Text

Monthly Operating Repts for Sept 1983
	ML20081M509
Person / Time
Site:	Surry
Issue date:	09/30/1983
From:	Jones V, Stewart W, Joshua Wilson; VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To:	Haller N; NRC OFFICE OF RESOURCE MANAGEMENT (ORM)
References
	583, NUDOCS 8311170282
	Download: ML20081M509 (61)
	v • d • e

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O VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION MONTIILY OPERATING REPORT REPORT NO. 83-09 APPROVED BY:

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Section Page

~)perating Data Report - Unit #1 1

Operating Data Report - Unit #2 2

Unit Shutdowns and power Reductions - Unit #1 3

Unit Shutdowns and Power Reductions - Unit #2 4

Load Reductions Due to Environmental Restrictions - Unit #1 5

Load Reductions Due to Environmental Restrictions - Unit #2 6

Average Daily Unit Power Level-Unit #1 7

Average Daily Unit Power Level-Unit #2 8

Summary of Operating Experience 9-12 Amendments to Facility License or Technical Specifications 13 Facility Changes Requiring NRC Approval 14 Facility Changes That Did Not Require NRC Approval 15-19 Tests and Experiments Requiring NRC Approval 20 Tests and Experiments That Did Not Require NRC Approval 20 s

Other Changes, Tests and Experiments 21 Chemistry Report 22 Description of AllInstances Where Thermal Discharge 23 Limits Were Exceeded 24,25 Fuel IIandling l

Procedure Revisions That Changed the Operating Mode l

Described in the FSAR 26 l

l Description of Periodic Tests Which Were Not Completed Within the Time Limits Specified in Technical Specifications 27 i

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fi Section Page Maintenance of Safety Related Systems During Outage or Reduced Power Periods - Unit #1 - Mechanical Maintenance 28-30 Maintenance of Safety Related Systems During Outage or Reduced Power Periods - Unit #2 - Mechanical Maintenance 31-4 4 Maintenance of Safety Related Systems During Outage or Reduced Power Periods - Unit #1 - Electrical Maintenance 45,46 Maintenance of Safety Related Systems During Outage or Reduced Power Periods - Unit #2 - Electrical Maintenance 4 7-51 Maintenance of Safety Related Systems During Outage or Reduced Power Periods - Unit #1 - Instrument Maintenance 52,53 Maintenance of Safety Related Systems During Outage or Reduced Power Periods - Unit #2 -Instrument Maintenance 54,55 Health Physics Summary

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56 Procedure Deviations reviewed by Station Nuclear Safety and Operating Committee af tter Time Limits Specified in T.S.

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1 C?ERATit:G DATA REPO.T O

i DO:KET NO. 50-280 e

DATE 06 OCT 83 C0t?LETED ?? Vivian Jones TELEv!!DNE 804-357-3184 0?ERCII:G STATUS

