ML20215C605

Monthly Operating Rept for Jul 1986

ML20215C605
Person / Time
Site:	Surry
Issue date:	07/31/1986
From:	Jones V, Saunders, Stewart W VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To:	Scroggins R NRC OFFICE OF RESOURCE MANAGEMENT (ORM)
References
86-525, NUDOCS 8610100367
Download: ML20215C605 (27)

Text

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VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION MONTHLY OPERATING REPORT REPORT NO. 86-07 m

APPROVED * $heruurrt,$n Jawnk STATION MAWAGER O

8610100367 860731 PDR ADOCK 05000280 R

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1 Section Page

- Operating Data Report - Unit No.1 '

1 Operating Data Report - Unit No. 2 2

Unit Shutdowns and Power Reductions - Unit No.1 3

Unit Shutdowns and Power Reductions - Unit No. 2 4

Average Daily Unit Power Level-Unit No.1 5

Average Daily Unit Power Level-Unit No. 2 6

Summary of Operating Experience 7

Facility Changes Requiring NRC Approval 11 Facility Changes That Did Not Require NRC Approval 12 Tests and Experiments Requiring NRC Approval 18 Tests and Experiments That Did Not Require NRC Approval 18 Other Changes, Test and Experiments 19 Chemistry Report 20 Fuel Handling 21 Procedure Revisions That Changed the Operating Mode Described 23 in the FSAR Description of Periodic Test Which Were Not Completed Within 24 the Time Limits Specified in Technical Specifications m

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(Corrected Copy)

Page1 OPERATING DATA REPORT

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• Surry Unit.1 DOCKET NO.

50-280 DATE R-5-Rfi COMPLETED BY V R Tnne TELEPHONE f 804)157-11 Rd 1

OPERATING STATUS 1.

Unit Name:

Surry Unit 1 Notes 2.

Reporting Period:

07-01-86 to 7-31-86 3.

Licensed Thermal Power (MWt):

2441 4 Nameplate Rating (Cross MWe):

847.5 5.

Design Electrical Rating (Net NWe):

788 6.

Maximus Dependable Capacity (Cross MWe): 820 7.

Maximus Dependable Capacity (Not MWe):

781 8.

If Changes occur in Capacity Ratings (Items Number 3 Through 7) Since Last Report, Give Reasons:

N/A 9.

Power Level To Which Restricted, If Any (Net MWe):

10. Reasons For Restrictions, If Any:

I This Month Yr.-to-Date Cumulative

11. Hours In Reporting Period 744.0 5087.0 11927_1 4._,

12. Number of Hours Reactor Was Critical 441.0 3171.2 75483.3

13. Reactor Reserve Shutdown Hours 0~

0 3774 L

14. Hours Generator On-Line 327.8 3023.9 73862.4

15. Unit Reserve Shutdown Hours 0

0 3736.2

16. Cross Thermal Energy Generated (MWR) 6481h.l 6973392.2 170856014.0

17. Cross Electrical Energy Generated (PSfR) 205250.0, 2308945.0 55080878.0

18. Net Electrical Energy Generated (MWR) 192484.0 2191310.0_,

52224653.0 l

19. Unit Service Factor 44.1%

59.4 %

61.9%

20. Unit Available Factor 44.1%

59.4 %

65.1%

21. Unit Capacity Factor. (Using MDC Net) 33.1%

55.1%

56.7 %

22. tinic Capacity % tor (Using UER Net) 32.8 %

54.7 %

55.6 %

UnitForced_RaIe 0

1.8%

.5%

23.

24. Shutdowns Scheduled Over Next 6 Months (Type, Date, and Duration of Each):

25.

If Shut Down At End Of Report Perie Estimated Date of Startup

26. Units In Test Status (Prior to Commercial Operation):

Forecast Achieved INITIAL CRITICALITY INITIAL ELECTRICITY ColetERCIAL OPERATION (9/77)

(Corrected Copy)

Page 2

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rPERATING DATA REPORT

• Suggit 2

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DATE 8-5-86 COMPLETED BY V. H. Jones i

TELEPHONE (804)357-3184 OPERATING STATUS 1.

