ML18153C972

Monthly Operating Repts for Mar 1992 for Surry Power Station,Units 1 & 2.W/920415 Ltr

ML18153C972
Person / Time
Site:	Surry
Issue date:	03/31/1992
From:	Mason D, Stewart W VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
92-274, NUDOCS 9204210006
Download: ML18153C972 (28)

Text

. . -*

e e VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND, VIRGINIA 23261 April 15, 1992 U. S. Nuclear Regulatory Commission Serial No.92-274 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 March 1992.

~\\ry trul~urs,

\~~~

W. L. Stewart Senior Vice President - Nuclear Enclosure cc: U. S. Nuclear Regulatory Commission Region II 101 Marietta Street, N. W.

Suite 2900 Atlanta, Georgia 30323 Mr. M. W. Branch NRG Senior Resident Inspector Surry Power Station 9204210006.920331 PDR ADOCK 05000280 R PDR

VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION MONTHLY OPERATING REPORT REPORT NO. 92-03 Approved:

~~{;;ag{!L- 'r .. .,_

Date

e Surry Monthly Operating Report No. 92-03 Page 2 of 27 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. .............................................. : .................*............. 10 Procedure or Method of Operation Changes That Did Not Require NRC Approval ........................................... 20 Tests and Experiments That Did Not Require NRC Approval ..........*........................................................... 24 Chemistry Report ..............................**.....................*......*...............................*................................ 25 Fuel Handling - Unit No. 1 .........*...........................................*............................................................. 26 Fuel Handling - Unit No. 2 ..............*..................*.*..................*............................................................ 26 Description of Periodic Test(s) Which Were Not Completed Within the Time Limits Specified in Technical Specifications .......................................................**.......................................... 27

e Surry Monthly Operating Report No. 92-03 Page 3 of 27 OPERATING DATA REPORT Docket No.: 50-280 Date: 04-07-92 Completed By: D. Mason Telephone: (804) 365-2459

1. Unit Name: .............................*.............*....... Surry Unit 1

2. Reporting Period: ......................................... . March 1992

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):

1 O. Reasons For Restrictions, If Any:

This Month YTD Cumulative

11. Hours In Reporting .................................... 744.0 2184.0 168960.0

12. Number of Hours Reactor Was Critical .......... 0.0 1288.0 109522.2

13. Reactor Reserve Shutdown Hours ............... 0.0 0.0 3774.5

14. Hours Generator On-Line ........................... 0.0 1271.8 107512.0

15. Unit Reserve Shutdown Hours..................... 0.0 0.0 3736.2

16. Gross Thermal Energy Generated (MWH) ...... 0.0 2727607.2 249844283.9

17. Gross Electrical Er:,ergy Generated (MWH) .... 0.0 919665.0 81434853.0

18. Net Electrical Energy Generated (MWH) ........ 0.0 871153.0 77245219.0

19. Unit Service Factor ................................... 0.0% 58.2% 63.6%

20. Unit Availability Factor............................... 0.0% 58.2% 65.8%

21. Unit Capacity Factor (Using MDC Net) ........... 0.0% 51.1% 59.0%

22. Unit Capacity Factor (Using DER Net) ........... 0.0% 50.6% 58.0%

23. Unit Forced Outage Rate ............................ 0.0% 11.6% 19.2%

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

Refueling - February 29, 1992, 64 days.

25. If Shut Down at End of Report Period Estimated Date of Start-up: May 3, 1992

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

FORECAST ACHIEVED INITIAL CRITICALITY INITIAL ELECTRICITY COMMERCIAL OPERATION

e Surry Monthly Operating Report No. 92-03 Page 4of27 OPERATING DATA REPORT Docket No.: 50-281 Date: 04-07-92 Completed By: D. Mason Telephone: (804) 365-2459

1. Unit Name: ......................*............................ Surry Unit 2

2. Reporting Period: ................*......................... March 1992

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 .............*...................... 744.0 2184.0 165840.0

