ML18152A333

Monthly Operating Repts for Mar 1993 for Surry Power Station,Units 1 & 2.W/930414 Ltr

ML18152A333
Person / Time
Site:	Surry
Issue date:	03/31/1993
From:	Bowling M, Mason D, Xenakis A VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
93-212, NUDOCS 9304190323
Download: ML18152A333 (27)

Text

e e VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND. VIRGINIA 23261 April 14, 1993 U. S. Nuclear Regulatory Commission Serial No.93-212 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 1993.

Very truly yours,

/IKIJ4 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. 93-03 Approved:

e Surry Monthly Operating Report No. 93-03 Page 2of 26 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 ........................................... 19 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 Specttications ................................................................................................... 26

e Surry Monthly Operating Report No. 93-03 Page 3of 26 OPERATING DATA REPORT Docket No.: 50-280 Date: 04-07-93 Completed By: D. Mason Telephone: (804) 365-2459

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

2. Reporting Period: ......................................... . March 1993

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 ......................... . 744.0 2160.0 177720.0

12. Number of Hours Reactor Was Critical. ........ . 744.0 2053.4 117428.4

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

14. Hours Generator On-Line .......................... . 744.0 2035.0 115310.4

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

16. Gross Thermal Energy Generated (MWH) ..... . 1604791.0 4733122.5 268352401.6

17. Gross Electrical Energy Generated (MWH) ... . 541650.0 1598920.0 87617173.0

18. Net Electrical Energy Generated (MWH) ....... . 514163.0 1519781.0 83117641.0

19. Unit Service Factor .................................. . 100.0% 94.2% 64.9%

20. Unit Availability Factor .............................. . 100.0% 94.2% 67.0%

21. Unit Capacity Factor (Using MDC Net) .......... . 88.5% 90.1% 60.3%

22. Unit Capacity Factor (Using DER Net) .......... . 87.7% 89.3% 59.4%

23. Unit Forced Outage Rate ........................... . 0.0% 5.8% 18.2%

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

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

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

FORECAST ACHIEVED INITIAL CRITICALITY INITIAL ELECTRICITY COMMERCIAL OPERATION

e Surry Monthly Operating Report No. 93-03 Page 4of 26 OPERATING DATA REPORT Docket No.: 50-281 Date: 04-07-93 Completed By: D. Mason Telephone: (804) 365-2459

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

2. Reporting Period: ......................................... . March 1993

3. Licensed Thermal Power (MWt): ...................... . 2441

4. Nameplate Rating (Gross MWe): ...................... . 847.5

5. Design Electrical Rating (Net MWe): ................. . 788

6. Maximum Dependable Capacity (Gross MWe): ... . 820

7. Maximum Dependable Capacity (Net MWe): ....... . 781

8. If Changes Occur in Capacity Ratings (Items Number 3 Through 7) Since Last Report, Give Reasons:

9. Power Level To Which Restricted, If Any (Net MWe):

10. Reasons For Restrictions, If Any:

This Month YTD Cumulative

11. Hours In Reporting Period .......................... 744.0 2160.0 174600.0

12. Number of Hours Reactor Was Critical. ......... 123.3 1539.3 115226.2

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

14. Hours Generator On-Line ........................... 123.0 1539.0 113470.0

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

16. Gross Thermal Energy Generated (MWH) ...... 235566.3 3529334.5 264860408.3

17. Gross Electrical Energy Generated (MWH) .... 79665.0 1183135.0 86379039.0

18. Net Electrical Energy Generated (MWH) ........ 75035.0 1122728.0 81913141.0

19. Unit Service Factor ................................... 16.5% 71.3% 65.0%

20. Unit Availability Factor ............................... 16.5% 71.3% 65.0%

21. Unit Capacity Factor (Using MDC Net)........... 12.9% 66.6% 60.2%

22. Unit Capacity Factor (Using DER Net) ........... 12.8% 66.0% 59.5%

23. Unit Forced Outage Rate ............................ 0.0% 0.0% 14.2%

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

Refueling - March 6, 1993, 60 days

25. If Shut Down at End of Report Period Estimated Date of Start-up: May 5, 1993

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

FORECAST ACHIEVED INITIAL CRITICALITY INITIAL ELECTRICITY COMMERCIAL OPERATION

e Surry Monthly Operating Report No. 93-03 Page 5of 26 UNIT SHUTDOWN AND POWER REDUCTION (EQUAL To OR GREATER THAN 20%)

REPORT MONTH: March 1993 Docket No.: 50-280 Unit Name: Surry Unit 1 Date: 04-07-93 Completed by: Anthony Xenakis Telephone: (804) 365-2145 (1) (2) (3) (4) (5)

Method Duration of LEA System Component Cause & Corrective Action to Date Type Hours Reason Shutting No. Code Code Prevent Recurrence Down Rx 930303 s 0 B 4 NIA SJ p Unit power was reduced to 61 %

to remove 1-FW-P-1 B from service to perform maintenance on one of its two motors.

