ML18152A439

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Monthly Operating Repts for Oct 1991 for Surry Power Station,Units 1 & 2.W/911115 Ltr
ML18152A439
Person / Time
Site: Surry  Dominion icon.png
Issue date: 10/31/1991
From: Negron M, Stewart W
VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
91-683, NUDOCS 9111220297
Download: ML18152A439 (23)
v • d • e


Text

e e VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND, VIRGINIA 23261 November 15, 1991 U. S. Nuclear Regulatory Commission Serial No.91-683 Attention: Document Control Desk NO/RPC:vlh Washington, D. C. 20555 Docket Nos. 50-280 50-281 License Nos. DPR-32 DPR-37 Gentlemen:

VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION UNITS 1 AND 2 MONTHLY OPERATING REPORT Enclosed is the Monthly Operating Report for Surry Power Station Units 1 and 2 for the month of October 1991.

W. L. St wart 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 r----.~T:1.12:20~~*?7 9f1n*-=*t----~

VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION MONTHLY OPERATING REPORT REPORT NO. 91-10 Approved:

e Surry Monthly Operating Report No. 91-10 Page 2of 22 TABLE OF CONTENTS Section 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 .................................................................................... 6 Average Daily Unit Power Level - Unit No. 1.............................................................................................. 7 Average Daily Unit Power Level - Unit No. 2 ............................................................................................... 8 Summary of Operating Experience - Unit No. 1 ......................................................................................... 9 Summary of Operating Experience - Unit No. 2 ......................................................................................... 9 Facility Changes That Did Not Require NRC Approval ............................................................................... 11 Procedure or Method of Operation Changes That Did Not Require NRC Approval ........................................... 18 Tests and Experiments That Did Not Require NRC Approval ......................................................... , ............ 19 Chemistry Report ............................................................................................................................. 20 Fuel Handling - Unit No. 1 ................................................................................................................... 21 Fuel Handling - Unit No. 2 ................................................................................................................... 21 Description of Periodic Test(s) Which Were Not Completed Within the Time Limits Specified in Technical Specifications ................................................................................................... 22 I --~-

e Surry Monthly Operating Report No. 91-10

  • . Page 3of 22 OPERATING DATA REPORT Docket No.: 50-280 Date: 11-06-91 Completed By: M.A. Negron Telephone: 804-365-2795
1. Unit Name: .................................................. . Surry Unit 1
2. Reporting Period: ........................................ .. October 1991
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. Reasons For Restrictions, If Any:

This Month YTD Cumulative

11. Hours In Reporting Period ......................... . 745.0 7296.0 165312.0
12. Number of Hours Reactor Was Critical ........ .. 745.0 7296.0 106770.2
13. Reactor Reserve Shutdown Hours ............. .. 0.0 0.0 3774.5
14. Hours Generator On-Line .......................... . 745.0 7296.0 104776.2
15. Unit Reserve Shutdown Hours ................... .. 0.0 0.0 3736.2
16. Gross Thermal Energy Generated (MWH) .... .. 1580299.0 17330660.4 243550570.0
17. Gross Electrical Energy Generated (MWH) ... . 520550.0 5738770.0 79315593.0
18. Net Electrical Energy Generated (MWH) ...... .. 492644.0 5449241.0 75232370.0
19. Unit Service Factor .................................. . 100.0% 100.0% 63.4%
20. Unit Availability Factor............................. .. 100.0% 100.0% 65.6%
21. Unit Capacity Factor (Using MDC Net).......... . 84.7% 95.6% 58.7%
22. Unit Capacity Factor (Using DER Net) .......... . 83.9% 94.8% 57.8%
23. Unit Forced Outage Rate ........................... . 0.0% 0.0% 19.5%
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):

FORECAST ACHIEVED INITIAL CRITICALITY INITIAL ELECTRICITY COMMERCIAL OPERATION

e Surry Monthly Operating Report No. 91-10 Page 4of 22 OPERATING DATA REPORT Docket No.: 50-281 Date: 11-06-91 Completed By: M.A. Negron Telephone: 804-365-2795

