ML18153D264

Monthly Operating Repts for Feb 1993 for Surry Power Station Units 1 & 2

ML18153D264
Person / Time
Site:	Surry
Issue date:	02/28/1993
From:	Mason D VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
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ML18153D265	List: ML18153D264 ML18153D266 ML18153D267
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Download: ML18153D264 (21)

Text

ATTACHMENT 1 SURRY POWER STATION MONTHLY OPERATING REPORT FEBRUARY 1993

VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION MONTHLY OPERATING REPORT REPORT NO. 93-02 Approved:

e Surry Monthly Operating Report No. 93-02 Page 2 of 20 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 ........................................... 13 Tests and Experiments That Did Not Require NRC Approval ...................................................................... 17 Chemistry Report ............................................................................................................................. 18 Fuel Handling - Unit No. 1 ................................................................................................................... 19 Fuel Handling - Unit No. 2 ................................................................................................................... 19 Description of Periodic Test(s) Which Were Not Completed Within the Time Limits Specified in Technical Specifications ................................................................................................... 20

e Surry Monthly Operating Report No. 93-02 Page 3 of 20 OPERATING DATA REPORT Docket No.: 50-280 Date: 03-05-93 Completed By: D. Mason Telephone: (804) 365-2459

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

2. Reporting Period: ......................................... . February 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 ......................... . 672.0 1416.0 176976.0

12. Number of Hours Reactor Was Critical. ........ . 626.8 1309.4 116684.4

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

14. Hours Generator On-Line .......................... . 616.5 1291.0 114566.4

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

16. Gross Thermal Energy Generated (MWH) ..... . 1490967.3 3128331.5 266747610.6

17. Gross Electrical Energy Generated (MWH) ... . 503805.0 1057270.0 87075523.0

18. Net Electrical Energy Generated (MWH) ....... . 479250.0 1005618.0 82603478.0

19. Unit Service Factor .................................. . 91.7% 91.2% 64.7%

20. Unit Availability Factor .............................. . 91.7% 91.2% 66.8%

21. Unit Capacity Factor (Using MDC Net) .......... . 91.3% 90.9% 60.2%

22. Unit Capacity Factor (Using DER Net) .......... . 90.5% 90.1% 59.2%

23. Unit Forced Outage Rate ........................... . 8.3% 8.8% 18.3%

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

-Surry Monthly Operating Report No. 93-02 Page 4of 20 OPERATING DATA REPORT Docket No.: 50-281 Date: 03-05-93 Completed By: D. Mason Telephone: (804) 365-2459

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

2. Reporting Period: ..............**......*................... February 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 ......................... . 672.0 1416.0 173856.0

12. Number of Hours Reactor Was Critical ........ .. 672.0 1416.0 115102.9

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

14. Hours Generator On-Line ......................... .. 672.0 1416.0 113347.0

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

16. Gross Thermal Energy Generated (MWH) ..... . 1481355.0 3293768.2 264624842.0

17. Gross Electrical Energy Generated (MWH) .. .. 497405.0 1103470.0 86299374.0

18. Net Electrical Energy Generated (MWH) ...... .. 471180.0 1047693.0 81838106.0

19. Unit Service Factor ................................. .. 100.0% 100.0% 65.2%

20. Unit Availability Factor.............................. . 100.0% 100.0% 65.2%

21. Unit Capacity Factor (Using MDC Net) .......... . 89.8% 94.7% 60.4%

22. Unit Capacity Factor (Using DER Net) .......... . 89.0% 93.9% 59.7%

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:

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

FORECAST ACHIEVED INITIAL CRITICALITY INITIAL ELECTRICITY COMMERCIAL OPERATION

• . esurry Monthly Operating Report No. 93-02 Page 5 of 20 UNIT SHUTDOWN AND POWER REDUCTION (EQUAL To OR GREATER THAN 20%)

REPORT MONTH: February 1993 Docket No.: 50-280 Unit Name: Surry Unit 1 Date: 03-05-93 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 930209 F 55.5 A 3 1 JC RLY An automatic reactor trip 002 occurred while performing PT-8.1 when a shunt trip coil relay failed on the "A" Reactor Trip Breaker.