,1. U!:IT !!AAF SURRY UNIT 1

2. RE?0!CING ?ERICD 901B3 TO 93083

3. LICE!! SED THER"AL POWER (??dT) 2441 l~~~"""~"""""")

o. NA!!E? LATE FATII;G (GROSS ITE) 847.5 INOTES l

5. DESIGN ELEC"'RICAL RATING (NET IT.T) 788

6. llA::I:!Un [E?ENDABLE CA?ACI."? (GROSS '?dE) 811

7. llAXI:llll! DE?E!!DAFLE CA?ACITY (NET %T) 775

8. IF CHA?!GES OCCUR Zll CA?ACITY RATINGS N/A (ITE'!S 3 TiiROUGH 7) SINCE LAST RE?CR", GILE REASONS

9. POYER LEVEL TO YHICH RESTRICTED, IF ANY N/A (NET !!E)

10. REASONS FO? RESTRIC* IONS, IF ANY N/A TdIS ::0 NTH YR-TO-DATE CU?!ULATILT

11. ROURS IN REPOR*ING PERIOD 720.0 6551.0 94439.0 12.1.7]?!BER GF HOURS REACTOR WAS CRITICAL h54.7 3194.1 57105.8

13. REACTOR RESERVE SHUTDOVR E0023 0.0 0.0 3765.2

14. HOURS GE!!EPATOR 01:-LINE 472.8 3087.9 55942.6

15. Ui:li REEERVE Sh7!TDOWN HOURS 0.0 0.0 3736.2

16. CRCSS 7EER!fAL ENERGY GENERATED (Ifv2) 1132999.9 7211317.9 129891917.8

17. GROSS ELEC"'RICAL ENERGY GENERATED (?GH) 357880.0 2283720.0 41889763.0

18. NET ELECTRICAL ENERGY GElERATED (?NH) 339040.0 2161543.0 39722006.0

19. UNIT SERVICE FACTOR 65.7 ole 47.1 o/*

59.2 olo

20. UNIT AVAILARILITY FACTOR 65.7 e/o 47.1 o/o 63.2 o/o

21. UNIT CA?ACITY FACTOR (USING 1:DC NET) 60.8 o/*

42.6 */c 54.3 e/o

22. UNIT CA?ACITY FACTOR (USING DER NET) 59.8 e/o 41.9 o/o 53.4 c/o

23. UNIT FORCED OUTAGE RATE 2.2 o/*

1.0 ofa 22.0 o/*

24. SHUTDOFNS SCHEDULED OLTR NEXT 6 /fCNTSS SPRING MAINTENANCE-10 DAYS-04-13-8 4 (TYPE,DATE, AND DURATION OF EACH)

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25. IF SH!!T DOWN AT END OF RE? ORT PERIOD, ESTI.\\! ATE DATE OF STAR"71?

26. UNITS IN TEST STATUS FORECAST ACH 3TD

(?nIOR TO COA:1ERCIAL 0?ERATION)

INITIAL CRITICALITY INITIAL ELEC*IRICITY C0!!hTRCIAL 0?ERATICN

2 0?: EATING DATA R: PORT DOCEET

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50-281

[ ATE 06 CC' 83 CO':?LETED 3? Vivinn Jones TELEPHOl.T 60:-357-3184 OPEMTING STAT'!S 1.'L7lIT N D.T SURRY UNIT 2

2. RE?ORTING ?:PICD 90163 TO 93083

3. LICE l?3ED THER'ML ?OVER ('9T) 2441 l ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~~ l

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?:A?S? LATE RATING (GROSS INE) 647. 5 l NOTES l

5. DESIG!! ELECTF1 CAL RATING (NET '5T) 786 6.11XI!!Ui! DE?ENDAELE CA?ACITY (GROSS *:iT) 811

7. ?'AXIn!U:! DE?ENDA5LE CA?ACITY (NET WE) 775

8. IF C.?ANGES OCCUR IN CA?ACITY RATINGS N/A (ITC'S 3 THROUGH 9 ) SINCE LAST RE?OR', GIVE REAS0!;S

9. PCLTR LEWL TO WHICH RESTRIC"TD, I? ANY N/A (NET lye)

13. REASONS FOR RESTRICTIONS, IF ANY N/A THIS l'ONTR YR-TO-DATE C7HlULATIVE

11. HOURS IN REPORTING ?ERIOD 720.0 6551.0 91319.0

12. NUNBER CF HOURS REACTOR WAS CRITICAL 119.2 4219.4 56893.9

13. EEACTOR RESERW SHUTD0k72 HOURS 0.0 0.0 0.0

14. HOURS GENERATOR ON-LINE 49.0 411C.6 55954.7

15. UNIT RESERVE SHUTDOWN HOURS 0.0 0.3 0.0

16. GROSS THERVAL ENERGY GENERATED (!.2H) 78502.6 9744992.7 130966338.8

17. GROSS ELECTRICAL El.TRGY GENERATED (L'iH) 21495.0 3139290.0 42592009.0

18. NET ELECTRICAL ENERGY GENERATED (!GH) 19536.0 2947032.0 40367953.0

15. UNI? SERVICE FACTOR 6.8 olo 62.7 */o 61.3 olo

83. UNIT AVAILABILITY FACTOR 6.8 o/o 62.7 o/o 61.3 o/o

21. UNIT CAPACITY FACTOR (USING llDC NET) 3.5 e/o 58.0 o/o 57.0 o/o

22. UNIT CA?ACITY FACTOR (USING DER NET) 3.4 o/o 57.1 o/o 56.1 o/o

23. UNIT FORCED CUTAGE RATE 31.9 a/o 1.9 e/o 14.5 e/o 24 SNUTDOWNS SCHEDULED OVER NEXT 6 !!DNTHS SPRING MAINTENANCE-10 DATS-03-30-84 (TZ?E,DATE,AND DURATION OF EACH)

25. IF SHUT DOWN AT END OF REPORT ?ERIOD, ESTIi! ATE DATE OF STARTU?

26. UNITS IN TEST STATUS FORECAST ACHIELTD (PRIOR TO COMl!ERCIAL OPERATION)

INITIAL C.UTICALITY INITIAL ELECTRICITY COleTRCIAL OPERATION

IM)CK E I NO.