Unit Name:

Surry Unit 2 Notes 2.

Reporting Period:

7-01-86 to 7-31-86 3.

Licensed Thermal Power (MWt):

2441 4

Nameplate Rating (Gross MWe):

847.5 5.

Design Electrical Rating (Net NWe):

788 6.

Maximum Dependable Capacity (Gross MWe): 820 7.

Maximus Dependable Capacity (Net MWe):

781 8.

If Changes Occur in Capacity Ratings (Items Number 3 Through 7) Since Last Report, Give Reasons:

9.

Power Level To Which Restricted, If Any (Net MWe):

10. Reasons For Restrictions, If Any:

1 This Month Tr.-to-Date Cumulative

11. Hours In Reporting Period 744.0 5087.0 116159.0-

12. Number of Hours Reactor Was Critical 592.I 4408.I 76350.8

13. Reactor Reserve Shutdown Hours 0

0 378.I

14. Hours Generator On-Line 584.1 4374.8 75140.2

15. Unit Reserve Shutdown Hours 0

0 0

16. Cross Thermal Energy Generated (MWE) 1331725.7 10495124.1 175802154.7

17. Gross Electrical Energy Generated (MMI) 427750.0 3447660.0 57035964.0

18. Net Electrical Energy Generated (MWR) 405202.0 3274891.0 54061474.0

19. Unit Service Factor 78.5 %

86.0 %

64.7 %

20. Unit Available Factor 78.5 %

86.0 %

64.7 %

21. Unit Capacity Factor,(Using MDC Net) 69.7 %

82.5%

59.8 %

Ifnit Capacitypto7(Ting DEN Net) 69.1%

81.7 %

59.1%

22.

23. Unit Forced l Rate 21.5%

10.4 %

13.3 %

24. Shutdowns Scheduled Over Neat 6 Months (Type, Date, and Duration of Each):

25. If Shut Down At End Of Report Period Estimated Date of Startup:

26. Units In Test Status (Prior to Commercial Operation):

Forecast Achieved INITIAL CP.IIICALITY INITIAL ELECTRICITY CONIERCIAL OPERATION I

(9/77)

(Corrected Copy)

UNIT SUUTDOWNS AND PONER REDUCTIONS DOCKET NO.

50-280 UNIT NA E Surry 1 DATE Auoust 5.1986 -

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I COMPLETED BY V.H. Tones I

REPORI, MONTH TULY 1986 TELEPHONE 804-357-3184 n

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I" LICENSEE e,

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{j CAUSE & CORRECIIVE ACTION TO

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• g E j j,I EVENT NO.

DATE REPORT #

=0 go PREVENT RECURRENT g

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8 86-05 05-10-86 S

416.1 C

1 Plant shutdown for refueling which commenced on 5-10-86.

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Exhib'.tb-Instructions T

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F: Forced Reason:

Method:

1 S: Scheduled A - Equipment Failure (Explain) 1 - Manual

' for Preparation of Data l

B - Maintenance or Test 2 - Manual Scram.

Entry Sheets for Licensee y

C - Refueling 3 t Automatic Scram.

Event Report (LER) File go D - Regulatory Restriction 4 - Other (Explain)

(NUREC 0161) y j

"3 E - Operator Training & License Examination Exhibit 1 - Same Source F - Administrative C)

G - Operational Error (Explain)

O (9/77)

H - Other (Explain)

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50-281 tMIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO.

UNIT NARE Surry ~2 DATE August 5,1986 y -

COMPLETED BY V. H. Jones REPORT MONTH IUbY I986 TELEPHONE 804-357-3I84 "m

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CAUSE & CORRECTIVE ACTION TO

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DATE o

o PREVENI RECURRENT dk E

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a 86-04 07-02-86 F

52i8 D

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• 86-006 Unit shutdown for repair on SW expansion Joint in RS-E-1 A and plugging of S/G tube leak, Continuation of 6-17-86 outage.

