ML18152A340

Monthly Operating Repts for Mar 1994 for Surry Power Station Units 1 & 2.W/940412 Ltr

ML18152A340
Person / Time
Site:	Surry
Issue date:	03/31/1994
From:	BOWLING M L, MASON D, OLSEN C VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
94-215, NUDOCS 9404180309
Download: ML18152A340 (26)

Text

e e VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND, VIRGINIA 23261 April 12, 1994 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.94-215 NO/RPC:vlh Docket No$ .. , .50'."280 50-281 License Nos. DPR-32 DPR-37 Enclosed is the Monthly Operating Report for Surry Power Station Units 1 and 2 for the month of March 1994. Very truly yours, /~i~ M. L. Bowling, ;7anager 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 NRG Senior Resident Inspector Surry Power Station -----940418036~

~4b33i--~~\ PDR ADOCK 05000280 R . PDR I ------------~-----* ---*--___ .:._. _, _* -__ _;!

VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION MONTHLY OPERATING REPORT REPORT NO. 94m03 Approved:

TABLE OF CONTENTS Section eurry Monthly Operating Report No. 94-03 Page 2of 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 ....................................................................................

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 .......................................................................................

10 Facility Changes That Did Not Require NRC Approval ...............................................................................

11 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 41,urry Monthly Operating Report .. No. 94-03 Page 3of 25 OPERATING DATA REPORT Docket No.: Date: Completed By: 50-280 04-06-94 D. Mason Telephone:

(804) 365-2459 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 1 March, 1994 2441 847.5 788 820 781 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 ..........................

744.0 2160.0 186480.0 12. Number of Hours Reactor Was Critical ..........

171.6 680.8 124488.0 13. Reactor Reserve Shutdown Hours ...............

0 0 3774.5 14. Hours Generator On-Line ...........................

141.8 647.9 122326.9 15. Unit Reserve Shutdown Hours .....................

0 0 3736.2 16. Gross Thermal Energy Generated (MWH) ...... 256304.9 1001728.0 284169473.1

17. Gross Electrical Energy Generated (MWH) .... 84040.0 ~35055.0 92874603.0

18. Net Electrical Energy Generated (MWH) ........ 80306.0 317769.0 88144870.0

19. Unit Service Factor ...................................

19.1% 30.0% 65.6% 20. Unit Availability Factor ...............................

19.1% 30.0% 67.6% 21. Unit Capacity Factor (Using MDC Net) ...........

13.8% 18.8% 60.9% 22. Unit Capacity Factor (Using DER Net) ...........

13.7% 18.7% 60.0% 23. Unit Forced Outage Rate ............................

0% 0% 17.4% 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 INITIAL CRITICALITY INITIAL ELECTRICITY COMMERCIAL OPERATION ACHIEVED

-aurry Monthly Operating Report -No. 94-03 Page 4of 25 OPERATING DATA REPORT Docket No.: 50-281 04-06-94 D. Mason Date: Completed By: Telephone:

(804) 365-2459 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 March, 1994 2441 847.5 788 820 781 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 ..........................

744.0 2160.0 183360.0 12. Number of Hours Reactor Was Critical ..........

744.0 2160.0 122236.3 13. Reactor Reserve Shutdown Hours ...............

0 0 328.1 14. Hours Generator On-Line ...........................

744.0 2160.0 120375.6 15. Unit Reserve Shutdown Hours .....................

0 0 0 16. Gross Thermal Energy Generated (MWH) ...... 1754374.1 5183840.1 280859582.5

17. Gross Electrical Energy Generated (MWH) .... 585635.0 1736585.0 91682209.0

18. Net Electrical Energy Generated (MWH) ........ 565310.0 1675337.0 87007407.0

19. Unit Service Factor ...................................

100.0% 100.0% 65.6% 20. Unit Availability Factor ...............................

100.0% 100.0% 65.6% 21. Unit Capacity Factor (Using MDC Net) ...........

97.3% 99.3% 60.9% 22. Unit Capacity Factor (Using DER Net) ...........

96.4% 98.4% 60.2% 23. Unit Forced Outage Rate ............................

