Text

Monthly Operating Repts for Sept 1989 for Surry Power Station Units 1 & 2
	ML18152A304
Person / Time
Site:	Surry
Issue date:	09/30/1989
From:	Arney C, Stewart W; VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To:	; NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
	89-737, NUDOCS 8910230097
	Download: ML18152A304 (27)
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VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND, VIRGINIA 23261 October 16, 1989 U.S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, D. C. 20555 Gentlemen:

VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION UNITS 1 AND 2 MONTHLY OPERATING REPORT Serial No.

NO/RPC:vlh Docket Nos.

License Nos.89-737 50-280 50-281 DPR-32 DPR-37 Enclosed is the Monthly Operating Report for Surry Power Station Units 1 and 2 for the month of September 1989.

Very truly yours,

\\\\JL\\~

W. L. Stewart Senior Vice President - Power Enclosure cc:

U. S. Nuclear Regulatory Commission Region II 101 Marietta Street, N. W.

Suite 2900 Atlanta, Georgia 30323 Mr. W. E. Holland NRC Senior Resident Inspector Surry Power Station I I

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VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION MONTHLY OPERATING REPORT REPORT 89-09 APPROVED:

POW 34-04

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e TABLE OF CONTENTS SECTION Operating Data Report - Unit No. 1 Operating Data Report - Unit No. 2 Unit Shutdowns and Power Reductions - Unit No. 1 Unit Shutdowns and Power Reductions - Unit No. 2 Average Daily Unit Power Level - Unit No. 1 Average Daily Unit Power Level - Unit No. 2 Summary of Operating Experience - Unit No. 1 Summary of Operating Experience - Unit No. 2 Facility Changes Requiring NRC Approval Facility Changes That Did Not Require NRC Approval e

Procedure or Method of Operation Changes Requiring NRC Approval Procedure or Method of Operation Changes that Did Not Require NRC Approval Tests and Experiments Requiring NRC Approval Tests and Experiments That Did Not Require NRC Approval Chemistry Report Fuel Handling - Unit No. 1 Fuel Handling - Unit No. 2 Description of Periodic Test Which Were Not Completed Within the Time Limits Specified in Technical Specifications PAGE 1

2 3

4 5

6 7

9 13 14 18 19 20 21 22 23 23 24

e OPERATING DATA REPORT DOCKET NO.:

50-280 DATE:

10/05/89 COMPLETED BY:

Christle Arney TELEPHONE:

(804)357-3184 x477 OPERATING STATUS NOTES

1. Unit Name:

Surry Unit 1

2. Reporting Period: Sept 1 - 30, 1989

3. Licensed Thermal Power (MWt):2441

4. Nameplate Rating (Gross MWe):847.5

5. Design Electrical Rating (Net MWe):

788

6. Maximum Dependable Capacity (Gross MWe):

820

7. Maximum 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. Reason For Restrictions, If Any: ----------------------

THIS MONTH YTD CUMULATIVE

11. Hours In Reporting Period 720.0 6551. 0 147047.0

12. Number of Hours Reactor Was Critical 720.0 2088.0 90566.6

13. Reactor Reserve Shutdown Hours 0

0 3774.5

14. Hours Generator On-Line 720.0 2036.7 88642.1

15. Unit Reserve Shutdown Hours 0

0 3736.2

16. Gross Thermal Energy Generated (MWH) 1724771.0 4685347.0 205856614.0

17. Gross Electrical Energy Generated (MWH) 578765.0 1554915.0 66758588.0

18. Net Electrical Energy Generated (MWH) 547473.0 1469275.0 63309678.0

19. Unit Service Factor 100%

31.1%

60.3%

20. Unit Available Factor 100%

31.1%

62.8%

21. Unit Capacity Factor (Using MDC Net) 97.4%

28.7%

55.6%

22. Unit Capacity Factor (Using DER Net) 96.5%

28.5%

54.6%

23. Unit Forced Rate 0%

68.9%

22.0%

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

25. If Shut Down at End of Report Period Estimated Date of Startup: ______ _

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

FORECAST INITIAL CRITICALITY INITIAL ELECTRICITY COMMERCIAL OPERATION 1

ACHIEVED

e OPERATING DATA REPORT DOCKET NO.:

50-281 DATE:

