ML18153C736

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Monthly Operating Repts for Aug 1991 for Surry Power Station,Units 1 & 2
ML18153C736
Person / Time
Site: Surry  Dominion icon.png
Issue date: 08/31/1991
From: Negron M, Stewart W
VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
91-536, NUDOCS 9109190136
Download: ML18153C736 (26)
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VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND, VIRGINIA 23261 September 16, 1991 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.91-536 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 August 1991.

Very truly yours,

\\\\Lm W. L. Stewart Senior Vice President - Nuclear Enclosure cc:

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

Suite 2900 Atlanta, Georgia 30323 Mr. M. W. Branch NRC Senior Resident Inspector Surry Power Station

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VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION MONTHLY OPERATING REPORT REPORT NO. 91-08 Approved:

i\\~ctZ,c.r; Station Manager

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Date

TABLE OF CONTENTS Section tlrry Monthly Operating Report No. 91-08 Page 2 of 25 Page Operating Data Report - Unit No. 1......................................................................................................... 3 Operating Data Report - Unit No. 2......................................................................................................... 4 Unit Shutdowns and Power Reductions - Unit No. 1.................................................................................... 5 Unit Shutdowns and Power Reductions - Unit No. 2.................................................................................... 7 Average Daily Unit Power Level - Unit No. 1.............................................................................................. 9 Average Daily Unit Power Level - Unit No. 2............................................................................................ 1 O Summary of Operating Experience - Unit No. 1....................................................................................... 11 Summary of Operating Experience - Unit No. 2....................................................................................... 12 Facility Changes That Did Not Require NRC Approval............................................................................... 15 Procedure or Method of Operation Changes That Did Not Require NRC Approval........................................... 20 Tests and Experiments That Did Not Require NRC Approval...................................................................... 22 Chemistry Report............................................................................................................................. 23 Fuel Handling - Unit No. 1................................................................................................................... 24 Fuel Handling - Unit No. 2................................................................................................................... 24 Description of Periodic Test(s) Which Were Not Completed Within the Time Limits Specified in Technical Specifications................................................................................................... 25

&rry Monthly Operating Report No. 91-08 Page 3 of 25 OPERATING DATA REPORT

1.

Unn Name:...................................................

2.

Reporting Period:..........................................

3. Licensed Thermal Power (MWt):.......................
4.

Nameplate Rating (Gross MWe):.......................

5.

Design Electrical Rating (Net MWe):..................

6.

Maximum Dependable Capacity (Gross MWe):....

7.

Maximum Dependable Capacity (Net MWe):........

Surry Unit 1 August 1991 2441 847.5 788 820 781 Docket No.:

Date:

Completed By:

Telephone:

50-280 09-06-91 M.A. Negron 804-365-2795

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:
11. Hours In Reporting Period..........................
12.

Number of Hours Reactor Was Critical..........

13.

Reactor Reserve Shutdown Hours...............

14. Hours Generator On-Line...........................
15. Unit Reserve Shutdown Hours.....................
16. Gross Thermal Energy Generated (MWH)......
17. Gross Electrical Energy Generated (MWH)....
18. Net Electrical Energy Generated (MWH)........
19. Unit Service Factor...................................
20.

Unit Availability Factor...............................

21.

Unit Capacity Factor (Using MDC Net)...........

22.

Unit Capacity Factor (Using DER Net)...........

23.

Unit Forced Outage Rate............................

This Month 744.0 744.0 0.0 744.0 0.0 1742868.0 558720.0 529647.0 100.0%

100.0%

91.2%

90.3%

0.0%

YTD 5831.0 5831.0 0.0 5831.0 0.0 14019732.4 4650720.0 4417262.0 100.0%

100.0%

97.0%

96.1%

0.0%

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

Refueling, February 16, 1991, 64 days.

25. If Shut Down at End of Report Period Estimated Date of Start-up:
26. Unit In Test Status (Prior to Commercial Operation):

Cumulative 163847.0 105305.2 3774.5 103311.2 3736.2 240239642.7 78227543.0 74200391.0 63.1%

65.3%

58.4%

57.5%

19.7%

FORECAST INITIAL CRITICALITY ACHIEVED INITIAL ELECTRICITY COMMERCIAL OPERATION

e esurry Monthly Operating Report No. 91-08 Page 4of 25 OPERATING DATA REPORT

1. Unit Name:...................................................
2. Reporting Period:..........................................
3. Licensed Thermal Power (MWt):.......................
4. Nameplate Rating (Gross MWe):.......................
5. Design Electrical Rating (Net MWe):..................
6.

Maximum Dependable Capacity (Gross MWe):....

