ML18139B082
ML18139B082 | |
Person / Time | |
---|---|
Site: | Surry |
Issue date: | 02/04/1981 |
From: | Dunn S VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.) |
To: | |
Shared Package | |
ML18139B081 | List: |
References | |
NUDOCS 8102230574 | |
Download: ML18139B082 (51) | |
Text
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VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION MONTHLY OPERATING REPORT REPORT NO. 81-01 JANUARY, 1981 APPROVED:
-i-e CONTENTS
'* I Section Operating Data Report - Unit #1 1 Operating Data Report - Unit #2 2 Operating Data Report - Unit #2 (Corrected Copy) 3 Unit Shutdowns and Power Reductions - Unit Ul 4 Unit Shutdowns and Power Reductions - Unit #2 5 Load Reductions Due to Environmental Res~rictions - Unit #1 6 Load Reductions Due to Environmental Restrictions - Unit f/2 7 Average Daily Unit Power Level - Unit #1 8 Average Daily Unit Power Level - Unit #2 9 Summary of Operating Experience 10
.Amendments to Facility License or Technical Specifications 11 Facility Changes Requiring NRC Approval 12 Facility Changes That Did Not Require NRC Approval 12 Facility Changes Requiring NRC Approval (NOVEMBER CORRECTED REPORT) 14 Facility Changes Tha.t Did Not Require NRC Approval (NOVEMBER CORRECTED 14 REPORT)
Facility Changes That Did Not*Require NRC Approval (DECEMBER CORRECTED 15 REPORT)
Tests and Experiments Requiring NRC Approval 16 I
Tests and Experiments That Did Not Require NRC Approval, 16 Other Changes, Tests and Experiments 17 Chemistry Report 18 Description of All Instance~ Where Thermal Discharge Limits Were 19 Exceeded Fuel Handling 20 Procedure Revisions That Changed the Operating Mode Described In The 22 FSAR Description of Periodic Tests Which Were Not Completed Within The 23 Time Limits Specified In Technical Specifications Inservice InspectiQn 24
i e CONTENTS e
S:ection P~ge Reportable Occurrences Pertaining to Any Outage or Power Reductions 25 Maintenance of Safety Related Systems During Outage or Reduc-ed Power 26 Periods - Unit #1 - Mechanical Maintenance Maintenance of Safety Related Systems During Outage or Reduced Power Periods - Unit 112 - Mechanical Maintenance Maintenance of Safety Related Systems During Outage or Reduced Power 36 Periods - Unit #1 - Electrical Maintenance Maintenance of Safety Related Systems During Outage or Reduced Power 38 Periods - Unit #2 - Electrical Maintenance Maintenance of Safety Related Systems During Outage or Reduced Power 40 Periods - Unit #1 - Instrument Maintenance Maintenance of Safety Related Systems During Outage or Reduced Power Periods - Unit #2 - Instrument Maintenance Health Physics S\DIIID.ary 44:
Procedure Devi~tions Reviewed by Station Nuclear Safety and 4~. -
Operating Committee After Time Limits Specified in T.S.
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- OPERATING DATA IBPOKI' DOCK.ET NO. 50-280 DATE 04 FEB 81 COMP~"'TED BY SUE D. DUNN TELEPHONE 804-357-3184 OPERATING STATUS
- 1. UNIT NAME SURRY UNIT 1
- 2. REPOKI'ING PERIOD 10181 TO 13181
- 3. LICENSED THERMAL POWER (H,IT) 2441 , - - - - - - - - -
4 .* NAMEPLATE RATING (GROSS WE) 847 .5 I NOTES
- 5. DESIGN ELECTRICAL RATING (NET MWE) 822 I
- 6. MAXIMUM DEPENDABLE CAPACITY (GROSS MWE) 740
- 7. MAXIMUM DEPENDABLE CAPACITY ( N'i:T MwE) 704
- 8. IF CHANGES OCCUR IN CAPACITY RATINGS NIA
( ITEMS 3 THROUGH 1) SINCE LAST
&"'PORT. GIVE RSASONS
- 9. PWER LEVEL TO WHICH RESTRICT-SD. IF ANY NIA
( NET f.f,/ E)
- 10. REASONS FOR IBSTRICTIONS. IF ANY NIA THIS MONTH IR-TO-DATE CUMULATIVE
- 11. HOURS IN REPOK!ING PSRIOD 744.0 744.0 71112.0
- 12. NUMBER OF HOURS REACTOR WAS CRITICAL o.o o.o 42538.5
- 13. RSACTOR RESERVE SHUTDOWN HOURS o.o o.o 3731.5
- 14. HOURS GENERATOR ON-LINE o.o o.o 41668.8
- 15. UNIT RESERVE SHUTDCl,/N HOURS o.o o.o 3736.2
- 16. GROSS THERMAL ENERGY GENERATED (MwH) 0.0 o.o 96389401.0
- 17. GROSS ELECTRICAL ENERGY GENERATED (MWH) o.o o.o 31301743.0
- 18. NET ELECTRICAL ENERGY GENERATED (MWH). o.o o.o 29699924.0
- 19. UNIT SERVICE FACTOR o.o 0.0 58.6 o/o