1. Unit Name: .................................................. . Surry Unit 2
2. Reporting Period: .................................*........ October 1991
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. Reasons For Restrictions, If Any:

This Month YTD Cumulative

11. Hours In Reporting Period ......................... . 745.0 7296.0 162192.0
12. Number of Hours Reactor Was Critical. ........ . 632.5 4741.5 103913.8
13. Reactor Reserve Shutdown Hours .............. . 0.0 0.0 328.1
14. Hours Generator On-Line .......................... . 610.9 4617.2 102187.8
15. Unit Reserve Shutdown Hours .................... . 0.0 0.0 0.0
16. Gross Thermal Energy Generated (MWH) ..... . 1442355.7 9739167.4 237874635.7
17. Gross Electrical Energy Generated (MWH) ... . 480370.0 3203380.0 77433494.0
18. Net Electrical Energy Generated (MWH) ....... ; 457256.0 3033368.0 73412093.0
19. Unit Service Factor .................................. . 82.0% 63.3% 63.0%
20. Unit Availability Factor.............................. . 82.0% 63.3% 63.0%
21. Unit Capacity Factor (Using MDC Net) .......... . 78.6% 53.2% 58.1%
22. Unit Capacity Factor (Using DER Net) .......... . 77.9% 52.8% 57.4%
23. Unit Forced Outage Rate ........................... . 18.0% 18.0% 15.4%
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 Start-up:
26. Unit In Test Status (Prior to Commercial Operation):

FORECAST ACHIEVED INITIAL CRITICALITY INITIAL ELECTRICITY COMMERCIAL OPERATION

e Surry Monthly Operating Report No. 91-10 Page 5of 22 UNIT SHUTDOWN AND POWER REDUCTION (EQUAL To OR GREATER THAN 20%)

REPORT MONTH: October 1991 Docket No.: 50-280 Unit Name: Surry Unit 1 Date: 11-06-91 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 Reason Shutting No. Code Code Prevent Recurrence Down Rx 10-02-91 s 0 B 4 NIA SD Hx Ramped unit down from 100% to 80% to remove a feedwater heater train from service. This was done to perform repairs on "A" Low Pressure Heater Drain Pump (1-SD-P-2A) recirculation line.

10-03-91 s 0 B 4 NIA SJ p Unit power was reduced from 79% to 60% to remove "B" Main Feed Pump from service so repairs could be made to the suction pressure sensing line.

(1) (2) (3)

F: Forced REASON: METHOD:

S: Scheduled A - Equipment Failure (Explain) 1 - Manual B Maintenance or Test 2 - Manual Scram.

C Refueling 3 - Automatic Scram.

D Regulatory Restriction 4 - Other (Explain)

E Operator Training & Licensing Examination F Administrative G Operational Error (Explain)

(4) (5)

Exhibit G - Instructions for Preparation of Data Entry Sheets Exhibit 1 - Same Source.

for Licensee Event Report (LER) File (NUREG 0161)

e e Surry Monthly Operating Report No. 91-10 Page 6of 22 UNIT SHUTDOWN AND POWER REDUCTION (EQUAL To OR GREATER THAN 20%)

REPORT MONTH: October 1991 Docket No.: 50-281 Unit Name: Surry Unit 2 Date: 11-06-91 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 Reason Shutting No. Code Code Prevent Recurrence Down Rx 10-20-91 s 0 B 4 NIA SJ p Unit power was reduced from 100% to 60% to remove "8" Main Feed Pump from service for repairs and perform 2-0SP-TM-001, (Turbine Valve Freedom Test).

10-25-91 F 134.1 B NIA SN EXJ Unit was shutdown in accordance with applicable operating procedures to replace a leaking expansion joint on "B" High Pressure Heater Drain Pump (2-SD-P-1B).