7.

Maximum Dependable Capacity (Net MWe):........

Surry Unit 2 August 1991 2441 847.5 788 820 781 Docket No.:

Date:

Completed By:

Telephone:

50-281 09-06-91 M.A. Negron 804-365-2795

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:
11. Hours In Reporting Period..........................
12. Number of Hours Reactor Was Critical..........
13. Reactor Reserve Shutdown Hours...............
14. Hours Generator On-Line...........................
15. Unit Reserve Shutdown Hours.....................
16. Gross Thermal Energy Generated (MWH)......
17. Gross Electrical Energy Generated (MWH)....
18. Net Electrical Energy Generated (MWH)........
19. Unit Service Factor...................................
20. Unit Availability Factor...............................
21.

Unit Capacity Factor (Using MDC Net)...........

22.

Unit Capacity Factor (Using DER Net)...........

23.

Unit Forced Outage Rate............................

This Month 744.0 647.2 0.0 638.7 0.0 1213098.8 384440.0 360820.0 85.8%

85.8%

62.1%

61.5%

14.2%

YTD 5831.0 3590.0 0.0 3494.5 0.0 7276454.3 2396435.0 2268414.0 59.9%

59.9%

49.8%

49.4%

16.2%

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

Planned maintenance, September 7, 1991, 7 days.

25. If Shut Down at End of Report Period Estimated Date of Start-up:
26. Unit In Test Status (Prior to Commercial Operation):

Cumulative 160727.0 102762.3 328.1 101065.1 0.0 235411922.6 76626549.0 72647139.0 62.9%

62.9%

58.0%

57.4%

15.3%

FORECAST INITIAL CRITICALITY ACHIEVED INITIAL ELECTRICITY COMMERCIAL OPERATION

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emy Monthly Operating Report No. 91-08 Page 5 of 25 UNIT SHUTDOWN AND POWER REDUCTION (EQUAL To OR GREATER THAN 20%)

REPORT MONTH: August 1991 Docket No.: 50-280 Unit Name: Surry Unit 1 Date: 09-06-91 Completed by:

M; A. Negron Telephone: 804-365-2795 (1)

(2)

(3)

(4)

(5)

Method Duration of LER System Component Cause & Corrective Action to Date Type Hours 8-1-91 s

0 8-4-91 s

0 8-10-91 s

0 8-16-91 s

0 8-23-91 s

0 (1)

F:

Forced S: Scheduled Reason B

B B

B B

(2)

REASON:

Shutting No.

Down Rx 4

N/A 4

NIA 4

N/A 4

N/A 4

NIA A -

Equipment Failure (Explain)

B Maintenance or Test C

Refueling D

Regulatory Restriction Code Code SH HX SH HX SH HX SH HX SH HX E

Operator Training & Licensing Examination F

Administrative G

Operational Error (Explain)

(4)

Exhibit G - Instructions for Preparation of Data Entry Sheets for Licensee Event Report (LER) File (NUREG 0161)

Prevent Recurrence Reduced power from 99.5% to 78.5% to maintain condenser vacuum while cleaning waterboxes.

Reduced power from 100% to 74.5% to maintain condenser vacuum while cleaning waterboxes.

Reduced power from 100% to 72% to maintain condenser vacuum while cleaning waterboxes.

Reduced power from 100% to 78% to maintain condenser vacuum while cleaning waterboxes.

Reduced power from 100% to 76% to maintain condenser vacuum while cleaning waterboxes.

(3)

METHOD:

1 -

Manual 2 -

Manual Scram.

3 -

Automatic Scram.

4 -

Other (Explain)

(5)

Exhibit 1 - Same Source.

(1)

Date Type 8-26-91 F

8-30-91 s

(1)

F:

Forced S: Scheduled (4) eirry Monthly Operating Report No. 91-08 Page 6 of 25 UNIT SHUTDOWN AND POWER REDUCTION (EQUAL To OR GREATER THAN 20%)

REPORT MONTH: August 1991

[continued]

(2)

(3)

(4)

Method (5)

Docket No.: 50-280 Unit Name: Surry Unit 1 Date: 09-06-91 Completed by: M. A. Negron Telephone: 804-365-2795 Duration of LER System Component Cause & Corrective Action to Hours 0

0 Reason A

B (2)

REASON:

Shutting Down Rx 4

4 No.

91-018-00 NIA A -

Equipment Failure (Explain)

B Maintenance or Test C

Refueling D

Regulatory Restriction Code Code EA BU SH HX E

Operator Training & Licensing Examination F

Administrative G

Operational Error (Explain)

Prevent Recurrence Fault on Bus 5 in switchyard caused the loss of "D" & "E" transfer bus which resulted in a runback from 100% to 70%.

