ML18153A367

Monthly Operating Repts for Jan 1998 for Surry Power Station,Units 1 & 2

ML18153A367
Person / Time
Site:	Surry
Issue date:	01/31/1998
From:	Marshall G, Mason D, Steinert J VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To:
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ML18153A366	List: ML18153A365 ML18153A367
References
NUDOCS 9802200165
Download: ML18153A367 (17)

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VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION MONTHLY OPERATING REPORT REPORT No. 98-01 Approved: 2.-, '<- -9 e Station Manager Date

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• TABLE OF CONTENTS

• Surry Monthly Operating Report No. 98-01 Page 2 of 17 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 Nos. 1 and 2 ............................................................................................. 9 Facility Changes That Did Not Require NRC Approval ............................................................................................ 1O Procedure or Method of Operation Changes That Did Not Require NRC Approval. ................................................ 13 Tests and Experiments That Did Not Require NRC Approval .................................................................................. 14 Chemistry Report ..................................................................................................................................................... 15 Fuel Handling - Unit Nos. 1 and 2 ............................................................................................................................ 16 Description of Periodic Test(s) Which Were Not Completed Within the Time Limits Specified in Technical Specifications ....................................................................................................................... 17

• OPERATING DATA REPORT

• Surry Monthly Operating Report No. 98-01 Page 3 of 17 Docket No.: 50-280 Date: 02/04/98 Completed By: D. K. Mason Telephone: (757) 365-2459

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

2. Reporting Period: ................................................ .. January, 1998

3. Licensed Thermal Power (MWt): ........................ :. 2546

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

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

6. Maximum Dependable Capacity (Gross MWe): ... . 840

7. Maximum Dependable Capacity (Net MWe): ...... .. 801

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 Year-To-Date Cumulative

11. Hours in Reporting Period 744.0 744.0 220128.0

12. Hours Reactor Was Critical 744.0 744.0 154769.8

13. Reactor Reserve Shutdown Hours 0.0 0.0 3774.5

14. Hours Generator On-Line 744.0 744.0 152343.5

15. Unit Reserve Shutdown Hours 0.0 0.0 3736.2

16. Gross Thermal Energy Generated (MWH) 1893551.9 1893551.9 358138567. 5

17. Gross Electrical Energy Generated (MWH) 634994.0 634994.0 117450748.0

18. Net Electrical Energy Generated (MWH) 613523.0 613523.0 111847744.0

19. Unit Service Factor 100.0% 100.0% 69.2%

20. Unit Availability Factor 100.0% 100.0% 70.9%

21. Unit Capacity Factor (Using MDC Net) 102.9% 102.9% 65.3%

22. Unit Capacity Factor (Using DER Net) 104.6% 104.6% 64.5%

23. Unit Forced Outage Rate 0.0% 0.0% 14.7%

24. Shutdowns Scheduled 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

• OPERATING DATA REPORT

• Surry Monthly Operating Report No. 98-01 Page 4 of 17 Docket No.: 50-281 Date: 02/04/98 Completed By: D. K. Mason Telephone: (757) 365-2459

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

2. Reporting Period: ................................................. . January, 1998

3. Licensed Thermal Power (MWt): ......................... . 2546

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

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

6. Maximum Dependable Capacity (Gross MWe): ... . 840

7. Maximum Dependable Capacity (Net MWe): ....... . 801

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. Year-To-Date Cumulative

11. Hours in Reporting Period 744.0 744.0 217009.0

12. Hours Reactor Was Critical 744.0 744.0 151894.3

13. Reactor Reserve Shutdown Hours o:o 0.0 328.1

14. Hours Generator On-Line 744.0 744.0 149877.4

15. Unit Reserve Shutdown Hours 0.0 0.0 0.0

16. Gross Thermal Energy Generated (MWH) 1894101.8 1894101.8 353427669.1

17. Gross Electrical Energy Generated (MWH) 635470.0 635470.0 115761078.0

18. Net Electrical Energy Generated (MWH) 614752.0 614752.0 110257903.0

19. Unit Service Factor 100.0% 100.0% 69.1%

20. Unit Availability Factor 100.0% 100.0% 69.1%

21. Unit Capacity Factor (Using MDC Net) 103.2% 103.2% 65.0%

22. Unit Capacity Factor (Using DER Net) 104.9% 104.9% 64.5%

23. Unit Forced Outage Rate 0.0% 0.0% 11.9%

24. Shutdowns Scheduled 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

• UNIT SHUTDOWN AND POWER REDUCTION (EQUAL To OR GREATER THAN 20%)

