;r,: 2 UNIT 1 AUGUST H7R I NAIN7'1,"NANCf: OF SAf'f.TY RF.l,ATED SYS1'ENS DURING 0/JT/ir,F, OR RTifJIJCISD f'Ol{E/i l'f."RWIJ:;)
111-:*rs,,:1,v m* ,*.:rs (:()/fl' MAm<NO S/1/.INIIRY l.'K/'/illF 11 NR 1'/1'/' /~I NTM 0'1/l'i/'lll CV /'UNI' 1-CV-/'-1,1 1)01'.:S NOT HJI.II' vow 1 R07:rn1ns IJ on/ 1 11r, 11 CV VAl,VS 1-cv-2r. C/IIXK AND RF:Pl,ACED 1F NF.IWP./J Rfil'l,AGelJ Dl Al'I/RAGM I 110111 ?.0170 5r; 011/')'l/'lll /JI/ VAl,VF. 1-rm-20:1 Vtlf,VE /IODY C.EAKlNG Rf::NEWIW V/11,Vf. DONNb"f1'~Dltll'/IR/117M l 110112'1111:IO 11
'/5 e
/JP,'/'/' 7'/11'/I/,
I
""I C]\
.. --~.-
--= - -- - - - --=-- -- e Maintenance of Safety Related Systems During Outage or Reduced Power*Periods UNIT //2 Mechanica.J::; 'Maintenance
\
- ,,;,. 711
- 12152 /'/.I /'/ir;/',' 2 UNIT 2-AUGUST lq7n -
<MAlNTf."NANCE OF SAf'f;J'Y R6LATTW SYSTEMS DURING OUTA<iK on RE/)UCF.TJ rornm l'l':RlOTJS)
RF.'/'SF.r.V/11' SYS COit/' f.lAl/KNO
SUMMARY
WKl'F.RF /I ltn 1'0'/'lMN'/'lf OH/01 /7n Cl/ l'll'lNG 2-CII-P-W u:AK AT VISCIIARGE FLANGE m:rLACED E'LANGF, GASKF.1' 2 IJ07lql711r, 113 on/01 r,n SI VAl.VP. 2-sr-n?. DODY 7'0 DONNF:T lJOLTSS VF.TERIORATED VOID 2 1107'..!710:IO 0
/Jf./"'1' 7'0'/'M, I
N 00 I i..
Maintenance of Safety Related Systems During Outage or Reduced Power Periods UNIT #1 Electrical Maintenance
e Electrical Maintenance Unit Ill There was none during this reporting period.
Maintenance of Safety Related Systems During Outage or Reduced Power Periods
,, UNIT {12 Electrical Maintenance
e Electrical Maintenance Unit 112 There was none during this reporting period.
Maintenance of Safety Related Systems During Outage or Reduced Power Periods UNIT #1 Instrument Maintenance
- e Instrument Maintenance Unit tfl There was none during this reporting period.
Maintenance of Safety Related Systems During Outage or Reduced Power*Periods UNIT f!2 Instrument Maintenance
1 :-:r.;r* 1n
- l'l.:57 /'N l'AGP. 1 f)f:1'/'c JN,'='/'
1/NlT 2-AUGUST 197R (MAlNTF:NANCE OF SAE'l':TY tunATl!:IJ SYSTf.NS DUf/lNG OU'I'AGE Of/ REDUCf.lJ l'OWER Pf.'RlOIJS) W/WERP II /.IR 7'0'/'/11/N1'M r,r,;r:;1mvm* SYS COM/' MAT/l<NO SUNNARY (.'I/ l'I-71~1 CAT,I/Jf/111'1? OR REPLACE AS NECF:SSARY CAL1Df/ATED GAUGE 1 no12s1 noo ')f, 011/(ll/"I" 1NS1' CIITiCl{f:V S1'ROKF.+STAR1'1NG l'OI NT-SAT 2 R073J075'1 Hi on /o 1/'111
- 11c VAT.VF. l'CV-'.2'155/J iXJl*:S f./m1Ut,,m; PRON1RLY
/lf:/'f T!J'l'AI, 112
! I I w CJ' I l J
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.