Reduced power from 100% to 66% to maintain condenser vacuum while cleaning waterboxes.

(3)

METHOD:

1 -

Manual 2 -

Manual Scram.

3 -

Automatic Scram.

4 -

Other (Explain)

(5)

Exhibit G - Instructions for Preparation of Data Entry Sheets for Licensee Event Report (LER) File (NUREG 0161)

Exhibit 1 - Same Source.

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9surry Monthly Operating Report No. 91-08 Page 7of 25 UNIT SHUTDOWN AND POWER REDUCTION (EQUAL To OR GREATER THAN 20%)

REPORT MONTH: August 1991 Docket No.: 50-281 Unit Name: Surry Unit 2 Date: 09-06-91 Completed by: M.A. Negron Telephone: 804-365-2795 (1)

(2)

(3)

(4)

(5)

Method Duration of LER System Component Cause & Corrective Action to Date Type Hours 8-2-91 F

105.3 8-11-91 s

0 8-12-91 s

0 8-14-91 F

0 8-18-91 s

0 (1)

F:

Forced S: Scheduled Reason A

B B

A B

(2)

REASON:

Shutting No.

Down Rx 3

91-007-00 4

NIA 4

NIA 4

NIA 4

NIA A -

Equipment Failure (Explain)

B Maintenance or Test C

Refueling D

Regulatory Restriction Code Code EE JX SH HX SH HX CL SH HX E

Operator Training & Licensing Examination F

Administrative G

Operational Error (Explain)

(4)

Exhibit G - Instructions for Preparation of Data Entry Sheets for Licensee Event Report (LER) File (NUREG 0161)

Prevent Recurrence Reactor trip and safety injection occurred due to a power supply failure on vital bus 2-IVA.

Safety Injection occurred from high steam flow/low Tave signal.

Reduced power from 100% to 80% to maintain condenser vacuum while cleaning waterboxes Reduced power from 100% to 79.7% maintain condenser vacuum while cleaning waterboxes.

Control rod D-4 dropped due to blown fuse resulting from a problem in the coil stack.

Runback occurred from 100%

to 53.9% power.

Reduced power from 90% to 70% to maintain condenser vacuum while cleaning waterboxes.

(3)

METHOD:

1 -

Manual 2 -

Manual Scram.

3 -

Automatic Scram.

4 -

Other (Explain)

(5)

Exhibit 1 - Same Source.

\\

r (1) esurry Monthly Operating Report No. 91-08 Page 8 of 25 UNIT SHUTDOWN AND POWER REDUCTION (EQUAL To OR GREATER THAN 20%)

REPORT MONTH: August 1991

[continued]

(2)

(3)

(4)

(5)

Docket No.: 50-281 Unit Name: Surry Unit 2 Date: 09-06-91 Completed by:

M. A. Negron Telephone: 804-365-2795 Duration Method of Reason Shutting Down Rx LER No.

System Component Cause & Corrective Action to Date Type Hours 8-23-91 F

0 (1)

F:

Forced S: Scheduled A

(2)

REASON:

4 NIA A -

Equipment Failure (Explain)

B Maintenance or Test C

Refueling D

Regulatory Restriction Code Code Prevent Recurrence CL Control rod D-4 dropped due to blown fuse resulting from a problem in the coil stack.

Runback occurred from 80% to 50% power.

(3)

METHOD:

1 -

Manual 2 -

Manual Scram.

3 -

Automatic Scram.

4 -

Other (Explain)

E Operator Training & Licensing Examination F

Administrative G

Operational Error (Explain)

(4)

Exhibit G - Instructions for Preparation of Data Entry Sheets for Licensee Event Report (LER) File (NUREG 0161)

(5)

Exhibit 1 - Same Source.

v Month:

August 1991 Day 1

2 3

4 5

6 7

8 9

10 11 12 13 14 15 16 INSTRUCTIONS eurry Monthly Operating Report No. 91-08 Page 9 of 25 AVERAGE DAILY UNIT POWER LEVEL Docket No.: 50-280 Unit Name: Surry Unit 1 Date: 09-06-91 Completed by: M.A. Negron Telephone: 804-365-2795 Average Daily Power Level Average Daily Power Level (MWe-Net)

Day (MWe-Net) 659.1 17 584.5 758.2 18 755.5 756.5 19 749.7 500.5 20 745.9 708.5 21 739.9 757.3 22 731.5 762.8 23 722.9 759.8 24 650.7 756.9 25 750.5 682.8 26 602.5 754.2 27 733.1 753.7 28 734.6 748.1 29 731.6 744.8 30 703.9 739.4 31 559.8 729.8 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.

