ML18153B287

Monthly Operating Repts for Jul 1993 for Surry Power Station,Units 1 & 2.W/930810 Ltr

ML18153B287
Person / Time
Site:	Surry
Issue date:	07/31/1993
From:	Bowling M, Mason D VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
93-503, NUDOCS 9308190175
Download: ML18153B287 (22)

Text

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e e VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND, VIRGINIA 23261 August 10, 1993 U. S. Nuclear Regulatory Commission Serial No.93-503 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 July 1993.

Very truly yours, 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

- - - - ~ -- - - -

9308190175 930731 PDR ADOCK 05000280 R _ ~ _ _____ ______ _ _P~R ____ 0 I J

VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION MONTHLY OPERATING REPORT REPORT NO. 93-07 Approved:

e e Surry Monthly Operating Report No. 93-07 Page 2 of 21 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 ....................................................................................... 1o Facility Changes That Did Not Require NRC Approval. .............................................................................. 11 Procedure or Method of Operation Changes That Did Not Require NRC Approval ........................................... 17 Tests and Experiments That Did Not Require NRC Approval ...................................................................... 18 Chemistry Report ............................................................................................................................. 19 Fuel Handling - Unit No. 1 ................................................................................................................... 20 Fuel Handling - Unit No. 2 ................................................................................................................... 20 Description of Periodic Test(s) Which Were Not Completed Within the Time Limits Specified in Technical Specifications ................................................................................................... 21

Surry Monthly Operating Report No. 93-07 Page 3 of 21 OPERATING DATA REPORT Docket No.

50-280 Date: 08-03-93 Completed By: D. Mason Telephone: (804) 365-2459

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

2. Reporting Period: ......................................... . July, 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 5087.0 180647.0

12. Number of Hours Reactor Was Critical .......... 744.0 4980.4 120355.4

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

14. Hours Generator On-Line ........................... 744.0 4962.0 118237.4

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

16. Gross Thermal Energy Generated (MWH) ...... 1804269.0 11851252.5 275470531.6

17. Gross Electrical Energy Generated (MWH) .... 575755.0 3954675.0 89972928.0

18. Net Electrical Energy Generated (MWH) ........ 550188.0 3773106.0 85370966.0

19. Unit Service Factor ................................... 100.0% 97.5% 65.5%

20. Unit Availability Factor ............................... 100.0% 97.5% 67.5%

21. Unit Capacity Factor (Using MDC Net) ........... 94.7% 95.0% 60.9%

22. Unit Capacity Factor (Using DER Net) ........... 93.8% 94.1% 60.0%

23. Unit Forced Outage Rate ............................ 0.0% 2.5% 17.9%

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

None

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

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

FORECAST ACHIEVED INITIAL CRITICALITY INITIAL ELECTRICITY COMMERCIAL OPERATION

J e Surry Monthly Operating Report No. 93-07 Page 4of 21 OPERATING DATA REPORT Docket No.: 50-281 Date: 08-03-93 Completed By: D. Mason Telephone: (804) 365-2459

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

2. Reporting Period: ......................................... . July, 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 5087.0 177527.0

12. Number of Hours Reactor Was Critical ......... . 744.4 3640.1 117327.0

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

14. Hours Generator On-Line ......................... .. 744.0 3575.1 115506.1

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

16. Gross Thermal Energy Generated (MWH) ..... . 1681009.3 7983828.0 269314901.8

17. Gross Electrical Energy Generated (MWH) ... . 542580.0 2638635.0 87834539.0

18. Net Electrical Energy Generated (MWH) ...... .. 518650.0 2511880.0 83302293.0

19. Unit Service Factor ................................. .. 100.0% 70.3% 65.1%

20. Unit Availability Factor .............................. . 100.0% 70.3% 65.1%

21. Unit Capacity Factor (Using MDC Net) .......... . 89.3% 63.2% 60.2%

22. Unit Capacity Factor (Using DER Net) .......... . 88.5% 62.7% 59.5%

23. Unit Forced Outage Rate .......................... .. 0.0% 1.3% 14.0%

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

None

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

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

FORECAST ACHIEVED INITIAL CRITICALITY INITIAL ELECTRICITY COMMERCIAL OPERATION

• Surry Monthly Operating Report No. 93-07 Page 5 of 21 UNIT SHUTDOWN AND POWER REDUCTION (EQUAL To OR GREATER THAN 20%)

REPORT MONTH: July, 1993 Docket No.: 50-280 Unit Name: Surry Unit 1 Date: 08-01-93 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 930715 s 0 8 4 NIA SG HX Unit power was reduced to 78%

to maintain condenser vacuum while cleaning water boxes.