86-05 07-23-86 F

107.1 D

1 86-007 Unit was shutdown to repair tube leak in

• 86-011 RS-E-1 B.

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1 2

3 4

F: Forced Reason:

Methods Exhibit C - Instructions S: Scheduled A - Equipment Failure (Explain) 1 - Marmaal for Preparation of Data T$g B - Maintenance or Test 2 - Manual Scram.

Entry Sheets for Licensee o,

Ca Refuelin's 3 p dutomatic Scram.

Event Report (LER) File o

D - Regulatory Restriction 4 - Other (Explain)

(NUREC 0161) y o

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E - Operator Training & l.b.ense Examination Exhibit 1 - Same Source F - Administrative O

C - Operational Error (f ta)

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(9/77)

H - Other (Explain)

(Corrected Copy) s.

Page 5 AVERACE DAILY UNIT POWER LEVEL DOCKET NO. 50-280 Surry Unit 1 UNIT 1

M 8

DATE 8-5-86 COMPLETED BY V. H. Tones TELEPHONE 477 noNru JULY DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net)

(MWe-Net) 1 0

17 0

2 0

18 92 3

0 19 167 4

0 20 361 5

0 21 468 6

0 22 420

+

7 0

23 573 8

0 24 712 9

0 25 746 10 0

26 749 11 0

27 747 12 0

28 738 13 0

29 743 14 0

30 752 15 0

31 752 16 0

INSTRUCTIONS On this format, list the average daily unit power level in MWe-Net for each day in the' reporting month.

Compute to the nearest whole megawatt.

(9/77)

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(Corrected Copy)(

Page 6 AVERACE DAILY UNIT POWER LEVEL DOCKET NO. 50-81 Surry Unit 2 UNIT 2 JUN 19 1986 DATE 8-5-86 COMPLETED BY V. H. Jones TELEPHONE 477 MONTH JULY DAY AVERACE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net)

(MWe-Net) 1 0

17 741 2

0 18 740 3

102 19 738 4

451 20 736 5

746 21 731 6

753 22 710 7

746 23 22 8

750 24 0

9 747 25 0

10 754 26 0

11 748 27 64 28 639 12 748 13 738 29 739 14 751 30 736 15 746 31 724 16 742 INSTRUCTIONS On this format, list the average daily unit power level in MWe-Net for each day in the reporting month. Compute to the nearest whole megawatt.

l (9/77) l

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Page 7

SUMMARY

OF OPERATING EXPERIENCE MONTH /YEARIULY 1986 Listed below in chronological sequence by unit is a summary of operating experiences for this month which required load reductions or resulted in significant non-load related incidents.

UNIT ONE 07-01-86 0000 This reporting period begins with the unit at CSD, preparing for Type "A" test.

07-02-86 2041 Commenced Type "A" test, pressurization of containment.

07-09-86 2215 Completed Type "A" test, containment depressurized.

07-10-86 2020 RCS > 200oF.

07-11-86 0330 RCS > 350oF/450 psig.

07-11-86 1350 RCS at HSD.

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07-12-86 1114 Completed hot rod drops.

07-12-86 2336 Rx critical for physics testing.

07-13-86 1355 Completed low power physics testing.

07-13-86 1430 Rx at 2% power for chemistry and testing of FW-P-2.

07-14-86 1221 Reactor shutdown to work in logic cabinet.

07-15-86 0345 Rx critical 07-15-86 0600 Rx at 2% power for chemistry and testing of FW-P-2.

07-18-86 0809 Generator on Une.

07-18-86 0852 Holding power at 30%,165 mw's for chemistry.

07-19-86 0912 Declare Unusual Event - Bomb Threat.

07-19-86 1019 Terminated Unusual Event.

07-19-86 1756 Commenced power increase at 3%/hr.

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(Corrected Copy)

Page 8

SUMMARY

OF OPERATING EXPERIENCE MONTH / YEAR JULY 1986

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

. UNIT ONE 07-20-86 0226 Holding power at 50%,325 mw's for flux mapping 07-20-86 0649 Commenced power increase at 3%/hr.