(1) (2) (3)

F: Forced REASON: METHOD:

S: Scheduled A - Equipment Failure (Explain) 1 - Manual B - Maintenance or Test 2 - Manual Scram.

C - Refueling 3 - Automatic Scram.

D - Regulatory Restriction 4 - Other (Explain)

E - Operator Training & Licensing Examination F - Administrative G * - Operational Error (Explain)

(4) (5)

Exhibit G - Instructions for Preparation of Data Entry Sheets Exhibit 1*- Same Source.

for Licensee Event Report (LER) File (NUREG 0161)

e Surry Monthly Operating Report No. 91-10 Page 7of 22 AVERAGE DAILY UNIT POWER LEVEL Docket No.: 50-280 Unit Name: Surry Unit 1 Date: 11-06-91 Completed by: M.A. Negron Telephone: 804-365-2795 Month: October 1991 Average Daily Power Level Average Daily Power Level Day (MWe-Net) Day (MWe- Net) 1 764.4 17 779.4 2 754.0 18 776.3 3 575.5 19 777.6 4 452.8 20 780.5 5 452.0 21 780.1 6 453.0 22 779.8 7 455.6 23 776.5 8 456.5 24 779.3 9 453.3 25 778.0 10 452.8 26 773.3 11 451.3 27 806.7 12 437.6 28 774.4 13 441.8 29 772.4 14 693.4 30 770.3 15 774.8 31 776.5 16 777.0 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.

e Surry Monthly Operating Report No. 91-10 Page 8of 22 AVERAGE DAILY UNIT POWER LEVEL Docket No.: 50-281 Unit Name: Surry Unit 2 Date: 11-06-91 Completed by: M.A. Negron Telephone: 804-365-2795 Month: October 1991 Average Daily Power Level Average Daily Power Level Day (MWe-Net) Day (MWe- Net) 762.7 17 781.0 2 751.4 18 781.1 3 772.2 19 780.0 4 761.8 20 778.4 5 740.8 21 488.3 6 758.8 22 710.7 7 757.3 23 783.4 8 776.8 24 777.2 9 778.6 25 759.0 10 774.0 26 28.1 11 778.2 27 0.0 12 779.6 28 0.0 13 775.9 29 0.0 14 768.5 30 0.0 15 772.0 31 101.6 16 775.0 INSTRUCTIONS On this format, list the average daily unit power level in MWe - Net for each day in th~ reporting month. Compute to the nearest whole megawatt.

e Surry Monthly Operating Report No. 91-10 Page 9 of 22

SUMMARY

OF OPERATING EXPERIENCE MONTH/YEAR: October 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 10-01-91 0000 This report period started with the Unit operating at 100% power, 805 MWe.

10-02-91 2118 Started ramp down to remove a feedwater heater train from service; 100%

power, 805 MWe.

2330 Stopped ramp 80% power, 630 MWe.

10-03-91 2203 Started ramp down to repair B main feedwater pump suction pressure sensing line; 79% power, 615 MWe.

2345 Stopped ramp; 60% power, 475 MWe.

10-14-91 0317 Started ramp up after repairs to B main feedwater pump motor were completed; 61% power, 460 MWe.

0946 Stopped ramp; 100% power, 825 MWe.

10-31-91 2400 This report period ended with the Unit operating at 100% power, 815 MWe.

UNIT TWO 10-01-91 0000 This report period started with the Unit operating at 100% power, 81 o MWe.

10-02-91 0139 Started ramp down to maintain condenser vacuum while cleaning waterboxes; 100% power, 775 MWe.

0237 Stopped ramp; 88.9% power, 700 MWe.

0457 Started ramp up; 88.2% power, 700 MWe.

0551 Stopped ramp; 99.8% power, 825 MWe.

10-05-91 0100 Started ramp down to maintain condenser vacuum while cleaning waterboxes; 100% power 790 MWe.

0225 Stopped ramp; 83% power, 640 MWe.

031 5 Started ramp up; 83% power, 640 MWe.

0634 Stopped ramp; 100% power, 795 MWe.

< ') *.

