ML18153A889

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Monthly Operating Repts for Feb 1994 for Surry Power Station.W/940311 Ltr
ML18153A889
Person / Time
Site: Surry  Dominion icon.png
Issue date: 02/28/1994
From: Bowling M
VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
94-147, NUDOCS 9403150467
Download: ML18153A889 (26)
v • d • e


Text

e e VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND, VIRGINIA 23261 March 11, 1994 U. S. Nuclear Regulatory Commission Serial No. 94-14 7 Attention: Document Control Desk NO/RPC:vlh Washington, D. C. 20555 _ Docket Nos. . . 5.0-280 .

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 February 1994.

Very truly yours,

!ffLIJ4 M. L. Bowling, Manager Nuclear Licensing & Programs 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

VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION MONTHLY OPERATING REPORT REPORT NO. 94-02 Approved:

e Surry Monthly Operating Report No. 94-02 Page 2 of 25 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 ............................................................................... 1O Procedure or Method of Operation Changes That Did Not Require NRC Approval ........................................... 18 Tests and Experiments That Did Not Require NRC Approval ...................................................................... 21 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 I

I

e e Surry Monthly Operating Report No. 94-02 Page 3of 25 OPERATING DATA REPORT Docket No.: 50-280 Date: 03-02-94 Completed By: D. Mason Telephone: (804) 365-2459

1. Unit Name: ................................ ,.................. Surry Unit 1
2. Reporting Period: ......................................... ;
  • February, 1994
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):

1o. Reasons For Restrictions, If Any:

This Month YTD Cumulative

11. Hours In Reporting Period .......................... 672.0 1416.0 185736.0
12. Number of Hours Reactor Was Critical .......... 0 509.2 124316.4
13. Reactor Reserve Shutdown Hours ............... 0 0 3774.5
14. Hours Generator On-Line ........................... 0 506.1 122185.1
15. Unit Reserve Shutdown Hours..................... 0 0 3736.2
16. Gross Thermal Energy Generated (MWH) ...... 0 745423.1 283913168.2
17. Gross Electrical Energy Generated (MWH) .... 0 251015.0 92790563.0
18. Net Electrical Energy Generated (MWH) ........ 0 237463.0 88064564.0
19. Unit Service Factor ................................... 0% 35.7% 65.8%
20. Unit Availability Factor............................... 0% 35.7% 67.8%
21. Unit Capacity Factor (Using MDC Net) ........... 0% 21.5% 61.1%
22. Unit Capacity Factor (Using DER Net) ........... 0% 21.3% 60.2%
23. Unit Forced Outage Rate ............................ 0% 0% 17.4%
24. Shutdowns Scheduled Over Next 6 Months (Type, Date, and Duration of Each):

Refueling (1 O Year ISi), January 22, 1994, 63 Days

25. If Shut Down at End of Report Period, Estimated Date of Start-up: March 25 1994
26. Unit In Test Status (Prior to Commercial Operation):

FORECAST ACHIEVED INITIAL CRITICALITY INITIAL ELECTRICITY COMMERCIAL OPERATION

e Surry Monthly Operating Report No. 94-02 Page 4of 25 OPERATING DATA REPORT Docket No.: 50-281 Date: 03-02-94 Completed By: D. Mason Telephone: (804) 365-2459

1. Unit Name: .................................................. . Surry Unit 2
2. Reporting Period: .......................................... - February; 1994
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 YID Cumulative

11. Hours In Reporting Period .......................... 672.0 1416.0 182616.0
12. Number of Hours Reactor Was Critical .......... 672.0 1416.0 121492.3
13. Reactor Reserve Shutdown Hours ............... 0 0 328.1
14. Hours Generator On-Line ........................... 672.0 1416.0 119631.6
15. Unit Reserve Shutdown Hours ..................... 0 0 0
16. Gross Thermal Energy Generated (MWH) ...... 1622542.2 3429466.0 279105208.4
17. Gross Electrical Energy Generated (MWH) .... 544370.0 1150950.0 91096574.0
18. Net Electrical Energy Generated (MWH) ........ 524503.0 1110027.0 86442097.0
19. Unit Service Factor ................................... 100.0% 100.0% 65.5%
20. Unit Availability Factor............................... 100.0% 100.0% 65.5%
21. Unit Capacity Factor (Using MDC Net) ........... 99.9% 100.4% 60.7%
22. Unit Capacity Factor (Using DER Net) ........... 99.0% 99.5% 60.1%
23. Unit Forced Outage Rate ............................ 0% 0% 14.0%
24. Shutdowns Scheduled Over Next 6 Months (Type, Date, and Duration of Each):