-------~, ..:._ ****--*. ***---- ..
*>razsm'3:19l'P:F-mm:ramnmcrc:ezt RIU'ORT 01 RAIJIOAC'l'IVI! lff~'I.UEN'l'S l'AGE 1
~*ilcllity: Suc-ry l'owcr Statlon DOCKET: 50-280 and 50-281 YEAR: 1978
- 1. l.L<!U 111 m,:1.EAS 1'8
)::::::::::::~.n~--;,;:-::::-:.::-::--H--,;-::;-;:-;:-::---H-.---;;-;:c;;---;----l------+------ll------B-------l-------1-------U l .____ t: rm;s 1!11,IJ-o*-,1*-,.,-.t*-1-.v-l-t_-}'__(_fl)'-/;
. ---_J~)__'l'uLal Hi:deuu1: Curles . l.99E-l 2.0SE-1 ___ (!u_ Avr,..' Concentration ReleaseJ _ _ ~i/ml _ 1.071~-9 8,78E-10~+------!------l!-------l-------ll-------D-----1-,-U u----'( C) Hu~i IIIUIII f.(,nceut rn t 1011 llel e11seJ )ICi/iiil -1,.c..9"5~E;,,_-;9;;--fl-,1i','J4c-;7ii'Eui9~-~------v------+-------{\-------l!------U------,
- 2. 'L'L"lt1uu,
--,~-)--1:t._>_lu-1-1-lu-*l-C! u~,~d Curles l.13E+2 l.41E+l 11cI7rnl ---r.T"lE;;-,_~7r--flr:--6ii-'.'-;o:'i4'-;';E:--;i-8-+------l1--,------il------~------~------~I------
=_(_l,_)_.J:':'.ll.: Co11c1:11Lrntlun Ucleaued
- i. ll I :rno l ve,l Nub 1 c Gat.1es Curles -i;:ui:o::~-='*z,----1!-,l-."3:;;9:;;E~---:;-l--t------l!------+-------11-------Y------R------
___ .. --1!0 Total l\cluaue _ _ i ! ! ~ ~ 1 c c n t r a t l o 1 1 llc.leiltJed llC1/ml _ -Z:75K-J.U 5. 9SE-10 !~=.. __ Grni;:; Al_i:!1a lludloacttvl ty (a) 'l'otul lleluased ___________ 11 _ Cur.ies _ _ ___, 2.04E-5 4.36E-6 (h) Av.i;. Cu!1ce11trntlo11 llelcased pCQml -r:TOE-lJ
- l.86E-14
~,__ _vol. of I.l,p,ld to D-lt.1ch. Cunnl Liters 3.90E+7 3.64E+7 I
[~ Vul. of Dllut1on \-later --'-------A*-----11-~_;c_;~-=---1 J.l.tcri. l.85E+ll 1
-~~-=---'
2.34E+ll l,) CX) ?.: __ T,rntopus 1-13] Rcleairnd HPC pCl/ml Curies
) K JO-,,_--~----- l*-----j!--:;--rn.:.-.,---\l-.,-,,-,..,,.-,--ll------11------11------11-----
I 7.52£-5 6,08E-Z.