12. Number of Hours Reactor Was Critical. ........ . 744.0 2184.0 107392.1

13. Reactor Reserve Shutdown Hours ..*............ 0.0 0.0 328.1

14. Hours Generator On-Line .......................... . 744.0 2184.0 105644.9

15. Unit Reserve Shutdown Hours.................... . 0.0 0.0 0.0

16. Gross Thermal Energy Generated (MWH) ..... . 1815008.4 5266132.2 246144814.3

17. Gross Electrical Energy Generated (MWH) ... . 607215.0 1762860.0 80196709.0

18. Net Electrical Energy Generated (MWH) ....... . 578197.0 1678110.0 76042048.0

19. Unit Service Factor .................................. . 100.0% 100.0% 63.7%

20. Unit Availability Factor .............................. . 100.0% 100.0% 63.7%

21. Unit Capacity Factor (Using MDC Net).......... . 99.5% 98.4% 58.8%

22. Unit Capacity Factor (Using DER Net) ......... .. 98.6% 97.5% 58.2%

23. Unit Forced Outage Rate ........................... . 0.0% 0.0% 15.1%

24. Shutdowns Schedule 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. 92-03 Page5of 27 UNIT SHUTDOWN AND POWER REDUCTION (EQUAL To OR GREATER THAN 20%)

REPORT MONTH: March 1992 Docket No.: 50-280 Unit Name: Surry Unit 1 Date: 04-07-92 Completed by: Anthony Xenakis Telephone: (804) 365-2145 (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 this 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. 92-03 Page 6of 27 UNIT SHUTDOWN AND POWER REDUCTION (EQUAL To OR GREATER THAN 20%)

REPORT MONTH: March 1992 Docket No.: 50-281 Unit Name: Surry Unit 2 Date: 04-07-92 Completed by: Anthony Xenakis Telephone: (804) 365-2145 (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 this 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. 92-03 Page 7of 27 AVERAGE DAILY UNIT POWER LEVEL Docket No.: 50-280 Unit Name: Surry Unit 1 Date: 04-07-92 Completed by: M.A. Negron Telephone: (804) 365-2795 Month: March 1992 Average Daily Power Level Average Daily Power Level Day (MWe-Net) Day (MWe-Net) 1 0.0 17 0.0 2 0.0 18 0.0 3 0.0 19 0.0

.. 4 0.0 20 0.0 5 0.0 21 0.0 6 0.0 22 0.0 7 0.0 23 0.0 8 0.0 24 0.0 9 0.0 25 0.0 10 0.0 26 0.0 11 0.0 27 0.0 12 0.0 28 0.0 13 0.0 29 0.0 14 0.0 30 0.0 15 0.0 31 0.0 16 0.0 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.

I I

e Surry Monthly Operating Report No. 92-03 Page 8 of 27 AVERAGE DAILY UNIT POWER LEVEL Docket No.: 50-281 Unit Name: Surry Unit 2 Date: 04-07-92 Completed by: M.A. Negron Telephone: (804) 365-2795 Month: March 1992 Average Daily Power Level Average Daily Power Level Day (MWe-Net) Day (MWe- Net) 1 778 17 778 2 777 18 777 3 776 19 778 4 .. *- 779 20 777 5 779 21 776 6 779 22 779 7 779 23 778 8 779 24 779 9 778 25 779 10 778 26 779 11 778 27 776 12 778 28 762 13 777 29 775 14 778 30 775 15 779 31 775 16 777 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. 92-03 Page 9 of 27

SUMMARY

OF OPERATING EXPERIENCE MONTH/VEAR: March 1992 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 03-01-92 0000 This reporting period started with the Unit at Hot Shutdown (HSD) for a scheduled 64 day Refueling Outage.

03-31-92 2400 This reporting period ended with the Unit in Refueling Shutdown (RSD) and no fuel in the reactor vessel.

UNIT TWO

- *oooo *This reporting period started with the Unit operating at 100% power, 820 MWe.

03-31-92 2400 This reporting period ended with the Unit operating at 100% power, 815 MWe.

e Surry Monthly Operating Report No. 92-03 Page 10 of 27 FACILITY CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTH/YEAR: March 1992 FS 90-63 UFSAR Change 02-20-92 (Safety Evaluation 92-027 A)

The Updated Final Safety Analysis Report (UFSAR) Section 9.1.3.1, "[Chemical And Volume Control System] Availability And Reliability" was revised to correctly identify the charging pump power supply.

The change is administrative/editorial in nature. No physical modifications are involved. Therefore an unreviewed safety question is not created.

DR S-92-0158 Deviation Report 03-02-92 (Safety Evaluation No.92-037)

A Safety Evaluation was performed to evaluate Deviation Report S-92-0158 concerning the operating practice of maintaining the residual heat removal

--.(RHR) system letdown isolation valves, 1-RH-HCV-1142 and 2-RH-HCV-2142 up to 20% open or fully closed during plant operation when the RHR system is not in service.

Operation of the subject valves up to 20% open allows letdown pressure to be maintained on the RHR system such that the system is assured to remain full.

This reduces the amount of operator action required to place the system in service. Operation with these valves fully closed allows isolation of the RHR system to quantify leakage, verify boundary valve integrity and provide operating flexibility.