None

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. 94-02 Page 5of 25 UNIT SHUTDOWN AND POWER REDUCTION (EQUAL To OR GREATER THAN 20%)

REPORT MONTH: February, 1994 Docket No.: 50-280 Unit Name: Surry Unit 1 Date: 03-01-94 Completed by: Craig Olsen

  • Telephone: **(804) 365-2155 (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 None During the Reporting Period (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. 94-02 Page 6 of 25 UNIT SHUTDOWN ANID POWER REDUCTION (EaUAL To OR GREATER THAN 20%)

REPORT MONTH: February, 1994 Docket No.: 50-281 Unit Name: Surry Unit 2 Date: 03-01-94 Completed by: Craig Olsen

  • *Telephone:** (804) 365-2155 (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 None During the Reporting Period (1) (2) (3)

F: Forced REASON: METHOD:

S: Scheduled A - Equipment Failure (Explain) 1 - Manual 8 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. 94-02 Page 7of 25 AVERAGE DAILY UNIT POWER LEVEL Docket No.: 50-280 Unit Name: Surry Unit 1 Date: 03-08-94 Completed by: Pat Kessler Telephone: 365-2790 MONTH: February, 1994 Average Daily Power Level Average Daily Power Level Day (MWe-Net) Day (MWe-Net) 1 0 17 0 2 0 18 0 3 0 19 0 4 0 20 0 5 0 21 0 6 0 22 0 7 0 23 0 8 0 24 0 9 0 25 0 10 0 26 0 11 0 27 0 12 0 28 0 13 0 14 0 15 0 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.

e Surry Monthly Operating Report No. 94-02 Page 8 of 25 AVERAGE DAILY UNIT POWER LEVEL Docket No.: 50-281 Unit Name: Surry Unit 2 Date: 03-08-94 Completed by: Pat Kessler Telephone: 365-2790 MONTH: February, 1994 Average Daily Power Level Average Daily Power Level Day (MWe- Net) Day (MWe- Net) 1 793 17 774 2 792 18 772 3 789 19 772 4 788 20 772 5 793 21 772 6 794 22 769 7 792 23 762 8 793 24 762 9 792 25 761 10 793 26 768 11 792 27 770 12 789 28 773 13 793 14 783 15 777 16 775 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. 94-02 Page 9 of 25

SUMMARY

OF OPERATING EXPERIENCE MONTHNEAR: February, 1994 The following 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:

02/01/94 0000 The reporting period began with the Unit in the refueling shutdown mode.

02/28/94 2400 The reporting period ended with the Unit in the refueling shutdown mode.

UNIT TWO:

02/01/94 0000 The reporting period began with the Unit operating at 100% power, 825 MWe.

02/12/94 0940 Started power reduction to facilitate repairs to No. 1 governor valve.

1043 Stopped power reduction at 93%. No. 1 governor valve removed from service.

1150 Started power increase.

1200 Stopped power increase at 100%, 825 MWe.

171 b Started power reduction to return No. 1 governor valve to service.

1715 Stopped power reduction at 95%, 785 MWe. No. 1 governor valve returned to service.

1825 Started power increase.

1854 Stopped power increase at 100%, 825 MWe.

02/14/94 0456 Started power reduction to mitigate Steam Generator "C" level oscillations.

0502 Stopped power reduction at 98%, 81 O MWe, to stabilize Steam Generator "C" level.

0532 Started power increase.

0549 Stopped power increase at 100%, 825 MWe.

1038 Started power reduction to mitigate Steam Generator "C" level oscillations.

1105 Stopped power reduction at 98%, 81 O MWe.

02/28/94 2400 The reporting period ended with the Unit operating at 98% power, 810 MWe, due to Steam Generator "C" level oscillations.

e Surry Monthly Operating Report No. 94-02 Page 10 of 25 FACILITY CHANGES THAT DID NIOT REQUIRE NRC APPROVAL MONTH/VEAR: February, 1994 TM S1-94-02 Temporary Modification 02-02-94 (Safety Evaluation No.94-022)

Temporary Modification S1-94-02 installed temporary telephone service between the Unit 1 Containment, the Fuel building, and the Control Room to facilitate communications during refueling operations.

The temporary telephone service is completely self-contained and cannot affect any plant control or logic circuitry. Therefore, an unreviewed safety question does not exist.