930324 s 0 B 4 NIA SJ p Unit power was reduced to 60%

to remove 1-FW-P-1B from service to perform maintenance on one of its two motors.

(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 (LEA) File (NUREG 0161)

e Surry Monthly Operating Report No. 93-03 Page 6 of 26 UNIT SHUTDOWN AND POWER REDUCTION (EQUAL To OR GREATER THAN 20%)

REPORT MONTH: March 1993 Docket No.: 50-281 Unit Name: Surry Unit 2 Date: 04-07-93 Completed by: Anthony Xenakis Telephone: (804) 365-2145 (1) (2) (3) (4) (5)

Method Duration of LEA System Component Cause & Corrective Action to Date Type Hours Reason Shutting No. Code Code Prevent Recurrence Down Rx 930306 s 621 C NIA NIA NIA Unit shutdown for 60 day refueling outage.

(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 (LEA) File (NUREG 0161)

e Surry Monthly Operating Report No. 93-03 Page 7of 26 AVERAGE DAILY UNIT POWER LEVEL Docket No.: 50-280 Unit Name: Surry Unit 1 Date: 04-07-93 Completed by: P. M. Kessler Telephone: (804) 365-2790 Month: March 1993 Average Daily Power Level Average Daily Power Level Day (MWe-Net) Day (MWe- Net) 1 785 17 788 2 785 18 786 3 682 19 787 4 443 20 788 5 443 21 788 6 438 22 787 7 441 23 788 8 444 24 493 9 443 25 489 10 593 26 785 11 785 27 785 12 785 28 785 13 787 29 785 14 787 30 787 15 788 31 786 16 787 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.

- Surry Monthly Operating Report No. 93-03 Page 8 of 26 AVERAGE DAILY UNIT POWER LEVEL Docket No.: 50-281 Unit Name: Surry Unit 2 Date: 04-07-93 Completed by: P. M. Kessler Telephone: (804) 365-2790 Month: March 1993 Average Daily Power Level Average Daily Power Level Day (MWe- Net) Day (MWe- Net) 1 634 17 0 2 626 18 0 3 622 19 0 4 617 20 0 5 607 21 0 6 21 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 29 0 14 0 30 0 15 0 31 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.

- Surry Monthly Operating Report No. 93-03 Page 9of 26

SUMMARY

OF OPERATING EXPERIENCE MONTH/YEAR: March 1993 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 03-01-93 0000 This reporting period began with the Unit operating at 100% power, 820 MWe.

03-03-93 1508 Commenced ramp down to remove 1-FW-P-1 B from service for motor maintenance; 100%

power, 825 MWe.

1737 Stopped ramp; 61% power, 500 MWe.

03-10-93 1204 Started ramp up; 58% power, 475 MWe.

1635 Stopped ramp; 100% power, 820 MWe.

03-24-93 0042 Started ramp down for 1-FW-P-1 B motor maintenance; 100% power, 825 MWe.

0311 Stopped ramp; 60% power, 480 MWe.

03-25-93 2132 Started ramp up; 61 o/o power, 500 MWe.

03-26-93 0024 Stopped ramp; 100% power, 825 MWe.

03-31-93 2400 This reporting period ended with the Unit operating at 100% power, 825 MWe.

UNIT TWO 03-01-93 0000 This reporting period began with the Unit in a coastdown due to fuel depletion at 78.5%

power, 655 MWe.

03-05-93 2207 Commenced Unit shutdown for scheduled refueling outage; 78.5% power, 655 MWe.

03-06-93 0302 Unit off line.

