ML18153B371

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

ML18153B371
Person / Time
Site:	Surry
Issue date:	10/31/1993
From:	Bowling M, Mason D, Olsen C VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
93-721, NUDOCS 9311180301
Download: ML18153B371 (18)

Text

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VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND, VIRGINIA 23261 November 12, 1993 U. S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, D. C. 20555 Gentlemen:

VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION UNITS 1 AND 2 MONTHLY OPERATING REPORT Serial No.

NO/RPC:vlh Docket Nos.

License Nos.93-721 50-280 50-281 DPR-32 DPR-37 Enclosed is the Monthly Operating Report for Surry Power Station Units 1 and 2 for the month of October 1993.

Very truly yours,

/f1I Id~

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 931118.0301 931031' ~ /f;l\\

PDR ADDCK.. 050.00280

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VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION MONTHLY OPERATING REPORT REPORT NO. 93-10 Approved:

TABLE OF CONTENTS Section

-urry Monthly Operating Report No. 93-10 Page 2 of 17 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........................................... 12 Tests and Experiments That Did Not Require NRC Approval...................................................................... 14 Chemistry Report............................................................................................................................. 15 Fuel Handling - Unit No. 1................................................................................................................... 16 Fuel Handling - Unit No. 2................................................................................................................... 16 Description of Periodic Test(s) Which Were Not Completed Within the Time Limits Specified in Technical Specifications................................................................................................... 17 l

-Surry Monthly Operating Report No. 93-10 Page 3 of 17 OPERATING DATA REPORT Docket No.:

Date:

Completed By:

50-280 11-03-93 D. Mason Telephone:

(804) 365-2459

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

2.

Reporting Period:..........................................

3.

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

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

5.

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

6.

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

7.

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

Surry Unit 1 October, 1993 2441 847.5 788 820 781

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

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

10. Reasons For Restrictions, If Any:

This Month

11. Hours In Reporting Period..........................

12. Number of Hours Reactor Was Critical..........

13. Reactor Reserve Shutdown Hours...............

14. Hours Generator On-Line...........................

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

16. Gross Thermal Energy Generated (MWH)......

17. Gross Electrical Energy Generated (MWH)....

18. Net Electrical Energy Generated (MWH)........

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

20. Unit Availability Factor...............................

21. Unit Capacity Factor (Using MDC Net)...........

22. Unit Capacity Factor (Using DER Net)...........

23. Unit Forced Outage Rate............................

745.0 745.0 0.0 745.0 0.0 1818545.0 608150.0 585636.0 100.0%

100.0%

100.7%

99.8%

0.0%

YTD 7296.0 6968.2 0.0 6939.6 0.0 16629517.4 5531775.0 5285586.0 95.1%

95.1%

92.8%

91.9%

1.8%

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

Refueling (10 Year ISi), February 4, 1994, 70 Days

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

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

Cumulative 182856.0 122343.2 3774.5 120215.0 3736.2 280248796.5 91550028.0 86883446.0 65.7%

67.8%

61.3%

60.3%

17.6%

FORECAST INITIAL CRITICALITY ACHIEVED INITIAL ELECTRICITY COMMERCIAL OPERATION

4lurry Monthly Operating Report No. 93-10 Page 4of 17 OPERATING DATA REPORT Docket No.:

Date:

Completed By:

50-281 11-03-93 D. Mason Telephone:

(804) 365-2459 1. Unit Name:...................................................

2.

Reporting Period:..........................................

3.

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

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

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

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

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

Surry Unit 2 October, 1993 2441 847.5 788 820 781

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

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

10. Reasons For Restrictions, If Any:

11. Hours In Reporting Period..........................

12. Number of Hours Reactor Was Critical..........

13. Reactor Reserve Shutdown Hours...............

14. Hours Generator On-Line...........................

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

16. Gross Thermal Energy Generated (MWH)......

17. Gross Electrical Energy Generated (MWH)....

18. Net Electrical Energy Generated (MWH)........

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

20. Unit Availability Factor...............................

21. Unit Capacity Factor (Using MDC Net)...........

22. Unit Capacity Factor (Using DER Net)...........

23. Unit Forced Outage Rate............................

This Month 745.0 745.0 0.0 745.0 0.0 1781856.3 593870.0 570895.0 100.0%

100.0%

98.1%

97.2%

0.0%

YID 7296.0 5294.6 0.0 5198.2 0.0 11807512.5 3898080.0 3721313.0 71.2%

71.2%

65.3%

64.7%

10.8%

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):