07-20-86 2000 Holding power at 70%,505 mw's for flux mappfng.

07-21-86 0992 Commenced power increase at 3%/hr.

07-21-86 1330 Started power decrease due to chemistry problems, reactor at 77% power,540 mw's.

1547 Holding power at 65%,440 mw's.

07-22-86 2006 Commenced power increase at 3%/hr.

07-23-86 1401 Commenced power reduction due to condenser vacuum problems, unit at 91% power,700 mw's I

07-23-86 1420 Holding power at 76%,570 mw's.

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07-23-86 1730 Commenced power increase at 3%/hr.

07-24-86 0130 Holding power at 95%,740 mw's to allow calibration of OTAT instrumentation.

07-24-86 2030 Commenced power increase at 3% hr.

f 2210 Unit at 100% power,790 mw's t

f 07-31-86 2400 This reporting period ends with the unit at 100% power,790 mw's.

(C.. rectcd Copy)

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SUMMARY

OF OPERATING EXPERIENCE MONTH /YE AR JULY 1986 Listed below in chronologica1 sequence by unit is a summary of operating experiences for this month which required load reductions or resulted in significant non-load related incidents.

UNIT TWO 07-01-86 0000 This reporting period begins with the unit heating up, on RHR.

07-01-86 1290 RCS > 3500F,450 psig.

07-02-86 2349 Rx critical.

07-03-86 0450 Generator on the line.

07-03-86 0625 Holding power at 28% power,160 mw's.

I 07-04-86 0609 Commenced power increase at 150 mw/hr.

07-04-86 2000 Unit at 100% power,780 mw's.

07-22-86 2118 Declared " Notification of Unusual Event"

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for load reduction required by Tech. Spec.

I L.C.O., service water tube leak in RS-E-1B.

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07-22-86 2139 Commenced power reduction at 150 mw's/hr.

07-23-86 0251 Generator off the Ene.

0308 Reactor shutdown, secured from Unusual Event.

0936 RCS < 3500F/450 psig.

07-23-86 1725 RCS < 2000F, 07-26-86 1145 RCS > 2000F.

f 07-26-86 1505 RCS > 350oF, 450 psig.

07-27-86 1112 Rx critical 07-27-86 1358 Generator on the line.

07-27-86 1509 Holding power at 30%,175 mw's for chemistry.

07-27-86 2220 Commenced power increase at 150 mw/hr.

Page 10 s.

SUMMARY

OF OPERATING EXPERIENCE MONTH / YEAR JULY 1986 Listed below in chronological sequence by unit is a summary of operating experiences for this month which required load reductions or resulted in significant non-load related incidents.

UNIT TWO 07-28-86 Og Unit at 100% power,780 mw's.

07-31-86 2400 This reporting period ends with the unit at 100% power,780 mw's.

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5 FACILITY CHANGES REQUIRING NRC APPROVAL MONTH / YEAR JULY 1986 NONE DURING THIS REPORTING PERIOD.

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Corrected Copy)

Page 12 FACILITY CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTH /DAYJULY 1986 DC 81-SI19J Nureg-0696 Short Term I & C Project UNIT Supplemental SPDS Inputs Installation 1

This design change inputs additional parameters, which were not covered in NUREG-0696, into the SPDS. It also installs additional multiplexers, related multiplexer hardware and wiring.

Summary of Safety Analysis The additionalinputs to the SPDS are an improvement in station design and emergency response capability, providing the control room operators with critical plant informcttion to assess the status of the safety system.

DC 83-09 Fuel Transfer Canal Blind Flange Replacement 1

The fuel transfer tube blind flanges, bolts and gaskets were replaced with a yoke closure mechanism. The yoke closure mechanism consists of an adapter flange and flat closure head held together by upper and lower clamp yokes. The adapter flange was bolted to the existing flange and then seal welded to eliminate the need for gackets at this joint.

Summary of Safety Analysis The installation of the new yoke type closure mechanism and the remote test correction for the fuel transfer tube make i

removal, re-installation, and testing of the fuel transfer tube closure mechanism simpler, less time consuming and thus less dose consuming.