0317 Reactor manually tripped in accordance with applicable Unit shut down procedure.

03-31-93 2400 This reporting period ended with the Unit in day 25 of a scheduled 60 day refueling outage.

e Surry Monthly Operating Report No. 93-03 Page 10of 26 FACILITY CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTH/YEAR: March 1993 SE 93-031 Safety Evaluation 02-23-93 Safety Evaluation 93-031 was performed to evaluate the 1993 Unit 2 refueling outage schedule.

The evaluation concluded that the refueling outage schedule is acceptable based on a review of the planning, procedures, policies, shutdown risk, and monitoring management that are performed for the outage. Therefore, an unreviewed safety question does not exist.

EWR 91-133 Engineering Work Request 03-03-93 (Safety Evaluation No.91-174)

Engineering Work Request 91-133 removed the internals from Unit 2

• condensate polishing (CP) system valve 2-CP-PCV-221 to allow air flow from air compressor 2-CP-C-1 to the CP air system.

This modification does not affect any safety-related equipment or design basis accident analyses. Therefore, an unreviewed safety question does not exist.

SE 93-038 Safety Evaluation 03-04-93 Safety Evaluation 93-038 was performed to assess the procedural requirements for the use of ladders, scaffolds, and manlifts provided in administrative procedure VPAP-1903, "Ladders, Scaffolds, and Man lifts." The evaluation also considered the causes and effects of potential ladder and scaffolding failures on plant personnel, systems and components.

It was concluded that temporary scaffolding erected in accordance with VPAP-1903 should not fail while in use, including during a design basis earthquake.

The procedure also provides requirements for the review and control of scaffolding erected in the vicinity of safe shutdown equipment to further minimize the potential risk associated with an earthquake. Therefore, an unreviewed safety question does not exist.

EWR 90-178 Engineering Work Request 03-05-93 Engineering Work Request 90-178 installed backflow preventers in the floor drains in each of the Unit 1 and 2 charging pump cubicles to prevent potential flooding of the areas through the floor drain system.

This modification affected only the floor drains which are not addressed by the Technical Specifications or the Safety Analysis Report. The change will help to assure charging pump operability in the event of internal flooding. Therefore, an unreviewed safety question does not exist.

e Surry Monthly Operating Report No. 93-03 Page 11 of 26 FACILITY CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTH/YEAR: March 1993 SE 93-041 Safety Evaluation 03-05-93 Safety Evaluation 93-041 was performed to evaluate the use of nonsafety-related Unit 2 charging system flow transmitter 2-CH-FT-2160 to support operation of the alternate charging header during the 1993 Unit 2 refueling outage.

The evaluation concluded that it is acceptable to use a nonsafety-related transmitter while the Unit is at cold shutdown (CSD). The transmitter is seismically installed and is capable of withstanding charging pump discharge pressure. A failure of the subject transmitter while the Unit is at CSD is not applicable to any of the design basis accidents described in the UFSAR. The transmitter will be replaced or removed from service prior to the Unit leaving CSD. Therefore, an unreviewed safety question does not exist.

TSR 93-041 Temporary Shielding Request 03-05-93 (Safety Evaluation 93-040)

Temporary Shielding Request 93-041 installed temporary lead shielding on Unit 2 safety injection and containment spray (CS) system piping to reduce the radiation dose received by personnel while performing work in the Unit 2 CS Pumphouse.

Installation of the shielding while the subject lines remain operable was determined to be acceptable through the performance of seismic piping analyses, provided the pressure and temperature do not exceed 350 psi and 450° 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 93-008 Temporary Shielding Request 03-08-98 (Safety Evaluation 93-042)

Temporary Shielding Request 93-008 installed temporary lead shielding on aerated drains and reactor cavity purification system piping in the Unit 2 containment basement 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 seismic piping analyses. The shielding will not adversely affect the design functions of the affected systems and will be removed prior to the Unit leaving cold shutdown.

Therefore, an unreviewed safety question does not exist.

e Surry Monthly Operating Report No. 93-03 Page 12of 26 FACILITY CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTH/YEAR: March 1993 TSR 93-018 Temporary Shleldlng Request 03-08-93 (Safety Evaluation 93-043)

Temporary Shielding Request 93-018 installed temporary lead shielding to the elbows of three safety injection (SI) system accumulator discharge lines in the Unit 2 containment 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 seismic and deadweight piping analyses. The shielding will be removed prior to Unit start-up.

Therefore, an unreviewed safety question does not exist.