TSR 94-015 Temporary Shielding !Request 02-04-94 (Safety Evaluation 94-026)

Temporary Shielding Request 94-015 installed temporary lead shielding on the Unit 1 Reactor Coolant system loop "A" flow bypass line, loop drain line, and valve 1-RC-11 to reduce the radiation dose received by personnel while performing work in the area.

Installation of the shielding while the subject lines are "operable" was determined to be acceptable through the performance of seismic piping analyses, provided the Reactor Coolant system temperature does not exceed 200° F. The shielding will not adversely affect the design functions of the affected system and will be removed prior to exceeding the specified operating condition. Therefore, an unreviewed safety question does not exist.

TSR 94-021 Temporary Shielding Request 02-04-94 (Safety Evaluation 94-028)

Temporary Shielding Request 94-021 installed temporary lead shielding on the Unit 1 Reactor Coolant system flow bypass lines to reduce the radiation dose received by personnel while performing work in the area.

Installation of the shielding while the subject lines are "operable" was determined to be acceptable through the performance of seismic piping analyses, provided the Reactor Coolant system temperature does not exceed 200° F. The shielding will not adversely affect the design functions of the affected system and will be removed prior to exceeding the specified operating condition. Therefore, an unreviewed safety question does not exist.

e Surry Monthly Operating Report No. 94-02 Page 11 of 25 FACILITY CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTH/YEAR: February, 1994 TSR 94-040 Temporary Shielding Request 02-04-94 (Safety Evaluation 94-027)

Temporary Shielding Request 94-040 installed temporary lead shielding on certain Unit 1 Reactor Coolant and Safety Injection system lines to reduce the radiation dose received by personnel while performing work in the area.

Installation of the shielding while the subject lines are "operable" was determined to be acceptable through the performance of deadweight and seismic piping analyses, provided the Reactor Coolant system is not pressurized and the temperature does not exceed 200° F. The shielding will not adversely affect the design functions of the affected systems and will be removed prior to exceeding the specified operating conditions. Therefore, an unreviewed safety question does not exist.

TSR 94-041 Temporary Shielding Request 02-04-94 (Safety Evaluation 94-025)

Temporary Shielding Request 94-041 installed temporary lead shielding on Unit 1 Residual Heat Removal (RHR) system valve 1-RH-MOV-1700 and around the adjoining piping to reduce the radiation dose received by personnel while performing work in the area. The shielding around the piping was supported by scaffolding.

Installation of the shielding while the subject line is "operable" was determined to be acceptable through the performance of a deadweight analysis, provided the Reactor Coolant system temperature does not exceed 200° F. The shielding will not adversely affect the design functions of the affected system and will be removed prior to exceeding the specified operating condition. Therefore, an unreviewed safety question does not exist.

TSR 94-046 Temporary Shielding Request 02-04-94 (Safety Evaluation 94-024)

Temporary Shielding Request 94-046 installed temporary lead shielding on the Unit 1 Reactor Coolant system loop "B" and "C" flow bypass and loop drain lines to reduce the radiation dose received by personnel while performing work in the area.

Installation of the shielding while the subject lines are "operable" was determined to be acceptable through the performance of seismic piping analyses, provided the Reactor Coolant system temperature does not exceed 200° F. The shielding will not adversely affect the design functions of the affected system and will be removed prior to exceeding the specified operating condition. Therefore, an unreviewed safety question does not exist.

- Surry Monthly Operating Report No. 94-02 Page 12 of 25 FACILITY CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTH/YEAR: February, 1994 EWR 92-010 Engineering Work Request 02-06-94 (Safety Evaluation No.92-132)

Engineering Work Request 92-010 established setpoints for the emergency diesel generator (EOG) fuel oil tank level switches and conversion tables for converting fuel height to gallons or percentage of volume to gallons.

This change will help to ensure that an adequate supply of diesel fuel is available in the EOG rooms and that the applicable Technical Specification requirements continue to be satisfied. Therefore, an unreviewed safety question does not exist.

TM S2-94-02 Temporary Modification 02-08-94 (Safety Evaluation No.94-030)

Temporary Modification S2-94-02 installed a temporary relief valve on the common discharge piping of Unit 2 Low Head Safety Injection pumps "A" and "B". The existing relief valve was mechanically gagged due to lealcage.

The temporary relief valve was identical to the existing valve and provides the same level of protection. The valve was tested and installed in accordance with applicable design standards. Therefore, an unreviewed safety question did not exist.

TM S1-94-04 Temporary Modification 02-10-94 (Safety Evaluation No.94-034)

Temporary Modification S1-94-04 installed electrical jumpers to maintain power to certain Unit 1 Reactor Protection system (RPS) train "A" circuits during the replacement of RPS test switch TS-LC-476-TA.