10/05/89 COMPLETED BY:

Christle Arney TELEPHONE:

(804)357-3184 x477 OPERATING STATUS NOTES

1. Unit Name:

Surry Unit 2

2. Reporting Period: Sept 1 -

30, 1989

3. Licensed Thermal Power (MWt): 2441

4. Nameplate Rating (Gross MWe): 847.5

5. Design Electrical Rating (Net MWe):

788

6. Maximum Dependable Capacity (Gross MWe): 820

7. Maximum 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. Reason For Restrictions, If Any: ----------------------

THIS MONTH YTD CUMULATIVE

11. Hours In Reporting Period 720.0 6551.0 143927.0

12. Number of Hours Reactor Was Critical 327.9 327.9 90022.2

13. Reactor Reserve Shutdown Hours 0

0 328.1

14. Hours Generator On-Line 189 189 88482

15. Unit Reserve Shutdown Hours 0

0 0

16. Gross Thermal Energy Generated (MWH) 187755.9 187755. 9 206928192.0

17. Gross Electrical Energy Generated (MWH) 46725.0 46725.0 67182969.0

18. Net Electrical Energy Generated (MWH) 40831. 0 40831.0 63688209.0

19. Unit Service Factor 26.3%

2.9%

61.5%

20. Unit Available Factor 26.3%

2.9%

61.5%

21. Unit Capacity Factor (Using MDC Net) 7.3%

.8%

56.8%

22. Unit Capacity Factor (Using DER Net) 7.2%

.8%

56.2%

23. Unit Forced Rate 34.4%

34.4%

15.0%

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

25. If Shut Down at End of Report Period Estimated Date of Startup=----------==--

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

FORECAST ACHIEVED INITIAL CRITICALITY INITIAL ELECTRICITY COMMERCIAL OPERATION 2

UNIT SHUTDOWN AND POWER REDUCTION REPORT MONTH:

SEPTEMBER 1989 I

I DOCKET NO.:

50-280

1

UNIT NAME: -s~u-rry-""':U:,:On~i~t'""""':11 _____

1 '

DATE:

10/05/89

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COMPLETED BY:

Christle Arney TELEPHONE: -,...,80""'4,---=3-=-5=-7 _""'!!3"""1-=8"""4"""x..,4,..,7""'7- \\

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NO.

DATE TYPE(l)

DURATION (HOURS)

SHU'ITIN'G EVENT SYSTEM COMPONENT ACTION TO PREVENT i

REASON(2) DOWN REACTOR(3) REPORT#

CODE(4)

CODE(5)

RECURRENT

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1 09-01-89 S

09-01-89 F 9 hours1.041667e-4 days 0.0025 hours 1.488095e-5 weeks 3.4245e-6 months B

40 min.

7 hours8.101852e-5 days 0.00194 hours 1.157407e-5 weeks 2.6635e-6 months A

54 min.

1 1

N/A KE N/A SL COND lPBU I

Cleaned Waterbox 'C'

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'A I Bus Duct cooling fan e \\

I motor grounded - placed

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alternate motor in service.,

Cleaned 'A', 'D' water-

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F:

S:

09-09-89 09-10-89 09-21-89 09-26-89 (1)

Forced Scheduled s

s s

s (2)

REASON:

11 hours1.273148e-4 days 0.00306 hours 1.818783e-5 weeks 4.1855e-6 months 36 min.

13 hours1.50463e-4 days 0.00361 hours 2.149471e-5 weeks 4.9465e-6 months 10 min.

9 hours1.041667e-4 days 0.0025 hours 1.488095e-5 weeks 3.4245e-6 months 14 min.

11 hours1.273148e-4 days 0.00306 hours 1.818783e-5 weeks 4.1855e-6 months 55 min.

B 1

A - Equipment Failure (Explain)

B - Maintenance or Test C - Refueling D - Regulatory Restriction E - Operator Training & License Examination F - Administrative G - Operational Error (Explain)

H - Other (Explain)

N/A N/A

'N/A N/A.

(3)

METHOD:

KE KE SB KE 1 - Manual 2 - Manual Scram.

3 - Automatic Scram.

4 - Other (Explain) 3 COND COND TRB COND boxes.

Clean waterboxes 'A' and

'CI.