(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. 93-07 Page 6 of 21 UNIT SHUTDOWN AND POWER REDUCTION

{EQUAL To OR GREATER THAN 20%)

REPORT MONTH: July, 1993 Docket No.: 50-281 Unit Name: Surry Unit 2 Date: 08-01-93 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. 93-07 Page ?of 21 AVERAGE DAILY UNIT POWER LEVEL Docket No.: 50-280 Unit Name: Surry Unit 1 Date: 08-03-93 Completed by: Pat Kessler Telephone: 365-2790 Month: July, 1993 Average Daily Power Level Average Daily Power Level Day (MWe- Net) Day (MWe- Net) 1 761 17 706 2 761 18 745 3 759 19 751 4 753 20 745 5 747 21 744 6 743 22 751 7 745 23 752 8 737 24 751 9 735 25 747 10 731 26 753 11 734 27 754 12 732 28 749 13 733 29 745 14 729 30 747 15 721 31 675 16 688 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. 93-07 Page 8 of 21 AVERAGE DAILY UNIT POWER LEVEL Docket No.: 50-281 Unit Name: Surry Unit 2 Date: 08-03-93 Completed by: Pat Kessler Telephone: 365-2790 Month: July, 1993 Average Daily Power Level Average Daily Power Level Day (MWe- Net) Day (MWe- Net) 470 17 747 2 471 18 752 3 465 19 753 4 466 20 750 5 465 21 745 6 571 22 748 7 752 23 748 8 754 24 749 9 751 25 747 10 746 26 749 11 753 27 752 12 753 28 749 13 749 29 744 14 747 30 743 15 750 31 742 16 730 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. 93-07 Page 9of 18

SUMMARY

OF OPERATING EXPERIENCE MONTH/YEAR: July, 1993 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; 07/01/93 0000 This reporting period began with the Unit operating at 100% power, 790 MWe.

07/15/93 2122 Started power reduct,ion to maintain condenser vacuum while cleaning water boxes; 100%

power, 755 MWe.

2256 Stopped power reduction; 78% power, 550 MWe.

07/16/93 0130 Reduced power as necessary to maintain condenser vacuum.

0302 Started ramp up; 74% power, 515 MWe.

0711 Stopped ramp at 99.5% power, 770 MWe; adjusted IRPls and increased power to 100%.

07/17/93 0453 Started ramp down to maintain condenser vacuum while cleaning water boxes; 100%

power, 765 MWe.

0549 Stopped ramp; 84% power, 620 MWe.

0719 Reduced power as necessary to maintain condenser vacuum.

0930 Started ramp up; 81% power, 695 MWe.

1100 Stopped ramp; 100% power, 780 MWe.

07/30/93 2226 Started ramp down to maintain condenser vacuum while "B" water .box was removed from service for cleaning, leak detection, and repair; 100% power, 780 MWe.

2309 Stopped ramp; 92% power, 700 MWe.

07/31/93 2400 This reporting period ended with the Unit operating at 92% power, 700 MWe with the "B" water box out of service for maintenance.

Surry Monthly Operating Report No. 93-07 Page 10 of 21

SUMMARY

OF OPERATING EXPERIENCE MONTH/YEAR: July, 1993 UNll TWO:

07/01/93 0000 This reporting period began with the Unit operating at 66.5% power, 505 MWe with the "A" Main Feedwater Pump out of service for maintenance.

07/06/93 1120 Started ramp up; 66% power, 500 MWe.

1824 Stopped ramp; 100% power, 795 MWe.

1841 Started power reduction due to "C" Main Feedwater Regulating Valve oscillations; 100%

power, 795 MWe.