- - - J :l~--8-KJ0_;-6 * -/C l-11:l 1 K TiY-'-_6__________ #r --r.zi7E-4 ---'f-l3/1 -2 )( 10-s* - ---- ,\- *~,..----**------R------A-------tt-------tt-------11-----"--*-
l-J35 ti x 6 -r.7lill=-S--- "' C!;-1311 - - - 9 x 10.:G* 3,_lSE-2 --.r."b4E-:r-H------ll------~------A-------11------11-----1 C,;-1]6 6 x 10-,---------- l\' C~-IJJ -2 xl1F 5
- 8.27£-2 ~-:7JE-l Cs-l:J8
---Cl1-57 i1 x fo-=-,;-
- 3.95E-4 4.03E-5
- - Co-5B - - x 1 0 - , - - - - - - - - 5.33E-l C54E-l
---C.i-60 J K j Q- s----- A - - - - - --,,--,,~--;----Jt--:;---:--::-:::-::---1,------U------H-------l!-------II--------Y-------11 3.62E-l l. llE-1
,:c--..;:---11--c;..:...==-=.--M------11-------li-------ll-------ll------11-------1 l-111-511 I. X -Tei" 11 1.0SE-2
- 4 .21E-3 l-lu-2/1 - '.I K ]()-*~,--------- 7.7/JE-11 3.69E-2
-* Cc-51 :.! X .ro-3 ---------*---- H--'--=---"-=---a-;;.:..::.,-;.-~--U-------
4.lJE-2 3.18£-3 Fe-59 5 X 10-5 - - - - - - - * - - - - - --,,'-',."'4",",'-"E'---=4'---M-.C...:..c;=.*=-=---1-------u-------fl------~-------H*------11--------
- - NTi°-95_ 1 x Ill-'* - - - -----
6
- 13 iI=-:r- -3.613-~ ------H------H------a------1~------~------
Bu-1.a-lt,o 2 x JCr-5 - - - - - _ _*____ J - . 4 ' , E - ~ 1 1 - - - - - - - a - - - - - - - u - - - - - - l l - - - - - - 1 1 - - - - - - - l l - - - - - - - - 1i1-;-::.BB .----- - - - - - - - - * - * * - ~ - - - -------1-------U-------l------1~------a-------
- ----------*--------------"-------'------..._-----ll.------!-------!.__----*-!e------_.!!__-----~-----'
w REPORT OF HAIHOACTIVE EFl'LUlmTS PAGE 2 llAClLl'l'Y; Suny l'uw"r $lilt_-'-J_o_n_ _ DOCKET; 50-230 and 50-281 YEAlt: 1978
--~- - ----,- -* .
L. 1.u1urn lrnLl,ASES (CON'T)
'l'QTAl, __ *-. +/-. Eq-qr ----z.;.:. C"-l'iJl,4l 9l x .10-"
x 1o-1i-------
--""-----*---""----11-------H*------;u-------11--------u------i
- 2. 79E-4 -1<
x,,-1 J 3 3 x l cF<>--------H----i,-2~.2""'8=E,...'-~2~--u--4-.-9-6_E___ 2_ Xu-135 AL--1,1 Sr-8_9_____ Sr-90 C-l 4
- u. ---------------------*
11.
!'l!rct:nt of lOCFH20 3 l _(o)~~-1,*---------Jil----U--'-4.::.*.::.0;::..:9E::*-~3:===~::==l 1 _~0~0 8 x 10-"
A ll<llOltN E HE!__ l(l{ 1 x 10..c,---------
.1,.c.:A:.ccS.cc.E.: .S. ___________ H Percent 1. 90E-2
~.~9~3,~E~-~2==j:==========-=-*ll ._-_-_-_-_-_-_-_-_-_-_--ll-"--_-_-_-_-_-_-_-_-_---ll-~*===========~:===========--*-----
H-----11--'6'-'.-'-5...C.6.C.CE_-.;;.5_ _ __;;.l..;;.*...;.4.::.0E::..'-_4.;___,~------u-------8-------A-------U----*--- 3.74E-2
- l. 1~Lul Nuhl" Gusl!H Curie,i 3.921Hl l.41E+l 2.____ T0Lt1 l llaln*~~,rn - C:11rjes 2.16E-7 2.79E-5
] . To tu l P <1 rt lcu l u-t-c-C_r:_o,_s_s-c:-R-ad-:-c-io------"..,_,,-LW'-=-':........11--------fll-------M-------ll-------M-------ll-------ll-------~-----
0
-- - - - - - ilC t IV l t_y_J/h)______________ CurJ.eL_. 2.80E-3 5. 71E-5
- 4. Total Tritium 1.63E+l 2,34E+l 5.