An evaluation of these operating configurations determined that adequate system overpressure protection exists to prevent an impact on the consequences or probability of a loss of cooling accident and that dilution possibilities are limited to system thermal expansion or boundary valve leakage, both of which are bounded by the existing dilution analysis. Therefore, an unreviewed safety question is not created.

SE 92-039 Safety Evaluatlon 03-02-92 This Safety Evaluation was performed to evaluate the 1992 Unit 1 refueling outage plan. This plan was developed with the intent of eliminating situations that could increase the probability of accidents or equipment malfunctions.

To ensure compliance with Technical Specification requirements for equipment operability/availability while in the cold/refueling shutdown modes, the Minimum Equipment Lists will be verified by each shift's Senior Reactor Operator. In addition the Shift Technical Advisor will perform a daily equipment status assessment utilizing the Cold Shutdown/Refueling Shutdown Critical Parameters and the Shutdown Safety Assessment processes.

This evaluation concluded, based on a review of station procedures, policies, and the performance of the assessments described above, that the outage plan will ensure that the outage activities will be accomplished in a safe manner.

Therefore, an unreviewed safety question is not created.

e Surry Monthly Operating Report No. 92-03 Page 11 of 27 FACILITY CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTH/YEAR: March 1992

[continued]

TSR 92-006 Temporary Shielding Requests 03-02-92 TSR 92-007 (Safety Evaluation 92-0~0)

TSR 92-013 TSR 92-024 These Temporary Shielding Requests install temporary lead shielding on TSR 92-025 pressurizer spray and pressurizer safety valve lines in the Unit 1 containment TSR 92-026 to reduce the radiation dose received by personnel while performing work in the area.

Installation of the shielding while the subject lines remain "operable" was determined to be acceptable through the performance of a seismic piping analysis, but the operating conditions will not be allowed to exceed 385 psi or 140° F. The shielding will not adversely affect the design functions of the affected system and will be removed prior to exceeding the specified operating conditions. Therefore an unreviewed safety question is not created.

FS 87-52 UFSAR Change 03-03-92 (Safety Evaluation 92-043)

The Updated Final Safety Analysis Report (UFSAR) Section 7.7.2, "[Operating Control Stations] System Description" and Section 9.10, "Fire Protection" were revised to reference the total fire protection program.

This change implements NRC recommendations contained in Generic Letter 86-10, Section F. The change is administrative in nature. No technical requirements are changed and no physical modifications are involved.

Therefore an unreviewed safety question is not created.

DR S-91-1552 Deviation Report 03-05-92 (Safety Evaluation No.92-047)

A Safety Evaluation was performed to evaluate Deviation Report S-91-1552 concerning installed instrument root valves for safety injection (SI) flow elements 1-SI-FE-1940 and 1-SI-FE-1943 as being A105 carbon steel, rather than stainless steel as required in the Updated Final Safety Analysis Report and NUS 20 class 1503 components.

An evaluation of this condition concluded that the A105 valve material exceeds the pressure and temperature ratings of the stainless steel valve material and is acceptable for the SI system pressure and temperature design conditions. It was also determined that the valve's limited exposure to system fluid (valve back leakage) did not pose a significant corrosion concern and thus, would not affect valve performance. Therefore, an unreviewed safety question is not created.

FACILITY CHANGES THAT DID NOT REQUIRE NRC APPROVAL

• Surry Monthly Operating Report No. 92-03 Page 12of 27 MONTH/YEAR: March 1992

[continued]

SE 92-050 Safety Evaluation 03-05-92 This Safety Evaluation was performed to evaluate the installation of a temporary suction tank for the recirculating spray heat exchanger (RSHX) service water (SW) radiation monitor pump 1-SW-P-5C during the performance of Special Test 1-ST-299, "Recirculating Spray Heat Exchangers Service Water Flow Test".

This temporary modification will be evaluated for improvement of the self-priming .for the RSHX SW radiation monitor pumps to ensure a reliable SW sample is pumped to the radiation monitors. The modification will be in place only while Unit 1 is at cold/refueling shutdown. Therefore, because this system is not required to be operable during cold/refueling shutdown, an unreviewed safety question is not created.

TSR 92-004 Temporary Shielding Request 03-05-92 TSR 92-022 (Safety Evaluation 92-052)

These Temporary Shielding Requests install temporary lead shielding on residual heat removal (RHR) system lines in the vicinity of the RHR pumps to reduce the radiation dose received by personnel while performing work in the area.