• Surry Monthly Operating Report No. 98-01 Page 5 of 17 REPORT MONTH: January, 1998 Docket No.: 50-280 Unit Name: Surry Unit 1 Date: 02/03/98 Completed by: G. N. Marshall Telephone: (757) 365-2465 (1) (2) (3) (4) (5)

Method Duration of LER No. System Component Cause & Corrective Action Date Type Hours Reason Shutting Code Code to Prevent Recurrence Down Rx None During the 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)

• UNIT SHUTDOWN AND POWER REDUCTION (EQUAL To OR GREATER THAN 20%)

• Surry Monthly Operating Report No. 98-01 Page 6 of 17 REPORT MONTH: January, 1998 Docket No.: 50-281 Unit Name: Surry Unit 2 Date: 02/03/98 Completed by: G. N. Marshall Telephone: (757) 365-2465 (1) (2) (3) (4) (5)

Method Duration of LER No. System Component Cause & Corrective Action Date Type Hours Reason Shutting Code Code to Prevent Recurrence Down Rx None During the 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)

• AVERAGE DAILY UNIT POWER LEVEL

• Surry Monthly Operating Report No. 98-01 Page 7 of 17 Docket No.: 50-280 Unit Name: Surry Unit 1 Date: 02/03/98 Completed by: J. C. Steinert Telephone: (757) 365-2834 MONTH: January, 1998 Average Daily Power Level Average Daily Power Level Day (MWe - Net) Day (MWe - Net) 1 821 17 824 2 825 18 827 3 825 19 828 4 825 20 827 5 825 21 823 6 825 22 823 7 825 23 827 8 824 24 827 9 823 25 824 10 824 26 825 11 824 27 827 12 824 28 826 13 823 29 825 14 823 30 826 15 821 31 826 16 821 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.

• AVERAGE DAILY UNIT POWER LEVEL

• Surry Monthly Operating Report Docket No.: 50-281 No. 98-01 Page 8 of 17 Unit Name: Surry Unit 2 Date: 02/03/98 Completed by: John C. Steinert Telephone: (757) 365-2837 MONTH: January, 1998 Average Daily Power Level Average Daily Power Level Day (MWe - Net) Day (MWe - Net) 1 830 17 826 2 827 18 827 3 827 19 826 4 827 20 826 5 827 21 827 6 827 22 826 7 824 23 827 8 824 24 827 9 827 25 828 10 827 26 828 11 828 27 823 12 827 28 826 13 827 29 826 14 822 30 827 15 822 31 827 16 822 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.

SUMMARY

OF OPERATING EXPERIENCE

• Surry Monthly Operating Report No. 98-01 Page 9 of 17 MONTHNEAR: JANUARY, 1998 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:

01/01/98 0000 Unit 1 operating at 100% / 855 MWe.

01/31/98 2400 Unit 1 operating at 100% / 855 MWe.

UNIT Two:

01/01/98 0000 Unit 2 operating at 100% / 855 MWe.

01/31/98 2400 Unit 2 operating at 100% / 855 MWe.

• FACILITY CHANGES THAT DID NOT REQUIRE NRC APPROVAL Surry Monthly Operating Report No. 98-01 Page 10 of 17 MONTHNEAR: JANUARY, 1998 FS 97-49 UFSAR Change Request 01/05/98 (Safety Evaluation No. 98-0001)

UFSAR Change Request FS 97-49 revised section 7.5.1.4.1 to clarify the terminology regarding administrative control for the containment vacuum pump Hand-Off-Auto Switch.