The activity was performed while Unit 1 was shutdown. RPS train "B" and the operation of. other systems were not affected. Double verification of jumper installation/removal and post maintenance testing were performed. Therefore, an unreviewed safety question did not exist.

TM S1-94-05 Temporary Modification 02-10-94 (Safety Evaluation No.94-035)

Temporary Modification S1-94-05 removed the control fuses for Unit 1 Consequence Limiting Safeguards (CLS) system train "B" circuits to prevent a spurious Hi-Hi CLS signal during the replacement of CLS relay 1-CLS-RLY-2BM-X.

The activity was performed while Unit 1 was at cold shutdown when the CLS system was not required. Therefore, an unreviewed safety question did not exist.

e Surry Monthly Operating Report No. 94-02 Page 13 of 25 FACILITY CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTH/YEAR: February, 1994 FS94-002 UFSAR Change 02-11-94 (Safety Evaluation 94-037)

Updated Final Safety Analysis Report Change 94-002 revised Section 8.4.3, "120-V Alternating Current Vital Bus System," to describe the 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> warm up period required for the uninterruptible power supply (UPS) voltage and frequency to conform to that specified for the normal operating range.

This change provided additional detail regarding the UPS. No procedures or plant equipment were affected and no physical modifications were involved.

Therefore, an unreviewed safety question did not exist.

TM S1-94-06 Temporary Modification 02-12-94 (Safety Evaluation No. 94-038B)

Temporary Modification S1-94-06 mechanically fixed the Condensate Polishing building air compressor cooling tower fan dampers in the open position to increase the cooling capability.

The activity improved the operation of the subject air compressors and did not affect any safety-related systems or components. Therefore, an unreviewed safety question did not exist.

TM S1-94-07 Temporary Modification 02-14-94 (Safety Evaluation No.94-041)

Temporary Modification S1-94-07 installed electrical jumpers and lifted electrical leads to maintain power to certain Unit 1 Consequence Limiting Safeguards (CLS) system circuits and prevent a spurious Hi-CLS signal during the replacement of CLS relay 1-CLS-RLY-1 AM.

The activity was performed while Unit 1 was at cold shutdown when the CLS system was not required. The operation of other systems was not affected.

Double verification of jumper installation/removal and post maintenance testing were performed. Therefore, an unreviewed safety question did not exist.

TM S1-94-08 Temporary Modification 02-14-94 (Safety Evaluation No.94-039)

Temporary Modification S1-94-08 installed electrical jumpers and lifted electrical leads to maintain power to certain Unit 1 Consequence Limiting Safeguards (CLS) system train "B" circuits and prevent a spurious Hi-CLS signal during the replacement of CLS relay 1-CLS-RLY-1 B1.

The activity was performed while Unit 1 was at cold shutdown when the CLS system was not required. CLS train "A" and the operation of other systems were not affected. Double verification of jumper installation/removal and post maintenance testing were performed. Therefore, an unreviewed safety question did not exist.

e Surry Monthly Operating Report No. 94-02 Page 14of 25 FACILITY CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTH/YEAR: February, 1994 TM S1-94-09 Temporary Modification 02-14-94 (Safety Evaluation No.94-040)

Temporary Modification S1-94-09 installed electrical jumpers and lifted electrical leads to maintain power to certain Unit 1 Consequence Limiting Safeguards (CLS) system train "B" circuits and prevent a spurious Hi-CLS signal during the replacement of CLS relay 1-CLS-RLY-3/4-1 B. * * **

The activity was performed while Unit 1 was at cold shutdown when the CLS system was not required. CLS train "A" and the operation of other systems were not affected. Double verification of jumper installation/removal and post maintenance testing were performed. Therefore, an unreviewed safety question did not exist.

DCP 92-64 Design Change Package 02-15-94 (Safety Evaluation No.92-199)

Design Change Package 92-64 modified the logic for Unit 1 and 2 Charging/High Head Safety Injection system pumps "A" and "C".

This change eliminated the need to temporarily modify the "A" pump logic when removing the "C" pump from service for maintenance. The integrity of the subject systems was enhanced and a potential vulnerability to a single failure was removed. Therefore, an unreviewed safety question did not exist.

EWR 89-718 Engineering Work Request 02-15-94 (Safety Evaluation No.89-058)

Engineering Work Request 89-718 installed voltage surge suppressers on the emergency diesel generator isolation panel lockout relays.