Installation of the shielding while the subject lines remain operable was determined to be acceptable through the performance of a seismic piping analysis. Installation of additional shielding (per TSR 92-022) while the RHR system is not in service was determined to be acceptable through the performance of a deadweight analysis. The additional shielding will be removed prior to returning the RHR system to service. The remaining shielding will be removed prior to leaving cold shutdown. Therefore an unreviewed safety question is not created.

DCP 87-015-1 Design Change Package 03-06-92 This Design Change Package DCP replaced the Unit 1 fuel transfer system underwater air motor and chain drive system with a cable drive system.

This modification improved the reliability of the fuel transfer system and did not adversely affect-the system design basis. Function of the system remains unchanged. Therefore an unreviewed safety question is not created.

e e Surry Monthly Operating Report No. 92-03 Page 13 of 27 FACILITY CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTH/YEAR: March 1992

[continued]

TM S1-92-10 Temporary Modification 03-08-92 TM S1-92-11 (Safety Evaluation No.92-053)

These Temporary Modifications (TMs) block open Unit 1 pressurizer power operated relief valves (PORVs) to ensure the reactor vessel is protected from potential pressure transients which could exceed the limits of 10 CFR 50 Appendix G when the reactor coolant system (RCS) is s. 350 ° F and the vessel head is bolted on.

This TM, which is required by applicable operating procedures, will be in place when the Unit is at refueling shutdown and the RCS loops are isolated and drained. The reactor coolant pumps will be tagged out and charging pump usage will be strictly controlled. Therefore, an unreviewed safety question is not created.

FS 87-38 UFSAR Change 03-10-92 (Safety Evaluation 92-056)

The Updated Final Safety Analysis Report (UFSAR) Section 10.3.1.1, "[Main Steam System] Design Basis" was revised to remove wording that states that the steam bypasses continually admit steam to the turbine-driven auxiliary feedwater (TDAFW) pump.

The current operating practice does not admit steam to the TDAFW pump without rotor movement. This practice is in accordance with the manufacturer's recommendations and prevents nonuniform heating of the rotor which could result in thermal shaft bow. This UFSAR change reflects current practice and does not involve physical modifications to the plant. Therefore an unreviewed safety question is not created.

FS 90-38 UFSAR Change 03-1 0-92 (Safety Evaluation 92-055)

The Updated Final Safety Analysis Report (UFSAR) Section 14.2.11, "Loss Of Normal Feedwater" was revised to clarify the signals which result in an automatic start of two motor-driven auxiliary feedwater pumps and to correctly describe the signals which result in an automatic start of the turbine-driven auxiliary feedwater pump.

This change does not affect plant equipment, procedures, or the loss of feedwater accident analysis. Therefore an unreviewed safety question is not created.

FACILITY CHANGES THAT DID NOT REQUIRE NRC APPROVAL

• Surry Monthly Operating Report No. 92-03 Page 14of 27 MONTH/YEAR: March 1992

[continued]

TM S2-92-02 Temporary Modification 03-10-92 (Safety Evaluation No.92-057)

This Temporary Modification (TM) installs a new electronic diaphragm-type blowdown system controller to permit field testing for several weeks.

This TM does not affect safety-related equipment and does not change the blowdown system design basis. An evaluation of potential accidents associated with the blowdown system concluded that the accident analyses remain bounding. Therefore, an unreviewed safety question is not created.

TM S1-92-08 Temporary Modification 03-10-92 (Safety Evaluation No.92-054)

This Temporary Modification (TM) installs temporary hoses from the chilled water (CD) system to an ion exchange filter skid. The ion exchanger will clean-up chilled water supplied to the air compressor aftercooler utilized for 10 CFR 50, Appendix J, Type A Unit 1 containment pressure testing. The modification will minimize the potential for contamination of the compressor and aftercooler. The chilled water is slightly contaminated and located within the plant's radiological controlled area (RCA).

Following installation of the TM, the chilled water system will be checked for leaks to minimize the potential for a spill of potentially contaminated fluid.

Precautions will also be taken to minimize the consequences of such a spill. The TM will be installed while the Unit is at cold shutdown and will be removed prior to the chilled water system being used to cool the refueling water storage tank water. Therefore, an unreviewed safety question is not created.

SE 92-058 Safety Evaluation 03-12-92 This Safety Evaluation was performed to evaluate the impact to plant safety with the vertical channel of one containment accelerometer inoperable until it is replaced during the 1992 Unit 1 refueling outage.