SE 93-044 Safety Evaluation 03-09-93 Safety Evaluation 93-044 was performed to evaluate the Unit 2 Cycle 12 reload core, including the use of fresh fuel assemblies that incorporate new anti-snag features in the fuel assembly lnconel grid.

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.

TM S2-93-02 Temporary Modification 03-10-93 (Safety Evaluation No.93-045)

Temporary Modification (TM) S2-93-02 installed four temporary telephone lines into the Unit 2 Containment using spare conductors in electrical penetration 9C.

This TM provides communications capability between personnel inside and those outside the containment during the 1993 Unit 2 refueling outage. The modification will not affect the ability of the electrical penetration to perform its design function or that of systems and components supplied by the penetration. The TM will be removed prior to the Unit exceeding 200 °F.

Therefore, an unreviewed safety question does not exist.

e e Surry Monthly Operating Report No. 93-03 Page 13 of 26 FACILITY CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTH/YEAR: March 1993 TSR 93-029 Temporary Shleldlng Request 03-10-93 TSR 93-030 (Safety Evaluation 93-047)

TSR 93-031 Temporary Shielding Requests93-029, 93-030, and 93-031 installed temporary lead shielding on the Unit 2 reactor coolant loop piping and valves (including the loop stop valve by-pass line and valve) to reduce the radiation dose received by personnel while removing the resistance temperature device by-pass lines and performing other work in the area.

Installation of the shielding while the subject lines remain operable was determined to be acceptable through the performance of seismic piping analyses, provided the pressure and temperature do not exceed 385 psi and 400° 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 does not exist.

TSR 93-011 Temporary Shielding Request 03-12-93 TSR 93-012 (Safety Evaluation 93-049)

TSR 93-043 Temporary Shielding Requests93-011, 93-012, and 93-043 installed temporary lead shielding on Unit 2 residual heat removal (RHR) system piping 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 (in accordance with TSR 93-011) while the subject piping remains operable was determined to be acceptable through the performance of a seismic piping analysis. Installation of additional shielding (in accordance with TSRs93-012 and 93-043) 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 does not exist.

TM S2-93-03 Temporary Modification 03-17-93 (Safety Evaluation No.93-051)

Temporary Modification (TM) S2-93-03 installed an electrical jumper around the seal-in contacts for Unit 2 safety injection (SI) system valves 2-SI-MOV-2869A and 2-SI-MOV-28698 to allow the valves to be throttled in order to control reactor coolant system flow from the volume control tank through the idle charging pumps.

This change maintains the full operating capability of the subject valves and will not impact the operation of the residual heat removal system. The TM will be in place only when the Unit is at less than 350°F and 450 psig to ensure the SI system is fully operable when required by Technical Specifications.

Therefore, an unreviewed safety question does not exist.

FACILITY CHANGES THAT DID NOT REQUIRE NRC APPROVAL e Surry Monthly Operating Report No. 93-03 Page 14of 26 MONTH/YEAR: March 1993 DCP 91-41-3 Design Change Package 03-18-93 (Safety Evaluation No.92-020)

Design Change Package (DCP) 91-41-3 installed dedicated steam generator pressure recorders (2 per Unit) to satisfy the requirements for Category I, Type A variables, defined in Regulatory Guide 1.97.

This modification provides control room operators with additional information to use during the performance of emergency operating procedures when determining the existence of a failed steam generator and/or tube rupture. The installation will not adversely affect any related systems or components.

Therefore, an unreviewed safety question does not exist.

DCP 90-20-02 Design Change Package 03-19-93

• (Safety Evaluation No.91-011)

Design Change Package (DCP) 90-20-02 added four Unit 2 reactor water storage tank (RWST) level channel trip annunciators to allow control room monitoring of RWST level channel tripping. Corresponding test points were also installed to provide local test capabilities of the process equipment in the emergency switchgear relay room.

This nonsafety-related modification was implemented to comply with the requirements of IEEE 279-1971, Section 4.19. No plant performance characteristics or parameters were altered by this modification. Therefore, an unreviewed safety question does not exist.

TSl-016 Technical Specification Interpretation 03-19-93 (Safety Evaluation No.93-055)

Technical Specification Interpretation TSl-016 was developed to describe the actions that need to be taken if the manipulator crane area or airborne radiation monitors become inoperable prior to or during refueling operations (Re:

Technical Specifications 3.1 O.A.2, 3.1 O.A.4).