Cumulative 179736.0 118981.5 328.1 117129.2 0.0 273138586.3 89093984.0 84511726.0 65.2%

65.2%

60.3%

59.7%

14.2%

FORECAST INITIAL CRITICALITY ACHIEVED INITIAL ELECTRICITY COMMERCIAL OPERATION

(1)

.urry Monthly Operating Report No. 93-10 Page 5of 17 UNIT SHUTDOWN AND POWER REDUCTION (EQUAL To OR GREATER THAN 20%}

REPORT MONTH: October, 1993 (2)

(3)

(4)

(5)

Docket No.: 50-280 Unit Name: Surry Unit 1 Date: 11-01-93 Completed by: Craig Olsen Telephone: (804) 365-2155 Duration Method of Reason Shutting Down Rx LER No.

System Component Cause & Corrective Action to Date Type Hours Code Code Prevent Recurrence (1)

F:

Forced S: Scheduled (4)

(2)

REASON:

None during this reporting period.

A -

Equipment Failur~ (Explain)

B Maintenance or Test C

Refueling D

Regulatory Restriction E

Operator Training & Licensing Examination F

Administrative G

Operational Error (Explain)

Exhibit G - Instructions for Preparation of Data Entry Sheets for Licensee Event Report (LER) File (NUREG 0161)

(3)

METHOD:

1 -

Manual 2 -

Manual Scram.

3 -

Automatic Scram.

4 -

Other (Explain)

(5)

Exhibit 1 - Same Source.

eurry Monthly Operating Report No. 93-10 Page 6 of 17 UNIT SHUTDOWN AND POWER REDUCTION (EQUAL To OR GREATER THAN 20%)

REPORT MONTH: October, 1993 (1)

(2)

(3)

(4)

(5)

Method Docket No.: 50-281 Unit Name: Surry Unit 2 Date: 11-01-93 Completed by: Craig Olsen Telephone: (804) 365-2155 Duration of LER No.

System Component Cause & Corrective Action to Date Type Hours Reason Shutting Code Code Prevent Recurrence (1)

F:

Forced S: Scheduled (4)

(2)

REASON:

Down Rx None during this reporting period.

A -

Equipment Failure (Explain)

B Maintenance or Test C

Refueling D

Regulatory Restriction E

Operator Training & Licensing Examination F

Administrative G

Operational Error (Explain)

Exhibit G - Instructions for Preparation of Data Entry Sheets for Licensee Event Report (LER) File (NUREG 0161)

(3)

METHOD:

1 -

Manual 2

Manual Scram.

3 -

Automatic Scram.

4 -

Other (Explain)

(5)

Exhibit 1 - Same Source.

MONTH:

October, 1993 Day 1

2 3

4 5

6 7

8 9

10 11 12 13 14 15 16 INSTRUCTIONS

-urry Monthly Operating Report No. 93-10 Page ?of 17 AVERAGE DAILY UNIT POWER LEVEL Docket No.: 50-280 Unit Name: Surry Unit 1 Date: 11-03-93 Completed by: Pat Kessler Telephone: 365-2790 Average Daily Power Level Average Daily Power Level (MWe-Net)

Day (MWe-Net) 787 17 789 787 18 789 787 19 783 787 20 785 787 21 787 788 22 789 785 23 787 770 24 786 777 25 789 776 26 784 784 27 792 786 28 791 785 29 788 787 30 788 790 31 792 789 On this format, list the average daily unit power level in MWe - Net for each day in the reporting month. Compute to the nearest whole megawatt.

MONTH:

October, 1993 Day 1

2 3

4 5

6 7

8 9

10 11 12 13 14 15 16 INSTRUCTIONS

.urry Monthly Operating Report No. 93-10 Page 8 of 17 AVERAGE DAILY UNIT POWER LEVEL Docket No.: 50-281 Unit Name: Surry Unit 2 Date: 11-03-93 Completed by: Pat Kessler Telephone: 365-2790 Average Daily Power Level Average Daily Power Level (MWe-Net)

Day (MWe-Net) 772 17 769 774 18 769 771 19 768 769 20 765 768 21 765 770 22 764 768 23 766 768 24 764 767 25 769 770 26 764 769 27 759 767 28 759 769 29 748 769 30 759 767 31 760 771 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.