Total PurLJ.culate Cro;;,i Alpha Guf'l CH ltadluuct lvl LV C11r (t!S 2.91E-5 3.71E-6 !
'I !!_! ___l*!,lldlllum Noble Gu,; llLde,rne Rate pc l /.,me
- 1.06E+3 -r:39E+l
- 7. l'~r<:eut: of Appll.:uhlt! l.Jmit for
----*~,,i:lonlt:11\ S1>'-'d_f~lc~*u~t~J~<~ll~W~-------- - ___ _J~_}_ ___ _u__c_:_u_s'-'_'tl______________ l'e rce t
_____ (h) JJ.1l~Clltl_ N_<,_h_l 11
.. l'lll:.;-;.;i:- 1.80£-6
- 2. 99£-2 l. l 7*c-:E,*-...:;2;.--Jf-------ff-------!-------11-------u-------H 2.99£-6
- - ~ - l'11r!:_lculute1i *J'erc1:1!f_ --o.!i"Tu-~ ~~
ll. T,wtupcti Re~etl:----------
- Cudei; (a) ParL l,'.111 al u,i --'-'-'=-'"-="-li-------11------~-------U-------R-------R-------U------
. _____ - - ~ ~ - - - - n - - - - - - - l l * - - - - - - n - - - - - - - 1 1 - - - - - - , , - - - - - - - 1 1 - - - - - - -4 , _ _ _ __
________g,i-1111 - - - -
- __2_. 4~_0_E_~-_6__ l_*..,.O_l_E_-_l_0_
--ll ___
0 11
------i-------*-------*------
C,i-135 * ""
------Cs-117 G,;-l"lB - - - - -T.7,BE-5
~-.-0~9=£-,_--~5~-----=-:~===4=-.~4~7=£=-:6==-:===========:,~===========:i 2.fill-5 ------i
------H---'-----U-------ii-----
c 5B - - -r..f9K-=1__ ,, __3~.-7~4-E--5~-U------n----- - - - - - ! l - - - - - - l f - - - - - - 1 1 - - - - -
*-------,;-:::60*--- ----- --:-z.GR=r-- 1. 23£-5
________ M11-'.i~ - - - - - - - - - - - - - - * - - - _____ -_. ,2" .-4,-~7~-E; _-~*s:==:=: ~-=.-=.-=.~...,..,-~~---_-_-_-_-~~===========~============~a~-_-_-__-_-_-_-_-_-_-_-_-,;*_-_-_-_-_-_-_-_-_-_-_-_-_-; _______ 1 11
-----~!*~°~-~)~- . -----* - - ~ - - - - * - - : - - - - -------41------~------- 11*------*-----*-
.-*--***-* .*--* . l<h-llh**--**** ---~-~--. - - - * *--~- . . - _ ...JI._~~-~~==-- -I<
-*-**-* ~~-~ -***-***~
1iiCPTZWttPSZ17 rmMnwzown:wuz Rln'Oll'r 01! HAnIOAC'l'IVE EFFLUENTS l'AGE 3 l'Al:11.ITY: Surry l'owcc Statton YEAR: _ _.l""9'""7~8_ _ __ DOCKE'J:; 50-280 11n<l 50-281 I IL.
. ~ - ~A[H!IOl<NE
. . ~- ltELEA!:iES (CON T)
~ . . . .-~~. ~ ~~iliL*n~=.,-::n:::,1":-,Y:=-~=u~=A;-;\':;IG:7:U;:;-~T=.. =___=_* 1= = = = =4 =-=-===-n=~~=~=-jf~=~=~--B~~~'-=-=~~~~~
-~___!_:!otopcs lteleaae<l (con It) Cud es (b) lla~.:_ucc.n:s'-'------------i-----ff--::-:-:--:::-::---ll--..--,-::;-;:--:--+------11------B-------R-------A------a----__jl 1-131 l.61E-7 2.67E-5 T 132 T-133 5.55E-8 l.15E-6 J--135
-----'(._,:c..<)_ _.:.;G.:.;a.::.a.::.c::.B_ _ _ _ _ _ _ _ _ _ _ _ _ i - - - - - l l -
Xe-] 33 °J.7oE+l l.21E+l Xe-1 :JJm 3.90E-6
- Xc-135 4.0BE-1 1. 72E+O
~.14E-2 Kr-85111 *-------'-K.c..cr_--::11,~5_____________ * "'
Kr-811 - .