50-280 l

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Ill while chnnnel II was being tested. Af ter trip,chnnnel III was checked and no problems found.

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Unit was shutdown for snubber inspection and f all outage.

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83-14 9-28-83 F

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3 Ilenctor trip caused by a high level in "II" li steam generator during plant startup. Problem was enused by feed regulating bypass viilves not working properly, had to be re-ndjusted.

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7 DOG:ET l'O 50-280 36-UNIT SURRY I DATS 10-1-83 C0!PLETED By Vivian Jones

' AWRAGE DAILY UiIT P0hTR LEVEL M0!G:. SEPTEMBER 83 AVERAGE EAILY POWER LEVEL AWRAGE CAILY P0hTR LEWL DAY (h%T-NET)

DAY

(!&T-NET) 1-727.8 16 735.0 2

733.6~

17 734.5 3

734.9.

18 734.3 4

732.9 19 734.2 5

728.5 20 718.4 6

728.6 21 31.3 7

724.9-22 0.0 8'

723.3 23 0.0 9

714.1 24 0.0

~10 728.7 25 0.0 11 727.4 26 0.0 12.

725.7 27 0.0 13 731.2 28 0.0 14 320.9 29 0.0 15 656.4' 30 0.0 DRILY UNIT POWER LEVEL FOR!! INSTRUCTIONS ON THIS FORM, LIST.THE AVERAGE DAILY UNIT POWER LEVEL IN MWE-NET FOR EACH DAY IN THE REPORTING ll0 NTH. TiiESE FIGURES WILL RE USED TO PLOT A GRAPH FOR EACH REPORT-ING MONT3. NOTE THAT BY USING llAXIMUM DEPENDAELE CAPACITY FOR THE NET ELECTRICAL RATING OF THE UNIT, T?ERE MAY BE OCCASIO!!S WHEN THE DAILY AVERAGE POWER EXCEEDS THE 100 e/o LINE (CR THE RESTRICTED P0kTR LEVEL LINE). IN SUCH CASES, THE AVERAGE EAILY UNIT POWER CUTPUT SHEET SHOULD BE FOOTROTED TO EXPLAIN THE APPARENT AN0llALY.

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DATE 10-1-83 C0!'?LETED BY Vivian ibnes AVERAGE DAILY UCIT PCWER LEVEL

.NO"TH: SEPTD2E? 83

- AWRAGE DAILY POWER LEVEL AVERAGE DAILY POWER LEVEL

DAY (b.VE-NET)

DAY (GT-NET) 1 0.0 16 0.0 2

0.0 17 0.0 3

0.0 18 0.0 4.

0.0 19 0.0 5

'0.0 20 0.0 6

0.0 21 0.0 7

0.0 22 0.0 8

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9 0.0 24 0.0 10 0.0 25 0.0 11 0.0 26 0.0 12.

0.0 27 0.0 13 0.0 28 0.0 14 0.0 29 302.2 15 0.0 30 511.8 DAILY UNIT' POWER LEVEL FO?E INSTRUCTIONS ON THIS FOR!', LIST THE AVERAGE DAILY UNIT POWER LEVEL IN HWE-NET FOR EACH DAY IN THE PZPORTING MONTH. THESE FIGURES VILL BE USED TO PLOT A GRAPH FOR EACH REPORT-ING HONTH. NOTE THAT BY USING MAXIMut! DEPENDABLE CA?ACITY FOR THE NET ELECTRICAL EATING OF THE UNIT, THERE VAY BE OCCASIONS WHEN THE DAILY AVERAGE POWER EXCEEDS THE 100 */o LINE (OR THE RESTRICTED POWER LEVEL LINE). IN SUCH CASES, THE AVERAGE DAILY UNIT POWER OUIPUT SHEET SHOULD BE FOOTNOTED TO EXPLAIN THE APPAFINT ANW ALY.