- 20. UNIT AVAILABILITY. FAC'rOR o.o o.o 63.8 o/o
- 21. UNIT CAPACITY FACTOR (USING MDC NE'r) o.o o.o 59.3 o/o
- 22. UNIT CAPACITY FACTOR (USING DER NE'r) o.o o.o *so.a o/o
- 23. UNIT FORCED OUTAGS RATE o.o o.o 26.4 olo
- 24. SHUTDClt/NS SCHEDULED OVER NEXT 6 MONTHS (TYPE.DATE.AND DURATION OF EACH)
- 25. IF SHUT .DOWN AT END OF REPOKI' PERIOD. July 1, 1981 ESTIMATE DATE OF STAR'rUP
- 26. UNITS IN TEST STATUS FORECAST ACHIEVED (PRIOR TO COMMERCIAL OPERATION)
INITIAL CRITICALITY INITIAL ELECTRICITY COMMSRCIAL OPERATION
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e e OPERATING DATA REPO!i'l' DOCKET NO. 50-281 DATE 04 FEB 81 COMPLETED BY SUE n**. DUNN TELEPHONE 804-357-3184 OPERATING STATUS
- 1. UNIT NAME SURRI UNIT 2
- 2. REPOR'rING PERIOD 10181 TO 13181
- 3. LIC'SNSED THERMAL P(X,IER (MwT) 2441 ,---------1
- 4. NAMSPLATE RATING ( GROSS /,s,/E) 847.5 INOTES I
- 5. DESIGN ELECTRICAL RATING (NET MWE) 022 I I
- 6. MAXIMUM DEPENDABLE CAPACITY ( GROSS WE) 011 I I
- 7. MAXIMUM DEPENDABLE CAPACITY (NET MWE) 775 I I
- 8. IF CHANGES OCCUR IN CAPACITY RATINGS NIA (ITEMS 3 THROUGH 7) SINCE.LAST REPOR'r. GIVE REASONS
- 10. REASONS FOR RESTRICTIONS. IF ANY NIA THIS MONTH YR-TO-DATE CUMULATIVE
- 11. HOURS IN REPOR'rING PERIOD 744.0 744.0 67992.0
- 12. NUMBER OF HOURS REACTOR WAS CRITICAL 744.0 744.0 38528.0
- 13. REACTOR RESSRVS SHUTDOWN HOURS o.o o.o o.o
- 14. HOURS GENERATOR ON-LINE 744.0 744.0 37880.6
- 15. UNIT RESERVE SHUTDOWN HOURS o.o 0.0 o.o
- 16. GROSS THERMAL ENERGY GENSRATSD (MWH) 1814981.0 1814981.0 88269642.0
- 17. GROSS ELECTRICAL ENERGY GENSRATED (J.MH) 594125.0 594125.0 28833119.0
- 18. NET ELECTRICAL ENERGY GENERATED (MWH) 563603.0 563603.0 27342091.0
- 19. UNIT SERVICE FACTOR 100.0 olo 100.0 olo 55.7 olo
- 20. UNIT AVAILABILITY FACTOR 100.0 olo 100.0 olo 55.7 olo
- 21. UNIT CAPACITY FACTOR (USING.MDC NET) 97.7 olo 97.7 o/o 51.9 o/o
- 22. UNIT CAPACITY FACTOR (USING DER NET) 92.2 olo 92.2 o/o 48.9 o/o
- 23. UNIT FORCED OUTAGE RATE o.o o.o 19.5 olo
- 24. SHUTDOWNS SCHEDULED OVER NEXT 6 MONTHS SNUBBER INSPECTION - MARCH.
(TYPE.DATE.AND DURATION OF EACH) 1981 - 4DA1S SPRING MAINT -
MAY. 1981 - 10 DAYS
- 25. IF SHUT DOWN AT END OF REPOR'r PERIOD.
ESTIMATE DATE OF STARTUP
- 26. UNITS IN TEST STATUS FORECAST ACHIEVSD (PRIOR TO COMMERCIAL OPERATION)
INITIAL CRITICALITY INITIAL ELECTRICITY COMMERCIAL OPSRATION
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- OPERATING DATA REPO'Kf e e CORRECTED REPORT DOCK.Er NO. 50-281 DATE 04 FEB 81 COMPLETED BY SUE D. DUNN ..
TELEPHONE 804-357-3184 OPERATING STATUS
- 1. *UNIT NAME SURRY UNIT 2
- 2. &""POR'rING PERIOD 120101 TO 120131
- 4. NAMEPLATE RATING (GROSS f,§IE) 847. 5 I NOTES
- 5. DESIGN El:SCTRICAL RATING ( N'S'r M,/E) 822 I
- 6. MAXIMUM DEPENDABLE CAPACITY ( GROSS frf,/E) 811 I
- 7. MAXIMUM DEPENDABLE CAPACITY (NET /rJWE)
- 8. IF CHANG'SS OCCUR IN CAPACITY RATINGS (ITEMS 3 THROUGH 7) SINCE LAST 775 NI A I
REPO'Kf. GIVE REASONS
- 9. POWER U,,EL TO WHICH RESTRICTED. IF ANY NIA (NET Mlt'E)
- 10. REASONS FOR RESTRICTIONS. IF ANY NIA THIS MONTH YR-TO-DATE CUMULATIVE
- 11. HOURS IN REPORTING PERIOD 744.0 8784.0 67248.0
- 12. NUMBER OF HOURS REACTOR WAS CRITICAL 744.0 3284.1 37784.0
- 13. REACTOR RESERVE SHUTIXltlN HOURS o.o. o.o o.o
- 14. HOURS GENERATOR ON-LINE 744.0 3140.4 37136.6
- 15. UNIT RESERVE SHUTDOWN HOURS o.o o.o o.o
- 16. GROSS THERMAL ENERGY GENERATED (WH) 1817675.0 7260578.0 86454661.0
- 17. GROSS ELECTRICAL ENERGY GENERATED (MWH) 597110.0 2370150.0 28238994.0 *
- 18. NE'! ELECTRICAL ENERGY GENERATED (MWH) 566703.0 2241883.0 26778488.0
- 19. UNIT SERVICE FACTOR 100.0 olo 35.8 olo 55.2 olo
- 20. UNIT AVAILABILITY FACTOR 100.0 olo 35.8 olo 55.2 olo
- 21. UNIT CAPACITY FACTOR (USING MDC NET) 98.3 olo 32.9 olo 51.4 olo
- 22. UNIT .CAPACITY FACTOR (USING DER NET) 92.7 olo 31.0 olo 48.4 olo
- 23. UNIT FORCED OUTAGE RATE 0.0 olo 3.1 o/o 19.8 o/o
- 24. SHUTDOWNS SCHEDULED OVE:R NEXT 6 MONTHS SNUBBER INSPECTION - MARCH *
(TYPE.DATE.AND DURATION OF EACH) 1981 - 4 DAYS SPRING MAINT.