1850 Stopped power reduction; 97.2% power.

1900 Increased power; 97.2% power.

2014 Unit at 100% power, 785 MWe.

2035 Reduced power to 99% due to "C" Main Feedwater Regulating Valve oscillations.

07/31/93 2400 This reporting period ended with the Unit operating at 98% power, 780 MWe due to "C" Main Feedwater Regulating Valve oscillations.

e Surry Monthly Operating Report No. 93-07 Page 11 of 21 FACILITY CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTH/YEAR: July, 1993 EWR 89-152 Engineering Work Request 06-03-93 Engineering Work Request 89-152 installed flow sensing elements in the Units 1

& 2 service water (SW) inlet side of the component cooling heat exchangers (CCHX) in order to determine SW flow. Differential pressure gauges were also installed across the CCHX's tubes to measure the degree of tube plugging.

The new instrumentation did not alter the function of the SW system while it improved the ability to monitor CCHX performance. The instrumentation was installed in accordance with previously approved codes and standards.

Therefore, an unreviewed safety question does not exist.

DCP 91-50 Design Change Package 06-04-93 (Safety Evaluation No.92-107)

Design Change Package 91-50 installed a vent valve in the instrument air system leading to ventilation dampers 1-VSP-AOD-107A, 1-VSP-AOD-107B, and 1-VSP-AOD-108. The vent valve was installed to provide another means to align these dampers to the auxiliary building category I filtration ventilation fans, 1-VSP-F-58A and 1-VSP-F-58B, during a 10 CFR 50 Appendix "R" event.

The ventilation dampers are designed to fail to a safe position. Upon an interruption of instrument air, the dampers align themselves to the category I filtration fans to ensure that airborne contamination is filtered out prior to exhausting through a vent stack. Furthermore, should the modified components fail, they can be easily isolated and repaired without affecting service to other equipment. Therefore, an unreviewed safety question does not exist.

EWR 88-484 Engineering Work Request 06-04-93 Engineering Work Request 88-484 installed gauge valves on the Units 1 & 2 auxiliary feedwater (AFW) lube oil system in order to isolate the lube oil pressure gauge and to provide ports for calibration connections.

This modification did not affect the AFW lube oil system since the gauge valves were installed off the main lube oil line for the AFW pumps. Therefore, an unreviewed safety question does not exist.

EWR 88-081 Engineering Work Request 06-10-93 Engineering Work Request (EWR)88-081 installed a vacuum adjustment valve on the inlet piping of the Unit 1 gland steam exhauster in order to minimize water leakage. The EWR also installed bracing on the gland steam exhauster motor base to stabilize the motor.

The gland steam exhauster is not safety-related and is not used to mitigate the consequences of accidents described in the UFSAR. Therefore, an unreviewed safety question does not exist.

e e Surry Monthly Operating Report No. 93-07 Page 12 of 21 FACILITY CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTH/YEAR: July, 1993 DCP 93-27 Design Change Package 06-11-93 (Safety Evaluation No.93-067)

Design Change Package 93-27 deleted the automatic transfer scheme between 34.5 KV switchyard buses 5 and 6 and between each of these buses and transformer number 4.

This modification maintained two independent off-site power sources and a third that is available with manual action. It did not negatively impact the operation of safety-related systems or components and eliminated the potential for damage to equipment caused by transferring loads out of phase. Therefore, a:n unreviewed safety question does not exist.

DCP 89-17 Design Change Package 06-16-93 (Safety Evaluation No.90-144)

Design Change Package (DCP) 89-17 installed a permanent charging system to the control room bottled air system to increase the charging capacity, enabling one compressed air bottle bank to be recharged within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.

The existing charging system required approximately 100 hours0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br /> to recharge one fully discharged bottled air bank. This DCP provides a permanent, larger capacity system which reduces the charging time significantly. The control room bottled air system is not safety-related, not powered from a safety-related power source, and not required for safety-related functions. Therefore, an unreviewed safety question does not exist.

EWR 89-352 Engineering Work Request 06-24-93 (Safety Evaluation No.90-086)

Engineering Work Request 89-352 replaced the Units 1 & 2 waste gas decay tank (WGDT) oxygen and hydrogen analyzers to improve the reliability and accuracy of gas concentration measurement in the WGDT.

