ML18153A367

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Monthly Operating Repts for Jan 1998 for Surry Power Station,Units 1 & 2
ML18153A367
Person / Time
Site: Surry  Dominion icon.png
Issue date: 01/31/1998
From: MARSHALL G N, MASON D K, STEINERT J C
VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To:
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ML18153A366 List:
References
NUDOCS 9802200165
Download: ML18153A367 (17)
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  • VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION MONTHLY OPERA TING REPORT REPORT No. 98-01 Approved:

Station Manager -------~ 2.-, '<--9 e Date

...

  • TABLE OF CONTENTS Section
  • Surry Monthly Operating Report No. 98-01 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 Nos. 1 and 2 .............................................................................................

9 Facility Changes That Did Not Require NRC Approval ............................................................................................

1 O 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

... *

  • Surry Monthly Operating Report No. 98-01 Page 3 of 17 OPERATING DATA REPORT Docket No.: Date: 50-280 02/04/98 Completed By: Telephone:

D. K. Mason (757) 365-2459 1. 2. 3. 4. 5. 6. 7. Unit Name: ........................................................... . Reporting Period: ................................................

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

. Nameplate Rating (Gross MWe): ......................... . Design Electrical Rating (Net MWe): ................... . Maximum Dependable Capacity (Gross MWe): ... . Maximum Dependable Capacity (Net MWe): ...... .. Surry Unit 1 January, 1998 2546 847.5 788 840 801 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: 11. 12. 13. 14. 15. 16. 17. 18. 19. 20. 21. 22. 23. Hours in Reporting Period Hours Reactor Was Critical Reactor Reserve Shutdown Hours Hours Generator On-Line Unit Reserve Shutdown Hours Gross Thermal Energy Generated (MWH) Gross Electrical Energy Generated (MWH) Net Electrical Energy Generated (MWH) Unit Service Factor Unit Availability Factor Unit Capacity Factor (Using MDC Net) Unit Capacity Factor (Using DER Net) Unit Forced Outage Rate This Month 744.0 744.0 0.0 744.0 0.0 1893551.9 634994.0 613523.0 100.0% 100.0% 102.9% 104.6% 0.0% Year-To-Date 744.0 744.0 0.0 744.0 0.0 1893551.9 634994.0 613523.0 100.0% 100.0% 102.9% 104.6% 0.0% 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 INITIAL CRITICALITY INITIAL ELECTRICITY COMMERCIAL OPERATION ACHIEVED Cumulative 220128.0 154769.8 3774.5 152343.5 3736.2 358138567.

5 117450748.0 111847744.0 69.2% 70.9% 65.3% 64.5% 14.7%

  • , *
  • Surry Monthly Operating Report No. 98-01 Page 4 of 17 1. 2. 3. 4. 5. 6. 7. OPERATING DATA REPORT Unit Name: ........................................................... . Reporting Period: ................................................. . Licensed Thermal Power (MWt): ......................... . Nameplate Rating (Gross MWe): ......................... . Design Electrical Rating (Net MWe): ................... . Maximum Dependable Capacity (Gross MWe): ... . Maximum Dependable Capacity (Net MWe): ....... . Surry Unit 2 January, 1998 2546 847.5 788 840 801 Docket No.: Date: Completed By: Telephone:

50-281 02/04/98 D. K. Mason (757) 365-2459 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. 12. 13. 14. 15. 16. 17. 18. 19. 20. 21. 22. 23. Hours in Reporting Period Hours Reactor Was Critical Reactor Reserve Shutdown Hours Hours Generator On-Line Unit Reserve Shutdown Hours Gross Thermal Energy Generated (MWH) Gross Electrical Energy Generated (MWH) Net Electrical Energy Generated (MWH) Unit Service Factor Unit Availability Factor Unit Capacity Factor (Using MDC Net) Unit Capacity Factor (Using DER Net) Unit Forced Outage Rate This Month. 744.0 744.0 o:o 744.0 0.0 1894101.8 635470.0 614752.0 100.0% 100.0% 103.2% 104.9% 0.0% Year-To-Date 744.0 744.0 0.0 744.0 0.0 1894101.8 635470.0 614752.0 100.0% 100.0% 103.2% 104.9% 0.0% 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 INITIAL CRITICALITY INITIAL ELECTRICITY COMMERCIAL OPERATION ACHIEVED Cumulative 217009.0 151894.3 328.1 149877.4 0.0 353427669.1 115761078.0 110257903.0 69.1% 69.1% 65.0% 64.5% 11.9%

.. *

  • Surry Monthly Operating Report No. 98-01 Page 5 of 17 UNIT SHUTDOWN AND POWER REDUCTION (EQUAL To OR GREATER THAN 20%) 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 (1) F: Forced S: Scheduled (4) (2) REASON: Down Rx None During the 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

  • Surry Monthly Operating Report No. 98-01 Page 6 of 17 UNIT SHUTDOWN AND POWER REDUCTION (EQUAL To OR GREATER THAN 20%) 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 (1) F: Forced S: Scheduled (4) (2) REASON: Down Rx None During the 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: January, 1998 Day 1 2 3 4 5 6 7 8 9 10 11 12 13 14 15 16 INSTRUCTIONS