MAY. 1981 - 10 DAIS
- 25. IF SHUT D'YIIN AT END OF REPORT PERIOD.
ESTIMATE DATE OF STAR'rUP
- 26. UNITS IN TEST STATUS FORECAST ACHIEVED (PRIOR TO COMMERCIAL OPERATION)-
INITIAL CRITICALITY INITIAL ELECTRICITY COMMERCIAL (JPERATION
- Indicates corrected figure
DOCKET NO. so-(,.80 :;-
UNIT S11U1D0\VNS AND POWER ~l!J)Ut110NS UNIT NAME 1 DATE
- February 9, 1981
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e LOAD REDUCTIONS DUE TO ENVIRONMENTAL RESTRICTIONS UNIT NO. 1 MONTH: JANUARY, J98J TIME HOURS LOAD, MW. REDUCTIONS, MW HWH REASON None d1 ring this ~eportin~ period.
MONTHLY TOTAL
e LOAD REDUCTIONS DUE TO ENVIRONMENTAL RESTRICTIONS UNIT N0.2 MONTH: JANUARY, J 9SJ REASON TIME HOURS LOAD, MW REDUCTIONS, MW
-HWH None dur ng this reporting beriod *
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MONTHLY TOTAL
e DOCKET NO 50-280 UNIT SURRY I DATE 2-1-81 .
COMPLE'rED BY ~UE D. DUNN*
AVERAGE DAILY UNIT POWER LEVEL MONTH:. JANUARY 81 AVERAGE DAILY POWER LEVEL AVERAGE DAILY PCNER LEVEL DAY (MWE-NET) DAY (NWE-NET) 1 o.o 17 o.o 2 o.o 18 o.o 3 o.o 19 o.o 4 o.o 20 o.o 5 o.o 21 o.o 6 o.o 22 o.o 7 o.o 23 o.o 8 o.o 24 o.o 9 0.0 25 o.o 10 0.0 26 o.o
- 11 o.o 27 o.o 12 o.o 28 o.o 13 o.o 29 o.o 14 o.o 30 o.o 15 o.o 31 o.o 16 o.o DAILY UNIT PCNER LEVEL FORM INSTRUCTIONS ON THIS FORM. LIST THE AVERAGE DAZLY UNIT PCMER LEVEL IN MWE-NET FOR EACH DAY IN.
THE REPORTING MONTH. THEE 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 PCNER.EXCEEDS
. THE 100 °/ 0 LINE. *coR 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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e e DOCKET NO 50-281 UNIT SURRY II DATE 2-1-81 COMPLETED BY -.SUE D. DUNN AVERAGE DAILY UNIT Pr.MER LEVEL MONTH: JANUARY 81 AVERAGE DAILY PfNER LEVEL AVERAGE DAILY PfNER LEVEL DAY (MIE-NET) DAI (MWE:NET) 1 761.0 17 755.4 2 761.8 18 755.0 3 759.5 19 _ 756. 5 4 759.3 20 758.9 5 761.9 21 759.8 6 762.3 , 22 758.7 7 758.2 23 756.7
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8 - 755.0 24 755.6 9 757 .5 25 753.4 10 752.0 .26 754.6 11 755.8 27 752.6 12 757.9 28 757.4 13 758.0 29 759.1
'14 759.5 30 758.8 15 758.3 31 757.9 16 754.9 DAILY UNIT PfNER LSVEL'FORM INSTRUC~IONS ON THIS FORM. LIST THE AVERAGE DAIL! UNIT PfNER LEVEL IN N'ilE-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.
e MMARY OF OPERATING EXPERIENCE e JANUARY,. 1981 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 JANUARY 1 This reporting period begins with the unit at cold shutdown for steam generator replacement and major design changes.
JANUARY 31 This reporting period ends with the unit at, cold shutdown for steam generator replacement and major design changes.
UNIT 2 JANUARY 1 This reporting period begins with*the unit@ 100% power.
JANUARY 2 At 1045 the Control Room Operator attempted to blend to the volume control tank (VCT). The attempt was unsucc'essftil and* an operator was sent to the Auxiliary Building to ascertain the cause. It was dis-covered that an operator had mistakenly tagged the Unit 2 blender instead of the Unit 1 blender.* At 1115 it was determined that the tagging of the Unit 2 blender violated Technical Specification 3.2.B.4, which requires two operabl~ boric acid flow paths to the reactor core,*
and a ramp down of the unit was commenced. At 1120 the tags were re-moved and the Unit 2 blender was returned to service and power was increased to 100%.
JANUARY 18 At 1054, the "2D" BORIC ACID TRANSFER~ (BATP) which was lined.up for service to Unit 2 blender, tripped. This violated Technical*
Specification 3.2.B.4, which requires two op_erable--boric acid. flow*"
paths to the reactor core, and a ramp down of the unit was commenced.
At 1100 the "2C" BATP was placed in service to supply boric acid to JANUARY 31 the Unit 2 blender and power was increased to 100%.
This reporting period -ends with the unit at 100% power.
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AMElIDMENTS TC- CILITY LICENSE OR TECHNICAL SPeFICATIOUS JANUARY, 1981 The Nuclear Regulatory Co11DD.ission issued, on December 18, 1980, Amendment No.
62 to the Operating License for Surry Power Station, Units No. 1 and No. 2.
The December 18, 1980 Condition of the License has been designated as Techni-cal Specification Change No. 68. The change requires the implementation of a secondary water chemistry monitoring program to inhibit steam generator tube degradation. Of significance, paragraph 3.K of the Surry Unit No. 1 and No. 2 Operating Licenses is amended to read as follows:
"K. Secondary Water Chemistry Monitoring Program The licensee shall implement a secondary water chemistry monitoring program to inhibit steam generator tube degradation. This program shall include:
- 1. Identification of a sampling schedule for the critical parameters and control points for these parameters;
- 2. Identification of the procedures used to quantify parameters that are critical to control points;
- 3. Identification of process sampling points;
- 4. Procedure for the recording and management of data;
- 5. Procedures defining corrective actions for off control point chemistry conditions; and
- 6. A procedure for identifying the authority responsible for the interpretation of the data, and the sequence and timing of administrative events required to initiate corrective action."