Clean waterboxes 'B' and

'C' Tested Main Turbine Valves in accordance with l-PT-29.1 Cleaned waterboxes 'B'

'C' (4)

Exhibit G - Instructions for Preparation of Data Entry Sheets for Licensee Event Report (LER)

File (NUREG 0161)

(5)

Exhibit 1 - Same Source and e

NO.

DATE TYPE(l)

C-10-1 09-18-89 F C-10-2 09-19-89 F 09-22-89 F 09-28-89 F (1)

UNIT SHUTDOWN AND POWER REDUCTION REPORT MONTH:

SEPTEMBER 1989 METHOD OF LICENSEE SHUTTING EVENT SYSTEM DURATION (HOURS)

REASON(2) DOWN REACTOR(3) REPORT#

CODE(4) 5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months A

4 min.

6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months G 50 min.

19 hours2.199074e-4 days 0.00528 hours 3.141534e-5 weeks 7.2295e-6 months B 49 min.

57 hours6.597222e-4 days 0.0158 hours 9.424603e-5 weeks 2.16885e-5 months B 55 min.

3 3

1 1

2-89-009 EL 2-89-010 JB N/A TA N/A TA F:

Forced (2)

REASON:

(3)

METHOD:

S:

Scheduled A - Equipment Failure (Explain)

B - Maintenance or Test C - Refueling D - Regulatory Restriction E - Operator Training & License Examination F - Administrative G - Operational Error (Explain)

H - Other (Explain) 1 - Manual 2 - Manual Scram.

3 - Automatic Scram.

4 - Other (Explain) 4

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1 DOCKET NO.:

50-281

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UNIT NAME: """""s-u-rry-""'Un.....,i,..t-.:2,----

DATE:

10/05/89 r

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COMPLETED BY:

Christle Arney

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TELEPHONE:

804-357-3184 x477\\

COMPONENT CODE(5)

CAUSE & CORRECTIVE ACTIOOO TO PREVENT RECURRENT

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GEOO SG TRB TRB

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Main Generator Lockout trip when exciter field breaker\\

closed. Repaired Genera~

Leads Differential Relay~

(4)

'B' Steam Generator Lo-Lo Level while attempting to place Main Feed Regulator Valves inservice.

Unit taken off line for Turbine Overspeed Test and Balancing of Main Turbine.

Reactor remained Critical.

Unit taken off line for Turbine Balancing.

remained critical.

Reactor e

Exhibit G - Instructions for Preparation of Data Entry Sheets for Licensee Event Report (LER)

File (NUREG 0161)

(5)

Exhibit 1 - Same Source

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AVERAGE DAILY UNIT POWER LEVEL DOCKET NO.:

50-280*

UNIT NAME:

Surry Unit 1 DATE:

10705789 COMPLETED BY:

Christle Arney

TELEPHONE:(8045357-3184 x477 MONTH:

SEPTEMBER 1989 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net)

(MWe-Net) 1 653 17 770 2

715 18 768 3

775 19 766 4

778 20 778 5

777 21 766 6

777 22 716 7

776 23 779 8

773 24 783 9

712 25 783 10 698 26 774 11 772 27 722 12 770 28 786 13 769 29 785 14 769 30 785 15 769 31 16 770 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.

5

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AVERAGE DAILY UNIT POWER LEVEL DOCKET NO.:

50-281 UNIT NAME: _.Su_r_r_y __

U_n-it __ 2 ____ _

DATE:

10/05/89 COMPLETED BY: -=ch~r~i~s~t~l-e-A~r-n_e_y __ __

TELEPHONE: (804)357-3184 x477 MONTH:

SEPTEMBER 1989

DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net)

(MWe-Net) 1 0

17 0

2 0

18 0

3 0

19 134 4

O*

20 165 5

0 21 165 6

0 22 173 7

0 23 251 8

0 24 240 9

0 25 240 10 0

26 244 11 0

27 247 12 0

28 216 13 0

29 0

14 0

30 0

15 0

31 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.

6

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SUMMARY

OF OPERATING EXPERIENCE MONTH/YEAR:

SEPTEMBER 1989 Listed below in chronological sequence experiences for this month which required significant non-load related incidents.

by unit is a summary of operating load reductions or resulted in UNIT ONE 09-01-89 09-02-89 09-09-89 09-10-89 09-21-89 0000 This reporting power.