(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. 93-02 Page 6 of 20 UNIT SHUTDOWN AND POWER REDUCTION (EQUAL To OR GREATER THAN 20%)

REPORT MONTH: February 1993 Docket No.: 50-281 Unit Name: Surry Unit 2 Date: 03-05-93 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 No entries for 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)

esurry Monthly Operating Report No. 93-02 Page 7of 20 AVERAGE DAILY UNIT POWER LEVEL Docket No.: 50-280 Unit Name: Surry Unit 1 Date: 03-05-93 Completed by: M.A. Negron Telephone: (804) 365-2795 Month: February 1993 Average Daily Power Level Average Daily Power Level Day (MWe- Net) Day (MWe- Net) 788 17 784 2 787 18 781 3 786 19 783 4 784 20 783 5 780 21 784 6 782 22 784 7 786 23 785 8 786 24 784 9 351 25 783 10 0 26 783 11 80 27 783 12 727 28 785 13 785 29 14 784 30 15 783 31 16 782 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. 93-02 Page Bot 20 AVERAGE DAILY UNIT POWER LEVEL Docket No.: 50-281 Unit Name: Surry Unit 2 Date: 03-05-93 Completed by: M.A. Negron Telephone: (804) 365-2795 Month: February 1993 Average Daily Power Level *

• Average Daily Power Level Day (MWe-Net) Day (MWe- Net) 1 773 17 689 2 770 18 684 3 762 19 679 4 756 20 675 5 747 21 670 6 746 22 667 7 742 23 661 8 732 24 657 9 725 25 653 10 718 26 649 11 708 27 646 12 708 28 639 13 698 29 14 701 30 15 693 31 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.

-Surry Monthly Operating Report No. 93-02 Page 9of 20

SUMMARY

OF OPERATING EXPERIENCE MONTH/YEAR: February 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 02-01-93 0000 This reporting period began with the Unit operating at 100% power, 825 MWe.

02-09-93 1043 Automatic reactor trip occurred while performing PT-8.1 when a shunt trip coil relay failed on the "A" Reactor Trip Breaker.

02-11-93 0755 Reactor critical.

1811 Unit on line.

02-12-93 0357 Stopped ramp at 97% power/BOO MWe, due to #4 governor valve indicating open with EHC isolated to the valve.

0606 Started ramp down to close and repair #4 governor valve; 97% power, 800 MWe.

0630 Stopped ramp; 92% power, 755 MWe.

1430 Started ramp up; 91% power, 750 MWe.

1700 Stopped ramp; 100% power, 825 MWe.

02-28-93 2400 This reporting period ended with the Unit operating at 100% power, 820 MWe.

UNIT TWO 02-01-93 0000 This reporting period began with the Unit operating at 100% power, 815 MWe.

02-02-93 1200 Started Unit coastdown to maintain primary coolant average temperature (Tave) due to fuel depletion; 100% power, 815 MWe.

02-28-93 2400 This reporting period ended with the Unit in a coastdown due to fuel depletion at 81.5%

power, 675 MWe.

e Surry Monthly Operating Report No. 93-02 Page 10 of 20 FACILITY CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTH/YEAR: February 1993 EWR 90-246 Engineering Work Request 02-04-93 (Safety Evaluation No.90-168)

Engineering Work Request EWR 90-246 installed foundations and services to support the erection of a modular office building located within the protected area.

The installation is a non-nuclear plant facility that has no adverse impact on any safety-related or nonsafety-related system, component, or structure.

Therefore, an unreviewed safety question was not created.

DCP 89-18-3 Design Change Package 02-09-93 (Safety Evaluation No.90-116)

Design Change Package DCP 89-18-3 installed an air conditioning unit inside mechanical equipment room (MER) 4 to improve the environmental parameters of the room.

The nonsafety-related modification does not negatively affect safety-related components or systems and will extend the life of equipment in MER 4.

Therefore, an unreviewed safety question was not created.

DCP 92-27-3 Design Change Package 02-09-93 Design Change Package DCP 92-27-3 replaced the Unit 1 and 2 charging pump service water temperature control valves.

The design of the new valves is similar to the original valves, but is less susceptible to clogging by service water particulate. The modification did not adversely impact the operation or alter the design requirements or design features of any system. Therefore, an unreviewed safety question was not created.

EDSCR S92-081 Equipment Data System Change Request 02-09-93 (Safety Evaluation No.93-020)

Equipment Data System Change Request S92-081 changes the classification of the Unit 1 and 2 containment gas and particulate radiation monitors (1-RM-RMS-159, 1-RM-RMS-160, 2-RM-RMS-259, and 2-RM-RMS-260) from "Safety-Related" (SR) to "Nonsafety-Related with Special Quality/Regulatory Requirements" (NSQ).

An evaluation of this change determined that these radiation monitors do not perform a safe shutdown function and are not required for accident mitigation.