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~ FACILITY CHANGES REQUIR.IHG NRC APPROVAL e
JANUARY, 1981 None during this r.eporting period.
FACILITY CBAHGES THAT DID NOT.REQUIRE NRC APPROVAL UNIT D/C 77-9 Containment Spray System Modifications 2 This design change meets the following objectives:
a) Increased spray coverage b) Decreased caustic spray transit time to the spray nozzles.
c) Addition of caustic solution to the spray water at an essen-tially constant rate*
d) Provide caustic spray until the contaimnent is depressurized under all operating modes of the safeguards system.
Summary of Safety Analysis This.modification requires a change to Technical Specifications. A review of the FSAR. indicates a change to the function of the affected systems are
.not required. An unreviewed safety question does not exist.
D/C 77-19F-l Makeup Water Treatment Modifications 1,2 This design change installed instrumentation and controls necessary for adequate regenerations.
Summary of Safety Analysis This modification does not affect the Tech. Spec., does not conflict with FSAR. requirements, except that additions might be made to Section 9.11.3 Flash Evaporator Systems.
D/C 78-10 Condensate Polishing Addition 1,2 Portions of this design change. involving Buried* & Embedded Grounding (78-lOF),
HVAC Erection (78-lOJ), Connecting Piping (78-lOKA), Air Compressors & Air Handling System (78-lOL), Aux. Control Pauel (78-lON), Control Panel Modifi-cations (78-lONA), Condensate Pump Verification Test (78-10), Interior Fire Protection (78-lOQ), *Electrical Installation (78-lOS), and Condensate Pump Modifications (78!..lOT) were implemented.
Summary of Safety Evaluation This design change neither constitutes an unreviewed safety question or requires a change to Tech. Specs.
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Fac+lity Changes That Did N~Require NRC Approval (Continu~ UNIT D/C 78-S35 LHSI & ORS Pump Bellmouth Modifications 2 This design change installed a crossvane type extension for both pumps to ensure radial flow into the pump suction to elimi.Ila.te excessive vartexing.
Summary of Safety Analysis This modification requires no change to the Technical Specifications FSAR. requirements, and does not create "an Unreviewed Safety Question".
__ JJ/C 78 Steam Generator Blowdown Treatment System 2 Portions of this design change involving mechanical (78-44A) and Instrumentation (78-44D) -have .been impl-emented.
Summary of Safety Evaluation This modification has improved the overall safety reliability and performance of the steam generator blowdown system. The design specifications have met or exceeds the specifications of the existing system. The system was designed to meet the NRC guidlines presented in Standard Review Plan (10.4.8) for steam generator blowdown systems. The overall effects of radiological releases to the environment will be significantly reduced by removal of activity in the demineralizers.
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- Corrected Page for November, 1980 monthly operating report.
l
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~CILITY. CHANGES REQUIRING
- CORRECTED PAGE NRC APPROVAL UNIT
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- DC 7a-is Part Length Control Rod Removal 1,2 This design change removed the part length control rods from the core and inserted thimble plugs where the rods have been removed. An anti-rotation device was in-stalled to keep the lead screw in the raised position.
SUMMARY
of SAFETY EVALUATION Since no credit has been given to the part length control rods in the FSAR safety analysis, no safety mar-gin previously analyzed has been reduced.
FACILITY CHANGES THAT DID NOT REQUIRE NRC APPROVAL DC 80-3A Installation of Flashing Lights in EDG 1,2 and Charging Pump Rooms Activated by Station Alarms This design change provides the capability of acti-vating flashing emerg~cy lights in the aforementioned
( spaces when the evacuation, fire, or first aid team alarms
'--* are annunciated.
SUMMARY
of SAFETY EVALUATION This improvement to the station communications system is designed to supplement the present audibility and visi-bility of alarms and evacuation announcements and has no impact on the safe reliable operation of the presently installed plant communication system.
- Corrected Design Change Number. In November, 1980 report appeared as DC 78-35 *
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- Corrected Page for December, 1980 monthly operating report.
- 1 *** .. **-*-***-****-* *-----*--* ....*... , ......
"'."13- CORRECTED PAGE F~cility Changes That_ Did ~Require NRC Approval (Continue UNIT Summary of Safety Analysis 1,2 This modification provides additional fire protection and increases c* the safety margin.
D/C-80-18 Temporary Low-Level Radwaste Storage Facility 1,2 This design change provides a temporary low-level radwaste storage building for compaction, handling and storage. This building holds the waste volume that is expected to exceed allotment quotas during normal plant operation and during the Unit 1, SGRP.
Summary of Safety Analysis This modification does not effect normal station operation or the
_operation of any.Safety related equipment. On~site storage of low level dry waste is not discussed in the FSAR..
- D/C 80-S37B AFB Redundant Level Indication and Alarm In Control Room 2 This design change installed instrument* and electrical equipment for the addition of Auxiliary Feedwater redundant level.indication and alarm capability in the Control Room.
Summary of Safety Analysis This modi£ ication does not affect the Technical Specifications and the FSAR. Installation of the safety grade redundant level indication and alarm capability for the AFW System Condensate Storage Tanks does not create an unreviewed safety question as defined in 10CFR 50.59, C-.* D/C 80-83 Charging Pump Safety Injection Automatic Removal 1,2 This design change was performed in response to I.E.Bulletin 80-18.
It provided a means of removing the Safety Injection Automatic closure signal from the charging pump miniflow isolation MOV's.
Summary of Analysis This modification increases the safety by preventing damage to the charging pumps. This interim measure is scheduled to be superceded by a more permanent method of controlling the system at a later date.