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SUMMARY

OF OPERATING EXPERIENCE MONTH / YEAR SEPTEMBER.1983

- Listed below in chronological sequence by unit is a summary of operating experiences for.this month which required load reductions or resulted in significar,'

non-load related incidents.

UNIT ONE See attached Sheet.

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0000 This reporting period begins with the unit at 100% power.

9-09-83. 2050 Commenced load reduction due to EHC problems.

2058 Holding power at 68%

2130 Commenced Power increase.

2343 Rx at 100% power.

.. 9-14-83 10933 Rx trip, caused by-OP6T' spike on channel III, while channel-II was in test.

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- 1455 Rx critical.

s' 2010 Main generator on the line, increasing power.

2120. Holding power at 35%, working on #1 governor valve.

L 2350 Increasing power at 150 mw/hr.

.9-15-83 0730.Rx at 100% power.

9-20-83 2132 Commenced plant shutdown for snubber outage.

. 9-21-83' 0318 - Main generat'or off the line.

1 0358 Rx shutdown.

-1454 -RCS <350*F,450 psig.

2333 RCS <200*F 9-25-83 1308 RCS drained to mid-nozzle.

9-26 2312 Declared an Unusual Event, due to a 4 minuteuncontrolled release to atmosphere via process vent. stacks.

9-27-83 0038 Secured from Unusual Event.

9-29-83 0715 RCS filled and vented.

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. 1924 Bubble in pressurizer.

9-30-83 2400 This reporting period ends witht the plant at <200'F.

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SUMMARY

OF OPERATING EXPERIENCE

- MONTH / YEAR SEPTEMBER.1983 Listed below in chronological sequence by unit is a summary o! operating experiences for this month which required load reductions or resulted in significant non-load related incidents.

~ UNIT TWO See attached sheet.

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9-01-8 3 0000 This reporting period begins with the unit at cold shutdown.

9-09-83 1743 Completed RCS venting prior to Type "A" test.

9-10-83 1615 Started pressurizing containment for Type "A" test.

9-14-8 3 De-pressurizing containment af ter successful Type "A" test.

9-19-83 2137 RCS >200'F.

9-20-83 2120 RCS >350'F,450 psig.

9-21-8 3 1815 Commenced RCS cooldown to repair weld leak on 2-RC-159.

9-22-83 0045 RCS <350'F,450 psig.

9-22-83 1032 RCS <200'F.

9-24-83 0245 RCS >200'F.

9-24-83 1140 RCS >350'F, 450 psig.

9-25-83 0150 RCS at HSD, performed system pressure test on RCS.

9-25-83 1902 Reactor critical, commenced physics testing.

9-27-83 ~1134 Completed physics testing.

9-28-83 1015 Reactor trip on startup due to high S/G level in "B" S/G.

111 9 Reactor critical.

1408 Reactor trip on startup due to high S/G level in "B" S/G.

1833 Reator critical.

2258 Main generator on the line, increasing power.

9-29-83 0740 Holding power at 53% for flux mapping.

114 0 Commenced power increase.

1400 Holding power at 60% for flux mapping.

1610 Commenced power increase.

4 2051 Holding power at 70% for flux mapping.

2145 Commenced power increase.

9-30-83 1300 Commenced power decrease due to chemistry in S/G's.

1507 Stopped power decrease, commenced power increase.

2400 This reporting period ends with Rx power at 83% and increasing at 3%/hr.

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AMENDMENTS TO FACILITY LICENSE OR TECHNICAL SPECIFICATIONS The Nuclear Regulatory Commission issued, on August 23, 1983, Amendment No. 89 to the Operating License for Surry Power Station Umt 1.

The change is designated for issuance as Technical Specification Change No.101.

The change allows a one-time extension in a surveillance interval for inspecting snubbers. The current interval is t_ jays 25% and the extension would be 21 days until September 21,1983.

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14 FACILITY CHANCES REQUIRING NRC APPROVAL None during this reporting period,

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s FACILITY CHANGES TRAT DID NOT REQUIRE NRC APPROVAL UNIT DC 79-62 Containment Hydrogen Analyzer and Isolation Valves 1&2 This design change installed two redundant hydrogen analyzers to be shared by Units 1 & 2 which are cap-able of measuring a range of 0 to 10 percent. The existing manual containment isolation valves were replaced with remote operated valves.