The seismic monitoring system consists of three accelerometers for sensing seismic motion. Each accelerometer has a set of triaxial transducers to monitor seismic accelerations in two horizontal directions and one vertical direction. The horizontal acceleration of a seismic event will indicate the most severe impact to plant design and operation. Thus, it was concluded that one inoperable vertical channel will not adversely impact safe plant operation since the horizontal accelerometers and two of the three vertical accelerometers function properly, enabling the seismic monitoring system to adequately evaluate a seismic event. Therefore, an unreviewed safety question is not created.

FACILITY CHANGES THAT DID NOT REQUIRE NRC APPROVAL

• Surry Monthly Operating Report No. 92-03 Page 15 of 27 MONTH/YEAR: March 1992

[continued)

SE 92-059 Safety E.valuatlon 03-12-92 This Safety Evaluation was performed to evaluate the Unit 1 Cycle 11 reload core, including the addition of skirts to the bottom periphery of the bottom nozzle plate of the new fuel assemblies and the incorporation of anti-snag features into the fuel assembly lnconnel grids.

Parameters affected by the reload have been calculated and compared to the existing safety analysis assumptions. These parameters have been shown to be either 1) explicitly bounded, or 2) accommodated by existing safety analysis margin 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 is not created.

TM S1-92-12 Temporary Modification 03-12-92 (Safety Evaluation No.92-061)

This Temporary Modification (TM) routes temporary teledose and communication cables through a spare Unit 1 containment pipe penetration to support the resistance temperature device elimination project.

This TM will be in place only while the unit is at cold shutdown and the penetration will be restored to its design configuration prior to unit startup.

The containment will be at a slightly subatmospheric pressure and a foam material will be installed (on both ends of the penetration) to prevent an out-leakage of air. Therefore, an unreviewed safety question is not created.

TSR 92-042 Temporary Shleldlng Request 03-12-92 (Safety Evaluation 92-060)

This Temporary Shielding Request installs temporary lead shielding on a charging system line in the Unit 1 charging pump cubicle "B" to reduce the radiation dose received by personnel while performing work in the area.

Installation of the shielding while the subject line remains operable was determined to be acceptable through the performance of a seismic piping analysis. The shielding will not adversely affect the design functions of the affected system and will be removed when work in the area is complete.

Therefore an unreviewed safety question is not created.

FACILITY CHANGES THAT DID NOT REQUIRE NRC APPROVAL

• Surry Monthly Operating Report No. 92-03 Page 16 of 27 MONTH/YEAR: March 1992

[continued]

TM S1-92-06 Temporary Mod lflcatlon 03-13-92 (Safety Evaluation No.92-062)

This Temporary Modification (TM) removes the internals from the spent fuel pool purification pump 1-FC-P-3A discharge check valve 1-FC-45 to allow the use of a portable clean-up ion exchanger.

This TM does not affect the operational or design intent of the spent fuel cooling system. The applicable operating procedures have been changed appropriately to support this TM by maintaining the pump discharge valve closed whenever the opposite pump is in service. Therefore, an unreviewed safety question is not created.

TM S1-92-13 Temporary Modification 03-14-92 (Safety Evaluation No.92-063)

This Temporary Modification (TM) installs sound powered phones using a spare Unit 1 containment penetration (120) to establish communications between the control room and the reactor cavity during refueling operations.

Containment penetration 120 is primarily used by the loose parts monitoring system which is not used when the unit is at cold shutdown. This portion of the containment pressure boundary (comprised by penetration 120) will not be breached at any time and will be restored to its normal functions following refueling operations. Therefore, an unreviewed safety question is not created.

FS 88-03 UFSAR Changes 03-17-92 FS 88-04 (Safety Evaluation 92-067)

The Updated Final Safety Analysis Report (UFSAR) Section 5.3.1.3.2, "Control-Rod Drive Mechanisms" and Table 5.3.1, "Principal Component Data -

Containment Systems" were revised to correctly reflect the operation of the control rod drive mechanism cooling system.

These changes do not affect plant operation or safety. No physical changes to the station were made. Therefore an unreviewed safety question is not created.

FS 88-07 UFSAR Change 03-17-92 (Safety Evaluation 92-066)

The Updated Final Safety Analysis Report (UFSAR) Section 7.2.2.2.12, "Turbine Trip Reactor Trip" was revised to provide a complete listing of turbine trip signals.

This change reflects the actual installed configuration of the plant and involves no modifications to circuitry or plant operations. Therefore an unreviewed safety question is not created.

e

• Surry Monthly Operating Report No. 92-03 Page 17 of 27 FACILITY CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTH/YEAR: March 1992

[continued)

TM S1-92-14 Temporary Modification 03-17-92 (Safety Evaluation No.92-068)

This Temporary Modification (TM) installs a piping jumper from the domestic water system to the central chilled water system as a source of make up water while the bearing cooling water system is out of service for maintenance.