The TSl-directed actions secure the containment ventilation purge system when the automatic isolation functions are not operable. This action places the system in its designed "safe" condition and serves the purpose of the automatic isolation design functions. This is an accident mitigation action that reduces the potential consequences of a fuel handling accident in the containment. It does not affect the initiating factors of a fuel handling accident in the containment or any other type of accident. The TSl-directed actions are consistent with Standard Technical Specifications for Westinghouse Pressurized Water Reactors, NUREG-0452, Revision 4, Section 3.9.9. Therefore, an unreviewed safety question does not exist. Furthermore, this TSI has been discussed with and concurred with by the NRC (Surry's Senior Resident Inspector and NRR Project Manager).

FACILITY CHANGES THAT DID NOT REQUIRE NRC APPROVAL

- Surry Monthly Operating Report No. 93-03 Page 15of 26 MONTH/YEAR: March 1993 EWA 90-336 Engineering Work Request 03-22-93 (Safety Evaluation No.90-265)

Engineering Work Request 90-336 replaced the Fischer Porter Unit 2 safety injection system flow transmitter 2-SI-FT-932 and number 3 reactor coolant pump seal pressure transmitter 2-SI-PT-154 with similar Rosemount transmitters.

This modification will improve the reliability of the subject transmitters and will not affect the operation of safety-related systems. Therefore, an unreviewed safety question does not exist.

TSR 93-001 Temporary Shielding Requests 03-23-93 TSR 93-002 (Safety Evaluation 93-046)

TSR *93-003 TSR 93-004 Temporary Shielding Requests93-001, 93-002,93-003, 93-004, TSR 93-022 93-022, 93-026, and 93-027 installed temporary lead shielding on TSR 93-026 pressurizer spray and pressurizer safety valve piping in the Unit 2 TSR 93-027 containment 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 seismic and deadweight piping analyses, provided the pressure and temperature do not exceed 385 psi and 400°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 does not exist.

TSR 93-010 Temporary Shleldlng Request 03-23-93 (Safety Evaluation 93-057)

Temporary Shielding Request 93-010 installed temporary lead shielding on the Unit 2 reactor cavity purification system piping (3"-RL-101-152) to reduce the radiation dose received by personnel while performing work in this area of the Unit 2 Auxiliary Building.

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 the Unit leaving cold shutdown.

Therefore, an unreviewed safety question does not exist.

I I

I

• Surry Monthly Operating Report No. 93-03 Page 16of 26 I

FACILITY CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTH/YEAR: March 1993 DCP 90-26-01 Design Change Package 03-25-93 (Safety Evaluation No.90-230)

Design Change Package (DCP) 90-26-01 provided for the inspection, cleaning, and recoating of the service water (SW) supply piping for the bearing cooling water heat exchangers, recirculating spray heat exchangers (RSHX), and the SW return piping from the component cooling water heat exchangers. The DCP also installed pressure taps on the SW supply and return piping for the B and C RSHXs.

• This DCP reconditioned the subject SW piping and did not modify the system function. Therefore, an unreviewed safety question does not exist.

TSR 93-028 Temporary Shielding Request 03-26-93 (Safety Evaluation 93-061)

Temporary Shielding Request 93-028 installed temporary lead shielding on the Unit 2 reactor coolant (RC) and safety injection system piping to reduce the radiation dose received by personnel while performing work in the Unit 2 C Loop Room on safety injection system valves 2-Sl-85 and 2-Sl-243.

Installation of the shielding while the subject lines remain operable was determined to be acceptable through the performance of seismic and deadweight piping analyses. The shielding will not adversely affect the design functions of the affected systems and will be removed prior to pressurizing the RC system or exceeding 140°F. Therefore, an unreviewed safety question does not exist.

AC S1-93-0329 Administrative Control 03-29-93 (Safety Evaluation No.93-031 A)

Administrative control of Unit 1 auxiliary feedwater (AFW) system valve 1-FW-MOV-1608 will be implemented to ensure AFW cross-tie capability from Unit 2 to Unit 1 is maintained during the period in which Unit 1 AFW system valve 1-FW-MOV-160A is tagged out as part of a 480V 2J bus outage.