Month:

August 1991 Day 2

3 4

5 6

7 8

9 10 11 12 13 14 15 16 INSTRUCTIONS 4lrry Monthly Operating Report No. 91-08 Page 1 O of 25 AVERAGE DAILY UNIT POWER LEVEL Docket No.: 50-281 Unit Name: Surry Unit 2 Date: 09-06-91 Completed by: M.A. Negron Telephone:

804-365-2795 Average Daily Power Level Average Daily Power Level (MWe-Net)

Day (MWe-Net) 756.8 17 657.7 529.0 18 612.2 0.0 19 629.9 0.0 20 706.8 0.0 21 581.6 0.0 22 588.2 461.3 23 430.0 727.8 24 416.8 712.8 25 425.3 705.4 26 423.4 709.5 27 429.8 701.8 28 401.0 702.3 29 404.0 617.2 30 414.4 418.2 31 410.6 460.6 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.

tlrry Monthly Operating Report No. 91-08 Page 11 of 25

SUMMARY

OF OPERATING EXPERIENCE MONTH/YEAR: August 1991 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 08-01-91 08-02-91 08-04-91

. 08-05-91 08-10-91 08-16-91 08-17-91 08-23-91 08-24-91 0000 This report period started with the Unit operating at 100% power and 765 MWe.

0945 Started unit power reduction to maintain condenser vacuum while cleaning waterboxes; 99.5% power, 765 MWe.

1224 Stopped power reduction; 78.5% power, 605 MWe.

2200 Started ramp up; 79.2% power, 625 MWe.

0005 0030 Stopped ramp; 99.5% power, 800 MWe.

Started power reduction to hydrolase waterboxes; 100% power, 790 MWe.

0252 Stopped power reduction; 74.5% power, 560 MWe.

0305 Started ramp up; 69.5% power, 51 O MWe.

0540 Stopped ramp; 100% power, 800 MWe.

0945 Started unit power reduction to maintain condenser vacuum while cleaning waterboxes; 100% power, 775 MWe.

1215 Stopped power reduction; 72% power, 530 MWe.

1534 Started ramp up; 70% power, 500 MWe.

2038 Stopped ramp; 100% power, 800 MWe.

2245 0116 Started unit power reduction to maintain condenser vacuum while cleaning waterboxes; 100% power, 760 MWe.

Stopped power reduction; 78% power, 575 MWe.

1912 Started ramp up; 74.5% power, 590 MWe.

2212 Stopped ramp; 100% power, 790 MWe.

2150 Started unit power reduction to maintain condenser vacuum while cleaning waterboxes; 100% power, 760 MWe.

2400 Stopped power reduction; 85.5% power, 640 MWe.

1326 Started power reduction while cleaning waterboxes; 85.5% power, 630 MWe.

1404 Stopped power reduction; 76% power, 540 MWe.

1456 Started ramp up; 76% power, 600 MWe.

emy Monthly Operating Report No. 91-08 Page 12 of 25

SUMMARY

OF OPERATING EXPERIENCE MONTH/YEAR: August 1991

[continued]

UNIT ONE [continued]

08-24-91

[continued]

08-26-91 08-30-91 08-31-91 UNIT TWO 08-01-91 08-02-91 08-06-91 08-07-91 08-08-91 08-09-91 1818 0329 Stopped ramp; 100% power, 790 MWe.

Unit experienced a turbine runback due to the loss of "D" and "E" Transfer Bus. Power was reduced from 100% power, 790 MWe to 70% power, 500 MWe.

1053 Started power increase; 73% power, 567 MWe.

0243 Stopped power increase; 100% power, 780 MWe.

1605 Started unit power reduction to maintain condenser vacuum while cleaning waterboxes; 100% power, 765 MWe.

2340 Stopped power reduction; 66% power, 450 MWe.

1302 Started ramp up; 63% power, 460 MWe.

1732 Stopped ramp; 100% power, 795 MWe.

2400 This reporting period ended with the Unit operating at 100% power and 790 MWe.

0000 1507 1657 1747 0217 2100 2020 0343 0616 2338 This report period started with the Unit operating at 100% power and 800 MWe.

Unit power was reduced to 92% power due to steam dump operation resulting from electrical spiking on Vital Bus 2-IVA.

The Unit experienced a Reactor Trip/Safety Injection as a result of a power supply failure on Vital Bus 2-IVA. The Unit was stabilized at Hot Shutdown.

Reactor critical.

Unit on line and increasing power.

Unit at 100% power.