This change was implemented to prevent the subject relay reset coils from causing the power available indicating light bulbs from prematurely burning out.

. The change does not alter the control logic or operation of the circuitry and does not impact 10 CFR 50 Appendix R compliance. Therefore, an unreviewed safety question did not exist.

SE 94-043 Safety Evaluation 02-16-94 Safety Evaluation 94-043 was performed to evaluate the Unit 1 Cycle 13 reload core, including the implementation of additional debris resistance features, flux suppression inserts, reduced active length burnable poison rod assemblies, and realigned mixing vane mid-grids to dampen assembly vibration.

Parameters affected by the reload were calculated and compared to the existing safety analysis assumptions. These parameters were shown to be either

1) explicitly bounded, or 2) accommodated by existing safety analysis margins and/or conservatism. Operation of the reload core in accordance with the Technical Specifications will not violate the design basis of plant safety equipment. Thus, the probabilities and consequences of analyzed accidents and equipment malfunctions are not changed by the reload. Therefore, an unreviewed safety question does not exist.

e Surry Monthly Operating Report No. 94-02 Page 15 of 25 FACILITY CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTH/YEAR: February, 1994 TM S1-94-10 Temporary Modification 02-17-94 (Safety Evaluation No.94-044)

Temporary Modification Si-94-10 installed Service Water (SW) system discharge swing check valve 1-SW-130 with the internals removed. The internals had been found degraded during an inspection of the valve.

A review of the SW system design concluded that the subject valve is not required since it is normally open and does not change state to perform any accident mitigation function. In addition, a redundant check valve exists at the discharge of SW pumps 1-SW-P-1 OA and 1-SW-P-1 OB. Therefore, an unreviewed safety question did not exist.

EWR 90-284 Engineering Work Request 02-18-94 (Safety Evaluation No.93-032)

Engineering Work Request 90-284 changed the corrosion inhibitor for the bearing cooling (BC) system from a sodium molybdate solution to sodium nitrate.

This change was implemented to prevent the formation of an iron phosphate precipitate that was fouling small heat exchangers and small diameter piping. The new chemical treatment was approved by the Virginia State Water Control Board and does not adversely affect the BC or any other plant system. Therefore, an unreviewed safety question does not exist.

EWR 91-109 Engineering Work Request 02-18-94 (Safety Evaluation No.91-214)

Engineering Work Request 91-109 disconnected the electrical power supply to Unit 1 and 2 Containment Spray (CS) system pump suction valves 1(2)-CS-MOV-103(203)A, B, C, and D, and the associated pressure switches. The motor-operated valves were also mechanically fixed in the open position.

This modification was implemented to prevent the spurious closure of the subject valves due to an erroneous indication of low pressure at the CS pump discharge following a Hi-Hi Consequence Limiting Safeguards (CLS) system actuation. An analysis of this change concluded that the performance of the CS system was not impacted and that the subject valves are not required to close during a Hi-Hi CLS condition with a low CS pump discharge pressure. Therefore, an unreviewed safety question did not exist.

e Surry Monthly Operating Report No. 94-02 Page 16 of 25 FACILITY CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTH/YEAR: February, 1994 TSR 94-048 Temporary Shielding Request 02-18-94 (Safety Evaluation 94-046)

Temporary Shielding Request 94-046 installed temporary lead shielding on certain Unit 1 Residual Heat Removal system lines in the vicinity of the lncore Room to reduce the radiation dose received by personnel while performing work in the area. * ** *

  • Installation of the shielding while the subject lines are "operable" was determined to be acceptable through the performance of seismic piping analyses, provided the Reactor Coolant system temperature does not exceed 200° F. The shielding will not adversely affect the design functions of the affected system and will be removed prior to exceeding the specified operating condition. Therefore, an unreviewed safety question does not exist.

DCP 92-66 Design Change Package 02-19-94 (Safety Evaluation No.92-207)

Design Change Package (DCP) 92-66 replaced certain Process Control system comparator fuses to ensure electrical coordination. The DCP also changed the source of power for certain instrument loop equipment from the 120 volt AC control-designated circuit to the instrument-designated circuit within the respective process rack to enhance the reliability of the_ indication circuits.

These changes did not affect the functional operation of the plant protective systems and will help to prevent the spurious operation of and challenges to such systems. Therefore, an unreviewed safety question did not exist.

EWR 91-063 Engineering Work Request 02-23-94 (Safety Evaluation No.91-221)

Engineering Work Request 91-063 identified and mechanically/electrically isolated certain abandoned equipment.