650 MW.

period begins with the

'C' waterbox cleaning.

Unit at 80%

0700 Start ramp up from 80% power.

0940 100% power.

820 MW.

1726 Start ramp down at 100%

power.

tripped.

1844 Stop ramp at 67.5%.

540 MW.

'A' Bus duct fan 0020 Start ramp up at 70% power.

530 MW.

'A' phase Bus duct fan returned to service; 'A' waterbox cleaned.

0118 Stop ramp at 80% power.

625 MW.

'D' waterbox out of service.

0350 Start ramp up at 80%.

625 MW.

'D' waterbox returned to service.

0903 Stop ramp at 100% power.

825 MW.

0038 Start ramp down for waterbox cleaning at 100%

power.

810 MW.

0214 Stop ramp at 80% power.

650 MW.

1002 Start ramp up at 82% power.

'C', 'A' waterbox cleaned.

660 MW.

1214 Stop ramp at 100% power.

820 MW.

0041 Start ramp down at 100% power.

MW.

0209 Stop ramp at 80% power.

650 MW.

1141 Start ramp up at 81%

power.

waterboxes cleaned.

1351 Stop ramp at 100% power.

820 MW.

Clean waterbox.

820 665 MW.

'BI'

'D' 2205 Start ramp down from 100% power for l-PT-29.1.

815 MW.

2345 Stop ramp at 75% power.

610 MW.

7

MONTH/YEAR:

SEPTEMBER-1989 Listed below in chronological sequence experiences for this month which required significant non-load related incidents.

by unit is a summary of operating load reductions or resulted in UNIT ONE 09-22-89 09-26-89 09-27-89 09-30-89 0543 Start ramp up at 76% power.

1-PT-29.1 completed.

600 MW.

0719 Stop ramp up at 100% power.

800 MW.

2205 Start ramp down from 100% power for waterbox cleaning.

820 MW.

2325 Stop ramp at 80%.

658 MW.

0839 Start ramp up from 82%.

'B', 'C' waterbox cleaned.

650 MW.

1000 Stop ramp at 100% power.

820 MW.

2400 Unit ended reporting period at 100% power.

8

MONTH/YEAR:

SEPTEMBER 1989 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 09-01-89 09-10-89 09-13-89 09-14-89 09-16-89 09-18-89 0000 2310 2003 1048 1016 1200 1228 Unit started reporting period at Cold Shutdown.

Reactor Coolant System> 200°.

Reactor Coolant System> 350°.

Unit at Hot Shutdown.

'A' and 'B' Shutdown Banks withdrew in preparation for dilution.

Commence pull to Criticality.

Experienced problems with bank overlap, 'A' Control Bank was at 13 steps and 'B' Bank was at 15 steps.

Bank overlap unit was at 143 steps.

Manually tripped reactor.

1458 4 hour4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months report for Manual Reactor Trip.

1744 Commenced Reactor Start-up.

1950 Reactor Critical.

'D' Bank at 147 steps.

2000 1030

-8 Reactor stable at 10 amps.

'D' Bank at 140 steps.

TAV=544.5.

CB - 1531; Letdown 1533 Pressure.

Increased Reactor power> 10% in preparation for going on line.

1042 Reactor Trip. First Outs EA8 (Reactor Trip by Turbine Trip) and F-E-1 (Generator Backup Lockout Relay Trip).

Enter EP occurred while attempting to raise generator voltage, 1045 1115 1546 1555 Closed Main Steam Trip Valves to stop cooldown.

Unit stable at Hot Shutdown.

Reactor Critical.

-8 Reactor at 10 amps 'D' Bank 152 steps; Tave-544.5; Reactor Coolant System Boron 1526 ppm.

9

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SUMMARY

OF OPERATING EXPERIENCE MONTH/YEAR:

SEPTEMBER 1989 Listed below in chronological sequence experiences for this month which required significant non-load related incidents.

by unit is a summary of operating load reductions or resulted in UNIT TWO 09-19-89 09-20-89 09-21-89 09-22-89 0032 Output breakers closed.

0050 Reactor trip on 'B' Steam Generator Low Level.

0801 Reactor Critical; 'D' 125 steps.

0812 Reactor at 10-8 amps; Tave-547; 'D' Bank -

112 steps; Reactor Coolant System Boron 1500 ppm.