0.0% 0.0% 13.9% 24. Shutdowns Scheduled Over Next 6 Months (Type, Date, and Duration of Each): Maintenance, June 4, 1994, 22 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 INITIAL CRITICALITY INITIAL ELECTRICITY COMMERCIAL OPERATION ACHIEVED (1) -urry Monthly Operating Report No. 94-03 Page 5 of 25 UNIT SHUTDOWN AND POWER REDUCTION (EQUAL To OR GREATER THAN 20%) REPORT MONTH: March, 1994 (2) (3) (4) (5) Docket No.: 50-280 Unit Name: Surry Unit 1 Date: 04-06-94 Completed by: Craig Olsen

• Telephone:

(804) 365-2155 Duration Method of Reason Shutting Down Rx LER No. System Component Cause & Corrective Action to Date Type Hours Code Code Prevent Recurrence (1) F: Forced S: Scheduled (4) (2) REASON: None During the Reporting Period A -Equipment Failure (Explain)

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

Exhibit G -Instructions for Preparation of Data Entry Sheets for Licensee Event Report (LER) File (NUREG 0161) (3) METHOD: 1 -Manual 2 -Manual Scram. 3 -Automatic Scram. 4 -Other (Explain)

(5) Exhibit 1 -Same Source.

(1) Date Type 940315 s (1) F: Forced S: Scheduled (4) aurry Monthly Operating Report No. 94-03 Page 6of 25 UNIT SHUTDOWN AND POWER REDUCTION (EQUAL To OR GREATER THAN 20%} REPORT MONTH: March, 1994 (2) (3) (4) Method (5) Docket No.: 50-281 Unit Name: Surry Unit 2 Date: 04-06-94 Completed-by:*

Craig Olsen Telephone:

(804) 365-2155 Duration of LER System Component Cause & Corrective Action to Hours 12.8 Reason B (2) REASON: Shutting No. Down Rx NIA NIA A -Equipment Failure (Explain)

B Maintenance or Test C Refueling D Regulatory Restriction Code Code TA TRB E Operator Training & Licensing Examination F Administrative G Operational Error (Explain)

Prevent Recurrence Reduced power to 75% to perform governor valve freedom of movement test. (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.

MONTH: March, 1994 Day 1 2 3 4 5 6 7 8 9 10 11 12 13 14 15 16 INSTRUCTIONS

&urry Monthly Operating Report No. 94-03 Page 7of 25 AVERAGE DAILY UNIT POWER LEVEL Docket No.: 50-280 Unit Name: Surry Unit 1 Date: 04-06-94 Completed by: Pat Kessler Telephone:

365-2790 Average Daily Power Level Average Daily Power Level (MWe-Net)

Day (MWe-Net) 0 17 0 0 18 0 0 19 0 0 20 0 0 21 0 0 22 0 0 23 0 0 24 0 0 25 0 0 26 168 0 27 370 0 28 554 0 29 671 0 30 791 0 31 792 0 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: March, 1994 Day 1 2 3 4 5 6 7 8 9 10 11 12 13 14 15 16 INSTRUCTIONS tltsurry Monthly Operating Report No. 94-03 Page 8 of 25 AVERAGE DAILY UNIT POWER LEVEL Docket No.: 50-281 Unit Name: Surry Unit 2 Date: 04-06-94 Completed by: Pat Kessler Telephone*:

365-2790.

Average Daily Power Level Average Daily Power level (MWe-Net) Day (MWe-Net) 771 17 758 774 18 758 773 19 758 773 20 749 772 21 749 772 22 752 772 23 752 771 24 751 771 25 752 770 26 751 764 27 758 763 28 757 764 29 755 760 30 753 718 31 756 762 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.

esurry Monthly Operating Report No. 94-03 Page 9 of 25

SUMMARY

OF OPERATING EXPERIENCE MONTH/YEAR:

March, 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: 03/01/94 03/24/94 03/26/94 03/27/94 03/28/94 03/29/94 03/30/94 03/31/94 0000 The reporting period began with the Unit in the refueling shutdown mode. 2023 Reactor critical.

0215 Unit on-line, started power increase.

0255 Stopped power increase at 26%, 215 MWe, to perform flux mapping. 0258 Started power increase.

0000 Stopped power increase at 70% power, 578 MWe, to perform flux mapping. 0600 Started power increase.

1700 Stopped power increase at 96%, 800 MWe. 0339 Started power increase.

0425 Stopped power increase at 98%, 816 MWe. 1350 Started power increase.

1418 Stopped power increase at 100%, 830 MWe. 2054 Started power reduction for core output evaluation.

2130 Stopped power reduction at 98% power, 820 MWe. 2400 The reporting period ended with the Unit at 98% power, 820 MWe, pending Engineering evaluation of reactor core power level.