SUMMARY

OF OPERATING EXPERIENCE

  • Surry Monthly Operating Report No.91-10 Page 10 of 22 MONTH/YEAR: October 1991

[continued]

10-06-91 2145 Started ramp down to maintain condenser vacuum while cleaning waterboxes; 100% power, 815 MWe.

2238 Stopped ramp; 88% power, 690 MWe.

10-07-91 0340 Started ramp up; 86% power, 700 MWe.

0445 Stopped ramp; 99.6% power, 810 MWe.

10-20-91 2247 Started ramp down to perform 2-0SP-TM-001 (turbine valve freedom test) and to perform maintenance on the "A" Main Feed Pump; 100% power, 825 MWe.

1*0-21-91 0540 .Stopped ramp; 60% power, 500 MWe.

10-22-91 0321 Started ramp up; 57% power, 475 MWe.

0609 Stopped ramp; 99% power, 820 MWe.

10-25-91 2042 Commence Unit shutdown to Hot Shutdown in accordance with 2-0P-2.1.2 to replace a leaking expansion joint on the suction line of 2-SD-P-1 B; 100%

power, 825 MWe.

10-26-91 0316 Unit offline.

0329 Manually tripped the Reactor in accordance with applicable shutdown procedures.

10-30-91 1859 Reactor critical.

10-31-91 1624 Unit on line and ramping up.

2139 Stopped ramp for a secondary chemistry hold; 53% power, 435 MWe.

2400 This report period ended with the Unit operating at 53% power, 435 MWe, due to a secondary chemistry hold resulting from a condenser tube leak.

e

.l Surry Monthly Operating Report No. 91-10 Page 11 of 22 FACILITY CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTH/YEAR: October 1991 FS-89-78 UFSAR Change 02-21-91 (Safety Evaluation No.91-032)

The Updated Final Safety Analysis Report (UFSAR) sections 4.2.6, 15A.3.4.1, Tables 4.1-6, 4.1-9, 15.2-1, 15A-1, References 15A and 15.2 were revised to include additional design criteria (in accordance with NRG Bulletin 88-11) and analysis to confirm pressurizer surge line integrity.

No physical changes were made to the station. Therefore, an unreviewed safety question does not exist.

FS 89-30 UFSAR Change 03-19-91 (Safety Evaluation No.91-059)

The Updated Final Safety Analysis Report (UFSAR) section 9.10.2.29 was revised to accurately reflect the operation and sequencing of the Emergency Switchgear Room Halon System.

This change was administrative in nature and made for clarification purposes only. No physical changes were made to the station. Therefore, an unreviewed safety question is not created.

FS 90-85 UFSAR Change 03-28-91 (Safety Evaluation No.91-073)

The Updated Final Safety Analysis Report (UFSAR) section 15.5.1.12 was revised to correctly state the Modal Combination Methodology used in the seismic analysis of the Reactor Coolant Loop.

The change was administrative in nature and made for clarification purposes only. No physical changes were made to the station. Therefore, an unreviewed safety question does not exist.

J FACILITY CHANGES THAT DID NOT REQUIRE NRC APPROVAL

  • Surry Monthly Operating Report No. 91-10 Page 12 of 22 MONTH/YEAR: October 1991

[continued]

FS-90-33 UFSAR Change 05-07-91 (Safety Evaluation No.91-118)

The Updated Final Safety Analysis Report (UFSAR) sections 3.6.3.1 and 3.6.3.2 were revised to reflect the current fuel product assurance methods used by the fuel vendor.

The changes were administrative in nature and made for clarification purposes only. No physical changes were made to the station. Therefore, an unreviewed safety question does not exist.

FS 90-35 UFSAR Change 05-07-91 (Safety Evaluation No.91-117)

The Updated Final Safety Analysis Report (UFSAR) sections 7.2.1.1 and 7.7 were revised to reference the proper section of the Code of Federal Regulations related to Control Room dose limits.