D/C 80S90 Diverse Isolation Signal Condenser Air Ejector Vent Trip Valve 1,2 This design change provides a diverse isolation signal to the condenser air ~jector vent trip valve. This modification involved the re-routing of new cable over to the Engineered Safeguards' Cabinet and terminating to existing safety injection signal outputs.
Sumnia.ry of Analysis This modification provides a more diverse and effective contaimnent isolation and com.plies with the requirements of NUREG-0578. This design change has no effect on the operation of othe,.r safety systems or safety related equipment.
- Corrected Design Change Number and Unit: desi~t-ion... -*-In *b~~ber i9SO report
~- appeared as DC 80-S27B for Units 1 & 2.
STS AND EXPERil-1ENTS REQUIRING A NRC APPROVAL
- JANUARY,. 1981 None during this reporting period.
TEST AlID EXPERIMENTS THAT DID NOT REQUIRE NRC APPROVAL None during this reporting period.
A A O'ta. CHANGES, TESTS .AND EXPERIMENT9 JANUARY,. 1981 None during this reporting period.
e SURRY POWER STATION e CHEMISTRY REPORT January , 19.JU_
T ~ S
- 6. 6
- 3.* d PRIMARY COOLANT UNIT NO. 1 UNIT NO. 2 ANALYSIS MAXIMUM MINIMUM AVERAGE MAXIMUM MINIMUM AVERAGE Gross Radioact., µCi/ml l?.49E**J 7.28E-2 1.4SE-1 Suspended Solids, ppm 0.1 0.1 0.1 Gross Tritium, µCi/ml 2.72E-1 2.44E-1 2.54E-1 Iodine-131, µCi/ml 2.49E-3 1.94E-3 2.18E-3 I-131/I-133 a..0318 .* 7288 .8268 Hydrogen, cc/kg 49.9 34.6 42.7 (c)
- (c Lithium, ppm 2.50 2.13 2.29
'Boron-10, ppm+ 142 127 114
_Oxygen-16, ppm .000 .000 .000 Chloride, *ppm .05 *.os .05 pH@ 25°C f!.94 6.81 6.87
+ 'Boron-10 = Total Boron x 0.196 NON-RADIOACTIVE CHEMICAL RELEASES, POUNDS T.S. 4.13.A ... §,~*
Phosphate 117 (B) Boron 436 Sulfate 0 Chromate .30 *
,50~ NaOJi 12 (B) Chlorine* 0 Remarks:(A) Unit 1 is at CSD & defueled with system drained for SGRP.
(B) P.hosphate a~d NaOH plus Slb. wetting agent us~d to chemically clean B" package boiler.
(C) High lithium due to inabi1ity to place cation bed in service These levels of chemicals should represent no major adverse enviromnental impact.
- _ _,.( .. -**
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D'CRIPTION OF ~ - INSTANCES WERE e THERMAL DISCHARGE .LiliITS WERE EXCEEDED JANUARY, 1981 0
Due to the :impairment of the circulating-water system on the following days, the thermal discharge limits were exceeded as noted.
JANUARY 7, 1981 Exceeded 15°F AT across station
- 0 *- .
JANUARY 8, 1981
- Exceeded 15 FAT across .station 0
JANUARY 14, 1981 Exceeded 15 FAT across station 0
JANUARY 18, 1981 Exceeded 15 FAT across station 0
JANUARY 19, 1981 Exceeded 15 FAT across station 0
JANUARY 20, 1981 Exceeded 15 FAT across station 0
JANUARY 21, 1981 Exceeded 15 FAT across station JANUARY 26, 1981 '
- Exceeded 15°F AT .across station JAUUARY 27, 1981 Exceeded 15°F AT across station JANUARY 28, 1981
- Exceeded 15°F AT across station___ -** .....
- Indicates dates where station AT was less than 15.0 F across station for 0
sometime.during the day.
The AT excursions were allowable under Technical Specification 4.14.B.2.
There were no repor~ed instances of adverse enviromnental impact.
FUEL HANDLING UNIT NO. 1 JANUARY, 1981 None during this reporting period.
FUEL HA?IDLillG
'tlNII NO. 2 e JANUARY, 1981 None during this reporting period
- I PROC URE REVISIONS THAT CHANGED THE e
OPERATING MODE DESCRIBED IN THE FSAR JANUARY, 1981 None during this reporting period.
~ PR~URE REVISIONS THAT CHANGED rue OPERATING MODE DESCRIBED IN THE FSAR JANUARY, 1981 None during this reporting period.
~ ~CRIPTION OF PERIODIC TESTS WH~ WERE NOT CO}fi>LETED WITHIN THE TIME L ITS SPECIFIED IN TECHNICAL SPECIFICATIONS JANUARY, 1981 A recent review of Tests conducted revealed the following tests were not performed:
PT-37.1 Electric Hydrogen Recombiners was not conducted on Unit No.l when scheduled on 7-15-80. This monthly test is perfopned to test the electric hydrogen recombiner control panel gauges and controls. The test was conducted satisfactorily on 8-18-80.
PT-53 Quarterly Testing of PORV was not conducted *on Unit No. 1 when scheduled on 6-15-80. This quarterly test is to sr.r:ake valves ta their required position and measure stroke time to monitor proper valve operation. The test was conducted satisfactorily on 9-l9-80
- e e, INSERVICE INSPECTION JANUARY, 1981 UNIT 1 The Westinghouse program for inservice inspection is still in progress.
No major indications have been noted. An inspection of ASME Class III.Han-gars and component supports is still being conducted. Conducted penetrant inspections of the penetration pipe cap program with no indications noted. ,.
The inspection of components associated with Unit 1 H.P. and L.P. turbines is still in progress. Conducted an ultrasonic inspection of the service water piping to the recirculation spray coolers in contaimn~t and a visual of the piping ID from the safeguard area into the service building - no problems were noted.
UNIT 2 No inservice work was conducted.