  • Surry Monthly Operating Report No. 98-01 Page 7 of 17 AVERAGE DAILY UNIT POWER LEVEL Average Daily Power Level (MWe -Net) Day 821 17 825 18 825 19 825 20 825 21 825 22 825 23 824 24 823 25 824 26 824 27 824 28 823 29 823 30 821 31 821 Docket No.: 50-280 Unit Name: Surry Unit 1 Date: 02/03/98 Completed by: J. C. Steinert Telephone:

(757) 365-2834 Average Daily Power Level (MWe -Net) 824 827 828 827 823 823 827 827 824 825 827 826 825 826 826 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: January, 1998 Day 1 2 3 4 5 6 7 8 9 10 11 12 13 14 15 16 INSTRUCTIONS

  • Surry Monthly Operating Report No. 98-01 Page 8 of 17 AVERAGE DAILY UNIT POWER LEVEL Average Daily Power Level (MWe -Net) Day 830 17 827 18 827 19 827 20 827 21 827 22 824 23 824 24 827 25 827 26 828 27 827 28 827 29 822 30 822 31 822 Docket No.: 50-281 Unit Name: Surry Unit 2 Date: 02/03/98 Completed by: John C. Steinert Telephone:

(757) 365-2837 Average Daily Power Level (MWe -Net) 826 827 826 826 827 826 827 827 828 828 823 826 826 827 827 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 MONTHNEAR:

JANUARY, 1998 Surry Monthly Operating Report No. 98-01 Page 9 of 17 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 01/31/98 UNIT Two: 01/01/98 01/31/98 0000 2400 0000 2400 Unit 1 operating at 100% / 855 MWe. Unit 1 operating at 100% / 855 MWe. Unit 2 operating at 100% / 855 MWe. Unit 2 operating at 100% / 855 MWe.

FS 97-49 DR S-97-3400 FS 97-12 TM S1-98-01 *

  • Surry Monthly Operating Report No. 98-01 Page 10 of 17 FACILITY CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTHNEAR:

JANUARY, 1998 UFSAR Change Request (Safety Evaluation No. 98-0001) 01/05/98 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. 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. UFSAR Change Request (Safety Evaluation No. 98-0004) 01/08/98 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 Temporary Modification (Safety Evaluation No. 98-0005) 01/13/98 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.

FS 97-45 FS 97-38 TM S1-98-02 FS 98-01 *

  • Surry Monthly Operating Report No. 98-01 Page 11 of 17 FACILITY CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTHNEAR:

JANUARY, 1998 UFSAR Change Request (Safety Evaluation No. 98-0007) 01/15/98 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 1 OCFR55 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. UFSAR Change Request (Safety Evaluation No. 98-0008) 01/15/98 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.

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. UFSAR Change Request (Safety Evaluation No. 98-0012) 01/26/98 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 DCP 97-001 *

  • Surry Monthly Operating Report No. 98-01 Page 12 of 17 FACILITY CHANGES THAT DID Nor REQUIRE NRC APPROVAL 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. 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.

1 /2-0P-S 1-002 1 /2-0P-S 1-004 STD-FP-1997

-8116 STD-FP-1986-2714 2-0SP-EG-001

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

January, 1998 Operations Procedures (Safety Evaluation No.98-006) Surry Monthly Operating Report No. 98-01 Page 13 of 17 01/15/98 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. Vendor Procedures 01/22/98 (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. Operations Surveillance Procedure (Safety Evaluation No. 98-0014) 01/28/98 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.

  • Surry Monthly Operating Report No. 98-01 Page 14 of 17 TESTS AND EXPERIMENTS THAT DID NOT REQUIRE NRC APPROVAL MONTHIYEAR:JANUARY, 1998 None During the Reporting Period
  • ., Primary Coolant Analysis Gross Radioactivity, µCi/ml Suspended Solids, ppm Gross Tritium, µCi/ml 1131, µCi/ml 113111133 Hydrogen, cc/kg Lithium, com Boron -10, com* Oxygen, (DO), ppm Chloride, PPm pH at 25 degree Celsius

None CHEMISTRY REPORT MONTHNEAR:

JANUARY, 1998 Unit No. 1 Max. Min. Avg. 3.38E-1 2.02E-1 2.64E-1 ---6.11 E-1 5.93E-1 6.02E-1 3.74E-3 4.70E-4 8.42E-4 0.52 0.08 0.13 32.4 28.9 30.3 I 2.33 2.06 2.20 157.2 140.3 149.2 :,;0.005 :,;0.005 :,;0.005 0.005 0.002 0.003 7.00 6.68 6.82

  • Surry Monthly Operating Report No. 98-01 Page 15 of 17 Unit No. 2 Max. Min. Avq. 2.04E-1 1.11 E-1 1.50E-1 ---6.25E-1 4.67E-1 5.52E-1 1.15E-4 2.46E-5 5.22E-5 0.10 0.05 0.07 38.4 35.1 36.9 2.33 2.07 2.22. 237.0 226.6 231.9 :,;0,005 :,;0.005 :,;Q.005 0.005 0.004 0.004 6.75 6.44 6.53

., New Fuel Shipment or Cask No.

  • FUEL HANDLING UNITS 1 & 2 MONTHNEAR:

January, 1998 Number of Date Stored or Assemblies Received per Shipment Assembly Number ANSI Number None During the Reporting Period

  • Surry Monthly Operating Report No. 98-01 Page 16 of 17 Initial Enrichment New or Spent Fuel Shipping Cask Activity

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