Summary of Safety Analysis The replacement of existing hydrogen analyzers with new redundant units, qualified nuclear safety-related Category I and seismic class 1, will enhance safe and reliable operation during post-accident operation.

The replacement of manual valves with remote operated valves used for containment isolation greatly reduces the personnel radiation exposure in placing the hy-drogen analyzer in operation after an accident.

DC 80-29 Reactor Coolant Vent System 2

This design change installed a remotely operated high point vent, to provide venting capability of the primary coolant system. The need for remote venting capability was identified upon review of the instal-led systers response to the accident conditions en-countered at TM1-2.

Summary of Safety Analysis The effect of this design change on station operation has not been clearly defined since specific procedure and functions are not available at this time. This design change will not have any adverse impact on the operation of any safety-related equipment.

DC 80-57 Service Water Radiation Monitoring Pump Modification 2

This design change replaced original Service Water Radiation Monitoring Pumps with pumps having necessary environmental qualification documentation. The new pumps installed meet the requirements of IEEE 323-1974 and IEEE 344-1975.

Summary of Safety Analysis The modification increases the reliability of the system under accident conditions.

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16 UNIT DC 80-98A CVCS Heat Tracing Modification 2

This design change provides c diesel-backed redun-dant heat tracing system for portions of the Chemical and Volume Control System containing Boric Acid.

Summary of Safety Analysis The modification provides a more reliable and accurate means of monitoring CVCS temperature. The diesel-backed redundant heat tracing will provide a continuour stand-by power source which will automatically provide heating upon loss of primary system.

DC 81-33 VCT Redundant Indication 2

This design change added a redundant Volume Control Tank level indicator to the control room. The second level indicator in the control room will enable the operator to manually control the related valves if the exis ting loop malfunctions in any way.

Summary of Safety Analysis The modification enhances the safe operation of the plant because it increases the reliability of the Chemical and Volume Control System.

DC 81-103 Class lE Solenoid Operated Valve Replacement 1&2 This design change removed certain solenoid operated valves (S0V's) whose qualifications have not been demonstrated to be adequate. The e valves were re-placed with equivalent SOV's whic h have adequately de-monstrated environmental qualification.

Summary of Safety Analysis The modification will provide additional assurance th at the SOV's will perform their intended safety function during and following any postulated LOCA or HELB accident.

DC 81-104 Class lE Transmitter Replacement 2

This design change replaced certain transmitters with equivalent transndtters which have adequately demonstrated environmental qualification per the guidelines set forth by IEEE Std. 323-1974.

Summary of 3afety Analysis The modification will provide additiona' assurance that the transmitters will perform their intended safety function during and following a postulated LOCA or HELB accident.

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DC 81-105 Class 1E Motor Operated Valve (MOV) 2 Actuator Replacement This design change removed the existing MOV actuators,

located inside the containment, from service and re-placed them with equivalent actuators which have adequately demonstrated environmental qualification.

The remaining non qualified actuators, located outside the containment, were converted to meet the requirements.

Summary of Safety Analysis The modification will provide additional assurance that the MOV's will perform their intended safety function during and following any postulated LOCA or HELB accident.

DC 81-119 NUREC-0696 Short Term I&C Project - Remote 2

Multiplexer Installation: Part E - Rack and Cabinet Mounted Multiplexer This design change provides a number of remote multi-plexers and buf fer units which are the front-end por-tions of the Data Aquisition System (DAS). The DAS will collect and transmit required data, vital information, and plant status.

Summary of Safety Analysis The modification does not affect normal station oper-ation nor the operation of any safety-related equipment.

In the event of an accident or on-site emergency, the independent DAS provides a separate source of plant status and information, therefore increasing overall plant safety.

DC 82-01 Containment Purge Leakage Test 1&2 This design change installed leakage monitoring connections on the containment side of the outside MOV's and providalblank flanges with a leakage mon-itoring connections on the other side of the outside MOV's.

This would allow leakage testing of the Contain-ment Purge MOV's with the units at power.

Summary of Safety Analysis The modification increases the reliability of the of the system by enabling the frequency of the test to increase.

18 UNIT 3

DC 82-10 Class ~ 1E Terminal Block Replacement 2

This design change replaced certain terminal blocks with equivalent terminal blocks which have adequately demonstrated environmental qualification per the-guide-lines set forth by IEEE Std. 323-1974, IEEE Std. 344-1975 and NUREG-0588.