Unit 1 will be at power and Unit 2 will be at refueling shutdc:,wn (with no fuel in the vessel) during this condition. Administrative control of the subject valve will not disable an automatic function (the valve is manipulated through remote manual control) and enables the cross-tie to be established within the time period assumed by the accident analyses. Therefore, an unreviewed safety question does not exist.

FACILITY CHANGES THAT DID NOT REQUIRE NRC APPROVAL

- Surry Monthly Operating Report No. 93-03 Page 17of 26 MONTH/YEAR: March 1993 EWR 91-062 Engineering Work Request 03-30-93 (Safety Evaluation No.91-130)

Engineering Work Request 91-062 replaced the pin joint with a welded joint on a valve extension coupling for Unit 2 recirculating spray (RS) system valves 2-RS-MOV-256A and 2-RS-MOV-2568.

This modification did not alter the function or operation of the subject valves or the RS system. Therefore, an unreviewed safety question does not exist.

FS89-040 UFSAR Change 03-30-93 (Safety Evaluation 93-063)

Updated Final Safety Analysis Report (UFSAR) Sections 2.3 "Hydrology,"

• 9.4 "Component Cooling System," 9.9 "Service Water System," and 10.3 "System Design and Operation" were revised to incorporate the results of the revised Probable Maximum Hurricane (PMH) analysis, coincident with the loss of offsite power.

The subject analysis and applicable abnormal operating procedure require both Units be placed in a safe condition (intermediate shutdown or lower) prior to the arrival of a PMH to eliminate design basis accident mitigation concerns.

With the Units in a safe condition, no new malfunction of equipment related to safety need to be evaluated and the margins of safety as reflected in the Technical Specifications are assured. Therefore, an unreviewed safety question does not exist.

FS92-124 UFSAR Change 03-30-93 (Safety Evaluation 93-066)

Updated Final Safety Analysis Report (UFSAR) Section 10.3.7.2, "[Lubricating Oil System] Description" was revised to correctly reflect the location of the main turbine lube oil cooler.

The change is administrative in nature and was made to be consistent with the as-built configuration. No procedures or plant equipment are affected and no physical modifications are involved. Therefore, an unreviewed safety question does not exist.

FS92-152 UFSAR Change 03-30-93 (Safety Evaluation 93-065)

Updated Final Safety Analysis Report (UFSAR) Section 9.4.3.2, "Chilled Water System Description" was revised to eliminate the implication that the chilled water system is intentionally chromated.

The change is administrative in nature and provides clarification only. No

• procedures or plant equipment are affected and no physical modifications are involved. Therefore, an unreviewed safety question does not exist.

FACILITY CHANGES THAT DID NOT REQUIRE NRC APPROVAL e Surry Monthly Operating Report No. 93-03 Page 18of 26 MONTH/YEAR: March 1993 SE 93-066 Safety Evaluation 03-30-93 Safety Evaluation 93-066 was performed to evaluate the effects on the Unit 1, Cycle 12 departure from nucleate boiling ratio (DNBR) resulting from a dropped control rod(s) using WCAP-11294-P-A, "Methodology for the Analysis of the Dropped Rod Event."

It was concluded that the DNBR design limit will not be exceeded for the remainder of Unit 1, Cycle 12. Therefore, an unreviewed safety question does not exist.

PROCEDURE OR METHOD OF OPERATION CHANGES e Surry Monthly Operating Report No. 93-03 Page 19 of 26 THAT DID NOT REQUIRE NRC APPROVAL MONTH/YEAR: March 1993 1-0PT-CT-201 Operations Periodic Test Procedures 03-02-93 2-0PT-CT-201 (Safety Evaluation No.93-036)

Operations Periodic Test Procedures 1/2-0PT-CT-201, ncontainment Isolation Valve Local Leak Rate Testing (Type C Containment Testingf were revised to provide instructions for implementing temporary modifications to prevent the automatic actuation of emergency safeguards systems during the Type C local leak rate test on the leakage monitoring system.

The procedures will be implemented with the respective Unit at cold shutdown when the emergency safeguards systems are not required to be operable.

Double verification will be used to verify that lifted electrical leads are properly landed and pulled fuses are replaced following the completion of the procedures. Therefore, an unreviewed safety question does not exist.

9058-IP-1 Vendor Procedure 03-04-93 (Safety Evaluation No.93-039)

Vendor procedure 9058-IP-1, "Fuel Oil Modification Installation," provides instructions for replacing the existing emergency diesel generator canister type fuel oil filter assemblies and piping/tubing with new spin on filter assemblies and tubing.