DC 84-28 Flow Transmitter Replacement Modification 1

This design change replaces a flow transmitter with an IEEE qualified transmitter.

Summary of Safety Analysis This modification replaces existing instrumentation with flow transmitters which are environmentally qualified. The Teplacement flow transmitter will provide a reliable means of assessing safety system operation and post accident monitoring.

r Page 13 6

y FACILITY CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTH /YEARIULY 1986 DC 84-30 Radioactive Gas Holdup Tank Instrument Modification UNIT

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l&2 This design change recalibrates four pressure transmitters, changing their present range of 0-150 psig to a new range of 0-225 psig. It also replaces the indicator scales with new faces within the new range of 0-225 psig.

1 Summary of Safety Analysis This modification affects the recalibration of the existing pressure transmitters for the Waste Gas Decay Tanks to expand the range of measurement. In addition, the indicator scales will be replaced to reflect the new wide range measure-ment. This modification is consistent with station design criteria and does not increase the possibility of an accident or malfunction.

DC 84-32 RG 1.97 Containment Fan Heat Removaland 1

Component Cooling Instrumentation Modifications This modification replaces existing and adds new RTD's and flow transmitters.

i Summary of Safety Analysis The new and replacement instrumentation satisifes RG 1.97 requirements, is environmentally and seismically qualified, l

and thus provides a reliable means of monitoring station l

operation during and after a design basis event.

i DC 84-34 Main Steam Safety Valve Position Indication 1

This design change installs flow sensors, with temperature flow probes, at each Main Steam Safety Valve. It also installs a new multiplexer and power supply local to the remote flow switch electronics.

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Summary of Safety Analysis This modification adds flow switches for main steam safety valve position indication for assessment of safety systems I

operation and post-accident monitoring.

1

Page 14 1

FACILITY CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTH /YEARIULY 1986 DC 84-36 DC RG 1.97 Emergency Ventilation Damper UNIT Position Indication 1

This design change provides position indications of emergency ventilation dampers and satisfied RG 1.97 and RG 1.89 requirements. Environmentally qualified limit switches were mounted on the dampers to provide position indication such that the original qualification and operation of the dampers is not degraded.

Summary of Safety Analysis The modification added limit switches, which are environmentally qualified;to emergency ventilation dampers. It does not change the operation of the emergency ventilation dampers or the operation of other safety systems.

DC 84-40 PressurizerInstrumentation Modification 1

This design change replaces the existing temperature element with a dual element resistance temperature detector (RTD).

Summary of Safety Analysis The replacement of the single element RTD with an environmentally and seismically qualified dual element RTD provides the operator with redundant information to assess the operation of safety systems.

DC 84-61 H.P. Heater Drain Pump Discharge Piping I

and Valve Replacement This design change upgrades the H.P. Heater Drains Pump Discharge piping to a 600 lb. (pipe class 601) system. In addition, small capacity relief valves were installed on the pump suction piping (one per pump) to prevent over-pressurization of the suction piping through valve leakage.

Summary of Safety Analysis The addition of electricalinterlocks to trip the H.P. Heater Drain Pumps ensures that overpressurization of the class 300 lb. piping will not occur.

(Corr:cted Copy)

Page 15 FACILITY CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTH /YEARIULY 1986 DC 84-77 10CFR50-Appendix 'R' RCS Letdown Valves UNIT Instrument Air Piping Modifications 1

This design change package involves modifications to the air supply lines of air-operated valves in the reactor coolant, residual heat removal and component cooling water systems.

Summary of Safety Analysis This modification will ensure operability of the identified valves to achieve hot shutdown following a fire and postulated loss of offsite power and/or instrument air.

DC 84-83 Reactor Vessel Head Shielding 1

This design change installs permanent reactor vessel head shielding and insulation.

Summary of Safety Analysis This design change reduces exposure from refueling operations. The shield protects the maintenance personnel from all major sources of gamma radiation originating at the reactor vessel head and its appendages.