UN!TTwo: 03/01/94 03/10/94 03/15/94 03/19/94 03/31/94 esurry Monthly Operating Report No. 94-03 Page 10 of 25

SUMMARY

OF OPERATING EXPERIENCE MONTH/YEAR:

March, 1994 0000 The reporting period began with the Unit at 98% power, 810 MWe due to Steam Generator "C" level oscillations.

2012 Started power reduction to stabilize Steam Generator "C" level oscillations 2030 Stopped power reduction at 97%, 800 MWe. 091 O Started power reduction to perform governor valve freedom of movement test, 2-0SP-TM-001. 1340 Stopped power reduction at 75%, 620 MWe. 1415 Started power increase after completion of governor valve freedom of movement test. 2200 Stopped power increase at 97%, 800 MWe. 2255 Started power reduction to stabilize Steam Generator "C" level oscillations.

2300 Stopped power reduction at 96%, 785 MWe 2400 The reporting period ended with the Unit operating at 96% power, 785 MWe, due to Steam Generator "C" level oscillations.

EWR 90-228 DCP 91-05-1 TM S1-94-12 EWR 89-132 FACILITY CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTH/YEAR:

March, 1994 Engineering Work Request (Safety Evaluation No.91-009) -Surry Monthly Operating Report No. 94-03 Page 11 of 25 02-28-94 Engineering Work Request 90-228 replaced the Residual Heat Removal system mechanical pump seals with an updated balanced seal. This change extends the life of the seal and minimizes seal leakage. Installation of the new balanced seal did not affect the original system design or function.

Therefore, an unreviewed safety question did not exist. Design Change Package (Safety Evaluation No.91-268) 03-02-94 Design Change Package 91-05-1 removed the resistance temperature device (RTD) bypass piping system and replaced it with thermowell mounted RTDs directly in the RCS hot and cold leg pipes. The modification did not degrade the performance or increase the challenges to equipment assumed to function during an accident condition.

Therefore, an unreviewed safety question did not exist. Temporary Modification (Safety Evaluation No.94-053) 03-03-94 Temporary Modification (TM) S1-94-12 de-energized Gaseous Drains System solenoid operated valve, 1-DG-SOV-100, and installed a mechanical jumper that bypassed 1-DG-SOV-100, thereby maintaining primary drain transfer tank pressure control valve, 1-DG-PCV-100, in the open position.

This modification was implemented to prevent spurious alarms that result from electrical noise that is generated when 1-DG-SOV-100 is energized to open 1-DG-PCV-100.

The Unit was at cold or refueling shutdown while the TM was in place. During these plant conditions, the operation of the Primary Drains System was not affected.

The mechanical jumper was tested following installation and the operation of 1-DG-PCV-100 was verified following its removal. Therefore, an unreviewed safety question did not exist. Engineering Work Request 03-03-94 Engineering Work Request 89-132 installed and secured cable tray covers which restores the Cable Tray System to Regulatory Guide 1.75 and IEEE STD 384-1974 commitments of the 10 CFR 50 Appendix R Report. This resolved Appendix R and seismic integrity nonconformances that existed for Station cable trays. Therefore, an unreviewed safety question did not exist.

SE 94-054 SE 94-055 DC P 92-043-1 FS 94-08 FACILITY CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTH/YEAR:

March, 1994 Safety Evaluation -Surry Monthly Operating Report No. 94-03 Page 12 of 25 03-04-94 Safety Evaluation 94-054 was performed to assess the removal of the baskets on the traveling water screens at the high and low level intake structures during an extreme cold weather period to prevent ice from forming and reducing the flow through the screens. * * * *' '1 The evaluation concluded that, while the temporary removal of the related baskets would allow more debris to pass by the screens, sufficient cooling water flow and heat exchanger heat transfer area would remain available for the heat exchangers to function as designed.

Therefore, an unreviewed safety question did not exist. Safety Evaluation 03-04-94 Safety Evaluation 94-055 was performed to assess an increase in the intake canal level from 30 feet to 32 feet to provide for increased cooling water inventory during an extreme cold weather period in which ice formation at the low level intake structure could result in reduced circulating water pump availability.

The evaluation concluded that the temporary change in canal level would not impact the integrity of the intake canal structure or affect the margin of safety of Technical Specifications.