This change was editorial in nature with no physical changes to any systems and/or components. The containment vacuum pumps are not safety related nor are their controls discussed in Technical Specifications. Therefore, an unreviewed safety question does not exist.

DR S-97-3400 Deviation Report 01/05/98 (Safety Evaluation No. 98-0002)

Safety Evaluation No. 98-0002 was written to evaluate the condition -addressed in Deviation Report S-97-3400 concerning the manual operation of a Unit 2 condensate recirculation valve. The purpose of this valve is to provide recirculation flow at low power levels to protect the main condensate pumps from overheating. A calculation was performed to determine the rate of temperature rise should the recirculation valve remain closed. Assuming equal rise across each of the nine stages of the pump, the first stage would flash first in approximately 55 minutes. This time is considered ample to manually open the valve.

The probability and consequences of an accident as identified in the SAR are not increased by this activity since the activity would be bounded by the analysis in the SAR.

This activity does not place the plant in an unanalyzed condition. Therefore, an unreviewed safety question does not exist.

FS 97-12 UFSAR Change Request 01/08/98 (Safety Evaluation No. 98-0004)

UFSAR Change Request FS 97-12 replaces various figures (photocopies of station controlled drawings) with simplified system diagrams. Limiting direct correlation between UFSAR figures and station controlled drawings will eliminate unnecessary redundancy of controlled documents and will reduce the potential for conflicting information in distinct documents. The simplified diagrams have been developed from Nuclear Control Room Operator Training Program Manual figures, Design Basis Document Figures, and CAD versions of the station controlled drawings.

Each section of the UFSAR which contain station controlled drawings will have a list of reference drawings added in order to maintain the link between the licensing basis and the design basis. Plant equipment will not be operated in a different manner. Therefore, an unreviewed safety question does not exist TM S1-98-01 Temporary Modification 01/13/98 (Safety Evaluation No. 98-0005)

This Temporary Modification (TM) involves the installation of two wire jumpers to provide continued operation of automatic safety functions of train "A" Safety Injection while replacing a failed test switch. Train "B" will be unaffected by the TM and will function as designed at all times.

This TM will allow train "A" of SI to provide automatic trip functions as designed while replacing the failed test switch. Therefore, an unreviewed safety question does not exist.

• FACILITY CHANGES THAT DID NOT REQUIRE NRC APPROVAL Surry Monthly Operating Report No. 98-01 Page 11 of 17 MONTHNEAR: JANUARY, 1998 FS 97-45 UFSAR Change Request 01/15/98 (Safety Evaluation No. 98-0007)

UFSAR Change Request FS 97-45 deleted section 12.2.2.3, item 6, which required Senior Reactor Operator (SRO) candidates to have held an RO license and to have engaged in licensed duties for a minimum of two years. The change also eliminated references No. 2 and No. 3 on page 12.2-5 which stated that the Licensed Operator Requalification Program (LORP) is in accordance with an NRC correspondence dates January 18, 1984, and March 30, 1984. These changes are consistent with 10CFR55 requirements, accredited training programs, and training program guides.

The changes made to the UFSAR were administrative in nature and not contrary to other commitments. Therefore, an unreviewed safety question does not exist.

FS 97-38 UFSAR Change Request 01/15/98 (Safety Evaluation No. 98-0008)

UFSAR Change Request FS 97-38 revised UFSAR Chapter 17, "Quality Assurance Topical Report," to change the approach for the qualification of inspection personnel. The method of qualification of inspection personnel described previously required one individual in the Training Department to be responsible for the training and qualification of inspection personnel. The revised approach will place the responsibility for qualification of inspection personnel with the Quality Inspection Coordinator in the Licensing Department.

The changes made to the UFSAR QA Topical Report will provide an additional level of assurance to the overall qualification program to prevent any conflicts in interest.

Therefore, an unreviewed safety question does not exist.