This modification will increase the availability and reliability of the EDG fuel oil system and will not change its functional requirements or performance.

Therefore, an unreviewed safety question does not exist.

1/2-IPT-CC-RC- Instrument Periodic Test Procedures 03-16-93 ICCM-001 (Safety Evaluation No.93-050) 1/2-IPT-CC-RC-ICCM-002 Instrument Periodic Test Procedures 1/2-IPT-CC-RC-ICCM-001 1/2-IPT-CC-RC- "Inadequate Core Cooling Monitor Train A Calibration," 1/2-IPT-CC-ICCM-003 RC-ICCM-002 "Inadequate Core Cooling Monitor Train B Calibration,"

1/2-IPT-CC-RC- 1/2-IPT-CC-RC-ICCM-003 "Inadequate Core Cooling Monitor Train A ICCM-004 RVLIS Sensor Calibration, n and 1/2-IPT-CC-RC-ICCM-004 "Inadequate Core Cooling Monitor Train B RVLIS Sensor Calibration" were developed to perform a calibration of the Inadequate Core Cooling Monitor and Reactor Vessel Level Indication systems.

These procedures will be performed when the affected Unit is at cold shutdown when the affected systems are not required to be operable. Therefore, an unreviewed safety question does not exist. *

• • e Surry Monthly Operating Report No. 93-03 Page 20of 26 PROCEDURE OR METHOD OF OPERATION CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTH/YEAR: March 1993 2-TOP-4028 Temporary Operating Procedure 03-17-93 (Safety Evaluation No.93-052)

Temporary Operating Procedure 2-TOP-4028, "Lineup #2 POTT to Pump to #2 VCT," was developed to provide instructions for establishing a valve lineup that allows the Unit 2 primary drains transfer tank (POTT) to be pumped directly to the volume control tank (VCT). This lineup will recycle loop stop valve leakage to the VCT to conserve reactor coolant system (RCS) inventory and boron while the RCS loops are isolated.

This procedure will be performed while the Unit is at cold shutdown and will not adversely impact the chemical and volume control system. Furthermore, sources of primary grade water to* the POTT will be isolated to prevent

.inadvertent dilution of the RCS. Therefore, an unreviewed safety question does not exist.

1-PT-17.7 Periodic Test Procedure 03-18-93 (Safety Evaluation No.93-053)

Periodic Test Procedure 1-PT-17. 7, "Recirculating Spray HX Service Water Radiation Monitor Pump Test," was temporarily changed to install electrical jumpers to allow the consequence limiting safeguards (CLS) automatic start features of Unit 1 recirculating spray heat exchanger service water radiation monitor sample pumps 1-SW-P-5A, 1-SW-P-5B, 1-SW-P-5C, and 1-SW-P-5D to be tested.

Installation of the electrical jumpers will not affect other systems or components. The applicable Emergency Operating Procedures (EOP) will be revised to require verification that the subject pumps have automatically started upon receipt of a Hi Hi CLS signal. . The EOPs will also direct appropriate actions to minimize the potential for a radioactive release in the event the pumps do not start. Therefore, an unreviewed safety question does not exist.

2-ECM-2403-02 Electrical Corrective Maintenance Procedure 03-25-93 2-TMOP-EPH-001 Temporary Maintenance Operating Procedure (Safety Evaluation No.93-059)

Electrical Corrective Maintenance Procedure 2-ECM-2403-02, "RSS Transformer B Outage with Backfeed of Transfer Bus E," was developed and Temporary Maintenance Operating Procedure 2-TMOP-EPH-001, "Unit 2 34.5 KV Bus 5 and RSS Transformer B Outage," was revised to provide instructions for conducting an outage of 34.5 KV Bus Number 5.

These procedures were performed with Unit 2 defueled on backfeed supplying the D and E transfer buses. Unit 1 was at power with safety systems and emergency diesel generators available. Therefore, an unreviewed safety question does not exist.

PROCEDURE OR METHOD OF OPERATION CHANGES e Surry Monthly Operating Report No. 93-03 Page 21 26of THAT DID NOT REQUIRE NRC APPROVAL MONTH/YEAR: March 1993 2-0P-FH-001 Operating Procedure 03-27-93 2-0SP-ZZ-004 Operations Surveillance Procedure (Safety Evaluation No.93-062)

Operating Procedure 2-0P-FH-001 "Refueling Operations" and Operations Surveillance Procedure 2-0SP-ZZ-004 "Unit 2 Safety Systems Status List for Cold Shutdown/Refueling Conditions" were changed to allow operation of the auxiliary building ventilation system with one Category I filtered exhaust fan secured.