Started unit power reduction to maintain condenser vacuum while cleaning waterboxes; 100% power, 770 MWe.

Stopped power reduction and started power increase; 81% power, 635 MWe.

Stopped power increase; 100% power, 795 MWe.

Started unit power reduction to maintain condenser vacuum while cleaning waterboxes; 100% power, 775 MWe.

4tsurry Monthly Operating Report No. 91-08 Page 13 of 25

SUMMARY

OF OPERATING EXPERIENCE MONTH/YEAR: August 1991

[continued]

UNIT TWO [continued]

08-10-91 08-11-91 08-12-91 08-13-91 08-14-91 08-15-91 08-16-91 0130 Stopped power reduction; 81.5% power, 628 MWe.

031 O Started power increase; 81.5% power, 625 MWe.

0910 Stopped power increase; 100% power, 800 MWe.

0745 Started unit power reduction to maintain condenser vacuum while cleaning waterboxes; 100% power, 775 MWe.

0940 Stopped power reduction; 80% power, 61 O MWe.

1226 Started ramp up; 80% power, 640 MWe.

1500 Stopped ramp; 100% power, 800 MWe.

1448 Started unit power reduction to maintain condenser vacuum while cleaning waterboxes; 100% power, 765 MWe.

2239 Stopped power reduction; 79.7% power, 600 MWe.

0217 Started ramp up; 80% power, 625 MWe.

0545 Stopped ramp; 100% power, 800 MWe.

2129 Started unit power reduction to maintain condenser vacuum while cleaning waterboxes; 100% power, 770 MWe.

2220 Stopped power reduction; 86% power, 670 MWe.

0548 Started ramp up; 85% power, 670 MWe.

0649 Stopped ramp; 100% power, 800 MWe.

1013 Started unit power reduction to maintain condenser vacuum while cleaning waterboxes; 99% power, 780 MWe.

1041 Stopped power reduction; 93% power, 710 MWe.

1252 Started ramp up; 93% power, 740 MWe.

1329 Stopped ramp; 100% power, 795 MWe.

1753 Control Rod D-4 dropped causing the unit to experience a runback to 53.9% power, 370 MWe.

2134 Started ramp up to stop Main Feedwater Pump recirculation mode; 58% power, 465 MWe.

2154 Stopped ramp below rod stop setpoint to perform flux mapping; 65% power, 490 MWe.

1735 Started ramp up following completion of flux mapping; 62% power, 470 MWe.

emy Monthly Operating Report No. 91-08 Page 14of 25

SUMMARY

OF OPERATING EXPERIENCE MONTH/YEAR: August 1991

[continued]

UNIT TWO [continued]

08-17-91 08-18-91 08-19-91 08-20-91 08-21-91 08-23-91 08-31-91 0642 1600 Stopped ramp due to power restriction (based on results of 8/16/91 flux mapping); 90%

power, 725 MWe.

Started unit power reduction to maintain condenser vacuum while cleaning waterboxes; 90% power, 700 MWe.

1820 Stopped power reduction; 70% power, 730 MWe.

0044 Started power increase; 70% power, 540 MWe.

1156 Stopped power increase; 90% power, 690 MWe.

0015 Started ramp up (power restriction cleared based on results of 8/17/91 flux mapping); 90%

power, 735 MWe.

0313 Stopped ramp; 100% power, 805 MWe.

1322 Started unit power reduction to maintain condenser vacuum while cleaning waterboxes; 100% power, 770 MWe.

0810 0435 Stopped power reduction; 81 % power; 620 MWe.

Control Rod D-4 dropped causing unit to runback from 80% power to 50% power.

1105 Started power increase; 52% power, 390 MWe.

1325 Stopped power increase; 60% power, 460 MWe.

2400 This report ended with the Unit operating at 60% power, 430 MWe because of dropped control rod D-4.

esurry Monthly Operating Report No. 91-08 Page 15 of 25 FACILITY CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTH/VEAR: August 1991 EWR 90-270J EWR 91-097 EWR 91-093 Engineering Work Request (Safety Evaluation No.90-222) 08-01-91 This Engineering Work Request (EWR) installed a flow path between the chilled Component Cooling (CC) Water system and the abandoned Boron Evaporator demineralizers to provide a means for removing contaminants from and reducing radiation levels in the CC system.

This modification is an extension of the CC system and does not affect the operability or function of the system. The piping modification was designed and installed in accordance with the original engineering design requirements of the CC system and thus does not adversely impact the previously analyzed accidents. Therefore, an unreviewed safety question was not created.