~TABLE OCCURRENCES PERTAINING T
...... ANY OUTAGE OR POWER REDUCTION; JANUARY, 1981 None during this reporting period.
e Maintenance of Safety Related Systems During
- 0utage or*Reduced*Power Periods UNIT #11 Mechanical Maintenance
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- -01/011/ilt*-- ss--ll'INB'R- **--------*-*. 1.A'N:R "BROlKN **-----------&-PAIR!lU--riA...2"'"'li'IFll---------i---u-to61532--*29 - - - - - * - - - **** -- * ..
n 01/09/111 DG PIPING 3-DG-26 DIC 79-S32C SUl?POR'r NOD. CONl?LSTI . 1 OOIJ21J105" 2731 ~ ') '.'
01/09/111 CR l'IPIIIC 2-C'R-59 . DIC 19-832C INSTAL£ SUPPPOR'l' NOD.
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1 00605071J9 2233 l-00902llfOr- *-- 600 * -****-- -* **:**-* . .
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01/09/111 CR VALVJ l-cH*391J R!l'LAC!l DIAPRRAN II VALVE R!lBUILT VALV.f l 101021"00 19
--u110,111r-ar--nLn--1-=c11;;s:, BYPTA~-01APHRArrnr,nn SBUitt'-v,ttv!lr-----------11----11flo102tff1s---20
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- 01/09/111 CB VA£V.f 1-cH-13 REP£A~ DIAPHRAN Ill VALVE OVBRRAULBO VA£V8 1 1010211f32 17 ')
01/09/81 CR VALV'6 1-cH-6 R'Sl'LAC!f DIAPHHAN Ill VA£VB ll!rl'LACBD DIAl.'BRAGN 1 1010211f39 20
- *-*-***-* --,.~ ~--1----- --***- " * - * * * - - * * * * * - -***********-***
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- 01/10/11 C'R VALV.f 1-cR-55 RBPLAC.f WJLTING . Rll'LACBD S'l'UDS OIi VALVJ 1. 010231656 35 *-,
01/10/111 IT: VALVE 1-rc-1 /M'LA{:g BOLTilfG R'Sl'LACSO sruos Olf VALV.f 1
- 012081130 1111 * . --
1 01/10/111 ---* IT: *-- VALV.f --* 1.:.rc-1& *----,m,LA~
- BOLTiltG-----------~R!'l'l;AC!'D ffl/D8-otr-rA£V!---------1--1>>12o111u2 * ---1111- ***-- .. ----*- ...... *
~'-* * ; 01/11/11 CR VALV.! 1-CR-..IJ RHPLAC!l BOLTING R!l'LAC5VD STUDS Olf VA£V!' 1 010231653 122 0 i 01/11/111 lJI VALB 1-IN-23 REP£AC.f BOLTING R.fPLAC1 STUDS 1 011171029 3..
.-01,111a1--n--,AL~-1 =BR"&*r---R!rl'IACS BOLTING R!'l'tilC!' *fflJm-* --t--1>>111919011----s-----------"'* - * *-
01/11/81 BR VALB . l*BR-63 RSPLACB BOLTING REPLACE STUDS 1 011191909 3.. 0 01/11/81 BR VALV.! 1-BR-2116 BPLAC!' BOLTING RSPLACS STUDS 1 011191916 31f
- --01111111*-* TIC .. ..... ,ALV.!--*1;;;RC=-1og --*-****---**Rsl'IACB BOLTING---- .. -***-****--- .. ---
- --ui'I.ACI 'STUDS ____ -------*---*--t--'0121011f22*----n--* * * -*****-**--** * ...
[; ! 01/11/11 RC VALV.f 1-IW:-112 R'Sl'LAC!' BOLTING - RSPLACS STUDS l Ol21011f23 35 . 0
- *: 01/11/81 RC VALV.! 1-RC-115 RSPLAC.! BOI.:rING R!PtAC!' STUDS 1 01210llf21f 35
- -lJI/ll/81-llC*-v.u;n-*--* 1 :.:RC.:.10& -*--~-llEPLA~ BOLTING -*- -- - ... - R!rl'tAC!J* STUm---***- - -t"-012101lf2S *--35----- ------**** ..
, ..I . 01/11/11 RC VALV.f. 1-RC-lllt RSPLAC.! BOLTING R3PLAC!' STUDS 1 , 01210llf26 35 o.
01/11/111 RC VALV.f 1-RC-1111 REPLAC.! BOLTI1'G REl?c.AC!' SWDS , 1 0121011f27 35
.----01/11/111 *--RC -- -VALV.f*-- - 1.:.RC.:.121 - -****** REl.'LAC.! BOLTING - -** * ** -** * * -- --*----R!l'tAC.f ffl/os*-**--- * *- - *- - **- --"* **-t-*0121011f28***-** ****S!I*--*-* *-**** * * -*-* -- * **** ** :
01/11/81 RC VALV!' 1-RC-120 REP£AC5 BOLTING llEl'LACI STUDS 1 0121011f29 35 I ()
. ----------- . . -------******- --**--** .....___________ **---*** *-* ... I
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f' . 01/11/11 RC VAlVI 1-RC-151 SPLA'3 BO£TI1'G RSPLAC!l STUDS 1 0121011J31 35
. , 01/11/111 RC . VALVE 1-RC-152 RE1'£AC!/ B0£TIN<J RHPLAC!I STUDS 1 012101432 35 r-*- **ot/11/iil' -**,c **--vAtVI **- -1;;RC;;153. *--~- -*nPLAC! WJL'/INO *-** *****- - ... -------*--nP£AC! STUDS **-----1-*i,121011J33-* ------*--*35-*--***--------* * --
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- 1' 01/11/11 RC VA£V.f 1-RC-113 REP£ACE B0£'l'ING R!/PLAC.f STUDS 1 Ol21011J37 35
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01/12/81 W NOV M1V-W-151D GROU1'D A1'D REPAIR f1E£DS CONP£ST!/D 1
- 00921f1901 1269 0 01/12/11 W: VAI,VI BCV-1550 REPUCB BOLf'INO * . llEP£ACED STUDS 1 0121011105 19
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(' ! 01/12/11 RC VALVI 1-RC-159 R§'LACE BOI.'l'Itr<J REPLAC8 STUDS 1 012101,.36 19
. : 01/12/11 RC VAI,Vll 1-RC-l'tl REPLAC.f IDIJIING REP£ACED STUDS 1 0121011flll0 1112
- RBPLACED M'llDS 1 012101-.u~r-------*-*.