Therefore, an unreviewed safety question did not exist. Design Change Package (Safety Evaluation No.93-176) 03-04-94 Design Change Package 92-043-1 replaced the pressurizer safety valves (PSVs) with safety valves that are designed to seal tighter under pressurizer steam conditions and discharge pipe loads. A loop seal drain line was installed to allow the loop seal to continuously drain condensation from the loop seal which allowed the removal of the loop seal ovens. Implementation of these changes eliminated the concern of Reactor Coolant System (RCS) over pressurization due to the PSV loop seals. Virginia Power calculations SM-727 and SM-700 indicated that RCS pressure will remain below 2735 psig during limiting events. Therefore, an unreviewed safety question does not exist. UFSAR Change 03-07-94 (Safety Evaluation No.94-058) Updated Final Safety Analysis Report Change 94-058 revised Sections 11.2.3.1.6, "RF Liquid Waste Evaporator System," and 11.2.4.1.4, "Evaporator Concentrate Operations," to reflect a change in the boron concentration in the Liquid Waste Evaporator System, which is located at the Surry Radwaste Facility.

The boron concentration was increased to reduce the volume of radioactive waste. This change did not impact safety-related systems or affect the margin of safety of Technical Specifications.

Therefore, an unreviewed safety question did not exist.

TM S1-94-13 TM S1-94-14 DCP 92-41-1 EWR 93-002 FACILITY CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTH/YEAR:

March, 1994 Temporary Modification (Safety Evaluation No.94-059) &urry Monthly Operating Report No. 94-03 Page 13 of 25 03-07-94 Temporary Modification S1-94-13 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 relay 1-CLS-RLY-1 BM. 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 was performed.

Therefore, an unreviewed safety question did not exist. Temporary Modification (Safety Evaluation No.94-060) 03-07-94 Temporary Modification S1-94-14 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 relay 1-CLS-RLY-1A1.

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 was performed.

Therefore, an unreviewed safety question did not exist. Design Change Package (Safety Evaluation No. 92-97) 03-08-94 Design Change Package 92-41-1 replaced a leaking level transmitter's manifold with three single valves since no direct replacement manifold was available.

The change enhanced the system because a single failure of a valve will not require the replacement of a manifold.

The operation and function of the system was not altered. Therefore, an unreviewed safety question did not exist. Engineering Work Request (Safety Evaluation No.93-035) 03-08-94 Engineering Work Request 93-002 completed steam generator wrapper modifications which involved permanent removal of all four wrapper plug assemblies, removal of a portion of the wrapper seal plates, and removal of the outer tube lane blocking devices. This modification reduces radiation exposure to personnel by reducing the effort and time required for wrapper entry. The modifications improve sludge lancing efficiency and improve access for foreign object search and recovery.

The modifications do not affect the safety limits, surveillance requirements, limiting conditions of operations or system tests as described in the Technical Specifications.

Therefore, an unreviewed safety question did not exist.

TM S1-94-15 TM S1-94-16 TM S1-94-17 TM S1-94-18 TM S1-94-19 FACILITY CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTH/YEAR:

March, 1994 Temporary Modifications (Safety Evaluation No.94-062) &urry Monthly Operating Report No. 94-03 Page 14of 25 03-09-94 Temporary Modifications (TM) S1-94-15 and S1-94-16 removed containment sump trip valve, 1-DA-TV-1 OOA, for maintenance and installed a spool piece and electrical jumpers to *maintain" an* operable flow path frorri *containment sump pumps 1-DA-P-4A and 1-DA-P-48.

The Unit was at cold shutdown while the TM was in place. The containment sump trip valve closure interlocks, which would shut off pumps 1-DA-P-4A and 1-DA-P-4B, were defeated to allow pump operation to continue as needed. The pump interlocks of the redundant valve 1-DA-TV-1008 remained operable.

Therefore, an unreviewed safety question did not exist. Temporary Modification (Safety Evaluation No.94-064) 03-10-94 Temporary Modification (TM) S1-94-17 installed electrical jumpers to bypass test switch 1-SI-CS-LC494-TB on the Unit 1 Safety Injection (SI) System Train "B" circuitry to allow the switch to be replaced without rendering the circuits inoperable.

The activity was performed while Unit 1 was at cold shutdown when the SI System was not required.

Double verification of jumper installation/removal and maintenance testing was performed.