Engineering Work Request (Safety Evaluation No.91-183) 08-04-91 This Engineering Work Request (EWR) modified the circuit breaker wiring in the 500 kilovolt switchyard such that a Unit 2 shutdown will be initiated if breakers G2T567 and G202 or 53102 are opened. The EWR also changes breaker 53102 to operate as a lagging reclose breaker.

This modification was implemented to prevent a scenario in which the Unit 2 main generator is isolated from the system but continues to supply station service loads. The affected switchyard equipment is non-safety related, thus the modification will not impact accident mitigation or safe shutdown capability.

Therefore, an unreviewed safety question is not created.

Engineering Work Request (Safety Evaluation No.91-175) 08-09-91 This Engineering Work Request (EWR) changes the alarm setpoint of the tailpipe temperature for the Unit 2 letdown relief valve, 2-CH-RV-2203.

This change increases the alarm setpoint temperature from 135 °F to 165 °F to eliminate nuisance alarms caused by high ambient temperatures.

This change affects only the Control Room annunciator alarm setpoint and is sufficiently low to indicate leakage through the valve. The alarm setpoint has no impact on any safety parameters and does not change the operational characteristics of the unit. Therefore, an unreviewed safety question is not created.

-Surry Monthly Operating Report No. 91-08 Page 16 of 25 FACILITY CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTH/YEAR: August 1991 AC S1 0808 TSR 91-073 TM S1-91-16

[continued]

Administrative Control (Safety Evaluation No.91-193) 08-22-91 Administrative Control of the Number 2 Emergency Switchgear room (ESGR)/Turbine Building door will be established by stationing a person at the door to immediately disconnect temporary air hoses routed through the door and close the door in the event of a main control room (MCR) air bottle bank discharge. The person will also perform the required fire watch responsibilities while the door is open.

Establishment of administrative control of the subject door ensures the capability of rapidly restoring the MCR/ESGR pressure envelope to required conditions, thus minimizing the potential for exposure of MCR personnel to radioactivity releases in the event of an accident. Therefore, an unreviewed safety question is not created..

Temporary Shielding Requests (Safety Evaluation No.91-194) 08-22-91 This Temporary Shielding Request (TSR) installs temporary lead shielding on Safety Injection (SI) System piping in the Unit 2 "B" Charging Pump cubicle to reduce the radiation dose received by personnel while working in the Charging Pump cubicle.

The subject SI lines will remain operable while the shielding is installed. A seismic analysis was performed and the installation was determined to be acceptable. Therefore, an unreviewed safety question does not exist.

Temporary Modification (Safety Evaluation No.91-188) 08-19-91 This Temporary Modification (TM) installs a gage, tubing, and fittings in the instrument air supply to the Unit 1 vent gas header containment isolation valve, 1-VG-TV-109B, to allow troubleshooting and analysis of the valve's air regulator.

The subject valve will be considered inoperable while this modification is in place, but will continue to function as designed (fail closed upon loss of air, power, or upon receipt of the Phase I containment isolation signal). The redundant valve, 1-VG-TV-109A, will be kept closed under administrative control to ensure Technical Specifications containment integrity requirements are maintained.

Therefore, an unreviewed safety question is not created.

esurry Monthly Operating Report No. 91-08 Page 17of 25 FACILITY CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTH/YEAR: August 1991 TM S2-91-36 QLCR R91-012 TM S2-91-37

[continued]

Temporary Modification (Safety Evaluation No.91-189) 08-21-91 This Temporary Modification (TM) installs a recorder to monitor the contact resistance of the Nuclear Instrumentation Source Range channel II high voltage switching circuit.

This TM will be used for identification of the cause of the high voltage power supply energizing when at power. The recorder will only monitor the circuit and will not affect the operation of the Source Range Nuclear Instrumentation.

Therefore, an unreviewed safety question is not created.

Q-Llst Change Request (Safety Evaluation No.91-190) 08-22-91 This Q-List Change Request changes the classification of some Emergency Diesel Generator (EDG) air starting system components from "safety-related" to "non-safety related."

The subject components do not perform a safety function and the EDG starting circuit is designed with adequate redundancy and capacity (designed to provide three starts with a loss of electrical power to the air compressor).

Therefore, an unreviewed safety question is not created.

Temporary Modification (Safety Evaluation No.91-195)

This TM will not affect the "B" train of the RPS and thus will not affect the ability of the RPS to perform its intended safety function. Therefore, an unreviewed safety question is not created.

e

-Surry Monthly Operating Report No. 91-08 Page 18 of 25 FACILITY CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTH/YEAR: August 1991

[continued]

TM S1-91-17 Temporary Modification (Safety Evaluation No. 91-196A) 08-25-91 SE 91-198 This Temporary Modification (TM) installs a capping device on the damaged Unit 1 Low Pressure (LP) Turbine rupture disc. The device will help to maintain condenser vacuum by sealing holes in the rupture disc until it can be replaced when the unit is off line.