f' 01/12/11 SI NOV lll7A CRECIC 'l'B!l NECH OP.fRAirIOII . CRIAs8D NOV 1 012180925 itlf 01/12/111 SI IIOV 11678 Cll!:CI IBCH OP!lRATIOlf . CR!IAsED /IIOV 1 012110926 !flt
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C\: .: 01/12/81 SI llfJV 1167D CR!:CI NECH OP!IR _ . . CR!lASEO NOV 1 012110921 ltlf
.' 01/12/11 CH VAtV.f 1-C'II-IJU DIAPHRAN BROK!ltr VALVE DO!/S trf1f' HOU CONPLff.fD 1 101071,.16 66
- :-u,12,u-w-NOv*--MW;:w=n1s tBAlS"'F!IRfr----** COMP£!2'ED 1 905I808IJO--n&g----------- .....
£i 01/13/81 CV VA£V5' l'V-CV-10C BXC!fSSIVY ~AICA<JB . D18ASSl VA£V-' 1 012051200 690 01/13/11 RC VAI,V!/ BCV-1523 REP£Af3 B0£TIN<J . REPiAC!fD STUDS Olt VA£VE t 0121011J03 IJ3
-*--o1,u1er-r . - . VAtv.t***--** Rcv;:u22A _____ RJPl'.ACJ -110ir1Nl: ------- RRE'IAC!' mos------- *- l 0l211J11UB ___ lf3 --*-**---*-- .
,-,; 01/13/11 RC VAI,V.f BCV-15228 REP£ACll BOIJIIN<J REI1£AC!J STUDS *: 1 0121011f17 lf3 01/13/81 RC VA£VE BCV-1522C REPLACE B0£TING REPLACE STUDS i 012101"11 lf3
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(,-, ' Ol/llt/81 RC VA£V.f RCV-151f9 REPLACE BOIJIING REPUCE STUDS 1 01210i1JOIJ 11
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.- Olllli7H-w--ar-,n*-1*;;;,v;:p;;>Jg----*ggAo Dir COO£ER-BR0ICE1'-- - "1l!fff0V!D-H8AlrBRAUD fWJil 1 --iot130illls-- 01/11f/81 W BX 1-W-3A REPAIR BROKEN WBE OIL COOUR R!/PLACED <JABIi.ff Al' ll!Ao; 1 10113011t7 31 0 01/15/11 CTI VA£V.f l-cH-62 REP£AC!f DIAPBRAN Itr VA£V!' CONPU'r'SD t 101021,.llf 161
. i-- 01/15/111 *--ca-- VA£V5' - * -*1 ;;cg;.55-* -* *- . -- . --REPI.ACS DIAPHRAN Itr VA£VE - --*----****- CONP£ST!/D**---*---*----- -*---**------*-*r-101021"19 ** ---1s1 -**- -* **- ... -- *- *-* .. .
(} 01/15/81 CH VA£V.f 1-CB-55 R!IP£AC!/ DIAPBRAN Itr VA£V!/ CONP£ff!'D 1 1010211f20 161 '.)
. 01/15/11 CB VALVE. 1-cH-50 UPI.AC!/ DIAPHRAN IN VA£V!f CONPLSTSD 1 l010211J23 161
--u111&7111- -so--- VA£F.! * - -* -1;;:BD;;& ----**-*-vALV.f IEAICING iJr**-- - * **--**--------. ,l!PLAC!fD rA£Vll ________ -- 1-002200737 ---21-* -*------ *-** --***
01/16/81 01/16/111 SI 81 VA£VI VA£VS IIOV-1865-A llfJV-1865-B RE1'£AC!/ B0£'l'IN<J REP£AC!f B0£T1NG RJPI.AC!/ STUDS RJP£Af:6 STUDS 1
1 012051106 012051107 79 79 u
.-- - -01;1&/lil * - *sr -- VA£VE * - ... llfJV-1965~ * - * *REPI,AC!J B0£TitrG * ****--- --- R!fP£AC!f STUDS -- .... - *012091101 ** * * -- 711 **-- ... - . *-****
01/16/11 NS PIPitr<J 1-NS-31J6 R!/P£ACJ 1-NS-31J6 INS'l'A££SD tr!'II VA£VE 1 101101253 150
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9 F!B 81
- 3130 l'N PAGE 5 0 . Ulfif'1- 2/09/81 ,-, ;
(1IAIN'l'DANCB OE' SAFH'l'1 RELATED srsrEN.S DURING OUTAGll OR R!Df/C8D PfNER P!RIODS)
IBT6ERVl6 Sl8 CONP NARICIIO SUNNAR1 JIKPERF u ,*)
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(_') 01/16/H FP Pf/MP l*FP-2 BEARING IS RUNRIIIO RO'l' CLEANED BARRING 1 10115221f7 lit , ') i 01/17/81 RC VA£V! 1-RC-1112 REPLACE '/XJLTING R!IPLAC!D STUDS 1 0121011flf2 IJ2 01/17/81--. BJ"- - VA£n* . ""RV=-SB=-101 *--*-*---* SEAL OIi REI.I!IF VALVE iEAKitrG* .. *-*-** -**-*c11wrED ItrrERNAC8 OF VA£V!I * --*-* * ---1--io11!11600 - - .....
- 10 ....
01/18/81 CB NOV NOV-1289A PACKING T.EAICIIIG 'I'IGIIT!NED PACKING GT.AIID 1 00709122't 5& rJ ' I
-*-* Ul/19/ll .. -*l:11 *-* --*vAtn --- 1 ;;ca;.;.119 **---R!lPLACE. BOL'I'IlfG-- -*-------* -*---REPI;ACirtrBOT.'ritra*-- ---*-~- -010231711---30 ----... _ ..._ .. **-****
- 0 01/18/81 CR VALV8 1-Cfl-122 REPLACE BOLTING REP£ACED BOLTING 1 010231713 30 '1 !