Furthermore, there is no failure mechanism associated with these radiation monitors that could result in a design basis accident. Therefore, an unreviewed safety question is not created.

e Surry Monthly Operating Report No. 93-02 Page 11 of 20 FACILITY CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTH/YEAR: February 1993 TM S1-93-03 Temporary Modification 02-16-93 (Safety Evaluation No.93-026)

Temporary Modification TM S1 03 installs temporary tubing to route the discharge of the Unit 1 recirculating spray heat exchanger (RSHX) service water (SW) radiation monitoring pumps 1-SW-P-5A, 58, 5C, and 5D to a spare penetration on the Unit 2 SW 24 inch pipe in the Unit 2 safeguards. This modification supports the installation of flow instrumentation in the Unit 2 RSHX SW 24 inch piping.

The temporary tubing is pressure rated to withstand the RSHX SW radiation monitoring system pump discharge. The RSHX SW radiation monitoring system will be tested following installation and removal of the modification and will remain operable. Therefore, an unreviewed safety question is not created.

TM S1-93-04 Temporary Modification 02-21-93 (Safety Evaluation No.93-030)

Temporary Modification TM S 1-93-04 installed a temporary 120 volt AC power strip from the radiation monitor cabinet 1-1 power supply to radiation monitor cabinet 1-2.

This modification returned cabinet 1-2 to service following the failure of its Sola transformer. This alignment does not constitute any additional emergency bus loading since both cabinets are normally powered from the 1H1-1 motor control center. Therefore, an unreviewed safety question was not created.

FS92-121 UFSAR Change 02-25-93 (Safety Evaluation 93-032)

Updated Final Safety Analysis Report (UFSAR) Section 10.3.9.2, "[Bearing Cooling Water System] Description" is being revised to reflect a change in the chemical treatment of the bearing cooling (BC) system.

The corrosion inhibitor for the bearing cooling system was changed from a sodium molybdate solution to sodium nitrate in 1992. This change was approved by the Virginia State Water Control Board. The new chemical treatment does not adversely affect the BC or any other plant system.

Therefore, an unreviewed safety question was not created.

. e Surry Monthly Operating Report No. 93-02 Page 12of 20 FACILITY CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTH/YEAR: February 1993 TM S1-93-05 Temporary Modification 02-26-93 (Safety Evaluation No.93-034)

Temporary Modification TM S1-93-05 removed the inspection plates from the Unit 1 A reactor coolant pump stator cooler. This modification was made to lower the stator temperature which had risen due to a degraded stator cooling heat exchanger.

This modification was recommended by the pump designer (Westinghouse) and does not impact reactor coolant pump operability. Therefore, an unreviewed safety question was not created.

e e Surry Monthly Operating Report No. 93-02 Page 13of 20 PROCEDURE OR METHOD OF OPERATION CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTH/YEAR: February 1993 1-PT-18.SA Periodic Test Procedures 02-04-93 2-PT-18.SA (Safety Evaluation No.93-018)

Periodic Test Procedures 1-PT-18.SA and 2-PT-18.SA, "Charging Pump Component Cooling Performance," were changed ("one-time only") to permit manual operator action in lieu of the automatic start function for component cooling (CC) pumps 1/2-CC-P-2A and 1/2-CC-P-2B during data collection for pump curve verification.

The standby pump will be placed in the "Off" mode (thereby defeating the automatic start capability) for approximately ten minutes while the running pump's discharge valve is throttled to obtain various flow rates. The running and standby pumps will both be considered fully operable since an operator will be present to initiate the required manual actions to ensure sufficient CC flow is maintained to the charging pump seals. Therefore, an unreviewed safety question is not created.

1-PT-18.8 Periodic Test Procedures 02-04-93 2-PT-18.8 (Safety Evaluation No.93-019)

Periodic Test Procedures 1-PT-18.8 and 2-PT-18.8, "Charging Pump Service Water Performance," were changed ("one-time only") to permit manual operator action in lieu of the automatic start function for service water (SW) pumps 1/2-SW-P-10A and 1/2-SW-P-10B during data collection for pump curve verification.

The standby pump will be placed in the "Off" mode (thereby defeating the automatic start capability) for approximately ten minutes while the running pump's discharge valve is throttled to obtain various flow rates. The running and standby pumps will both be considered fully operable since an operator will be present to initiate the required manual actions to ensure sufficient SW flow is maintained to the charging pump lube oil coolers. Therefore, an unreviewed safety question is not created.

O-ECM-0105-01 Electrlcal Corrective Maintenance Procedure 02-11-93 O-ECM-0105-02 (Safety Evaluation No.93-022)

Electrical Corrective Maintenance Procedures O-ECM-0105-01, "Appendix R ELT Inspection and Rework" and O-ECM-0105-02, "Fire Code ELT Inspection and Rework" were developed to provide instructions for conducting performance discharge tests for emergency lighting.