This change was editorial in nature. No physical changes were made to the station. Therefore, an unresolved safety question does not exist.

FS90-042 UFSAR Change 05-07-91 (Safety Evaluation No.91-119)

The Updated Final Safety Analysis Report (UFSAR) section 1.1 was revised to be consistent with the current safety analysis basis.

This change was administrative in nature and made for clarification purposes only. No physical changes were made to the station. Therefore, an unreviewed safety question does not exist.

FS 91-18 UFSAR Change 06-14-91 (Safety Evaluation No.91-157)

The Updated Final Safety Analysis Report (UFSAR) sections 9.12.5.2 and 9.12.5.4 was revised to delete references to raising and lowering the refueling cavity water level simultaneously with lifting and lowering the reactor head.

These changes are consistent with applicable operating procedures and do not affect NUREG-0612 related commitments. No physical changes were made to the plant. Therefore, an unreviewed safety question does not exist.

e Surry Monthly Operating Report No. 91-10 Page 13 of 22 FACILITY CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTH/YEAR: October 1991

[continued]

FS 90-43 UFSAR Change 07-23-91 (Safety Evaluation No. 91-177A)

The Updated Final Safety Analysis Report (UFSAR) section 14.2.4 was revised to reflect the current analysis methodology for the control rod assembly drop/misalignment accident analysis.

This change simplifies the analysis by conservatively eliminating credit for the effect of the turbine runback on the post rod drop power recovery. No physical changes were made to the station. Therefore an unreviewed safety question does not exist.

FS90-012 UFSAR Change 09-03-91 (Safety Evaluation No.91-204)

The Updated Final Safety Analysis Report (UFSAR) section 8.5 was revised to correct information on heat tracing power supplies and to eliminate the detailed setpoints of operation.

The changes were administrative in nature and made for clarification purposes only. No physical changes were made to the station. Therefore, an unreviewed safety question does not exist.

UFSAR Change 1 0-03-91 (Safety Evaluation No.91-223)

The Updated Final Safety Analysis Report (UFSAR) section 9.12.4.2 was revised to clarify a discussion of the reactor head lifting device and its attachment to the reactor head.

The changes were editorial in nature and made for clarification purposes only.

No physical or procedural changes were made. Therefore, a unreviewed safety question does not exist.

EWR 91-017 Engineering Work Request 10-21-91 (Safety Evaluation No.91-008)

This Engineering Work Request (EWR) replaced the Condensate Polishing acid neutralization flow control valve, 1-CP-FCV-1 00-2, with a temporary pipe spool piece until the leaking valve can be repaired or replaced.

This modification does not affect the ability of the nonsafety-related acid neutralization system to perform its intended function. Therefore, an unreviewed safety question is not created.

f I FACILITY CHANGES THAT DID NOT REQUIRE NRC APPROVAL e Surry Monthly Operating Report No. 91-10 Page 14 of 22 MONTH/YEAR: October 1991

[continued]

AC S2-91-0930 Administrative Control 1 0-01-91 (Safety Evaluation No.91-222)

Administrative Control (AC) was established to permit the temporary removal and maintenance of the Mechanical Equipment Room Number 4 flood dike.

The administrative controls require that the control room be notified prior to removal of the dike, that a flood watch be stationed while the dike is not in place, and that personnel be available to promptly reinstall the dike in the event of turbine building flooding. These controls provide assurance that the dike can be reinstalled to mitigate flooding effects. Therefore, an unreviewed safety question is not created.

TM S2-91-41 Temporary Modification 1 0-08-91 (Safety Evaluation No.91-224)

This Temporary Modification (TM) lifted an electrical lead to remove the undervoltage lockout for the Unit 2 Charging Pump "A" to prevent the potential loss of high head safety injection (assuming the active failure to be the charging pump powered from the emergency bus "J" or emergency diesel generator number 3) in the event of a simultaneous design basis accident and emergency bus "H" undervoltage condition.