.urry Monthly Operating Report No. 93-10 Page 9 of 17

SUMMARY

OF OPERATING EXPERIIENCE MONTH/YEAR: October 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:

10/01/93 10/31 /93 UNIT Two:

10/01 /93 10/31 /93 0000 2400 0000 2400 The reporting period began with the Unit operating at 100% power, 820 MWe.

The reporting period ended with the Unit operating at 100% power, 820 MWe.

The reporting period began with the Unit operating at 98% power, 792 MWe, due to Steam Generator "C" level oscillations.

The reporting period ended with the Unit operating at 98.5% power, 790 MWe, due to Steam Generator "C" level oscillations.

FS 92-66 EWR 89-167 JCO C-93-004 EWR 87-224 FACILITY CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTH/YEAR: October, 1993 UFSAR Change (Safety Evaluation 93-192)

-urry Monthly Operating Report No. 93-10 Page 10 of 17 10-08-93 Updated Final Safety Analysis Report Change 92-66 revised section 10.3.5.2,

"[Condensate and Feedwater Systems] Description", to reflect the installation of a new resin separation system in the Condensate Polishing building.

This change to the nonsafety-related Condensate Polishing system did not affect any safety-related equipment or UFSAR accident analyses. Therefore, an unreviewed safety question does not exist.

Engineering Work Request 10-21-93 Engineering Work Request (EWR)89-167 evaluated the capped leak-off lines of certain Charging and Safety Injection system motor operated valves (MOVs) that are exposed to containment sump recirculation flow. The EWR also implemented the capping of some MOV leak-off lines.

The evaluation concluded that the subject.modifications did not affect the performance of the respective systems, did not change the total leakage to the atmosphere, or affect the applicable accident analyses.

Therefore, an unreviewed safety question does not exist.

Justification for Continued Operation (Safety Evaluation Nos.93-193, 93-197) 10-22-93 Justification for Continued Operation C-93-004 assessed continued operation with through wall leakage of certain Charging Pump Service Water system valves.

The assessment concluded, based on the design rating of the valves, the small amount of leakage, and a seismic integrity evaluation, that the subject system remained capable of performing its intended design function. The system will be walked down on a weekly basis to ensure any further degradation is promptly identified. Therefore, an unreviewed safety question does not exist.

Engineering Work Request 10-26-93 Engineering Work Request 87-224 installed an alternate power supply for the Emergency Radio Communications system "B" repeaters to ensure operation of the system in the event of a fire in the Unit 1 Cable Vault.

This modification enhanced the reliability of the nonsafety-related Emergency Radio Communications system and did not impact any safety-related equipment.

Therefore, an unreviewed safety question does not exist.

EWA 91-010 FACILITY CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTH/YEAR: October, 1993 Engineering Work Request (Safety Evaluation No. 91 ~164) 4lmy Monthly Operating Report No. 93-10 Page 11 of 17 10-26-93 Engineering Work Request 91-01 O installed quick disconnects and valves on certain Charging and Safety Injection system vents to reduce the potential for the spillage of radioactive fluids during the performance of periodic testing to ensure trapped gases are not present in the charging pump suction lines.

These modifications did not affect the safety-related boundaries of the Charging and Safety Injection systems or the ability of these systems to perform their intended safety functions. Therefore, an unreviewed safety question does not exist.

O-RM-B4, O-RM-B5 O-RM-C5, O-RM-D5 O-AP-20.01 O-AP-22.00 O-OPT-VS-001 SE 93-191 1-ECM-2403-01 4lmy Monthly Operating Report No. 93-10 Page 12 of 17 PROCEDURE OR METHOD OF OPERATION CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTH/YEAR: October, 1993 Annunciator Response Procedures Abnormal Operating Procedures Operations Periodic Test Procedure (Safety Evaluation No.93-189) 10-01-93 Annunciator Response Procedures O-RM-B4, "New Fuel Storage-Hi", O-RM-B5, "Fuel Pit Bridge-Hi", O-RM-C5, "Control Room Alert", O-RM-D5, "Control Room Hi", Abnormal Operating Procedures O-AP-20.01, "Main Control Room Oxygen Monitor - Alarm or Malfunction", O-AP-22.00, "Fuel Handling Abnormal Conditions", and Operations Periodic Test Procedure, O-OPT-VS-001, "Control Room Air Conditioning System Pump and Valve lnservice Testing" were revised to provide instructions for throttling chilled water to the main control room air handling units in order to improve ambient temperature control.