Summary of Safety Analysis The modification will provide additional assurance that the terminal blocks will perform their intended safety function during and following any postulated LOCA or HELB accident.

-DC 82-22 Steam-Generator Blowdown Trip Valve Replacement 2

Steam Generator Blowdown trip valves, TV-BD-100A-F and 200 A-F had experienced numerous problems with valve seat leak-through and body-to-bonnet le aks.

This design change replaces the twelve 3 inch globe-type trip valves with 2 inch double-disc pressure seal-type gate valves.

Summary of Safety Analysis The modification does not affect station operations

. or the operation of any equipment which is safety related. Proper operation of the system will be enhanced by the replacement of trip valves, which have shown themselves to be of inadequate design for system application, with a qualified, suitably designed valve type.

DC 82-27 Component Cooling Trip Valve Operator Airline 2

Filter This design change added filters to the air supply

'_5nes of the' actuator pneumatic pilot relay valves for Component Cooling Trip valves TV-CC-109A & B and TV-CC-209A & B.

The filters are capable of removing both particulates and moisture to prevent pneumatic-pilot relay valve malfunction.

Summary of Safety Analysis The installation of air supply filters together with the establishment of an effective filter element re-placement periodicity will result in increased trip valve operational reliability.

19 t'

UNIT DC 83-06 Replacement of MOV-CS-102A & 102B 1

The original Chemical Addition Tank isolation valves MOV-CS-102A & 102B leaked excessively. This design change replaced the original valves with flex-wedge valves of a higher pressure rating and physically larger. Opening times are f aster for these valves but they do not alter system operation.

Summary of Safety Analysis The modification provides a return to the degree of design leak tightness specified for this system.

DC 83-15 Re-alignment of Piping to 2-RS-E-1A Service Water 2

Expansion Joint This desigr. change corrected a cisalignment problem of expansion joint 2-MEJ-15.

Line 24"-SW-133-10 was brought back on line by an adjustment between the 45 elbow and the flanged Recirculating Spray Heat Ex-changer Service Water outlet nozzle.

, Summary of Safety Analysis The modification only corrects a piping misalign-ment problem to allow proper installation of an ex-pansion joint.

DC 83-25 Replacement of Unit 2 Steam Generator J-Tubes 2

Visual and ultrasonic inspection of feed ring J-tube nozzles in Unit 2 Steam Generators revealed loss of J-tube wall thickness in numerous tubes. Deterioration varied from negligible on some tubes to through-wall on othe rs. This design change replaced carbon steel J-tubes with Inconel 600 tubes as recommended by Westinghouse.

Summary of Safety Analysis The modification does not affect any station operations g

or the operation of any equipment which is safety-related.

It provides a higher degree of material strength in the affected region.

DC 83-26 Tiedng Circuitry for Reactor Trip Breaker 2

This design change permanently installed test circuitry to measure the time response of the reactor trip breaker to a trip signal.

Summarf of Safety Analysis a

The permanent installation of cables and test connections will minindze the caance for errors and improve the overall safety of personnel and equipment.

-6

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w 6-

-,---A m_ - - -, ma

.-e 20 TESTS AND EXPERIMENTS REQUIRING NRC APPROVAL l

NONE DURING THIS REPORTING PERIOD!

TESTS AND EXPERIMENTS THAT DID NOT REQUIRE NRC APPROVAL NONE DURING THIS REPORTING PERIOD!

)

a a

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OTIIER CIIANGES, TESTS AND EXPERIMENTS None during this reporting period.

22 i

d VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION CHEMISTRY REPORT September 19 83 T.S.

6.6.3.d PR RY COO N UNIT NO. 1 UNIT NO. 2 ANALYSIS MAXIMUM' MINIMUM AVERAGE MAXIMUM MINIMUM AVERAGE Gross'Radioact., uCi/ml 1.12E 2.30E-2 4.59E-I 3.77E-I 3.36E-3 1.22E-1 O

0.0 0.0 0.0 0.0 0.0 0.0 Suseened solids, pom 2.83E-I 7.37E-2 1.91E-I 7.78E-3 6.47E-3 7.13E-3 Gross Tritium, uci/ml 5.35E-1 4.57E-4 7.63E-2 1.63E-3 2.37E-5 8.46E-4 Iodine 131, uci/mi I