• TM S1-98-02 Temporary Modification 01/16/98 (Safety Evaluation No. 98-0009)

This Temporary Modification (TM) involves the installation of a replacement resistance temperature device (RTD) in the local temperature indicator thermowell to monitor "C" Steam Generator Feedwater inlet temperature. The thermowell normally used has failed, rendering the normal RTD inoperable. The modification is needed so that a reliable and accurate calorimetric can be retained. The normal RTD thermowell length is longer than the local temperature thermowell. The safety evaluation concluded that the difference in length is acceptable because historical data shows close agreement in the temperature readings, having a negligible effect on the calorimetric.

The use of the local temperature indication thermowell will be of the same design as the normal RTD with the exception of the thermowell length. Therefore, an unreviewed safety question does not exist.

FS 98-01 UFSAR Change Request 01/26/98 (Safety Evaluation No. 98-0012)

UFSAR Change Request FS 98-01 revised section 11.2.3. References to typical steam flow rates and generator blowdown flow rates were changed. The steam generator blowdown flow rates reflect typical operation at 60 gallons per minute per steam generator (180 gpm total) versus the 50 gpm (150 gpm total) noted in the UFSAR. By increasing the referenced blowdown flow rate to a more typical value, the accuracy of the UFSAR is

• FACILITY CHANGES THAT DID Nor REQUIRE NRC APPROVAL Surry Monthly Operating Report No. 98-01 Page 12 of 17 MONTHNEAR: JANUARY, 1998 improved and the higher flow rate is conservative with respect to expected blowdown ion exchanger run length.

Obsolete data was eliminated from the UFSAR, and where appropriate, updated references were added. No plant systems, structures or components were altered.

Therefore, an unreviewed safety question does not exist.

DCP 97-001 Design Change Package 01/05/98 (Safety Evaluation 97-004 Rev. 1)

Design Change Package (DCP)97-001, relocated the flow switch for a safety related auxiliary ventilation system exhaust filter fan to the opposite side of the ventilation duct allowing for a proper flow profile. The switch will be easier to calibrate in the new location and will improve the representation of the sample. The purpose of the switch is to ensure that the fan is de-energized, closing the outlet damper, preventing backflow and the possible spread of contamination.

The low flow trip of the fan is not required for the fan to meet its design function for filtering.

Therefore, an unreviewed safety question does not exist.

• PROCEDURE OR METHOD OF OPERATION CHANGES THAT DID Nor REQUIRE NRC APPROVAL

• Surry Monthly Operating Report No. 98-01 Page 13 of 17 MONTHNEAR: January, 1998 1/2-0P-S 1-002 Operations Procedures 01/15/98 1/2-0P-S 1-004 (Safety Evaluation No.98-006)

Operations procedures 1/2-0P-Sl-002, 'SI Accumulators," and 1/2-0P-Sl-004, 'Filling SI Accumulators," were revised to provide provisions to allow associated valves, being controlled administratively, to be closed within ten minutes after a safety injection signal is received instead of immediately. The associated valves are administratively controlled during the filling of the Safety Injection (SI) Accumulators using the above procedures. A conservative time of ten minutes will be used as the required time to close the valves to maintain the minimum RWST level required by technical specification. An Engineering calculation determined that inventory loss would take approximately eighteen minutes.

Specifying that the valves will be closed within ten minutes will ensure that the RWST level limit are not violated and that the assumptions made in the engineering calculation for the accident analysis for the SI and Containment Spray systems remain valid. Therefore, an unreviewed safety question does not exist.