This modification did not adversely affect the performance or design basis of the WGDT analyzers and did not impact other systems. The equipment and mounting were evaluated for seismic integrity. Therefore, an unreviewed safety question does not exist.

e Surry Monthly Operating Report No. 93-07 Page 13 of 21 FACILITY CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTH/YEAR: July, 1993 SE 93-146 Safety Evaluation 07-09-93 Safety Evaluation 93-146 was performed, as a result of a review of Information Notice 91-40, to evaluate the potential for unmonitored, uncontrolled radioactivity releases to the environment from the auxiliary steam system drains (from the auxiliary building).

The evaluation concluded that contamination from a leaking pipe or spill to the floor drains would be required for a release to the discharge canal to occur. In the event of such a leak or spill, minimal circulating/service water system flow would dilute contamination levels to well below the maximum release levels. Periodic sampling is performed to monitor system contamination levels to ensure a release can be adequately diluted. Therefore, an unreviewed safety question does not exist.

SE 93-147 Safety Evaluation 07-09-93 Safety Evaluation 93-147 was performed, as a result of a review of Information Notice 91-40, to evaluate the potential for unmonitored, uncontrolled radioactivity releases to the environment from the component cooling (CC) system.

The evaluation concluded that a CC system heat exchanger tube leak to the service water system would be required for a release to the discharge canal to occur. In the event of such a leak, minimal service water system flow would dilute contamination levels to well below the maximum release levels. Periodic sampling is performed to monitor system contamination levels to ensure a release can be adequately diluted. System gases are also monitored at the CC system surge tank and are vented to the process vent system. Therefore, an unreviewed safety question does not exist.

SE 93-148 Safety Evaluation 07-09-93 Safety Evaluation 93-148 was performed, as a result of a review of Information Notice 91-40, to evaluate the potential for unmonitored, uncontrolled radioactivity releases to the environment from the chilled water system.

The evaluation concluded that a chiller heat exchanger tube leak to the service water system would be required for a release to the discharge canal to occur. In the event of such a leak, minimal service water system flow would dilute contamination levels to well below the maximum release levels. Periodic sampling is performed to monitor system contamination levels to ensure a release can b$

adequately diluted. Therefore, an unreviewed safety question does not exist.

e Surry Monthly Operating Report No. 93-07 Page 14 of 21 FACILITY CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTH/YEAR: July, 1993 SE 93-149 Safety Evaluation 07-09-93 Safety Evaluation 93-149 was performed, as a result of a review of Information Notice 91-40, to evaluate the potential for unmonitored, uncontrolled radioactivity releases to the environment from the containment subsurface drain system.

The evaluation concluded that existing contamination levels (undiluted) are less than that permitted by 10 CFR 20 for release to the environment. These low contamination levels are further diluted by the circulating and service water systems prior to release. The system is also sampled daily to ensure compliance with Technical Specifications. Therefore, an unreviewed safety question does not exist.

TSR 93-055 Temporary Shielding Request 07-09-93 (Safety Evaluation 93-145)

Temporary Shielding Request 93-055 installed temporary lead shielding on pressurizer spray and pressurizer safety valve piping in the Unit 1 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 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 does not exist.

TM S1-93-08 Temporary Modification 07-10-93 (Safety Evaluation No.93-152)

Temporary Modification S1-93-08 temporarily lined up the fire suppression water supply to the Unit 1 exterior containment spray ring to provide an evaporative cooling medium. This measure was taken to help reduce the containment interior ambient temperature.

This modification did not decrease the effectiveness of the fire suppression system or affect the emergency plan or Fire Contingency Action procedures.

Therefore, an unreviewed safety question does not exist.

e Surry Monthly Operating Report No. 93-07 Page 15 of 21 FACILITY CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTH/YEAR: July, 1993 TM S1-93-09 Temporary Modification 07-10-93 (Safety Evaluation No.93-151)

Temporary Modification S1-93-09 installed electrical jumpers to prevent Chilled Water Refrigeration Unit 1-CD-REF-1A from tripping (as a result of a spurious low bearing oil pressure or high temperature indication) while the chiller's defective oil pump run permissive relay was being replaced.