The abandoned equipment was not used to mitigate or monitor a design basis accident. The Technical Specification margin of safety was not affected by this activity. Therefore, an unreviewed safety question did not exist.

JCO C-94-001 Justification For Continued Operation 02-25-94 (Safety Evaluation No.94-049)

Justification For Continued Operation C-94-001 assessed the acceptability of controlling steam generator level during a loss of all AC power event by using local control of the turbine-driven auxiliary feedwater pump (TDAFWP) manual discharge valves in lieu of automatic control from the Control Room.

The assessment concluded that the procedurally controlled use of the TDAFWP manual discharge valves is an acceptable method for controlling steam generator level until a modification can be implemented. Therefore, an unreviewed safety question does not exist.

e Surry Monthly Operating Report No. 94-02 Page 17 of 25 FACILITY CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTH/YEAR: February, 1994 TM S1-94-11 Temporary Modification 02-26-94 (Safety Evaluation No.94-050)

Temporary Modification S1-94-11 installed electrical jumpers to maintain power to certain Unit 1 Reactor Protection system (RPS) circuits during the replacement of RPS relay P1 OXA.

The activity was performed while Unit 1 was shutdown with the reactor trip breakers open. The operation of other systems was not affected. Double verification of jumper installation/removal and post maintenance testing were performed. Therefore, an unreviewed safety question did not exist.

.* e e Surry Monthly Operating Report No. 94-02 Page 18 of 25 PROCEDURE OR METHOD OF OPERATION CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTH/YEAR: February, 1994 1/2-0PT-22-001 Operations Periodic Test Procedures 10-27-93 1/2-0PT-22-002 (Safety Evaluation No. 93-201A)

Operations Periodic Test Procedures 1/2-0PT-22-001, "ESF Actuation with Undervoltage and Degraded Voltage - 1H [2H] Bus" and 1/2-0PT-22-002, "ESF Actuation with Undervoltage and Degraded Voltage - 1J [2J] Bus" were revised to provide instructions for temporarilydisconnectingan electrical lead to prevent the operation of the Safety Injection (SI) system train that is not being tested while performing the manual SI push-button portion of these procedures.

The unit will be at cold shutdown when the manual SI push-button portion of these procedures is performed. The temporary modification will not affect the control circuits for the Residual Heat Removal or Reactor Coolant System pumps that are in service. Therefore, an unreviewed safety question does not exist.

1-0PT-Sl-013 Operations Periodic Test Procedure 02-07-94 (Safety Evaluation No.94-029)

Operations Periodic Test Procedure 1-0PT-Sl-013, "Valve lnservice Testing -

Leak Test of LHSI Pump Recirc Valves" was developed to provide instructions for .

testing Unit 1 low head safety injection pump recirculation valves 1-SI--MOV-1885A, B, C, and D, as required by NRC Information Notice 91-56.

The procedure will be performed when the unit is at cold shutdown when the safety injection system is not required. Procedural controls will minimize the boron dilution of the Reactor Coolant system and ensure that an adequate shutdown margin is maintained. Therefore, an unreviewed safety question does not exist.

O-ECM-1406-01 Electrical Corrective Maintenance Procedure 02-09-94 (Safety Evaluation No.94-033)

Electrical Corrective Maintenance Procedure O-ECM-1406-01, "Main Feedwater Pump Motor Maintenance" was developed to provide instructions for performing maintenance and post-maintenance testing on main feedwater pump motors.

The post-maintenance testing portion of the procedure includes the use of temporary modifications to defeat various interlocks to facilitate an uncoupled test run of the motor. The performance of this procedure will not result in inadvertent feedwater additions since the pump discharge motor operated valves are not affected. Therefore, an unreviewed safety question does not exist.

. e Surry Monthly Operating Report No. 94-02 Page 19 of 25 PROCEDURE OR METHOD OF OPERATION CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTH/YEAR: February, 1994 1-MOP-EPH-012 Maintenance Operating Procedures 02-09-94 2-MOP-EPH-012 (Safety Evaluation No.94-032)

Maintenance Operating Procedures 1-MOP-EPH-012, "RSS Transformer A Outage with Transfer Bus D and Station Service Bus 1A De-energized" and 2-MOP-EPH-012, "RSS Transformer B Outage with Transfer Bus E and Station

        • Service Bus 2B*De-energized"were developed to*provide*instructions for de-energizing the respective reserve station service transformer and transfer bus to facilitate the performance of preventive maintenance and testing of the associated 4160 volt circuit breakers and relays.