Therefore, an unreviewed safety question did not exist. Temporary Modification (Safety Evaluation No.94-066) 03-10-94 Temporary Modification (TM) S1-94-18 installed electrical jumpers to bypass test switch TS-LC-476-TB on the Unit 1 Safety Injection (SI) System Train "B" circuitry to allow the switch to be replaced without rendering the circuits inoperable.

The activity was performed while Unit 1 was at cold shutdown when the SI System was not required.

Double verification of jumper installation/removal and maintenance testing was performed.

Therefore, an unreviewed safety question did not exist. Temporary Modification (Safety Evaluation No.94-063) 03-10-94 Temporary Modification S1-94-19 installed electrical jumpers to maintain power to certain Unit 1 Safety Injection (SI) System circuits and prevent a spurious SI signal during the replacement of relay 1-SI-RL Y-FC-475-XA.

The activity was performed while Unit 1 was at cold shutdown when the SI System was not required.

The operation of other systems was not affected.

Double verification of jumper installation/removal and post-maintenance testing was performed.

Therefore, an unreviewed safety question did not exist.

TM S1-94-20 TM S1-94-21 DCP 93-018-1 DCP 93-15-1 FACILITY CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTH/YEAR:

March, 1994 Temporary Modification (Safety Evaluation No.94-065) -Surry Monthly Operating Report No. 94-03 Page 15 of 25 03-10-94 Temporary Modification (TM) S1 20 installed electrical jumpers to maintain power to certain Unit 1 Reactor Protection (RP) System Train "~" circuits during the replacement of rela:y TT-XB. * *

• The activity was performed while Unit 1 was at cold shutdown and did not affect RP System Train "A". The TM did not impact the operation of the Residual Heat Removal or other systems. Double verification of jumper installation/removal and post-maintenance testing was performed.

Therefore, an unreviewed safety question did not exist. Temporary Modification (Safety Evaluation No.94-068) 03-13-94 Temporary Modification (TM) S1-94-21 installed an electrical jumper to provide the proper input to the Unit 1 reactor coolant pump (RCP) "A" trip logic to enable the pump to be started. This TM was necessary since the loop "A" isolation valve "open" stem position switch was not in the correct position.

The activity was performed while Unit 1 was at cold shutdown.

The TM placed the RCP "A" trip logic in the normal state for power operation and did not affect the integrity or operation of the valve. Double verification of jumper installation/removal was performed.

Therefore, an unreviewed safety question did not exist. Design Change Package (Safety Evaluation No.93-175) 03-13-94 Design Change Package 93-018-1 re-routed the miniflow recirculation line due to a leak in the buried portion of the line. The line previously discharged directly into the Emergency Condensate Storage Tank and now discharges into the Emergency Condensate Storage Tank via the Auxiliary Feedwater Pumps Flow Recirculation line. Although the mini-flow recirculation line has been re-routed to discharge into the Emergency Condensate Storage Tank via the Auxiliary Feedwater Pumps Flow Recirculation line, the operation/performance of the Auxiliary Feedwater Pumps was not altered. Therefore, an unreviewed safety question did not exist. Design Change Package (Safety Evaluation No.93-169) 03-14-93 Design Change Package 93-15-1 replaced 01-CS-MOV-102A and B valves and operators because of a less than satisfactory material condition due to high thrust seating loads. This was an in-kind replacement and had no affect on the consequences of any evaluated accidents.

Therefore, an unreviewed safety question did not exist..

DR S-94-0615 TM S1-94-22 TM S1-94-23 TM S1-94-24 e FACILITY CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTH/YEAR:

March, 1994 Deviation Report (Safety Evaluation No.94-071) -Surry Monthly Operating Report No. 94-03 Page 16 of 25 03-14-94 Safety Evaluation 94-071 assessed the condition reported by Deviation Report S-94-0615 concerning the continued operation of Unit 1 with a small immobile foreign* object (wire approximately 1/8" to 5/32" diameter estimated to be less than 0.1 pounds) in the secondary side of Unit 1 steam generator (SG) "A". Attempts to remove the object have been unsuccessful.

An evaluation of Unit 1 operation with the SG containing the foreign object was performed by Westinghouse Nuclear Safety. The evaluation concluded that the presence of the object will have no adverse effect on the pressure boundary integrity of the SG and does not create an unreviewed safety question provided future eddy current inspections support no tube degradation due to wear. Temporary Modification (Safety Evaluation No.94-070) 03-14-94 Temporary Modification S1-94-22 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 relay 1-CLS-RLY-1A02.