The capping device will be held in place only by the condenser vacuum and will not affect the ability of the rupture disc to perform its intended function (condenser overpressure protection).

In addition, a lanyard will be attached to the cap to prevent a missile hazard in the event the rupture disc is actuated.

Therefore, an unreviewed safety question is not created.

Safety Evaluation 08-27-91 This Safety Evaluation assesses the operation of Unit 2 at 60% power with Rod Cluster Control Assembly D-4 fully inserted for a period of fourteen days during which troubleshooting and corrective actions will be performed to address the related dropped rod event.

The evaluation concluded that safety limits will continue to be met while operating under these conditions for a period of fourteen days. In addition, it was determined by an evaluation that the applicable UFSAR accident analyses remain bounding. Therefore, an unreviewed safety question is not created.

SE 91-1988

&rry Monthly Operating Report No. 91-08 Page 19 of 25 FACILITY CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTH/VEAR: August 1991

[continued]

Safety Evaluation 08-28-91 This Safety Evaluation assesses blocking the Unit 2 Turbine Load Reference Runback signal from Nuclear Instrumentation system channel, N-43, during the withdrawal of Rod Cluster Control Assembly (RCCA) D-4 from the fully inserted to the fully withdrawn position and engaging the stationary gripper using the "DC Hold" power supply. This action will prevent a potential turbine runback and reactor trip in the event RCCA D-4 is dropped during this.

evolution.

The evaluation concluded that this activity is acceptable on the condition that the power level be maintained at or below 60% reactor thermal power (while the rod is being withdrawn), the rod control system is placed in the manual mode, and that the turbine runback feature be reenabled within two hours of withdrawing RCCA D-4.

In addition, it was concluded that the current core reload safety evaluation remains bounding and the assumptions of the UFSAR accident analyses remain unchanged. Therefore, an unreviewed safety question is not created.

1-0SP-AMS-001 2-0SP-AMS-001 1-0PT-ZZ-001 4tsurry Monthly Operating Report No. 91-08 Page 20 of 25 PROCEDURES OR METHOD OF OPERATION CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTH/YEAR: August 1991 Operations Surveillance Procedure (Safety Evaluation No.91-192) 08-22-91 Unit 1 Operations Surveillance Procedure, 1-0SP-AMS-001, "Anticipated Transients Without Scram (ATWS) System Functional Surveillance" was developed to provide instructions for conducting a functional test of ATWS Mitigation System Actuation Circuitry (AMSAC).

This procedure will be performed with the unit at cold shutdown and will not affect station control systems.

Therefore, an unreviewed safety question is not created.

Operations Surveillance Procedure (Safety Evaluation No.91-191) 08-22-91 Unit 2 Operations Surveillance Procedure, 2-0SP-AMS-001, "Anticipated Transients Without Scram (ATWS) System Functional Surveillance" was developed to provide instructions for conducting a functional test of ATWS Mitigation System Actuation Circuitry (AMSAC).

This procedure will be performed with the unit at cold shutdown and will not affect station control systems.

Therefore, an unreviewed safety question is not created.

Operations Periodic Test Procedure (Safety Evaluation No.91-199) 08-29-91 Unit 1 Operations* Periodic Test Procedure, 1-0PT-ZZ-001, "Engineered Safety Features Actuation With Delayed Undervoltage 1 H Bus" was revised to include verification that temporary modifications, used for the testing of the Safety Injection system undervoltage logic, do not adversely impact plant operation.

This procedure will be performed with the unit at cold shutdown and at least two cooling loops operable (i.e. the Residual Heat Removal system pump not being tested and a Reactor Coolant pump). Only one train of a safety system will be tested at a time. Therefore, an unreviewed safety question is not created.

i

'i 1-0PT-ZZ-002 2-0PT-ZZ-001 2-0PT-ZZ-002 esurry Monthly Operating Report No. 91-08 Page 21 of 25 PROCEDURES OR METHOD OF OPERATION CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTH/YEAR: August 1991

[continued]

Operations Periodic Test Procedure (Safety Evaluation No.91-200) 08-29-91 Unit 1 Operations Periodic Test Procedure, 1-0PT-ZZ-002, "Engineered Safety Features Actuation With Delayed Undervoltage 1J Bus" Was revised to include verification that temporary modifications, used for the testing of the Safety Injection system undervoltage logic, do not adversely impact plant operation.