133

- (D)

_(D)

_ (D)

I

/I

.74

.15

.48 (A) th)

(t)

Hydrocen, co/ka 35.6 4.6 12.3 57.0 11.6 39.9 II Lithium. opm 2.10-

.80 1.32 2.08

.33 1.37 Boron-10, p m*

347 124 195 425 188 305 (C)-

(C)

(F)

Oxyaen, (D. O. ), cpm 2.60

<0.005

.079 1.00

<0.005

.144 Chloride, com

< 0.02

< 0.02 pH @ 25'C 6.78 5.80 6.39 6.45 5.48 5.90

'* Boron-10 = Total Boron x 0.196 NON-RADIOACTIVE CHEMICAL (G)

RELEASES, POUNDS T.S.

4.1.5. A. 6 Phosphate Baron 983.

Sulfate Chromate 0.0 50% NaOH Chlorine 0.0 (A). Unit 1 degassing for Snubber Inspection.

(B). Lithium additions made to

.. REMARKS:

Unit 1: 300 gms. 9/3; 600 gms-9/.15; 2610 gms. 9/29. Additions to Unit 2:

1000 gms. 9/19; 1200 gms. 9/19; 1200 gms. 9/20; 1900 gms. 9/22; 1300 gms. 9/23; 650 gms. 9/25; 570 gms. 9/26; l

700 gms. 9/29.

(C).

Unit I heating up to 190*; D.0., following filling & venting, removed by hydrazine add'n.

(D). Unit 2 not at stable power for meaningful ratio.

(E). Hydrogen conc.

during power escalation (adjusted by VCT press to between 25-50cc/KG).

(F). Unit 2 heating up to 250*; D.0. removed by hydrazine add'n.

(G). The levels of these chemicals should pro-l' duce no adverse environmental impact.

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23 DESCRIPTION OF ALL INSTANCES WHERE THERMAL DISCHARGE LIMITS WERE EXCEEDED None during this reporting period.

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57 o -4 o l** PROCEDURE DEVIATIONS REVIEWED BY STATION NUCLEAR D SAFETY AND OPERATING COMMrlTEE AFTER TIME LIMITS SPECIFIED IN TECHNICAL SPECIFICATIONS September.1983 Date Date SNSOC Procedure No. Unit Title Deviated Reviewed M M P-C-RC-034 2 Disassembly and Reassembly of 8-15-83 9-15-93 Instrument Parts MMP-C-RC 038 2 Removal and Reinstallation 8-13-83 9-15-83 of Reactor Vessel Studs OP 4.1 2 Controlling Procedure for 8-12-83 9-8-83 Refueling PT 16.4 2 Containment Isolation Valve 8-29-83 9-22-83 Leakage (Type C Testing) PT 53.1 2 ASME System Pressure Test 8-22-83 9-22-83 2H-500 Repair Welds for Orifice on 3"-SHP-131-601 1 ^~" "'~ *** ~~ ,_m,,.. ...e.-m- - -" -**" _,, ' - * * * * * ' ' ~ ' ' * " ' * ~

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3: ) -9 VIRGINIA ELECTRIC AND PowEn CoxPANY' RIcnwown, VIRGINIA 23261 W.L.Stewaar -viesp s.,. October 14, 1983 Noctuan Ormaatsome Mr. N. M.~Haller, Director Serial No. 583 -Office of Management and Program Analysis N0/WDC:acm ~U. S. Nuclear ~ Regulatory Commission Docket Nos. 50-280 Washington, D. C. 20555 50-281 License Nos. DPR-32 DPR-37

Dear Mr. Haller:

-Enclosed is the Monthly Operating' Report for Surry Power Station Unit Nos. I and 2 for the month of September, 1983. ]ytrlyyours, W. L. Stewart . Enclosure (3 copies) cc: Mr. R. C. DcYoung, Director (12 copies) Office of Inspection and Enforcement Mr. James P. O'Reilly (1 copy) Regional Administrator Region II Mr. D. J. Burke NRC Resident Inspector Surry Power Station 9,\\ 1.}}

ML20081M509

Contents

Text

SUMMARY

SUMMARY

.

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2 = n = = = =

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ML20081M509

Text

SUMMARY

SUMMARY

.

N=

= = = = =

4 e e

= - = -

2 = n = = = =

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=

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Dear Mr. Haller:

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