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 was performed.

Therefore, an unreviewed safety question did not exist. Temporary Modification (Safety Evaluation No.94-069) 03-14-94 Temporary Modification S1-94-23 removed the control fuses for Unit 1 Consequence Limiting Safeguards (CLS) System Train "A" circuits to prevent a spurious Hi-Hi CLS signal during the replacement of Leakage Monitoring System relay 1-LM-RL Y-1 OOA 1. 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.

• Temporary Modification (Safety Evaluation No.94-072) 03-15-94 Temporary Modification S1-94-24 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 B13. 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 was performed.

Therefore, an unreviewed safety question did not exist.

TM S1-94-25 TM S1-94-26 DR S-94-0097 TM S1-94-27 FACILITY CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTH/YEAR:

March, 1994 Temporary Modification (Safety Evaluation No.94-073) &urry Monthly Operating Report No. 94-03 Page 17of 25 03-16-94 Temporary Modification (TM) S1-94-25 installed an electrical jumper to bypass the failed Unit 1 Consequence Limiting Safeguards (CLS) alarm ~ircuit relay 1808 and

• clear Control Room annunciator 1-8-4, "CLS Coil Failure." * ** *

• The subject Hi CLS System Train "B" relay is a spare that performs no function.

The activity did not affect other systems or the Hi CLS System Train "A". The operability of the affected alarms were verified following the installation of the TM. Therefore, an unreviewed safety question did not exist. Temporary Modification (Safety Evaluation No.94-074) 03-16-94 Temporary Modification S1-94-26 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 relay 1-CLS-RL Y-2804. 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. Deviation Report 03-17-94 (Safety Evaluation No.94-076) Safety Evaluation 94-076 assessed the condition reported by Deviation Report S-94-0097 concerning continued station operation with a through-wall leak of charging pump service water discharge piping located in the Auxiliary Building.

The assessment concluded that the leak does not affect the design function of the Charging Service Water System, other safety-related systems, or reduce the Technical Specifications margin of safety. Therefore, an unreviewed safety question did not exist. Temporary Modification (Safety Evaluation No.94-075) 03-17-94 Temporary Modification S1-94-27 installed an electrical jumper to maintain power to. certain Unit 1 Reactor Protection System (RPS) Train "A" circuits during the replacement of relay 1-RP-RL Y-AFP1-XA.

The activity was performed while Unit 1 was shut down with the reactor trip and bypass breakers open. The operation of RPS train "B" and other systems was not affected.

Double verification of jumper installation/removal and maintenance testing was performed.

Therefore, an unreviewed safety question did not exist.

EWR 88-476 TM S1-94-28 TM S1-94-29 DC P 93-036-1 FACILITY CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTH/YEAR:

March, 1994 Engineering Work Request tltsurry Monthly Operating Report No. 94-03 Page 18 of 25 03-19-94 Engineering Work Request 88-476 assessed the spiking of instrumentation in the Nuclear Instrumentation system (NIS) cabinets and removed line conditioning transformers that had failed. It was determined that the power coming from the

• Uninterruptible Power Supply system was sufficiently*clean as a source of power to the NIS System. Only one channel of NIS was altered at a time. Therefore, an unreviewed safety . question did not exist. Temporary Modification (Safety Evaluation No.94-079) 03-21-94 Temporary Modification (TM) S1-94-28 installed an electrical jumper to maintain power to certain Unit 1 Reactor Protection (RP) System Train "B" circuits during the replacement of relay AST1-XB. The activity was performed while Unit 1 was below 350 °F/450 psig and did not affect RP System train "A". The TM did not impact the operation of the Residual Heat Removal or other systems. Double verification of jumper installation/removal and post-maintenance testing was performed.

Therefore, an unreviewed safety question did not exist. Temporary Modification (Safety Evaluation No.94-080) 03-22-94 Temporary Modification S1-94-29 installed electrical jumpers to maintain power to certain Unit 1 Reactor Protection System (RPS) Train "A" circuits during the replacement of RPS relay SV3XA. The activity was performed while Unit 1 was subcritical with all contrql rods inserted.

The operation of RPS Train "B" and other systems was not affected.

Double verification of jumper installation/removal and post-maintenance testing was performed.

Therefore, an unreviewed safety question did not exist. Design Change Package (Safety Evaluation No.93-165) 03-22-94 Design Change Package 93-036-1 replaced carbon steel piping with moly piping to mitigate flow accelerated corrosion.