01/18/81 CH VA£V! 1-cH-123 REPLACE IJ()£'l'ING . REPLACED BOL'l'ING 1 010231711t 36
.--- 01/111/111--. 'Ill-*-- VA£VJ' ---- 1;.;.m.::310 *-*-*--* R'!rPLACE IJ()LTI1'G ...... _... * - * -***-..--..-*-REPLACT *sruos------**-- ----*---i-011171030 ....... _. __ 38 -* * .. * * * * * * ...
0, . 01/19/H BR VALVE 1-BR-12 REPLACE WJ£TI1'G REPLACED BOL'l'IIIG 1 011191902 30
. I 01/11/81 BR V4£VE 1-BR:..15 REE'£AC! BOT.'rIRG REPLACE STUDS 1
- 011191903 21f
-*-** 01/11/Bl"-** BR ..--. VA£VB ----1.::BR.::73* -----RTIPIAc:K *mr:r111r;--* - ~£AC3D B0£'1Itra--* 1 011191901J----30**-----------*-- -
- 01/19/91 FP DI&'JEL 1-FP-P-2 ~OIN'l' !IXHAUS'l' SPI.I'r RSWELD!lD JOINT 1 10115221f6 62 01l19~~! ___ BD PIPIIIG 3-flGCB*2 ' DIC 79-S32C IIIB_!~~~-~~~1.'!_ NOD. ' SUE'POH.l' INS'l'ALi!D 1 005051~01 817 O : 01/19/H IS PIPIIIG 3-WST.-'t DC79-S32C IWSTALT. SUPPORr CONP~~. 1 0090211f12 839
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o 01/19/81 01/19/111 DI DI VALV!I VAT.VE 1-I>>-337 1-I>>-179 R!lPLACE IJ()£TING RSPT.AC! BOLTING
. REPLACED STt/Ds AIID lrUTS Iii VAT.VE Rlll'LAC!D STUDS.
1 1
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01/20/81 81 VALV! 1-SI-28 REPLACE BOLTS , RAS RO IJ()L'rS '10 REPiAC! . 1 010011332 1733
- - . 01/20/81- --* o r - -vALV! ----- 1 "Df'-322 --MPLAC! 80£'1Itra ___________ *R!P£AC!
- S'l'UDS - *- - -~011111051 --*110----**--- .... *-- **- -
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.i 01/20/111 BR VALVE l*BR-310 R!PLAC! BOLTING REPLACE S'l'UDS 1 01U91111J9 60 0
,. *-1J11201u---BR-rALn----1-BR-327 -
1 0l/20/91 01/20/H BR BR VALV!
VALV!
1-BR-71 1-BR-285 R!PLAC! IJ()LTIIIG---
REPLACt BOLTING RBPTACE BOLTING ,
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REPLACED l10£'1IWG R!fPLACED BOlll'INO
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1 011191901 1 011191911 78 78 e,.)
Q,. 1 01/20/111 8S DOOR R&'JEA!, DOORS REPAIRED + RESEA£!:D DOORS 1 101192230 22
. , I . 01/20/H BS DOOR FB DOOR 23 R&'J!AT. DOORS CONPUTBD 1 101192233 22
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o' j 01/22/H DI VALV8 . 1-l.N-1155 REPLACE 80£'1IIIG REPLACED() S'l'UDS AND DI'f'HRAN 1 011171011f 36 *J
- *1 01/22/H 1.N VALVJ' 1-1.N-lfS& REPLACE WT.TING RSPLAC!l Sf'UllS AtrD DI11PHRAN 1 011171015 36 .
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r, *i 01/23/81 CH VALV!S VALVES NEED LAGGING CORRECT!lD PROBI,JN JIITH IISULATIOII 1 011270232 1188 .... )
. . ! 01/23/81 CH PUMEIS 1-CH-P-2A PUMPS NEED INSUC.ATED BOXES .
- BUIC.T + INSUC.ATSD PUMP COVERS 1 . 011270233 11118
! t--Oi/2:ililf-- ctr- PUMPS**-* 1;;:cg.;.p-2s --***-- PUNP8 NEED INSULATED BOXEs**--*---BUilll'-i-*1NSUCATED"PIINP-COVERS _ _ _ _r-01121023q--- uaa--**-. --- ***-**- ..... .
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01/23/81 CR 01/23/81 CH PUNPS . 1-CR-P-20 VAC.V.! 1-Cll-lt9 PUNPS NEED INSULATED BOXES REPLACB DIAPHRAN IN VAI,V.!
BUilll' BOXES + INSUc.ATED THEN REPLACED DIAE'HRAN Ill VALVE 1
1 011270235 10102111211 1188 3117
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- , I 01/ill/81 BD E'IE'IIIG 3-fiGCB-2 DIC 19-S32C INSTALL SUPPOR'l . IISTAI,£ RANGER TO SKE'rCH 1 005021600 2203
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3-DG-23 1-lll-259 IX:79-S32C INSTALL SUPPorrr R!lPLAC.! BOLTING
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e HEAL1"t:l "PHYSICS t ' . ~ JANUARY, 1981 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.
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PROCEDURE WIATIONS REVIEWED BY STATION
' "" SAFETY AND PERATING COMMITTEE AFTER TIME
- ' . SPECIFIED IN TECHNICAL SPECIFICATIONS JANUARY 2 1981 Date SNSOC No.
PT-24.14
-Unit N/A Title Date Deviated Reviewed Fire Protection System- 12.-17-80 1-8-81 Security Halon System**
MOP-1.5 1 Removal of Safety Related 10-22-79 1-8-81 Heat Exchanger OP-8.8 1 Operation of Excess 10-22-79 1-8-81 Letdown OP-14 1 Residual Heat Removal 10-22-79 1-8-81 System