1-CD-REF-1A is not safety-related and is not used to mitigate the consequences of accidents described in the UFSAR. Automatic chiller trip functions remained operable during this activity. Double verification of jumper installation/removal and post maintenance testing were performed. Therefore, an unreviewed safety question does not exist.

TM S2-93-40 Temporary Modification 07-10-93 (Safety Evaluation No.93-150)

Temporary Modification S2-93-40 installed electrical jumpers to prevent Chilled Water Refrigeration Unit 2-CD-REF-1 from tripping (as a result of a spurious high bearing temperature indication) until the chiller's defective bearing temperature sensor can be replaced.

2-CD-REF-1 is not safety-related and is not used to mitigate the consequences of accidents described in the UFSAR. The bearing oil header temperature was monitored routinely by operators and the other automatic chiller trip functions remained operable during this activity. Double verification of jumper installation/removal and post maintenance testing were performed. Therefore, an unreviewed safety question does not exist.

DCP 88-13 Design Change Package 07-12-93 (Safety Evaluation No.90-177)

Design Change Package 88-13 modified the Unit 1 reactor coolant pumps' (RCP) oil collection enclosures to facilitate maintenance on the pumps.

The modification changed the method of attaching the oil enclosure to each RCP while maintaining the seismic integrity and leak-tightness of the original installation. The oil enclosures are passive devices that do not affect the design or function of a safety-related system. Therefore, an unreviewed safety question does not exist.

EWR 90-280 Engineering Work Request 07-12-93 (Safety Evaluation No.90-241)

Engineering Work Request 90-280 isolated the auxiliary steam supply lines to the Unit 1 flash evaporator (which was no longer in service) in order to eliminate potential sources of air in-leakage to the main steam condenser.

The modification did not affect the operation or function of safety-related systems and will help to minimize air in-leakage to the main condenser. Therefore, an unreviewed safety question does not exist.

e Surry Monthly Operating Report No. 93-07 Page 16 of 21 FACILITY CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTH/VEAR: July, 1993 TM $1-93-10 Temporary Modification 07-15-93 (Safety Evaluation No.93-153)

Temporary Modification S1-93-10 temporarily installed a television camera in the Unit 1 containment, associated cables, and a television monitor in the control room to enable operators to monitor a leak from Steam Generator 1-RC-E-18.

This modification did not impact on plant control or protection systems. The camera was mounted in a manner that ensured that equipment would not be damaged if it fell. Therefore, an unreviewed safety question does not exist.

EWR 90-375 Engineering Work Request 07-21-93 (Safety Evaluation No.91-187)

Engineering Work Request 90-375 replaced various pressure transmitters with Rosemount transmitters throughout Units 1 and 2. Rosemount transmitters were selected due to their ready availability of replacement and repair parts.

The transmitter replacements were made on a one-for-one basis and met or exceeded the respective system design criteria. The operation or function of safety-related systems were not affected. Therefore, an unreviewed safety question does not exist.

TSl-014C Technical Specification Interpretation 07-16-93 (Safety Evaluation No.93-155)

Technical Specification Interpretation TSl-014C was developed to describe the actions that need to be taken if a main feedwater regulating valve (MFRV) must be placed on its jack. (Re: Technical Specifications 3.7, Table 3.7-3).

The TSI directed controls permit no more than one MFRV on its jack at one time and for a period not to exceed 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />. The TSI also requires that the isolation motor operated valve (MOV) associated with the affected main feedwater line be stroked partially closed to ensure it can be manually closed, if required. In addition, the controls require a dedicated control room operator to close the isolation MOV on a safety injection signal or a steam generator Hi-Hi level signal and a dedicated operator (located at the MFRV) to close the MFRV as required.