In addition, the new reactor head insulation will help alleviate the high airborne contamination created when handling the existing reactor head insulation.

DC 85-04 Large Bore Snubber Leak Before Break Modifications 1

This design change eliminates six large bore snubbers in each of the three reactor coolant loops, and four small bore snubbers on the diagonals of each RCP support. It also replaces the four snubbers on the pressurizer supports with fixed gap restraints. In addition, the snubber bolt design on the steam generator upper restrains has been modified to eliminate the hydraulic operation of the snubber bolts. Finally, on the main steam line, two 8-inch bore ITT snubbers replaced two 10-inch bore ITT snubbers.

Summary of Safety Analysis The deletion of the large bore snubbers eliminates a source of occupational exposure and facilitates maintenanco and inservice inspections of piping and components by reducing plant congestion.

Page 16

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FACILITY CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTH /YEARIULY 1986 DC 85-19-1

_ Containment Sump Trip Valves Replacement UNIT 1

The containment sump trip valves have been a continual problem during Type A and Type C containment leak testing. This design change replaces the existing globe valves with air operated ball valves.

Summary of Safety Aralysis This design change is an enhancement over the existing equipment because it reduces the leakage rate of these valves to well within the established allowable range, thus improving the overall containment leakage rate.

DC 85-21 RCP Thermal Barrier CCW System Modification 1

This design change installs check valves, trip valves, and relief valves on the component cooling water (CCW) return heater. Installation of these valves prevents overpressurization and contamination of the CCW system.

Summary of Safety Analysis The installation of the valves and controlinstrumentation will provide Station Operations with automatic isolation of the leaking reactor coolant pump (RCP) and will not require unit shutdown. This modification will prevent overpressuriza-tion ana contamination of the CCW system.

DC 85-25 Feedwater Heater Replacement (Phase 1 - 5th and 6th 1

Pt. Tube Bundle Replacement)

This design change replaces the fifth and sixth point feedwater heater tube bundles and tubeside relief valves.

Summary of Safety Analysis This modification willimprove system performance and

-increase heater life. The operation of safety-related equipment under normal or accident conditions is not affected by this design change.

Page 17 FACILITY CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTH /YEARIULY 1986 DC 86-05 PORV Modifications UNIT i

This design change removes solenoid valves, modifies tubing, and rewires the PORV control circuits at the main control boards.

Summary of Safety Analysis This modification will provide RCS overpressure mitigation through QA Category I, Class IE, seismicaHy and environmentally qualified components.

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Page 18 TESTS AND EXPERIMENTS REQUIRING NRC APPROVAL MONTH / YEAR JULY 1986 NONE DURING THIS REPORTING PERIOD.

TESTS AND EXPERIMENTS THAT DID NOT REQUIRE NRC APPROVAL MONTH / YEAR JULY 1986 NONE DURING THIS REPORTING PERIOD.

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Page 19 OTHER CHANGES, TESTS AND EXPERIMENTS MONTH / YEAR TULY 1986 NONE DURING THIS REPORTING PERIOD.

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Page 20 0

4 VIRGINIA POWER SURRY POWER STATION CHEMISTRY REPORT July 19 86 UNIT NO. 1 UNIT NO. 2 MAX.

MIN.

AVG.

MAX.

MIN.

AVG.

Gross Radioact., uCi/mi 7.79E-1 3.19E-2 2.10E-1 2.13E-1 2.19E-3 1.05E-1 Suspended Solids, ppa 0.0 0.0 0.0 0.0 0.0 0.0 Gross Tritium, uCi/mi 8.68E-2 1.15E-2 5.51E-2 2.19E-1 2.08E-2 8.74E-2 I

I3I Iodine

, uC1/ml 4.76E-3 6.17E-4 2.61E-3 2.16E-4 6.64E-5 1.21E-4 131 I

/1 0.14 0.07 0.11 0.20 0.08 0.10 II Hydrogen, cc/kg 28.3 15.1(C) 21.6 30.2 1.8 (D) 17.4 3.08 1.75 2.27 1.93 0.61 0.95 l

Lithium, ppm 413 210 289 385 54 117 Boron-10, ppm

• 3.40 0.0D5 0.48dAI 4 0.005 60.005

<0.005 IAI 0xygen, (DO), ppa.