These procedures affect the nonsafety-related portion of the Electrical Distribution system and will be performed during unit refueling outages when the reactor vessel is empty. Safety-related systems will not be affected. Therefore, an unreviewed safety question does not exist.

Electrical Preventive Maintenance Procedures 02-11-94 (Safety Evaluation No.94-038)

Various Electrical Preventive Maintenance Procedures were revised to provide instructions for installing electrical jumpers and lifting electrical leads to facilitate the functional testing of the 4160 volt AC breakers that are connected to busses "A", "B", "C", "D, "E", "F", "G", "H", and "J".

Special precautions are provided to positively account for electrical jumper installation and removal. Lifted electrical leads will be functionally tested (where practical) or independently verified when re-terminated. The AC portion of the system will be removed from service during the performance of the procedures.

Appropriate controls are provided to ensure that the performance characteristics of safety-related systems linked to the DC portion of the system will not be altered. Therefore, an unreviewed safety question does not exist.

1-EPT-0902-01 Electrical Periodic Test Procedures 02-17-94 2-EPT-0902-01 (Safety Evaluation No.94-045)

Electrical Periodic Test Procedures 1(2)-EPT-0902-01, "Fire Protection Low Pressure CO2 System Puff Test," were revised to provide instructions for administratively controlling the low pressure carbon dioxide tank manual isolation valves to facilitate the performance of Technical Specification required surveillance flow testing.

Appropriate administrative controls are provided in the procedure to ensure that the Low Pressure Carbon Dioxide fire suppression system remains capable of performing its design function during the testing. Therefore, an unreviewed safety question does not exist.

- Surry Monthly Operating Report No. 94-02 Page 20 of 25 PROCEDURE OR METHOD OF OPERATION CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTHNEAR: February, 1994 O-OP-RW-002 Operating Procedure 02-28-94 (Safety Evaluation No.94-051)

Operating Procedure O-OP-RW-002, "Resin Transfer from IXs to Spent Resin Catch Tk," was temporarily revised to provide instructions for establishing a different flow path to transfer depleted resin from ion exchanger 1-CH-1-2 to the spent resin catch tank.

  • The flow path change was* required due to the inlet isolation valve for 1-CH-1-2 being failed open.

This activity was performed while Unit 1 was at cold shutdown. The Letdown system was not in service and was isolated from the Reactor Coolant system.

Therefore, an unreviewed safety question did not exist.

, - Surry Monthly Operating Report

' No. 94-02 Page 21 of 25 TESTS AND EXPERIMENTS THAT DID NOT REQUIRE NRC APPROVAL MONTHNEAR: February, 1994 1-ST-311 Special Test 01-20-94 (Safety Evaluation 94-009)

Special Test 1-ST-311, "Nuclear Instrumentation System Source and Intermediate Range Noise Measurement and Analysis," was conducted during January, 1994, to measure and analyze certain characteristics (e.g., resistance, impedance, capacitance) of the Unit 1 Nuclear Instrumentation (NI) system source and intermediate range detectors. These characteristics can provide an indication of noise induced by degraded cables or connectors. The testing was performed in preparation for the installation of Hafnium flux suppression inserts into the reactor core during the 1994 Unit 1 refueling outage. The presence of electrical noise could impact the operation of the NI system, since the flux suppression inserts will reduce the nuclear instrumentation signal.

The test results indicated that the electrical noise measured was a significant portion of the overall source range signal. Troubleshooting will be performed during the 1994 Unit 1 refueling outage. The results of this activity and the Special Test will be evaluated and appropriate actions will be implemented to reduce the electrical noise.

  • This test was performed with the unit at cold shutdown and in conjunction with the normal Technical Specification required functional test of the NI channels.

Each channel (one at a time) was monitored for electrical noise while in the test mode, in accordance with the functional test procedure. Therefore, an unreviewed safety question did not exist.

1-ST-312 Special Test 01-20-94 (Safety Evaluation 94-010)

Special Test 1-ST-307, "Nuclear Instrumentation System Noise Measurement and Analysis at Zero Power," was conducted during January, 1994, to measure and analyze electrical noise on the Unit 1 Nuclear Instrumentation (NI) system power range drawers while the Unit was shutdown to establish a noise baseline.

The testing was performed in preparation for the installation of Hafnium flux suppressiof1 inserts into the reactor core during the 1994 Unit 1 refueling outage.

The presence of electrical noise could impact the operation of the NI system, since the flux suppression inserts will reduce the nuclear instrumentation signal.