2105 Unit on line.

0200 2134 Turbine load at 200 MW, Reactor Power at 34%.

Commence ramp up at 3%/hr, Reactor power 34%, 195 MW.

2227 Reactor power at 37%, 220 MW, Turbine Vibrations -

7.26 mils.

2354 0626 Secured ramp vibration.

at 41.5%,

255 MW, due to turbine Start ramp down at 150/hr to 30% power.

39% power, 240 MW.

0700 Stop ramp at 30% power, 190 MW.

0930 Received report of seal leak on 2-FW-P-lB.

Inboard seal failed.

0934 Start 2-FW-P-lA.

0935 Secured 2-FW-P-lB.

1013 Commenced unit ramp down for Turbine Overspeed Test and Balance.

1130 Generator off line.

1207 Turbine Overspeed Test OP-2.2.6.

10 Tripped at 1954 RPM

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SUMMARY

OF OPERATING EXPERIENCE MONTH/YEAR:

SEPTEMBER 1989 Listed below in chronological sequence experiences for this month which required significant non-load related incidents.

by unit is a summary of operating load reductions or resulted in UNIT TWO 09-23-89 09-24-89 09-26-89 09-27-89 0719 Unit on line.

0803 Holding ramp at 120 MW.

1024 Commence ramp up at 3%/hr.

2006 Reactor Power 59%, 410 MW.

2045 Holding ramp at 59.5%, 410 MW.

2258 Commence ramp down for turbine vibrations.

power 59%, 410 MW.

2330 Secured ramp at 50% power, 360 MW.

2333 Commence ramp down.

Secured ramp down at 40% power, 290 MW.

Reactor 0010 1300 Commence ramp up to monitor turbine vibrations.

Reactor power 40%, 270 MW.

1312 Secured ramp at Technicians replace F-8 (2-PT-5.1).

40.5%

power while Instrument Individual Rod Position Indicator 1400 Instrument Technicians complete replacement of F-8.

1539 Commence ramp up at 30%/hr.

Holding ramp at 46%,

330 MW.

increasing.

Turbine vibrations 1654 Commence ramp down.

Reactor power 46%, 330 MW, due to High Vibration on Main Turbine.

1735 Secured ramp at 40% power, 285 MW.

5 Bearing - 5.5 mils, #6 Bearing - 5.8 mils.

0931 Start ramp up at 40% power, 290 MW.

0932 Secured ramp at 40% power, 290 MW.

11

Listed below in chronological sequence by unit is experiences for this month which required load significant non-load related incidents.

a summary of operating reductions or resulted in UNIT TWO 09-28-89 09-29-89 09-30-89 1059 Commence ramp down from 40% power, 290 MW.

1135 Secure ramp at 200 MW for vibration data.

1154 Commence ramp down.

1235 Secure ramp at 110 MW for vibration data.

1250 Commence ramp down.

1405 Unit off line in order to balance main turbine jackshaft.

1421 Manually tripped turbine.

0234 0645 2-CH-RV-2203 lifted when letdown line flashed when charging flow was reduced in "AUTO".

Start up Reactor power to 2% to bring in steam.

1913 2-CH-RV-2203 repair complete.

2400 Ended the reporting period with the reactor at 2%

power.

Turbine Balance was complete and preparations were under way to place unit back on line.

12

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FACILITY CHANGES REQUIRING NRC APPROVAL MONTH/YEAR: SEPTEMBER 1989 NONE DURING THIS PERIOD 13

DC-84-70 DC-88-36 MONTH/YEAR:

SEPTEMBER 1989 PRESSURIZER SAFETY VALVE LOOP-SEAL INSULATION OVEN - UNIT 2 This design change installed metal reflective thermal insulation boxes which will enclose the safety valves loop seal piping.

This is to maintain the loop seal water temperature at approxi-mately 400°F.

This temperature will allow part of the water to flash to steam after passing through the safety valves.

The reduced density of the watersteam mixture will cause reduced fluid transient loads for the piping and supports.

SUMMARY

OF SAFETY ANALYSIS The installation of the boxes will not affect the operation of the pressurizer or the safety valves.