This TM will not impact safety-related systems. The cross connect capability between the nonsafety-related central chillers and the safety-related chillers is presently isolated (a continuous fire watch is posted) and is not considered in the accident analyses. Therefore, an unreviewed safety question is not created .

DCP 89-008-3 . Design Change Package 03-19-92 This Design Change Package DCP replaced the swing check valves in the Units 1 and 2 reactor coolant pump (RCP) thermal barrier component cooling (CC) water supply piping with two safety related piston type check valves. The CC nonsafety-related thermal relief valves (1/2-CC-RV-116/21 SA, B, C) were also replaced with safety-related relief valves.

This modification provides redundant check valves which have a more positive seating design and reduces the likelihood of leakage of reactor coolant into the low pressure CC water piping in the event of a thermal barrier leak. The affected piping was also upgraded to meet safety-related and seismic criteria.

Therefore an unreviewed safety question is not created.

TM S1-92-15 Temporary Modification 03-24-92 (Safety Evaluation No.92-072)

This Temporary Modification (TM) lifts leads at the emergency diesel generator number 3 (EOG 3) junction box, rendering the EOG 1 throwover switch inoperable.

• This TM will enable an evaluation of the operability of EDGs 1 and 3 with the throwover switch inoperable. The normal 125 volt DC systems for EDGs 1 and 3 will be unaffected by this TM and each EOG will remain operable. Therefore, an unreviewed safety question is not created.

FACILITY CHANGES THAT DID NOT REQUIRE NRC APPROVAL

• Surry Monthly Operating Report No. 92-03 Page 18 of 27 MONTH/YEAR: March 1992

[continued]

TSR 92-023 Temporary Shielding Request 03-25-92 (Safety Evaluation 92-072A)

This Temporary Shielding Request installs temporary lead shielding on a reactor purification system line in the Unit 1 auxiliary building to reduce the radiation dose received by personnel while performing work in the area.

Installation of the shielding while the subject line remains operable was determined to be acceptable through the performance of a seismic piping analysis. The shielding will not adversely affect the design functions of the affected system and will be removed prior to leaving cold shutdown. Therefore an unreviewed safety question is not created.

DR S-91-1936 Deviation Report 03-26-92 (Safety Evaluation No.92-074)

This Safety Evaluation was performed to evaluate Deviation Report S-91-1936 concerning the operation of the general auxiliary building ventilation system with the normal exhaust fans 1-VS-F-8A and 88 out of service, the ventilation supply units 1-HV-1A and 18 off, and the category II filter (1-VS-F-59) operating. This abnormal mode of operation is required while repairs are being made to the 1-VS-F-8A and 88 fan discharge dampers and expansion boots.

The evaluation of this operational configuration concluded that the auxiliary building central ventilation is not negatively affected by this mode of operation.

Therefore, an unreviewed safety question is not created.

FS 91-15 UFSAR Change 03-26-92 (Safety Evaluation 92-073)

The Updated Final Safety Analysis Report (UFSAR) Sections 5.1, "Containment System", 5.2, "Containment Isolation", 5.3, "Containment Systems", and 5.5, "Containment Tests And Inspections" were revised to reflect current plant configuration and operating practices for refueling, cold shutdown, and operating conditions.

These changes include additional administrative controls to further assure containment integrity, but do not modify plant or system operation. Therefore an unreviewed safety question is not created.

e Surry Monthly Operating Report No. 92-03 Page 19 of 27 FACILITY CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTH/YEAR: March 1992

[continued]

TM S1-92-16 Temporary Modification 03-29-92 (Safety Evaluation No. 92-074A)

This Temporary Modification (TM) installs two plugs and blocks the cross-tie capability between emergency condensate storage tank 1-CN-TK-1 and emergency condensate make-up tank 1-CN-TK-3 to allow the replacement of feedwater system valve 1-FW-276.