Each unit has three charging pumps with two required to be operable. One pump is normally operating and the other pump is in standby designed to start automatically upon receipt of an engineered safeguards (ESF) signal. One of the three pumps can be supplied from either emergency electrical bus ("H" or "J" bus). The charging pump electrical supply breakers are equipped with interlock logic to ensure that only one charging pump can be supplied from an emergency bus at any given time. One such interlock for the "A" pump can stop the pump or prevent the pump from auto-starting in one operational configuration. This TM ensures that Unit 2 Charging Pump "A" will continue to operate or automatically start following receipt of an ESF signal coincident with a loss of offsite power. This TM does not affect Emergency Diesel Generator loading and assures the proper equipment response during accident conditions. Therefore, an u_nreviewed safety question is not created.

e Surry Monthly Operating Report No. 91-10 Page 15 of 22 FACILITY CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTH/YEAR: October 1991

[continued)

TM S1-91-20 Temporary Modification 10-10-91 (Safety Evaluation No.91-225)

This Temporary Modification (TM) lifted an electrical lead to remove the undervoltage lockout for the Unit 1 Charging Pump "A" to prevent the potential loss of high head safety injection (assuming the active failure to be the charging pump powered from the emergency bus "J" or emergency diesel generator number 3) in the event of a simultaneous design basis accident and emergency bus "H" undervoltage condition.

Each unit has three charging pumps with two required to be operable. One pump is normally operating and the other pump is in standby designed to start automatically upon receipt of an engineered safeguards (ESF) signal. One of the three pumps can be supplied from either emergency electrical bus ("H" or "J" bus). The charging pump electrical supply breakers are equipped with interlock logic to ensure that only one charging pump can be supplied from an emergency bus at any given time. One such interlock for the "A" pump can stop the pump or prevent the pump from auto-starting in one operational configuration. This TM ensures that Unit 1 Charging Pump "A" will continue to operate or automatically start following receipt of an ESF signal coincident with a loss of offsite power. This TM does not affect Emergency Diesel Generator loading and assures the proper equipment response during accident conditions. Therefore, an unreviewed safety question is not created.

TM S1-91-22 Temporary Modification 10-16-91 (Safety Evaluation No.91-227)

This Temporary Modification (TM) provides a temporary water supply to the Vacuum Priming (VP) system seal recirculation subsystem until the normal well water supply pump breakers can be replaced.

This TM will enable the nonsafety-related VP system to operate normally with the alternate water supply. Therefore, an unreviewed safety question is not created.

SE 91-228 Safety Evaluation 10-17-91 This Safety Evaluation assesses continued operation of the Component Cooling system heat exchanger radiation monitors in their present design configuration (in which four radiation monitors alarm the same annunciator) until channel independent alarms (reflash capability) can be implemented.

The evaluation concluded that since the compensatory actions specified in the applicable Annunciator Response Procedures are more conservative than the Technical Specifications requirements for inoperable monitors, continued operation of the system is acceptable. Therefore, an unreviewed safety question is not created.

e

.al\ /

Surry Monthly Operating Report No. 91-10 Page 16of 22 FACILITY CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTH/YEAR: October 1991

[continued]

TM S1-91-23 Temporary Modification 10-20-91 (Safety Evaluation No.91-230)

This Temporary Modification (TM) lifted an electrical lead to remove the undervoltage trip from Unit 1 Charging Pump "A" to prevent the potential loss of high head safety injection (assuming the active failure to be the charging pump powered from the emergency bus "J" or emergency diesel generator number 3) in the event of a simultaneous design basis accident and emergency bus "H" undervoltage condition while maintenance is performed on Charging Pump "C" suction motor operated valves.