The boxes will reduce fluid transient loads to ensure the piping and supports are qualified for the design basis transients once the supports have been modified.

The boxes do not affect any safety related system or component and does not impact any Technical Specification.

CONTROL ROOM ENVELOPE HEATING, VENTILATING, AIR CONDITIONING (HVAC) INTERIM MODIFICATIONS - UNITS 1 & 2 This design change involved several modifications to the present equipment on an interim basis until larger capacity replacement equipment can be procured (approximately 24 months).

The redun-dancy of certain equipment had been lost due to increased heat loads exceeding the rated capacity of the equipment.

Each of the air handling units had a

redundant drive motor installed which was powered from a different power source.

This will ensure operability of the air handling unit from a loss of the drive motor or it power source.

In addition, the belt drive was modified to increase the fan speed and therefore increase the air flow and cooling capacity.

The increased air flow through the ventilation ducting created the requirement to modify the ducting to keep the air velocity below 2,000 feet per minute (FPM).

One of the chillers and support equipment, i.e. chilled water and service water pumps and chilled water outlet MOV, was provided with a redundant source of power.

SUMMARY

OF SAFETY ANALYSIS This design change.restores the control room and emergency switchgear room Technical Specification design basis by ensuring that equipment and operational capability exists to compensate for normal and accident heat loads therein.

The installation of the new motors will not affect other safety-related equipment or the qualification of the air handling units.

The redundancy of the HVAC system is restored to provide single failure protection.

The added equipment is seismically qualified and seismically installed and supported.

14

FACILITY CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTH/YEAR:

SEPTEMBER 1989 SCAFFOLDING REQUEST -

09-01-89 This request is to document the erection of temporary scaffolding located in the Emergency Service Water Pump House to support painting and associated preparatory work.

Installation of this temporary scaffolding was reviewed for effect on accident analyses and equipment operability/function.

Conclusion is that assumptions, bases and probabilities of accident analyses and equipment malfunctions are not affected.

TM-SZ-89-114 TEMPORARY MODIFICATION -

09-01-89 Temporary Modification to document that "B" Reactor Coolant Pump Containment Isolation Valve for Component Cooling (TV-CC-205B) will be blocked open using a split schedule 80 pipe with clamps attached to the valve stem.

This modification will be installed to maintain component cooling flow during certain testing performed at cold shutdown.

Technical Specification 3.8.A.l requires that containment integrity is maintained when in refueling mode or above cold shutdown.

The isolation valve will only be blocked for the duration of the test.

The valve will be returned to service prior to exceeding cold shutdown.

Therefore, no unreviewed safety question is created.

TM-SZ-89-118 TEMPORARY MODIFICATION -

09-04-89 This modification was to document that 2-DA-TV-200B was removed to allow repair.

A spool piece was installed in its place to allow continued operation of the containment sump pump.

This Temporary Modification does not present an unreviewed safety question since the unit will be at cold shutdown throughout the Temporary Modification installation.

2-DA-TV-200A will remain operational allowing closure for isolation of the flow path from containment, if required.

AC-SZ-89-0909 ADMINISTRATIVE CONTROL -

09-09-89 Administrative control will be maintained to ensure that TV-CV-250D will remain closed until it is operable.

The solenoid leads will be lifted, the air to the solenoid will be tagged closed and the valve will be under Administrative Control.

Failing TV-CV-250D closed has been evaluated and it is determined that since the valve will be in its closed (accident) position the consequences or probability of any accident will not be increased.

This change will not create an unreviewed safety question.

15

e FACILITY CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTH/YEAR:

SEPTEMBER 1989 TM-Sl-89-165 TEMPORARY MODIFICATION 13-89 Temporary Modification to document that a hose from the Fire Pro-tection air compressor will be connected to the upstream side of the fill valve for Main Control Room air bottles located in the cable tunnel and a hose will be run through the fire door separating #1 and

2 Emergency Switchgear Rooms and the #3 Mechanical Equipment Room fire door.

The Main Control Room pressure boundary fire doors will be closed if required, remain operable while l-TOP-2128 is in unreviewed safety question is created.

AC-S2-89-0917 ADMINISTRATIVE CONTROL 18-89 will not be breached, and air bottle banks will effect.

Therefore, no Administrative Control will be maintained to line-up service air to containment to support activities requiring service air usage.