-------'-K:;i-_-087,,------------H-----B*-~----U-...:.:7:.::..._::_-Jl------i------~------#------U------ll 9.44E-4
- l. 2'.>E+O
!II. Ar-41 SOI.In RADIOAC'l'IVE \/ASTE DISPOSAL
- 1. (11) Tornl Amount Solid Waste I
_ _ _ _ _ _ _l'_il_c_lrn!L!:...cd ____________ _:_F'.:..l'_ (b) E:itlmatcd 1'otul Actlv1 cy 8 3
--U-3. 25E+3 Cude!! 9-:T9E+l 3 :o9E+3 9.23E+O f (c) Da cu u f ShJ puumt and 1larnwcir;-- Dfa;;-;r:;:n;-;-w:::e:'l'l~l-,--11------t------+------~-------II-------U -----1
_ _ _ _ _ _ _..;..D...cl!Jpu:;ltion S.C. S,C.
---fl-----n------tt-----+-----a-----n------11-----li 7-6-78 7-9-78 7-15-78 7-17-78 7-22-78 7-22-78 7-25-78 7-27-78 8-2-78 8-4-78 11-7-78 8-15-78 8-25-78 7-27-713 7-31-78
* ',I\
l.
.. - , , " C.*
b.
!*!.i:i:..=.-..:::i. De.:ec:able Accivi.tY G=oss ;..lpha; 5.27Z-9 Tritiu::i; 4.0~-6 µCi/ml.
µCi/!:l.l
- c. Stron:iu:::::-89; less than 3.0E+l pCi per toca~ filter co:pos~~e. .,
d.. Stronti~90; less tna.:J. 2:0E+o pCi per total £~leer cocpos~ce.
- e. COz-14; less th.an 7.0E-10 µCi/mJ..
-. Stronti~89; less ~an 9.0E-9 µCi/ml.
- g. Stronti~90; less than 8.0E-10 µCi./m:!...
- a. Liauid and/or Radiogases - 100cc Ba-La-140 2.0E-7 I-131 5.lE-8 Xe-133 5.4E-8 Xa-135 2.9E-8 Cs-137 9.2E-8 Cs-l34 7.2E-8 Co-60 l.SE-7
.Co-58 9.SE-8 C:r-51 3.SE-7 Mn-54 l.OE-7 Fe-59 2.4:E:-7
\
Ar-41 1. 6E.-7 1~134 .l.lE-7 . I-132. l.OE-7 Na-24 1. TE.-7
.,_ *r-133 6.9E-8 I-135. 4.5E-7 Kr-85 1.36:E-5 K:r-88 5.5:E-8 *--**..
Kr-87 *
*K=-8.5m 5.3:E-8 2.3:E-7 Xe-138 4.7Z-9 Xe-13.Sm *S.SE-8 Xe-133m l.7E-7 ._ . ~. -. . .- - ..
llli-88 8.5:E-7
- b. R.adioiodines I-131 **2.:3E-6 I-133 3.l.E-6.-
I-132 4. 71::-6 I-134 4.SE-:6
!-135 2.0E-5 ---C... *
- .. _,J
PROCED~EVIATIONS R~~D BY STATION~CLEAR SAFETY AND OPERATING COMMITTEE AFTER TIME LH1ITS SPECIFIED" IN TECHNICAL SPECIFICATIONS AUGUST, 1978 There were none during this reporting period.}}