ML18153B207

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Monthly Operating Repts for Dec 1994 for Surry Power Station.W/950112 Ltr
ML18153B207
Person / Time
Site: Surry  Dominion icon.png
Issue date: 12/31/1994
From: Bowling M, Kessler P, Olsen C
VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
95-015, 95-15, NUDOCS 9501230301
Download: ML18153B207 (20)
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Text

VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND, VIRGINIA 23261 January 12, 1995 U.S. Nuclear Regulatory Commission Serial No.95-015 Attention: Document Control Desk NO/RPC:vlh Washington, D. C. 20555 Docket Nos. 50-280 50-281 License Nos. DPR-32 DPR-37 Gentlemen:

VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION UNITS 1 AND 2 MONTHLY OPERATING REPORT Enclosed is the Monthly Operating Report for Surry Power Station Units 1 and 2 for the month of December 1994.

Very truly yours,

  1. -Id~

M. L. Bowling, Manager Nuclear Licensing and 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

. 9501230301 - --- ---- - --- -*-C" ,'i PDR ADOCK 941231 05000280 jti i R ,.,.,.:. :._'*:. : . *. ..*.. ~PDB_ - -

VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION MONTHLY OPERATING REPORT REPORT No. 94-12 Approved:

Station Manager Date

e Surry Monthly Operating Report No. 94-12 Page 2of 19 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 **...............*********..........*****.....*........................................ 10 Facility Changes That Did Not Require NRC Approval. .............*********...........................*...*..**....*..............* 11 Procedure or Method of Operation Changes That Did Not Require NRC Approval *.*...*.................................... 14 Tests and Experiments That Did Not Require NRC Approval .......***..*.....................**...**...**..**....*............... 15 Chemistry Report *........*.......*...**...***......***.*...............************.......*****...**........................*................ 16 Fuel Handling - Unit No. 1 ..*........*.......*.........................*.*.*******......*..**........*......................*..*..***........ 17 Fuel Handling - Unit No. 2 ......................................................................*....*...*.*.........................*....... 17 Description of Periodic Test(s) Which Were Not Completed Within the Time Limits Specified in Technical Specifications .........*..**.................*...*........................................**..................... 19

e Surry Monthly Operating Report No. 94-12 Page 3of 19 OPERATING DATA RIEPORT Docket No.: 50-280 Date: 01-05-95 Completed By: D. Mason Telephone: (804) 365-2459

1. Unit Name: .................................................. . Surry Unit 1
2. Reporting Period: ......................................... . December, 1994
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 YID Cumulative

11. Hours In Reporting Period ......................... . 744.0 8760.0 193080.0
12. Number of Hours Reactor Was Critical ......... . 215.4 6662.5 130469.7
13. Reactor Reserve Shutdown Hours .............. . 0 0 3774.5
14. Hours Generator On-Line .......................... . 152.3 6562.0 128241.0
15. Unit Reserve Shutdown Hours.................... . 0 0 3736.2
16. Gross Thermal Energy Generated (MWH) ..... . 331175.4 15285994.1 298453739.2
17. Gross Electrical Energy Generated (MWH) ... . 110500.0 5074285.0 97613833.0
18. Net Electrical Energy Generated (MWH) ....... . 106379.0 4881922.0 92709023.0
19. Unit Service Factor .................................. . 20.5% 74.9% 66.4%
20. Unit Availability Factor.............................. . 20.5% 74.9% 68.4%
21. Unit Capacity Factor (Using MDC Net) .......... . 18.3% 71.4% 61.9%
22. Unit Capacity Factor (Using DER Net) .......... . 18.1% 70.7% 60.9%
23. Unit Forced Outage Rate ........................... . 0.0% 0.4% 16.7%
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

e -

Surry Monthly Operating Report No. 94-12 Page 4of 19 OPERATING DATA REPORT Docket No.: 50-281 Date: 01-05-95 Completed By: D. Mason Telephone: (804) 365-2459

1. Unit Name: ................................................. .. Surry Unit 2
2. Reporting Period: ........................................ .. December, 1994
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, HAny (Net MWe):
10. Reasons For Restrictions, If Any:

This Month YTD Cumulative

11. Hours In Reporting Period ........................ .. 744.0 8760.0 189960.0
12. Number of Hours Reactor Was Critical ........ .. 744.0 8261.2 128337.5
13. Reactor Reserve Shutdown Hours .............. . 0 0 328.1
14. Hours Generator On-Line .......................... . 744.0 8251.5 126467.1
15. Unit Reserve Shutdown Hours .................... . 0 0 0
16. Gross Thermal Energy Generated (MWH) ..... . 1814475.4 19592721.9 295268464.3
17. Gross Electrical Energy Generated (MWH) ... . 605405.0 6496670.0 96442294.0
18. Net Electrical Energy Generated (MWH) ...... .. 584305.0 6260966.0 91593036.0
19. Unit Service Factor ................................. .. 100.0% 94.2% 66.6%
20. Unit Availability Factor.............................. . 100.0% 94.2% 66.6%
21. Unit Capacity Factor (Using MDC Net) .......... . 100.6% 91.5% 61.8%
22. Unit Capacity Factor (Using DER Net) .......... . 99.7% 90.7% 61.2%
23. Unit Forced Outage Rate ............................ 0% 0% 13.3%
24. Shutdowns Scheduled Over Next 6 Months (Type, Date, and Duration of Each):

Refueling (1 O Year ISi), February 2, 1995, 53 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

~urry Monthly Operating Report No. 94-12 Page 5of 19 UNIT SHUTDOWN AND POWER REDUCTION (EQUAL To OR GREATER THAN 20%)

REPORT MoNTH: December, 1994 Docket No.: 50-280 Unit Name: Surry Unit 1 Date: 01-05-95 Completed by: Craig Olsen Telephone: (804) 365-2155 (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 941229 F NIA A NIA NIA JD RCT Turbine runback initiated when IRPI K-02 failed. IRPI K-02 instrumentation cable was replaced.

(1) (2) (3)

F: Forced REASON: METI-IOD:

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)

~urry Monthly Operating Report No. 94-12 Page 6of 19 UNIT SHUTDOWN AND POWER REDUCTION (EQUAL To OR GREATER THAN 20%)

REPORT MoNTH: December, 1994 Docket No.: 50-281 Unit Name: Surry Unit 2 Date: 01-05-95 Completed by: Craig Olsen Telephone: (804) 365-2155 (1) (2) (3) (4) (5)

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

~urry Monthly Operating Report No. 94-12 Page 7of 19 AVERAGE DAILY UNIT POWER LEVEL Docket No.: 50-280 Unit Name: Surry Unit 1 Date: 01-04-95 Completed by: Pat Kessler Telephone: 365-2790 MONTH: December, 1994 Average Daily Power Level Average Daily Power Level Day (MWe-Net) Day (MWe-Net) 1 0 17 0 2 0 18 0 3 0 19 0 4 0 20 0 5 0 21 0 6 0 22 0 7 0 23 0 8 0 24 0 9 0 25 70 10 0 26 488 11 0 27 767 12 0 28 775 13 0 29 742 14 0 30 795 15 0 31 795 16 0 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. 94-12 Page 8of 19 AVERAGE DAILY UNIT POWER LEVEL Docket No.: 50-281 Unit Name: Surry Unit 2 Date: 01-04-95 Completed by: Pat Kessler Telephone: 365-2790 MONTH: December, 1994 Average Daily Power Level Average Daily Power Level Day (MWe-Net) Day (MWe-Net) 1 787 17 786 2 787 18 786 3 789 19 786 4 790 20 785 5 783 21 784 6 783 22 784 7 789 23 784 8 790 24 785 9 790 25 785 10 789 26 785 11 790 27 782 12 785 28 763 13 782 29 785 14 786 30 786 15 786 31 787 16 787 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.

~urry Monthly Operating Report No. 94-12 Page 9 of 19

SUMMARY

OF OPERATING EXPERIENCE MONTH/YEAR: December, 1994 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.

UNIIQNE:

12/01/94 0000 The reporting period began with the unit shutdown for a maintenance outage (steam generator chemical cleaning).

12/23/94 0039 Reactor critical.

12/25/94 1544 Generator on line. Started power increase.

1629 Stopped power increase at 33%, 210 MWe.

12/26/94 0344 Started power increase.

0500 Stopped power increase at 57%, 400 MWe.

0834 Started power increase.

0910 Stopped power increase at 70"/o, 510 MWe.

1847 Started power increase.

2235 Stopped power increase at 97%, 795 MWe.

12/28/94 1115 Started power increase.

1230 Stopped power increase at 99%, 820 MWe.

1433 Started power reduction to perform Delta T calibration.

1448 Stopped power reduction at 98%, 810 MWe.

2217 Started power increase.

2300 Stopped power increase at 100%, 825 MWe.

12/29/94 1626 Turbine runback initiated due to failed IRPI K-02.