This TM will not affect the ability of the auxiliary feedwater (AFW) pumps to perform their intended function. Measures will also be taken (e.g. positive checks to ensure proper placement of the plugging devices) to ensure the Unit 1/2 cross-tie capability is maintained. Therefore, an unreviewed safety question is not created.

e e Surry Monthly Operating Report No. 92-03 Page 20 of 27 PROCEDURE OR METHOD OF OPERATION CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTH/YEAR: March 1992 ECM-1504 Electrlcal Corrective Maintenance Procedure 03-03-92 (Safety Evaluation No.92-044)

Electrical Corrective Maintenance Procedure ECM-1504, "MOV Seal-In Removal And Installation" was revised to provide instructions for the temporary removal of seal-in contacts for extraction steam system motor operated valves 1/2-ES-MOV-1/200, main steam system motor operated valves 1/2-MS-MOV-1/200A, B, C, D, and safety injection (SI) system motor operated valves 1/2-SI-MOV-1/2865A, B, C. This change allows the subject valves to be throttled and/or slowly opened and closed during startup and/or shutdown operations for improved secondary system control and to permit testing of the accumulator check valves, respectively.

The subject valves will be capable of fully opening or closing using the normal control switch, except that an operator must hold the control switch throughout the entire valve stroke. This manual operator action is not a replacement for an automatic function of the SI system valves since they are not assumed to be open when the RCS is < 1000 psig (a requirement of this procedure). The other valves are nonsafety-related and have no nuclear safety significant control functions. Therefore, an unreviewed safety question is not created.

1-MPT-1205-01 Mechanical Periodic Test Procedure 03-03-92 (Safety Evaluation No.92-045)

Unit 1 Mechanical Periodic Test Procedure 1-MPT-1205-01, "Containment Sump Setup For Inspection And Testing" was developed to provide instructions for relocating one of the Unit 1 containment sump pumps (1-DA-P-4A, 1-DA-P-

48) to the containment trough to permit the pumping of containment drains to the low level waste header while the containment sump is being inspected.

This procedure will be implemented while the Unit is at cold shutdown (CSD) and will not affect any safety-related system or component. In addition, these pumps are not required to mitigate an accident while the Unit is at CSD.

Therefore, an unreviewed safety question is not created.

e Surry Monthly Operating Report No. 92-03 Page 21 of 27 PROCEDURE OR METHOD OF OPERATION CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTH/YEAR: March 1992

[continued)

SU-C-DC0-807 Surry Swltchyard Procedure 03-03-92 (Safety Evaluation No.92-042)

Surry Switchyard Procedure SU-C-DC0-807, "Surry Switchyard Generator No. 1 230 KV Leads Relaying Upgrade" was developed to provide instructions for upgrading existing pilotwire relaying and impedance back-up relaying. This procedure also installs an additional relay to provide 100% back-up protection for the main transformer and generator No. 1, and an overcurrent relay to '

provide "zero voltage fault. protection should a breaker be closed on a set of grounds.

This procedure will be implemented with Unit 1 offline with the station service buses powered from the transfer buses and will not impact any safety-related systems or components. Therefore, an unreviewed safety question is not created.

1-0P-RC-004 Operating Procedure 03-04-92 (Safety Evaluation No.92-038)

Operating Procedure 1-0P-RC-004, "Draining The RCS To 5% Pressurizer Level (29.0 ft.)" was developed to provide instructions for implementing an alternate hydrogen peroxide addition method for crud burst treatment of the reactor coolant system (RCS).

The new procedure allows hydrogen peroxide addition under more manageable operating conditions (with the reactor coolant pumps operating and a bubble in the pressurizer). The procedure requires precautionary measures be taken to prevent an explosive mixture from forming in the RCS. These measures include: 1) verifying through sampling that the RCS has been degassed, 2) verifying that oxygen introduced remains s. 5 ppm during the entire evolution,

3) the duration, from the introduction of the hydrogen peroxide to the collapse of the pressurizer bubble, cannot exceed 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> and the pressurizer level cannot exceed 50% prior to the peak RCS activity, and 4) the volume control tank is on nitrogen with hydrogen isolated. Therefore, an unreviewed safety question is not created.

e e Surry Monthly Operating Report No. 92-03 Page 22of 27 PROCEDURE OR METHOD OF OPERATION CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTH/VEAR: March 1992

[continued]

O-ECM-0701-02 Electrlcal Corrective Maintenance Procedure 03-14-92 (Safety Evaluation No.92-064)

Electrical Corrective Maintenance Procedure O-ECM-0701-02, "Emergency Diesel Generator Pole Bolting Inspection And Replacement" was revised to provide instructions for rebalancing the emergency diesel generator No. 1 shaft, if needed, following the generator rotor pole bolting replacement.

This procedure will be implemented while Unit 1 is at cold shutdown. The activity will not affect the probability of occurrence or the consequences of any previously analyzed accidents. Therefore, an unreviewed safety question is .not created.