Piping was replaced in the Main Steam Trap Discharge Header, the Secondary Plant Drain system and the Condensate system. This material replacement did not result in any changes to the system form, fit, function, or operation.

Therefore, an unreviewed safety question did not exist.

TM S1-94-30 DCP 91-027-3 SE 94-082 FACILITY CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTH/YEAR:

March, 1994 Temporary Modification (Safety Evaluation No.94-081) &urry Monthly Operating Report No. 94-03 Page 19 of 25 03-23-94 Temporary Modification S1-94-30 installed electrical jumpers to maintain power to certain Unit 1 Reactor Protection System (RPS) Train "B" circuits during the *

• replacement of RPS relay SRB-XB. The activity was performed while Unit 1 was at hot shutdown with the reactor trip breakers open. The operation of RPS Train "A" and other systems was not affected.

Double verification of jumper installation/removal and post-maintenance testing was performed.

Therefore, an unreviewed safety question did not exist. Design Change Package (Safety Evaluation No.93-060) 03-24-94 Design Change Package 91-027-3 modified the closed loop seal cooling circuit for the Low Head Safety Injection (LHSI) and Outside Recirculating Spray (ORS) Pumps. The modification included the replacement of the seal cooling coils with new seal coolers and the addition of isolation valves at the seal and cooler. This change eliminated the venting and filling difficulties with the LHSI and ORS pump seal cooling circuits which caused seal head tank low level alarms. The design of the new seal coolers and its cooling circuit meet the trequirements of ASM E Section VIII for design basis accident conditions to a rating of 170 psig/250° F which is consistent with the LHSI and ORS pump seal cooling circuits.

Therefore, an unreviewed safety question does not exist. Safety Evaluation 03-28-94 Safety Evaluation 94-082 was performed to assess a re-analysis of the Large Break Loss of Coolant Accident (LBLOCA) that used Westinghouse's ECCS Evaluation Model, denoted as the 1981 Model with BASH (computer code). The evaluation concluded that the analysis parameters were equivalent to, or conservative with respect to, those allowed by the Technical Specifications, and that the LBLOCA meets the requirements of 1 O CFR 50.46. Therefore, an unreviewed safety question does not exist.

1-0P-Sl-002 O-MOP-SW-010 O-MOP-SW-011 O-EPM-0105-01

&urry Monthly Operating Report No. 94-03 Page 20 of 25 PROCEDURE OR METHOD OF OPERATION CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTH/YEAR:

March, 1994 Operating Procedure (Safety Evaluation No.94-057) 03-06-94 Operating Procedure 1-0P-Sl-002, "Safety Injection Accumulators", was temporarily changed to provide instructions for installing a temporary mechanical jumper to permit the Unit 1 refueling water storage tank recirculation pumps to be used to fill the Safety Injection (SI) System accumulators while the SI hydro pump is out of service. The mechanical jumper was installed when the Unit was at cold/refueling shutdown and the SI System was not required.

The jumper was rated for the pressure of the associated piping flow path, inspected for leakage after it was placed in service, and removed before the Unit left cold shutdown.

Therefore, an unreviewed safety question did not exist. Maintenance Operating Procedures (Safety Evaluation No.94-061) 03-07-94 Maintenance Operating Procedures O-MOP-SW-010, "Removal From Service of the Unit 1 Service Water Supply Header and O-MOP-SW-011, "Return to Service of the Unit 1 Service Water Supply Header" were developed to provide instructions for removing the Service Water Supply Header from service (and returning it to service) to permit the replacement of degraded equipment.

Any blank flanges used during the performance of these procedures will meet the criteria for the piping class for which they are installed and a leak test will be performed to verify the adequacy of the installation.

These procedures will be performed within the Limiting Conditions for Operation as defined by the Technical Specifications.

Therefore, an unreviewed safety question does not exist. Electrical Preventive Maintenance Procedure (Safety Evaluation No.94-067) 03-11-94 Electrical Preventive Maintenance Procedure O-EPM-0105-01 , "Appendix R EL T Eight Hour Duration Test" was developed to provide instructions for conducting performance discharge tests for emergency lighting, replacing lamp heads, and performing minor cleaning.

This procedure may be implemented while the units are at power and will be performed for only one fire area at a time. Battery powered lanterns are provided in the Appendix R cabinet for use by Operations personnel during the test and for the 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> post test period in which the emergency lighting batteries are being recharged.