Each unit has three charging pumps with two required to be operable. One pump is normally operating and the other pump is in standby designed to start automatically upon receipt of an engineered safeguards (ESF) signal. One of the three pumps can be supplied from either emergency electrical bus ("H" or "J" bus). The charging pump electrical supply breakers are equipped with interlock logic to ensure that only one charging pump can be supplied from an emergency bus at any given time. One such interlock for the "A" pump can stop the pump or prevent the pump from auto-starting in one operational configuration. This TM ensures that Unit 1 Charging Pump "A" will continue to operate or automatically start following receipt of an ESF signal coincident with a loss of offsite power. This TM does not affect Emergency Diesel Generator loading and assures the proper equipment response during accident conditions. Therefore, an unreviewed safety question is not created.

QLCR S91-188 Q-Llst Change Request 1 0-24-91 (Safety Evaluation No.91-231)

This Q-List Change Request changes the classification of some Containment Spray system recirculation and spray nozzle test lines to the refueling water storage tank from "safety-related" to "nonsafety quality related (NSQ)."

This change is administrative in nature with no associated physical modifications being made. The affected components are used' only for testing the containment spray pumps and do not perform a safety-related function.

Therefore, an unreviewed safety question is not created.

Temporary Modification 10-28-91 (Safety Evaluation No.91-232)

This Temporary Modification (TM) installed electrical jumpers to permit the replacement of Unit 2 Reactor Protection System relay, 02-RP-REL-P7YB.

This TM was used to maintain downstream RPS "B" train relays energized during this activity. Double verification of the jumper installation/removal and post maintenance testing were performed. The unit was at hot shutdown and the RPS "A" train logic was not affected. Therefore, an unreviewed safety question is not created.

e e Surry Monthly Operating Report No. 91-10 Page 17of 22 FACILITY CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTH/YEAR: October 1991

[continued)

TM S2-91-44 Temporary Modification 10-29-91 (Safety Evaluation No.91-233)

This Temporary Modification (TM) installed an electrical jumper to permit the relocation of wires from a damaged contact to a spare contact on Unit 2 Reactor Protection System (RPS) relay, 02-RP-REL-PSXB.

This TM was used to maintain downstream RPS "B" train relays energized during this activity. Double verification of the jumper installation/removal and post maintenance testing were performed. The unit was at hot shutdown and the RPS "A" train logic was not affected. Therefore, an unreviewed safety question is not created.

1-0SP-TM-001 Operations Surveillance Procedure 1 0-30-91 (Safety Evaluation No.91-234)

Unit 1 Operations Surveillance Procedure, 1-0SP-TM-001, "Turbine Inlet Valve Freedom Test" was temporarily changed to allow the subject testing to be performed on a quarterly basis due to the difficulties in performing the test resulting from the failure of the turbine control. system speed channels.

An independent evalu,;1.tion, performed by Westinghouse (also used in the Owners Group Study, WCAP-11525, "Probabilistic Evaluation of Reduction in Turbine Valve Test Frequency"), determined that the probability of a turbine missile ejection event will not increase above the probability assumed in the UFSAR or the acceptance criteria developed by the NRC. This analysis demonstrates that it is acceptable to defer the performance of the subject test.

Therefore, an unreviewed safety question is not created.

TM S2-91-45 Temporary Modification 10-31-91 (Safety Evaluation No.91-236)

This Temporary Modification (TM) installed a mechanical blocking device on Main Steam system trip valve bypass valve, 2-MS-155, to maintain the valve in the closed position, ensuring that the valve will satisfy its requirements for containment integrity.

The blocking device will reduce the loading on the valve bushing and prevent the stem from backing out to its backseat. It will remain in place until the damaged valve stem threads can be repaired. This TM will maintain the valve in its normally closed (for power operation) position and will not affect its ability to perform its intended function. Therefore, an unreviewed safety question is not created.

e e Surry Monthly Operating Report No. 91-10 Page 18 of 22 PROCEDURES OR METHOD OF OPERATION CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTH/YEAR: October 1991 ECM-1504 Electrlcal Corrective Maintenance Procedure 10-31-91 (Safety Evaluation No.91-235)

Electrical Corrective Maintenance Procedure, ECM-1504, "Motor Operated Valve Seal-In Removal And Installation" was performed to temporarily remove the seal-in contacts for Unit 2 Extraction Steam motor operated valve (MOY),

2-ES-MOV-200 and Main Steam MOVs, 2-MS-MOV-200A, 2-MS-MOV-2008, 2-MS-MOV-200C, and 2-MS-MOV-200D to allow the valves to be throttled during plant startup.