1-0P-RC-008 Operating Procedure 03-16-92 (Safety Evaluation No.92-065)

Unit 1 Operating Procedure 1-0P-RC-008, "Reactor Coolant Loop Fill And Opening Loop Stop Valves For Cold Shutdown Or Refueling Shutdown Operations" was developed to provide instructions for bypassing the loop stop valves interlocks to fill and drain the reactor coolant system (RCS) piping with Unit 1 at cold shutdown.

This procedure will be conducted in a slow, controlled manner to prevent rapid RCS level changes and will not adversely affect other systems. Source range nuclear instrumentation will be closely monitored during these evolutions and the loop boron concentration will be verified ~ RCS boron concentration.

Therefore, an unreviewed safety question is not created.

ARP 2A-G3 Annunciator Response Procedure 03-24-92 (Safety Evaluation No.92-071)

Unit 2 Annunciator Response Procedure ARP 2A-G3, "LHSI PP 1A SEAL HD TK LO LVL" was revised to provide additional guidance to use alternate methods to monitor for a failure of the low head safety injection (LHSI) pump "A" outer seal utilizing the vent vent radiation monitors. This change allows the continued operation of the LHSI pump "A" with a known inner seal leak which requires frequent seal head tank filling.

The pump's current inner seal leakage is not considered safety injection (SI) system external leakage and thus does not adversely impact the SI system external leakage Technical Specification limits. The pump's outer seal remains intact and will continue to be monitored through routine surveillance. The subject pump is considered fully operable and capable of performing its intended functions during an emergency safety features actuation. Therefore, an unreviewed safety question is not created.

-

• J

,* e Surry Monthly Operating Report No. 92-03 Page 23of 27 PROCEDURE OR METHOD OF OPERATION CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTH/YEAR: March 1992

[continued]

GMP-010 General Maintenance Procedure 03-24-92 (Safety Evaluation No.92-070)

General Maintenance Procedure GMP-010, "Removable Block Administrative Controls" was revised to provide instructions for the installation of missile (tornado generated) protection of underground Unit 1 auxiliary feedwater (AFW) lines which will be uncovered during the replacement of FW system valve 1-FW-276 The Unit 1 AFW lines will be excavated for a short period of time during which Unit 1 will be at cold shutdown and Unit 2 will be operating. The provision for temporary missile protection of the subject AFW lines will ensure the requirements for Unit 2 AFW cross-connect from Unit 1 are maintained.

Therefore, an unreviewed safety question is not created.

e Surry Monthly Operating Report No. 92-03 Page 24of 27 TESTS AND EXPERIMENTS THAT DID NOT REQUIRE NRC APPROVAL MONTH/YEAR: March 1992 None During This Reporting Period.

. ' \ e Surry Monthly Operating Report No. 92-03 Page 25 of 27 CHEMISTRY REPORT MONTH/YEAR: March 1992 Unit No. 1 Unit No. 2 Primary Coolant Analysis Max. Min. Avg. Max. Min. Ava.

Gross Radioact., uCi/ml 6.80E-1 1.78E-4 1.94E-2 2.15E-1 1.18E-1 1.77E-1 Susoended Solids, oom 0.0 0.0 0.0 0.0 0.0 0.0 Gross Tritium, µCi/ml --- --- --- 5.36E-1 4.29E-1 4.75E-1 1131, uCi/ml 6.91 E-4 5.53E-4 6.21 E-4 5.40E-4 1.99E-4 3.23E-4 1131 /1133 0.14 0.14 0.14 0.18 0.10 0.07 Hvdroaen, ccA<a 3.6 3.5 3.6 34.2 23.7 29.6 Lithium, oom 0.88 <0.1 0.03 2.35 2.05 2.19 Boron - 10, oom* 483.9 378.7 466.9 192.5 176.2 183.5 Oxyqen, (DO), oom 6.5 0.005 2.9 0.005 0.005 0.005 Chloride, oom 0.006 0.001 0.002 0.004 0.001 0.002 pH at 25 dearee Celsius 5.25 4.59 4.85 6.68 6.44 6.57

• Boron - 1O = Total Boron x 0.196 Comments:

Unit 1 in refueling during March.

~ . l e Surry Monthly Operating Report No. 92-03 Page2Sof 27 FUEL HANDLING UNITS 1 & 2 MONTH/YEAR: March 1992 New or Spent Number for 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 Stored or Received in March, 1992

... ,. l ,.. e e Surry Monthly Operating Report No. 92-03 Page 27of 27 DESCRIPTION OF PERIODIC TEST(S) WHICH WERE NOT COMPLETED WITHIN THE TIME LIMITS SPECIFIED IN TECHNICAL SPECIFICATIONS MONTH/YEAR: March 1992 None During This Reporting Period.