This activity will not affect the probability of occurrence or the consequences of any previously analyzed accidents.

Therefore, an unreviewed safety question does not exist.

1-IPT-RP-TM-001 2-IPT-RP-TM-001 1-PT-8.2 -Surry Monthly Operating Report No. 94-03 Page 21 of 25 PROCEDURE OR METHOD OF OPERATION CHANGES THAT DID NOT REQUIRE NRC* APPROVAL MONTH/YEAR:

March, 1994 Instrument Periodic Test Procedures (Safety Evaluation No.94-077) 03-17-94 Instrument Periodic Test Procedures 1/2-IPT-RP-TM-001, "Turbine Trip Signal to Reactor Protection System Functional Test" were developed to provide instructions for installing electrical jumpers to permit testing of the turbine trip signal to the Reactor Protection System.

• The procedures will be performed on only one channel of the circuitry at a time and at less than 10% reactor power, thereby preventing a spurious reactor trip. The installation and removal of the electrical jumpers will be independently verified.

Therefore, an unreviewed safety question does not exist. Instrumentation Periodic Test Procedure (Safety Evaluation No.93-075, Revision 1) 03-18-94 Periodic Test procedure 1-PT-8.2, "Reactor Protection Logic," was temporarily changed to provide instructions for testing the Station service bus undervoltage automatic start signal for the Turbine-Driven Auxiliary Feedwater Pump (TDAFWP) and the steam generator low-low level TDAFWP trip signal. The procedure included administrative control steps for the steam generator (SG) blowdown permissive key switches to ensure proper operation of the SG blowdown trip valves during the performance of the procedure.

During the performance of this test, the SG blowdown permissive key switches were placed under administrative control when in the permissive mode. The procedural steps directed an operator to place the key switches in the normal position in the event of an Auxiliary Feedwater System automatic start signal. This action ensured the operability of the SG blowdown trip valves. Therefore, an unreviewed safety question did not exist.

&urry Monthly Operating Report No. 94-03 Page 22 of 25 TESTS AND EXPERIMENTS THAT DID NOT REQUIRE NRC APPROVAL MONTH/YEAR:

March, 1994 None During the Reporting Period Primary Coolant Analysis Gross Radioactivity, µCi/ml Susoended Solids, oom Gross Tritium, µCi/ml 1131, µCi/ml 113111133 Hydroaen, cc/ka Lithium, oom Boron -1 o, oom* Oxvaen, (DO), oom Chloride, oom pH at 25 degree Celsius Boron -1 O = Total Boron x 0.196 Comments:

None CHEMISTRY REPORT MONTH/YEAR:

March, 1994 Unit No. 1 Max. Min. Ava. 2.81 E-1 2.03E-4 3.01 E-2 0.150 < 0.01 0.050 9.73E-3 5.40E-3 7.57E-3 2.53E-4 3.61E-5 1.04E-4 ---36.8 4.9 22.0 3.48 < 0.1 2.34 481.0 . 229.3 400.3 6.0 0.005 2.48 0.050 0.001 0.005 6.29 4.42 4.91 -Surry Monthly Operating Report No. 94-03 Page 23 of 25 Unit No. 2 Max. Min. Ava. 2.19E-1 1.15E-1 1.56E-1 < 0.1 < o.*1 < 0.1 6.95E-1 6.49E-1 6.72E-1 2.71 E-4 4.62E-5 7.90E-5 0.09 0.05 0.07 43.0 35.0 38.4 2.31 2.06 2.19 174.6 159.3 167.5 0.005 0.005 0.005 0.050 0.002 0.008 6.57 6.19 6.44 New or Spent Fuel Shipment Date Stored or Number Received FUEL HANDLING UNITS 1 & 2 MONTH/YEAR:

March, 1994 Number of Assemblies per Shipment Assembly Number ANSI Number &urry Monthly Operating Report No. 94-03 Page 24of 25 Initial Enrichment New or Spent Fuel Shipping Cask Activity No Fuel Received or Stored During the Reporting Period.

e &urry Monthly Operating Report No. 94-03 Page 25 of 25 DESCRIPTION OF PERIODIC TEST(S) WHICH WERE NOT COMPLETIED WITHIN THE TIME LIMITS SPECIFIED IN TECHNICAL SPECIFICATIONS MONTH/YEAR:

March, 1994 None During the Reporting Period.