Administrative Control of the valves will maintain containment integrity and the valves provide redundant isolation capability.

Therefore, no unreviewed safety question is created.

SCAFFOLDING REQUEST 21-89 This request is to document the erection of temporary scaffolding located in Unit 2 cable vault to work cable tray covers.

Installation of this temporary scaffolding was reviewed for effect on accident analyses and equipment operability/function.

Conclusion is that assumptions, bases and probabilities of accident analyses and equipment malfunctions are not affected.

SCAFFOLDING REQUEST 21-89 This request is to document the erection of temporary scaffolding located in #3 Mechanical Equipment Room to work l-VS-PCV-531.

Installation of this temporary scaffolding was reviewed for effect on accident analyses and equipment operability/function.

Conclusion is that assumptions, bases and probabilities of accident analyses and equipment malfunctions are not affected.

SCAFFOLDING REQUEST 21-89 This request is to document the erection of temporary scaffolding located in the Fire Pump House, in the diesel driven fire pump area for painting.

Installation of this temporary scaffolding was reviewed for effect on accident analyses and equipment operability/function.

Conclusion is that assumptions, bases and probabilities of accident analyses and equipment malfunctions are not affected.

16

JC0-89-311 e

FACILITY CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTH/YEAR:

SEPTEMBER 1989 JUSTIFICATION FOR CONTINUED OPERATION 26-89 This JCO provides compensatory actions to ensure the Emergency Service Water pump diesel drivers will reliably start when the outside ambient temperature is below 50°F.

The JCO provides actions to be taken to ensure that the Emergency Service Water pump house temperature remains above the manufac-turer's recommended minimum temperature for reliable diesel starting.

Therefore, no unreviewed safety question is created via this JCO.

SCAFFOLDING REQUEST 27-89 This request is to document erection of temporary scaffolding located in Unit 2 Safeguards Basement (Steam side) for cable tray cover installation.

Installation of this temporary scaffolding was reviewed for effect on accident analyses and equipment operability/function.

Conclusion is that assumptions, bases and probabilities of accident analyses and equipment malfunctions are not affected.

SCAFFOLDING REQUEST -

09-27-89 This request is to document erection of temporary scaffolding located in Unit 1 valve pit at the 12' level for cable tray cover installation.

Installation of this temporary scaffolding was reviewed for effect on accident analyses and equipment operability/function.

Conclusion is that assumptions,

bases, and probabilities of accident analyses and equipment malfunctions are not affected.

UFSAR CHANGE REQUEST FOR SECTION 9.1.2.6.21 27-89 UFSAR Change Request to clarify the operating sequence between the duplicate heat trace circuits and enhance the coordination of the primary circuit under-temperature setpoint with the backup circuit control setpoint.

The 10CFR50.59 Review concluded that an unreviewed safety question was not created.

Malfunction of Heat Trace Circuit will not contribute to an over dilution. If Boric Acid precipitation occurred, alternate Chemical Volume and Control System flow paths exist.

17

'1 PROCEDURE OR METHOD OF OPERATION CHANGES REQUIRING NRC APPROVAL MONTH/YEAR:

SEPTEMBER 1989 NONE DURING THIS PERIOD 18

2-PT-25.2 l-TOP-2128 PROCEDURE OR METHOD OF OPERATION CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTH/YEAR:

SEPTEMBER 1989 REQUEST TO CHANGE 01-89 This procedure change request requires the non-automatic contain-ment isolation vents to be opened and a safety-related MOV to be de-energized under administrative controls.

An unreviewed safety question does not exist since administrative control of the vent valves and of the MOV will be required and utilized in accordance with Technical Specification 1.0.H, definition of containment integrity, and Surry Power Station's Administrative procedures.

PROCEDURE CHANGE REQUEST 13-89 Procedure to document that a

hose from Fire Protection air compressor will be connected to upstream side of fill valve for Main Control Room air bottles located in cable tunnel and a hose will be run through the fire door separating 1 and 2 Emergency Switchgear Rooms and the #3 Mechanical Equipment Room fire door.

The Main Control Room pressure boundary will fire doors will be closed if required, and air remain operable while this Temporary Operating effect.

No unreviewed safety question created.

19 not be breached, bottle banks will Procedure is in

4,.