This change did not involve any physical modifications to the plant. Procedural guidance ensures that the minimum chilled water flow requirements are met during normal and post-accident operation. Therefore, an unreviewed safety question does not exist.

Safety Evaluation 10-05-93 Safety Evaluation 93-191 reviewed the previous safety evaluation performed for the Unit 1 Cycle 12 core reload in order to enhance the flexibility of operation following the end of full power reactivity (i.e., coastdown operation).

The review determined that the previous evaluation (which addressed a T avg/Power coast) was adequate to permit the plant to operate in a power only coastdown, except for three events. These events (Rod Withdrawal from Power, Rod Withdrawal from Subcritical, and Main Steamline Break) were reevaluated using conservative assumptions that are bounding for a power only coast. It was concluded that continued operation and subsequent coastdown to the cycle burn-up limit in accordance with the Technical Specifications would not violate the plant's design basis. Therefore, an unreviewed safety question does not exist.

Electrical Corrective Maintenance Procedure (Safety Evaluation No.93-199) 10-25-93 Electrical Corrective Maintenance Procedure 1-ECM-2403-01, "ASS Transformer A Outage with Backfeed of Transfer Bus D" was written 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 1 backfeed to transfer bus D.

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

1-ECM-2403-03 4lmy Monthly Operating Report No. 93-10 Page 13 of 17 PROCEDURE OR METHOD OF OPERATION CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTH/YEAR: October, 1993 Electrical Corrective Maintenance Procedure (Safety Evaluation No.93-200) 10-25-93 Electrical Corrective Maintenance Procedure 1-ECM-2403-03, "RSS Transformer C Outage with Backfeed of Transfer Bus F" was written to provide instructions for implementing temporary modifications to def eat automatic tripping and lockout of selected 4160 volt breakers associated with transfer bus F. These modifications will ensure a reliable electric plant lineup during a reserve station service transformer C outage while on Unit 1 backfeed to transfer bus F.

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

4lrry Monthly Operating Report No. 93-10 Page 14of 17 TESTS AND EXPERIMENTS THAT DID NOT REQUIRIE NRC APPROVAL MONTH/YEAR: October, 1993 None during this reporting period.

Primary Coolant Analysis Gross Radioactivitv, u.Ci/ml Susoended Solids, com Gross Tritium, u.Ci/ml 1131, u.Ci/ml 113111133 Hvdroaen, cc/ka Lithium, com Boron - 10, com*

Oxygen, (DO), ppm Chloride, com pH at 25 demee Celsius Boron - 1 O = Total Boron x 0.196 Comments:

None CHEMISTRY REPORT MONTH/YEAR: October, 1993 Unit No. 1 Max.

Min.

Avg.

4.47E-1 2.96E-1 3.64E-1

< 0.1

< 0.1

< 0.1 9.04E-2 5.68E-2 7.74E-2 1.70E-3 1.36E-4 1.1 OE-3 0.14 0.07 0.10 40.8 34.0 36.6 1.22 0.77 0.98 19.0 1.8 9.5

<0.005

~0.005

<0.005 0.003

<0.001 0.001 7.71 7.26 7.46

.urry Monthly Operating Report No. 93-10 Page 15 of 17 Unit No. 2 Max.

Min.

Avg.

2.28E-1 1.26E-1 1.64E-1

< 0.1

< 0.1

< 0.1 5.28E-1 3.52E-1 4.53E-1 1.07E-4 4.73E-5 7.53E-5 0.15 0.06 0.10 35.8 29.9 33.1 2.31 2.06 2.19 235.4 224.0 229.0

<0.005

~0.005

<0.005 0.010 0.004 0.007 6.50 6.25 6.34

New or Spent Fuel Shipment Date Stored or Number Received FUEL HANDLING UNITS 1 & 2 MONTH/YEAR: October, 1993 Number of Assemblies per Shipment Assembly Number ANSI Number

.urry Monthly Operating Report No. 93-10 Page 16 of 17 Initial Enrichment New or Spent Fuel Shipping Cask Activity No fuel received or stored during this reporting period.

.urry Monthly Operating Report No. 93-10 Page 17 of 17 DESCRIPTION OF PERIODIC TEST(S) WHICH WERE NOT COMPLETED WITHIN THE TIME LIMITS SPECIFIED IN TECHNICAL SPECIFICATIONS MONTH/YEAR: October, 1993 None during this reporting period.

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