The test results indicated that the electrical noise measured was not a significant portion of the overall power range signal. Based on the results of this test and Special Test 1-ST-307, it was concluded that the operation of the power range drawers with Hafnium flux suppression inserts installed would not be impacted by the electrical noise measured on the power range detectors.

This test was performed with the unit at cold shutdown and in conjunction with the normal Technical Specification required functional test of the NI channels.

Each channel (one at a time) was monitored for electrical noise while in the test mode, in accordance with the functional test procedure. Therefore, an unreviewed safety question did not exist.

e e Surry Monthly Operating Report No. 94-02 Page 22 of 25 TESTS AND EXPERIMENTS THAT DID NOT REQUIRE NRC APPROVAL MONTH/YEAR: February, 1994 1-ST-310 Special Test 02-15-94 (Safety Evaluation No.94-002)

Special Test 1-ST-310, "Recirculation Spray Heat Exchanger Service Water Flow Test," was performed on January 24, 1994. The test verified that the Unit 1 "B" and "C" recirculating spray heat exchanger (RSHX) service water (SW) system will deliver design basis flow to reject design ba*sis heat loads from the containment.

In addition, Recirculating Spray system valves 1-RS-MOV-1048 and 1-RS-MOV-104C were stroked with the RSHX SW system in service to collect data relative to Generic Letter 89-1 o.

The test was performed with the unit at cold shutdown when the RS system was not required. Therefore, an unreviewed safety question did not exist.

2-ST-307 Special Test 02-15-94 (Safety Evaluation 93-202)

Special Test 2-ST-307, "Nuclear Instrumentation System Noise Measurement and Analysis," was conducted during January, 1994, to measure and analyze electrical noise on the Unit 2 Nuclear Instrumentation (NI) system power range drawers while the unit was at power. The testing was performed to enable a comparison of the results from the corresponding Unit 1 testing (re:1-ST-307), in preparation for the installation of Hafnium flux suppression inserts into the Unit 1 reactor core during the 1994 refueling outage. The presence of electrical noise could impact the operation of the NI system, since the flux suppression inserts will reduce the nuclear instrumentation signal.

The test was not completed since a control power fuse blew on power range drawer N-41, resulting in a turbine runback. A root cause evaluation was initiated to determine the cause of the transient.

This test was being performed in conjunction with the normal monthly Technical Specification required surveillance of the power range drawers. The test points in each drawer were to be monitored for electrical noise while the drawer was placed in the test mode, in accordance with the surveillance test procedure. Therefore, an unreviewed safety question did not exist.

e Surry Monthly Operating Report No. 94-02

.' Page 23 of 25 CHEMISTRY REPORT MONTH/YEAR: February, 1994 Unit No. 1 UnitNo.2 Primary Coolant Analysis Max. Min. Avg. Max. Min. Avg.

Gross Radioactivity, µCi/ml 4.29E-2 2.11E-4 2.58E-3 1.83E-1 1.17E-1 1.53E-1 Suspended Solids, oom < 0.1 < 0.1 < 0.1 < 0.1 < 0.1 < 0.1 Gross Tritium, µCi/ml - - - 6.36E-1 5.56E-1 6.04E-1 1131, uci/ml 8.35E-4 8.86E-6 1.62E-4 1.03E-4 4.96E-5 7.59E-5 1131JI133 - - - 0.11 0.05 0.07 Hvdrooen, cc/ko - - - 45.6 33.6 38.4 Lithium, oom - - - 2.33 2.08 2.19 Boron - 10, oom* 472.8 456.1 466.3 186.4 174.8 180.8 Oxvoen, (DO), oom 7.0 1.0 5.3 < 0.005 <0.005 < 0.005 Chloride oom 0.032 <0.001 0.004 0.009 0.004 0.006 PH at 25 deoree Celsius 4.78 4.38 4.57 6.53 6.26 6.39 Boron -10 = Total Boron x 0.196 Comments:

None

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ft Surry Monthly Operating Report No. 94-02 Page 24 of 25 FUEL HANDLING UNITS 1 & 2 MONTH/YEAR: February, 1994 New or Spent Number of New or Spent Fuel Shipment Date Stored or Assemblies Assembly ANSI Initial Fuel Shipping Number Received per Shipment Number Number Enrichment Cask Activity No Fuel Received or Stored During the Reporting Period.

e Surry Monthly Operating Report No. 94-02 Page25 of 25 DESCRIPTION OF PERIODIC TEST(S) WHICH WERE NOT COMPLETED WITHIN THE TIME LIMITS SPECIFIED IN TECHNICAL SPECIFICATIONS MONTH/YEAR: February, 1994

.. None During the Reporting Period.

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