._,_, (

TESTS AND EXPERIMENTS REQUIRING NRC APPROVAL MONTH/YEAR:

SEPTEMBER 1989 NONE DURING THIS PERIOD 20

]

TESTS AND EXPERIMENTS THAT DID NOT REQUIRE NRC APPROVAL MONTH/YEAR:

SEPTEMBER 1989 NONE DURING THIS PERIOD 21

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PRIMARY COOLANT ANALYSIS VIRGINIA POWER SURRY POWER STATION CHEMISTRY REPORT MONTH/YEAR: SEPTEMBER 1989 UNIT NO. 1 UNIT NO. 2 MAX.

MIN.

AVG.

MAX.

MIN.

AVG.

(1)

Gross Radioact., µCi/ml

8. 44 (E-1) 4.15(E-1) 6.52(E-1)

I. 23 (E-1) 7.lO(E-4) 2.79(E-2)

Suspended Solids, ppm 0.0 o.o o.o o.o 0.0 0.0 Gross Tritium, µCi/ml 3.15 (E-1)

2. 91 (E-1) 2.99(E-1)

I. 72 (E-2) 1.10 (E-2)

1. 41 (E-2)

Iodine-131, µCi/ml 7.14(E-3) 2.14(E-3) 3,36(E-3) 2.60(E-4) 1.51(E-5) 9.73(E-5)

Iodine-131/Iodine-133 0.18 0.08 0.12 0.07 0.07 0.07 Hydrogen, cc/kg 28.6 25.5 27.7 34.0 23,0 27.6 Lithium, ppm 2.33 2.06 2.24 2.86 1.33 2.02 Boron - 10, ppm*

158 143 150 434 240 314 Oxygen, (DO)* ppm 0.005 0.005 0.005 0.005 0.005 0.005 Chloride, ppm 0.012 0.007 0.009 0.014 0.008 0.011 pH@ 25 degree Celsius 6.76 6.61 6.67 6.34 5.63

Boron - 10 = Total Boron x 0.196 UNIT ONE:

Unit one started September at 100% power with BMB in service.

On September 1, 140 grams of lithium were added.

Later on September 1, the unit ramped back to 70% to clean water boxes.

On September 9, the unit ramped to 77% to clean water boxes.

On September 24, the unit ramped back to 74% to conduct turbine valve freedom tests.

On September 26, the unit ramped back to 80% to clean water boxes, and ended the month at 100% full power.

UNIT TWO:

Unit two started the month at cold shutdown with BMB and RHR in service.

On September 7 the "A" RCP was placed in service and "B" taken out.

On September 10 the unit exceeded 200°F just prior to midnight while heating up towards startup.

On September 11 the "C" RCP was taken out of service because of high temperature buildup within the pump.

On September 16, 2167 grams of lithium were added to the RCS.

The reactor startup commenced on September 16 at 1205 hours0.0139 days 0.335 hours 0.00199 weeks 4.585025e-4 months and went critical at 1950 hours0.0226 days 0.542 hours 0.00322 weeks 7.41975e-4 months .

The RCS dissolved hydrogen was out-of-specification after criticality until 0310 hours0.00359 days 0.0861 hours 5.125661e-4 weeks 1.17955e-4 months on September 17.

On September 18, 162 grams and then another 243 grams of lithium were added to the RCS.

On September 19, 162 grams of lithium were added to the RCS.

On September 29, letdown was isolated due to a leaking relief valve on the letdown system.

The unit ended the month at 2% power.

22 5.93

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NEW OR SPENT FUEL SHIPMENT II DATE SHIPPED OR RECEIVED FUEL HANDLING NUMBER OF ASSEMBLIES ASSEMBLY ANSI PER SHIPMENT NUMBER NUMBER NONE DURING THIS PERIOD 23 e

DATE: SEPTEMBER 1989 INITIAL ENRICHMENT NEW OR SPENT FUEL SHIPPING CASK ACTIVITY LEVEL

~,

r DESCRIPTION OF PERIODIC TEST WHICH WERE NOT COMPLETED WITHIN THE TIME LIMITS SPECIFIED IN TECHNICAL SPECIFICATIONS MONTH/YEAR:

SEPTEMBER 1989 NONE DURING THIS PERIOD 24

ML18152A304

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