The subject valves are nonsafety-related and will be able to be operated using their normal control switch. Therefore, an unreviewed safety question does not exist.

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Surry Monthly Operating Report No. 91-10 Page 19 of 22 TESTS AND EXPERIMENTS THAT DID NOT REQUIRE NRC APPROVAL MONTH/YEAR: October 1991 2-ST-302 Callbratlon Unit 2 Steam and Feedwater Flow 10-03-91 Transmitters At Power (Safety Evaluation No.91-141)

The purpose of this test was to collect data from the newly installed and calibrated feedwater flow venturis (

Reference:

Design Change 90-34-2, "Feedwater Flow Element Replacement").

Following an evaluation of the special test data, the Unit 2 steam and feedwater flow transmitters were respanned and the steam flow circuitry and associated Engineered Safeguards Features (ESF) actuation functions were rescaled. These actions corrected the steam flow/feedwater flow mismatch to less than 0.2E6 pounds per hour on each loop.

. e e Surry Monthly Operating Report No. 91-10 Page 20of 22 CHEMISTRY REPORT MONTH/YEAR: October 1991 Unit No.1 Unit No. 2 Primarv Coolant Analvsis Max. Min. Ava. Max. Min. Ava.

Gross Radioact., u.Ci/ml 7.30E-1 3.07E-1 3.27E-1 2.23E-1 3.37E-3 1.50E-1 Suspended Solids, oom 0.0 0.0 0.0 0.0 0.0 0.0 Gross Tritium, LLCi/ml 1.90E-1 1.50E-1 1.75E-1 3.46E-1 2.13E-1 2.81E-1 1131, u.Ci/ml 3.07E-3 1.15E-3 2.00E-3 2.06E-3 9.22E-5 3.SOE-4 11311I133 0.13 0.07 0.09 0.14 0.06 0.10 Hvdroaen, cc/kg 39.6 27.0 31.4 42.5 26.6 32.4 Lithium, ppm 2.33 1.77 2.04 2.97 1.56 2.23 Boron - 10, oom* 74.5 43.1 57.9 445.5 237.9 293.6 Oxvoen, (DO), oom <0.005 <0.005 <0.005 <0.005 <0.005 <0.005 Chloride oom 0.003 0.001 0.002 0.006 0.002 0.004 pH at 25 degree Celsius 7.32 7.01 7.18 6.43 5.75 6.28 Boron - 1O = Total Boron x 0.196 Comments:

Unit 1: Lithium was below the recommended limits of the Boron/Lithium Program on 10-4-91 for 5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br />.

Unit 2: Lithium was above the recommended limits of the Boron/Lithium Program on 10-3-91 for 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br />, and on 10-21-91 for 7 hours8.101852e-5 days <br />0.00194 hours <br />1.157407e-5 weeks <br />2.6635e-6 months <br /> and 15 minutes. Lithium was outside the recommended limits of the Boron/Lithium Program for a total of 1O hours and 15 minutes.

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Surry Monthly Operating Report No.91-10 Page 21 of 22 FUEL HANDLING UNITS 1 & 2 MONTH/YEAR: October 1991 Units One and Two Number for Nominal New or Spent Assemblies Assembly ANSI Initial Fuel Shipping Cask Stored per Shipment Number Number Enrichment Cask Activity None during this reporting peripd.

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DESCRIPTION OF PERIODIC TEST(S) WHICH WERE NOT COMPLETED e Surry Monthly Operating Report No. 91-10 Page 22 of 22 WITHIN THE TIME LIMITS SPECIFIED IN TECHNICAL SPECIFICATIONS MONTH/YEAR: October 1991 None During This Reporting Period.

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