These procedures may be implemented while the Units are at power and will be performed for only one common (to both Units) fire area at a time or for one fire area on each Unit at a time. Battery powered lanterns are provided in the Appendix R cabinet for use by Operations personnel during the test and for the 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> post test period in which the emergency lighting batteries are being recharged. This activity will not affect the probability of occurrence or the consequences of any previously analyzed accidents. Therefore, an unreviewed safety question is not created.

. e e Surry Monthly Operating Report No. 93-02 Page 14of 20 PROCEDURE OR METHOD OF OPERATION CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTH/YEAR: February 1993 1-0P-RC-005 Operating Procedure 02-11-93 2-0P-RC-005 (Safety Evaluation No.93-023)

Operating Procedures 1-0P-RC-005 and 2-0P-RC-005, "Draining the RCS From Flange Level to Mid-Nozzle (Reduced Inventory)" were revised to change the residual heat removal (RHR) low flow alarm setpoint and the RHR heat exchanger outlet high temperature alarm setpoint to compensate for reduced inventory operating conditions.

These changes establish an additional annunciator setpoint for use during reduced inventory operation since RHR flow during reduced inventory operation can be less than the normal low flow annunciator setpoint, resulting in a continuous alarm condition. The changes do not affect control or protective circuits and will ensure annunciation of a loss of RHR flow. Therefore, an unreviewed safety question is not created.

1-0P-5.1.5 Operating Procedure 02-12-93 (Safety Evaluation No.93-025)

Operating Procedure 1-0P-5.1.5, "Venting the PRT" was temporarily changed to provide instructions for venting the pressurizer relief tank (PRT) to the containment atmosphere.

The procedure imposes special venting requirements to significantly reduce the hazards associated with venting hydrogen from the PRT. The release of the PRT contents to the containment atmosphere does not pose any design or operational concerns and has no impact on the UFSAR accident analyses. Therefore, an unreviewed safety question is not created.

2-ECM-2403-02 Electrlcal Corrective Maintenance Procedure 02-16-93 (Safety Evaluation No.93-027)

Electrical Corrective Maintenance Procedure 2-ECM-2403-02, "RSS Transformer B Outage with Backfeed of Transfer Bus E" was revised to provide instructions for implementing temporary modifications to defeat automatic tripping and lockout of selected 4160 volt breakers associated with transfer bus E. These modifications will ensure a reliable electric plant lineup during a reserve station service transformer B outage while on Unit 2 backfeed to transfer bus E.

This procedure will be performed with Unit 2 at cold shutdown and will provide for the normal Unit 2 backfeed line-up. Safety systems and emergency diesel generators will remain available to Unit 1. Therefore, an unreviewed safety question is not created.

-Surry Monthly Operating Report No. 93-02 Page 15 of 20 PROCEDURE OR METHOD OF OPERATION CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTH/YEAR: February 1993 2-ECM-2403-01 Electrlcal Corrective Maintenance Procedure 02-16-93 (Safety Evaluation No.93-028)

Electrical Corrective Maintenance Procedure 2-ECM-2403-01, "RSS Transformer A Outage with Backfeed of Transfer Bus D" was revised to provide instructions for implementing temporary modifications to defeat automatic tripping and lockout of selected 4160 volt breakers associated with transfer bus D. These modifications will ensure a reliable electric plant lineup during a reserve station service transformer A outage while on Unit 2 backfeed to transfer bus D.

This procedure will be performed with Unit 2 at cold shutdown and will provide for the normal Unit 2 backfeed line-up. Safety systems and emergency diesel generators will remain available to Unit 1. Therefore, an unreviewed safety question is not created.

1/2-0PT-ZZ-001 Operations Periodic Test Procedures 02-18-93 1/2-0PT-ZZ-002 Electrical Periodic Test Procedures 1/2-EPT-1801-01 (Safety Evaluation No.93-029) 1/2-EPT-1801-02 Operations Periodic Test Procedures 1/2-0PT-ZZ-001, "ESF Actuation with Undervoltage and Degraded Voltage - 1H [2H] Bus", 1/2-0PT-ZZ-002, "ESF Actuation with Undervoltage and Degraded Voltage - 1J [2J] Bus" and Electrical Periodic Test Procedures 1/2-EPT-1801-01, "Bus 1H [2H] Protective Relay Testing" and 1/2-EPT-1801-02, "Bus 1J [2J] Protective Relay Testing" were revised/developed to provide instructions for lifting electrical leads and installing jumpers to support engineered safety feature (ESF) and undervoltage testing.