STD-FP-1997 -8116 Vendor Procedures 01/22/98 STD-FP-1986-2714 (Safety Evaluation No. 98-0010)

Westinghouse vendor procedures STD-FP-1997-i3116 Rev. 0, 'Surry Fuel Assembly 16A/

5K7 Recovery Site Specific Procedure," and SE-FP-1986-2714 Rev. 5, 'MFRS Elevator and Basket System," were evaluated for use in the fuel reconstitution effort of fuel assemblies 16A and 5K7. The process involves the installation of Westinghouse's Multipurpose Fuel Repair System (MFRS) in the spent fuel pool to allow rotation of the fuel assembly for access to both the top and bottom nozzle. The MFRS is used to raise the irradiated fuel assemblies nearer to the pool's surface but a mechanical stop will be installed to ensure that UFSAR criterion will not be exceeded. Temporary replacement of the new fuel elevator basket with a Westinghouse basket may be required. If required, the replacement will be performed in accordance with the station Temporary Modification Program.

The possibility of an accident or malfunction of a different type than any evaluated previously in the safety analysis report is not increased and the margin of safety as defined in any Technical Specifications is not reduced. Therefore, an unreviewed safety question does not exist.

2-0SP-EG-001 Operations Surveillance Procedure 01/28/98 (Safety Evaluation No. 98-0014)

Operations Surveillance Procedure 2-0SP-EG-001, 'Number 2 Emergency Diesel Generator Local Alarm Panel Functional Test,"was developed to perform a functional test on the Number 2 Emergency Diesel Generator Local Alarm Panel. A procedurally controlled Temporary Modification (electrical jumper) will be installed between the terminal board and the alarm test points. Failure of the jumper or inadvertent shorting will not feed into another systems protective or control circuitry.

The diesel generator will be removed from service during the test and applicable Technical Specification action statements entered. No other systems will be affected other than the Main Control Room annunciator system. Therefore, an unreviewed safety question does not exist.

TESTS AND EXPERIMENTS THAT DID NOT REQUIRE

• Surry Monthly Operating Report NRC APPROVAL No. 98-01 Page 14 of 17 MONTHIYEAR:JANUARY, 1998 None During the Reporting Period

• Surry Monthly Operating Report No. 98-01 Page 15 of 17 CHEMISTRY REPORT MONTHNEAR: JANUARY, 1998 Unit No. 1 Unit No. 2 Primary Coolant Analysis Max. Min. Avg. Max. Min. Avq.

Gross Radioactivity, µCi/ml 3.38E-1 2.02E-1 2.64E-1 2.04E-1 1.11 E-1 1.50E-1 Suspended Solids, ppm - - - - - -

Gross Tritium, µCi/ml 6.11 E-1 5.93E-1 6.02E-1 6.25E-1 4.67E-1 5.52E-1 1131, µCi/ml 3.74E-3 4.70E-4 8.42E-4 1.15E-4 2.46E-5 5.22E-5 113111133 0.52 0.08 0.13 0.10 0.05 0.07 Hydrogen, cc/kg 32.4 28.9 30.3 38.4 35.1 36.9 I

Lithium, com 2.33 2.06 2.20 2.33 2.07 2.22.

Boron - 10, com* 157.2 140.3 149.2 237.0 226.6 231.9 Oxygen, (DO), ppm  :,;0.005  :,;0.005  :,;0.005 :,;0,005  :,;0.005  :,;Q.005 Chloride, PPm 0.005 0.002 0.003 0.005 0.004 0.004 pH at 25 degree Celsius 7.00 6.68 6.82 6.75 6.44 6.53

• Boron - 10 = Total Boron x 0.196 Comments:

None

• FUEL HANDLING

• Surry Monthly Operating Report No. 98-01 Page 16 of 17 UNITS 1 & 2 MONTHNEAR: January, 1998 New Fuel Number of New or Spent Shipment or Date Stored or Assemblies Assembly ANSI Initial Fuel Shipping Cask No. Received per Shipment Number Number Enrichment Cask Activity None During the Reporting Period

'f

• Surry Monthly Operating Report DESCRIPTION OF PERIODIC TEST(S) WHICH WERE NOT COMPLETED WITHIN THE TIME LIMITS SPECIFIED IN TECHNICAL SPECIFICATIONS No. 98-01 Page 17 of 17 MONTH/YEAR:JANUARY, 1998 None During the Reporting Period