1628 Runback stopped at 46% power, 370 MWe.

1650 Started power increase to close the main steam dump valves.

1658 Stopped power increase at 68%, 510 MWe.

1944 Started power increase.

2258 Stopped power increase at 100%, 825 MWe.

12/31/94 2400 The reporting period ended with the unit operating at 100% power, 825 MWe.

e Surry Monthly Operating Report No. 94-12 Page 10 of 19

SUMMARY

OF OPERATING EXPERIENCE MONTH/YEAR: December, 1994 ,

UNIJJwo:

12/01/94 0000 The reporting period began with the unit operating at 1OOo/o power, 820 MWe.

12/28/94 0935 Started power reduction to perform Operations Surveillance Test, 2-0SP-TM-001,

Turbine Inlet Valve Freedom Test."

1010 Stopped power reduction at 94%, 775 MWe.

1226 Started power reduction.

1323 Stopped power reduction at 85%, 700 MWe.

1417 Started power increase.

1700 Stopped power increase at 100%, 825 MWe.

12/31/94 2400 The reporting period ended with the unit operating at 1OOo/o power, 825 MWe.

  • FACILITY CHANGES THAT DID NOT tlurry Monthly Operating Report No. 94-12 Page 11 of 19 REQUIRE NRC APPROVAL MONTH/YEAR: December, 1994 DR S-94-2132 Deviation Reports 12-06-94 DR S-94-2138 (Safety Evaluation No.94-208)

Safety Evaluation 94-208 assessed the condition addressed by Deviation Reports S 2132 and S-94-2138 concerning the operation of Unit 1 with hot leg loop stop valve 1-RC-MOV-1594 fixed on its backseat with the disc assembly wedged between the seat ring and the backseat.

A UT examination was performed on the hot leg loop stop valve to ensure the stem' was free of cracks. The valve manufacturer was contacted and concurred that no additional valve damage would result from leaving the valve in the fixed position during unit heat-up and operation. The subject configuration was determined to be acceptable since the loop stop valves are used for maintenance isolation and are not required for accident mitigation. Therefore, an unreviewed safety question does not exist.

TM S1-94-038 Temporary Modification 12-06-94 (Safety Evaluation No.94-210)

Temporary Modification (TM) S1-94-038 failed Primary Drains Transfer Tank (POTT) pressure control valve, 1-DG-PCV-100, in the open position to eliminate spurious High Flux at Shutdown alarms caused from electrical noise generated when 1-DG-SOV-100 energizes to open 1-DG-PCV-100.

The TM was in place while the unit was at Cold Shutdown (CSD) with the containment at atmospheric conditions. At these conditions, the Primary Drains System functioned normally. Containment isolation capability was maintained and unaffected by this TM.

Therefore, an unreviewed safety question did not exist.

DR S-94-2248 Deviation Report 12-16-94 (Safety Evaluation No.94-211)

Safety Evaluation 94-211 assessed the condition identified by Deviation Report S 2248 concerning the induction of pieces of 1.5 inch rubber hose ~ six inches per steam generator) into the secondary side of the Unit 1 steam generators (SG) during the SG chemical cleaning process.

An evaluation of Unit 1 operation with the SGs containing the foreign objects was performed by Westinghouse Nuclear Safety. The evaluation concluded that the presence of the objects is not expected to have an adverse effect on the primary pressure boundary integrity of the SGs. Therefore, an unreviewed safety question does not exist.

tlurry Monthly Operating Report No. 94-12 Page 12 of 19 FACILITY CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTH/YEAR: December, 1994 FS 94-01 Updated Flnal Safety Analysls Report Change 12-19-94 (Safety Evaluation No.93-212)

UFSAR Change 94-01 revised Section 6.3, "Consequence-Limiting Safeguards,n to identify the types of fibrous material used inside containment and added a section to discuss how the containment design reduces the potential for significant debris buildup on the containment sump screens during a loss of coolant accident or high energy line break.

This change was administrative in nature and did not involve any physical changes to the plant. Therefore, an unreviewed safety question does not exist.

DCP94-56 Design Change Package 12-23-94 (Safety Evaluation No.93-182)

Design Change Package 94-56 connected the compensating lead to one of the two normal leads for Unit 2 Reactor Coolant System (RCS) "Cn hot leg wide range temperature indication spare element, 2-RC-TE-2433-2. This configuration allows the compensating lead to be used in lieu of a failed normal lead, enabling 2-RC-TE-2433-2 to be returned to service.

The associated transmitter was adjusted, based on previous measurements, to offset the change in lead resistance and ensure the accuracy of the subject temperature indicator.

This modification did not affect other RCS temperature indication. Therefore, an unreviewed safety question does not exist.