The Unit will be at cold shutdown during the performance of these tests. 1/2-0PT-ZZ-001 and 1/2-0PT-ZZ-002 will be performed prior to refueling operations and will require two methods of core cooling. 1/2-EPT-1801-01 and 1/2-EPT-1801-02 will be performed with no fuel in the reactor vessel and no fuel movement in progress. The procedurally controlled temporary modifications and administrative controls will ensure compliance with the Technical Specifications. Therefore, an unreviewed safety question is not created.

e Surry Monthly Operating Report No. 93-02 Page 16 of 20 PROCEDURE OR METHOD OF OPERATION CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTH/VEAR: February 1993 2-0PT-Sl-006 Operations Periodic Test Procedure 02-23-93 (Safety Evaluation No.93-031)

Operations Periodic Test Procedure, 2-0PT-Sl-006, "SI Accumulator Discharge Check Valves Full Open Test" was developed to verify that SI accumulator discharge check valves are free to open and exhibit full stroke operation.

The Unit will be at cold shutdown and the equipment and systems will be operated within design limits during the performance of this test. Measures will be taken to preclude the introduction of gas into the reactor coolant and residual heat removal systems. Reactivity addition will be precluded by ensuring the accumulator boron concentration is greater than the reactor coolant system (RCS) concentration and by ensuring accumulator temperature is greater than the RCS shutdown margin temperature. Therefore, an unreviewed safety question is not created.

• ' -Surry Monthly Operating Report No. 93-02 Page 17 of 20 TESTS AND EXPERIMENTS THAT DID NOT REQUIRE NRC APPROVAL MONTH/YEAR: February 1993 No entries for this reporting period.

e Surry Monthly Operating Report No. 93-02 Page 18 of 20 CHEMISTRY REPORT MONTH/YEAR: February 1993 Unit No. 1 Unit No. 2 Primarv Coolant Analvsis Max. Min. Ava. Max. Min. Ava.

Gross Radioact., u.Cilml 4.95E-1 2.33E-2 3.30E-1 3.57E-1 1.63E-1 2.59E-1 Suspended Solids, oom < 0.1 < 0.1 < 0.1 < 0.1 < 0.1 < 0.1 Gross Tritium, u.Ci/ml 2.38E-1 1.51E-1 1.99E-1 8.22E-2 4.89E-2 2.65E-1 1131, u.Ci/ml 1.06E-3 8.69E-5 6.58E-4 4.92E-3 3.16E-4 2.43E-3 1131/I133 0.14 0.07 0.09 0.32 0.11 0.20 Hvdroaen, cc/ka 47.5 28.2 37.2 48.2 31.4 39.0 Lithium, oom 2.30 2.06 2.15 1.13 0.64 0.78 Boron - 10, oom

• 226.4 132.5 157.7 0.98 0.22 0.37 Oxvaen, (DO). oom < 0.005 < 0.005 < 0.005 < 0.005 < 0.005 < 0.005 Chloride oom 0.004 0.002 0.003 0.005 < 0.001 0.002 pH at 25 degree Celsius 6.76 6.42 6.70 9.03 8.32 8.68 Boron - 10 = Total Boron x 0.196 Comments:

None.

e Surry Monthly Operating Report No. 93-02 Page 19 of 20 FUEL HANDLING UNITS 1 & 2 MONTH/YEAR: February 1993 New or Spent Number of New or Spent Fuel Shipment Date Stored or Assemblies Assembly ANSI Initial Fuel Shipping Number Received eer Shiement Number Number Enrichment Cask Activit~

Unit2 Total Batch 14 Shipment Shipment 6 02-11-93 14 6W2 LMOX47 4.0 17.29 Ci OW9 LMOX2N 3.8 1W3 LMOX2S 3.8 3W2 LMOX45 3.8 6W5 LMOX4A 4.0 6W6 LMOX4B 4.0 3W1 LMOX44 3.8 6W3 LMOX48 4.0 6W7 LMOX4C 4.0 6W8 LMOX4D 4.0 2W9 LMOX42 3.8 6W4 LMOX49 4.0 3WO LMOX43 3.8 6W1 LMOX46 4.0

e Surry Monthly Operating Report No. 93-02 Page 20 of 20 DESCRIPTION OF PERIODIC TEST(S) WHICH WERE NOT COMPLETED WITHIN THE TIME LIMITS SPECIFIED IN TECHNICAL SPECIFICATIONS MONTH/YEAR: February 1993 None During This Reporting Period.