0.039(B: 60.001 0.013 0.010 40.001 0.003 Chloride, ppm 6.44 4.92 5.92 6.93 6.00 6.61 pH @ 25 degree Celsius

• Boron-10 = Total Boron X 0.196 REMARKS:

(A) Unit 1 Recoverira frcm refuelina outaae RCS still c:aturatM with oxygen.

(B) Primary Mixed bed deoleted.

(C) Irw valno nccurnd Anving l

startup of unit one follcwing refuelina; 13.300 crama of Lithium Hvdrn-xide-added to RCS.

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1 (D)Establishino hydrogen concentration orior to ronent hoing cri* ion 1 -

i 4306 grams of Lithium Hydroxide added to RCS.

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Page 21 UNIT I

FUEL HANDLING DATE JULY 1986 i

NEW OR DATE NUMBER OF NEW OR SPENT SPENT FUEL SHIPPED OR ASSEMBLIES ASSEMBLY ANSI INITIAL FUEL SHIPPING SHIPMENT f RECEIVED PER SHIPMENT ENRICHMENT CASK ACTIVITY LEVEL N O N F nir12TNG THTR P PRTnn h

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l Page 22 UNIT 2 FUEL HANDLING DATE TULY 1986 (bjR DATE NUMBER OF NEW OR SPENT SPENT FUEL SHI R

ASSEMBLIES ASSEMBLY ANSI INITIAL FUEL SHIPPING SHIPMENT #

RECEIVED PER SHIPMENT ENRICHMENT CASK ACTIVITY LEVEL NEW FUEL RECEIVED S HIP, # 1 7-29-86 12 3T5 LMOK8X 3.80

<5 mr/hr SURRY 2 i

BATCH 11 3T7 LMOK82 3.80 4T8 LMOK9H 3.80 ST2 LMOK91 3.80 4T4 LMOK9B 3.80 4T3 LMOK9K 3.80 3Tl LMOK9C 3.80 3T4 LMOK97 3.80 I

ST0 LMOK9L 3.80 4T5 LMOK99 3.80 4T9

.LMOK94 3.80 N/

V s]

2T9 LMOK92 3.80 I

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Page 23

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e PROCEDURE REVISIONS THAT CHANGED THE OPERATING MODE DESCRIBED IN THE FSAR MONTH / DAY JULY 1986 NONE DURING THIS REPORTING PERIOD.

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.y DESCRIPTION OF PERIODIC TESTS WHICH WERE NOT COMPLETED WITHIN THE TIME LIMITS SPECIFIED IN TECHNICAL SPECL'ICATIONS MONTH / YEAR JULY 1986 NONE DURING THIS REPORTING PERIOD.

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R' VIRGINIA ELECTRIC AND Powsu COMPANY Ricnwoxn,VINOINIA 20261 W. L. STEWART vien r......,

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August 15,1986 Mr. Ronald M. Scroggins, Director Serial No.86-525 Office of Resource Management N0/JDH:acn U.S. Nuclear Regulatory Cmmission Docket Nos. 50-280 Washington, D.C. 20555 50-281 License Nos. DPR-32

Dear Mr. Scroggins:

DPR-37 VIRGINIA ELELTRIC AND POWER COMPANY SURRY POWER STATION UNIT N'S. 1 AND 2 bONIHLY OPERATING REPORT Enclosed is the Monthly Operating Report for Surry Power Station Unit Nos. 1 and 2 for the month of July 1986.

Very truly yours, W. L. Stewart Enclosure (3 copies) cc: Mr. James M. Taylor, Director (12 copies)

Office of Inspection and Enforcement Dr. J. Nelson Grace (1 copy)

Regional Administrator Region II Mr. W. E. Holland NRC Senior Resident Inspector Surry Power Station l

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