This procedure will be performed with the unit at cold shutdown and at least two cooling loops operable (i.e. the Residual Heat Removal system pump not being tested and a Reactor Coolant pump). Only one train of a safety system will be tested at a time. Therefore, an unreviewed safety question is not created.

Operations Periodic Test Procedure (Safety Evaluation No.91-201) 08-29-91 Unit 2 Operations Periodic Test Procedure, 2-0PT-ZZ-001, "Engineered Safety Features Actuation With Delayed Undervoltage 2H Bus" was revised to include verification that temporary modifications, used for the testing of the Safety Injection system undervoltage logic, do not adversely impact plant operation.

This procedure will be performed with the unit at cold shutdown and at least two cooling loops operable (i.e. the Residual Heat Removal system pump not being tested and a Reactor Coolant pump). Only one train of a safety system will be tested at a time. Therefore, an unreviewed safety question is not created.

Operations Periodic Test Procedure (Safety Evaluation No.91-202) 08-29-91 Unit 2 Operations Periodic Test Procedure, 2-0PT-ZZ-002, "Engineered Safety Features Actuation With Delayed Undervoltage 2J Bus" was revised to include verification that temporary modifications, used for the testing of the Safety Injection system undervoltage logic, do not adversely impact plant operation.

This procedure will be performed with the unit at cold shutdown and at least two cooling loops operable (i.e. the Residual Heat Removal system pump not being tested and a Reactor Coolant pump). Only one train of a safety system will be tested at a time. Therefore, an unreviewed safety question is not created.

.~

e 9urry Monthly Operating Report No. 91-08 Page 22 of 25 TESTS AND EXPERIMENTS THAT DID NOT REQUIRE NRC APPROVAL MONTH/YEAR: August 1991 None During This Reporting Period.

.).

')

e Primary Coolant Analysis Gross Radioact., u.Ci/ml Suspended Solids, oom Gross Tritium, u.Ci/ml 1131, µCi/ml 1131/I133 Hydrogen, cc/kci Lithium, corn Boron - 1 O, oom*

Oxvaen, (DOl, oom Chloride, oom oH at 25 deciree Celsius Boron - 10 = Total Boron x 0.196 Comments:

CHEMISTRY REPORT MONTH/YEAR: August 1991 Unit No. 1 Max.

Min.

Avg.

6.68E-1 3.96E-1 5.08E-1 0.0 0.0 0.0 1.86E-1 1.79E-1 1.84E-1 3.24E-3 1.61 E-3 2.11 E-3 0.13 0.07 0.09 38.7 29.1 32.8 2.33 1.94 2.17 97.6 72.3 81.3

<0.005

<0.005

<0.005 0.003 0.002 0.002 7.13 6.89 7.04 esurry Monthly Operating Report No. 91-08 Page 23 of 25 Unit No. 2 Max.

Min.

Ava.

2.17E-1 3.99E-3 1.05E-1 0.0 0.0 0.0 2.29E-1 1.89E-1 2.09E-1 4.33E-3 5.35E-5 5.22E-4 0.21 0.07 0.12 40.0 29.6 32.7 3.29 1.77 2.26 372.2 257.7 293.2

<0.005

<0.005

<0.005 0.003

~0.001 0.002 6.38 5.81 6.26 Unit 1:

Lithium was outside the limits of the Boron/Lithium Program, low on 8-24 for 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> and 20 minutes.

Unit 2:

Lithium was outside the limits of the Boron/Lithium Program, low on 8-15 for 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and 5 minutes, 8-16 for 5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br />, 8-24 for 20 hours2.314815e-4 days <br />0.00556 hours <br />3.306878e-5 weeks <br />7.61e-6 months <br /> and 20 minutes and 8-25 for 50 minutes. Lithium was outside the limits of the Boron/Lithium Program for a total of 32 hours3.703704e-4 days <br />0.00889 hours <br />5.291005e-5 weeks <br />1.2176e-5 months <br /> and 15 minutes.

'1 Units One and Two Cask Stored FUEL HANDLING UNITS 1 & 2 MONTH/VEAR: August 1991 Number for Assemblies per Shipment Assembly Number ANSI Number None during this reporting period.

tlrry Monthly Operating Report No. 91-08 Page 24of 25 Nominal Initial Enrichment New or Spent Fuel Shipping Cask Activity

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9urry Monthly Operating Report No. 91-08 Page 25 of 25 DESCRIPTION OF PERIODIC TEST(S) WHICH WERE NOT COMPLETED WITHIN THE TIME LIMITS SPECIFIED IN TECHNICAL SPECIFICATIONS MONTH/VEAR: August 1991 None During This Reporting Period.

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