Both trains of the auxiliary building ventilation system will remain operable and capable of performing their design function during this mode of operation. The requirements of Technical' Specifications 3.1 o and 3.22 will be adhered to.

Therefore, an unreviewed safety question does not exist.

TESTS AND EXPERIMENTS THAT DID NOT REQUIRE NRC APPROVAL e Surry Monthly Operating Report No. 93-03 Page 22of 26 MONTH/YEAR: March 1993 2-ST-299 Speclal Test 03-31 -93 (Safety Evaluation No.93-003)

Special Test 2-ST-299, "Recirculation Spray Heat Exchanger Service Water Flow Test," was performed satisfactorily on March 22, 1993. The test verified that the Unit 2 B and C recirculating spray heat exchanger (RSHX) service water (SW) system will deliver design basis flow to reject design basis heat loads from the containment. In addition, the test verified the satisfactory performance of new V-cone flow elements and modified radiation monitor pump suction piping.

The test was performed with the Unit at refueling shutdown during which the RS system was not required. Therefore, an unreviewed safety question does not exist.

• e Surry Monthly Operating Report No. 93-03 Page 23of 26 CHEMISTRY REPORT MONTH/YEAR: March 1993 Unit No.1 Unit No. 2 Primarv Coolant Analvsis Max. Min. Ava. Max. Min. Ava.

Gross Radioact., uCi/ml 4.41E-1 1.73E-1 3.23E-1 2.10E-1 1.03E-5 2.31E-2 Suspended Solids, oom < 0.1 < 0.1 < 0.1 < 0.1 < 0.1 < 0.1 Gross Tritium, uCi/ml 1.99E-1 1.78E-1 1.89E-1 8.22E-2 8.22E-2 8.22E-2 1131, uCi/ml 1.21E-3 4.12E-4 7.34E-4 4.15E-4 1.67E-4 2.76E-4 113111133 0.13 0.07 0.10 0.12 0.08 0.10 Hydrogen, cc/kg 44.9 25.4 35.7 46.3 3.5 18.1 Lithium, oom 2.34 2.05 2.20 0.89 0.72 0.75 Boron - 10, oom* 153.8 117.8 132.9 178.9 0.2 63.1 Oxvoen. (DO), oom < 0.005 < 0.005 < 0.005 6.0 < 0.005 2.3 Chloride, ppm 0.005 .s;0.001 0.003 0.526 ~ 0.001 0.099 oH at 25 dearee Celsius 6.92 6.52 6.73 8.75 4.62 5.11

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

Unit 2 shut down for refueling on 3/6/93.

• FUEL HANDLING e Surry Monthly Operating Report No. 93-03 Page 24of 26 UNITS 1 & 2 MONTH/YEAR: March 1993 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 NAC-128.2 02/25/93 28 F09 LMOOW9 1.86 NIA F11 LMOOW6 1.86 L06 1.86 L07 1.86 L09 1.86 L13 1.86 L17 1.86 L19 1.86 L20 1.86 L21 1.86 L23 1.86 L24 1.86 L26 1.86 L27 1.86 L28 1.86 L29 1.86 L33 1.86 L34 1.86 L35 1.86 L38 1.86 L39 1.86 L43 1.86 L45 1.86 L46 1.86

• FUEL HANDLING e Surry Monthly Operating Report No. 93-03 Page 25of 26 UNITS 1 & 2 MONTH/YEAR: March 1993 New or Spent Number of New or Spent Fuel Shipment Date Stored or Assemblies Assembly ANSI Initial Fuel Shipping Number Received ~rShiement Number Number Enrichment Cask Activi~

L48 1.86 L49 1.86 L51 1.86 L53 1.86 I

L__

• e DESCRIPTION OF PERIODIC TEST(S) WHICH WERE NOT COMPLETED Surry Monthly Operating Report No. 93-03 Page 26of 26 WITHIN THE TIME LIMITS SPECIFIED IN TECHNICAL SPECIFICATIONS MONTH/YEAR: March 1993 None During This Reporting Period.