These measures do not affect other accident mitigation systems and ensure that feedwater isolation is achieved within the main steam line break accident analysis assumptions. Accident probability and consequences are not increased. The proposed limited duration and controls to provide alternative isolation assure that the probability of equipment malfunction has not increased. The margin of safety is assured by the diverse and redundant isolation control measures. Therefore, an unreviewed safety question does not exist.

e Surry Monthly Operating Report No. 93-07 Page 17 of 21 PROCEDURE OR METHOD OF OPERATION CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTH/YEAR: July 1993 1/2-0PT-ZZ-001 Operations Periodic Test Procedures 07-02-93 1/2-0PT-ZZ-002 (Safety Evaluation No.93-143)

Operations Periodic Test Procedures 1/2-0PT-ZZ-001, "ESF Actuation with Undervoltage and Degraded Voltage - 1H [2H] Bus" and 1/2-0PT-ZZ-002, "ESF Actuation with Undervoltage and Degraded Voltage - 1J [2J] Bus" were revised to permit the test set-up to be performed when the pressure and temperature are less than 450 psi and 350° F, respectively (instead of cold shutdown).

This change involves only the initial conditions for test set-up and does not affect the requirements for performing the tests or the acceptance criteria. Therefore, an unreviewed safety question does not exist.

1-0PT-Sl-005 Operations Periodic Test Procedures 07-20-93 2-0PT-Sl-005 (Safety Evaluation No.93-156)

Operations Periodic Test Procedures 1-0PT-Sl-005 and 2-0PT-Sl-005, "LHSI Pump Test" were temporarily revised to permit the use of temporary transmitters to enable the measurement of low head safety injection pump pressure during the few seconds following pump start.

The use of the temporary safety-related transmitters does not affect the operation of the subject pumps or the ability of the safety injection system to perform its required safety function. Therefore, an unreviewed safety question does not exist.

1-0SP-TM-001 Operations Surveillance Procedures 07-30-93 2-0SP-TM-001 (Safety Evaluation No.93-161)

Operations Surveillance Procedures 1-0SP-TM-001 and 2-0SP-TM-001,

Turbine Inlet Valve Freedom Test" were revised to allow the turbine inlet valve testing to be performed on a quarterly (instead of monthly) basis.

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

Therefore, an unreviewed safety question does not exist.

• e Surry Monthly Operating Report No. 93-07 Page 18 of 21 TESTS AND EXPERIMENTS THAT DID NOT REQUIRE NRC APPROVAL MONTH/YEAR: July, 1993 None during this reporting period.

. e Surry Monthly Operating Report No. 93-07 Page 19 of 21 CHEMISTRY REPORT MONTH/YEAR: July, 1993 Unit No. 1 Unit No. 2 Primary Coolant Analysis Max. Min. Avg. Max. Min. Avo.

Gross Radioactivity, µCi/ml 3.97E-1 2.79E-1 3.49E-1 1.90E-1 8.79E-2 1.43E-1 Suspended Solids, oom < 0.1 < 0.1 < 0.1 < 0.1 < 0.1 < 0.1 Gross Tritium, µ.Ci/ml 1.90E-1 1.36E-1 1.64E-1 5.21 E-1 3.85E-1 4.43E-1 1131 µ.Ci/ml 1.50E-3 6.90E-4 9.31 E-4 1.59E-4 3.60E-5 8.04E-5 1131 /1133 0.11 0.07 0.09 0.20 0.06 0.12 Hydrogen, cc/ka 38.3 25.5 32.9 36.1 24.2 33.5 Lithium, ppm 2.27 1.92 2.12 2.39 2.07 2.20 Boron - 10, ppm* 68.0 50.6 59.2 278.1 249.7 257.7 Oxygen, (DO), ppm S0.005 S0.005 S0.005 .:;;,0.005 S0.005 .:;;,0.005 Chloride, oom 0.005 <0.001 0.002 0.016 0.006 0.012 pH at 25 deoree Celsius 7.17 6.99 7.12 6.35 6.20 6.26 Boron - 1 O = Total Boron x 0.196 Comments:

None

... e Surry Monthly Operating Report No. 93-07 Page 20 of 21 FUEL HANDLING UNITS 1 & 2 MONTH/YEAR: July,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 No fuel received or stored during this reporting period.

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• Surry Monthly Operating Report DESCRIPTION OF PERIODIC TEST(S) WHICH WERE NOT COMPLETED WITHIN THE TIME LIMITS SPECIFIED IN TECHNICAL SPECIFICATIONS No. 93-07 Page 21 of 21 MONTH/YEAR: July, 1993 None during this reporting period.