DCP88-24 Design Change Package 12-30-94 Design Change Package 88-24 modified or replaced various indicators, recorders, and controllers in the Main Control Room and Emergency Switchgear Room to correct Human Engineering Deficiencies (HED).

These modifications correct HEDs identified during the Control Room Design Review that was required by NUREG-0737. Implementation of these modifications did not affect the operation of safety-related equipment or systems or the availability of safety-related power sources. Therefore, an unreviewed safety question does not exist.

DCP93-53 Design Change Package 12-30-94 (Safety Evaluation No.94-142)

Design Change Package 93-53 corrected Human Engineering Deficiencies (HED) including the labeling of the auxiliary shutdown panel, certain heat tracing, and emergency diesel generator switches and indicators and respective panels. The titles of certain control room status tiles were also changed to improve clarity.

These modifications correct HEDs identified in the Control Room Design Review Reassessment Report that was required by NUREG-0737. Implementation of these modifications did not affect the operation of safety-related equipment or systems or the availability of safety-related power sources. Therefore, an unreviewed safety question does not exist.

e .

Surry Monthly Operating Report No. 94-12 Page 13 of 19 FACILITY CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTH/YEAR: December, 1994 TM S1-94-39 Temporary Modification 12-31-94 (Safety Evaluation No.94-214)

Temporary Modification (TM) S1-94-39 installed an individual rod position indication (IRPI) rod bottom bistable module with a soldered jumper which defeats the IRPI dropped control rod turbine runback and rod stop for Unit 1 control rod K-2. This modification will prevent a spurious turbine runback and allow continued operation of Unit 1.

Other IRPI turbine runback and rod stop circuits, as well as nuclear instrument, over-pressure delta temperature and over-temperature delta temperature turbine runback and rod stop circuitry remain operable while this modification is installed. Therefore, an unreviewed safety question does not exist.

.urry Monthly Operating Report No. 94-12 Page 14of 19 PROCEDURE OR METHOD OF OPERATION CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTH/YEAR: December, 1994 1-0PT-Sl-005 Operations Periodic Test Procedures 12-06-94 2-0PT-Sl-005 (Safety Evaluation No.94-209)

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

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

~urry Monthly Operating Report No. 94-12 Page 15 of 19 TESTS AND EXPERIMENTS THAT DID NOT REQUIRE NRC APPROVAL MONTH/YEAR: December, 1994 None During the Reporting Period

-Surry Monthly Operating Report No. 94-12 Page 16 of 19 CHEMISTRY REPORT MONTH/YEAR: December, 1994 Unit No.1 Unit No. 2 Primary Coolant Analysis Max. Min. Ava. Max. Min. Ava.

Gross Radioactivity, J.LCi/ml 4.01E-1 4.18E-3 9.09E-2 1.54E-1 8.89E-2 1.17E-1 Suspended Solids, ppm _s0.1 _s0.1 _s0.1 _s0.1 _s0.1 _s0.1 Gross Tritium uCi/ml 1.94E-2 1.94E-2 1.94E-2 1.52E-1 8.49E-2 1.23E-1 1131, J.LCilml 4.55E-4 5.28E-5 2.66E-4 1.35E-4 6.00E-5 9.83E-5 113111133 0.06 0.06 0.06 0.10 0.05 0.07 Hydroaen, cc/ka 43.7 3.2 28.1 45.4 36.5 41.5 Lithium oom 2.33 0.57 1.50 1.41 0.89 1.14 Boron - 10, oom* 332.6 122.7 278.1 25.3 5.9 15.6 Oxygen, (DO), ppm 8.0 _s0.005 1.2 s0.005 s0.005 s0.005 Chloride, ppm s0.050 so.001 0.006 <0.050 so.001 0.003 oH at 25 dearee Celsius 7.08 5.76 6.24 7.96 7.51 7.65

None

Surry Monthly Operating Report No. 94-12 Page 17 of 19 FUEL HANDLING UNITS 1 & 2 MONTH/YEAR: December, 1994 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 Activi~

ISFSI CASTORX/33 12/14/94 33 B01 NOANSI 2.573 NIA B06 NOANSI 2.573 807 NOANSI 2.573 B09 NOANSI 2.573 B14 NOANSI 2.573 B15 NOANSI 2.573 B17 NOANSI 2.573 B19 NOANSI 2.573 B21 NOANSI 2.573 822 NOANSI 2.573 B25 NOANSI 2.573 B26 NOANSI 2.573 B27 NOANSI 2.573 B29 NOANSI 2.573 B30 NOANSI 2.573 B33 NOANSI 2.573 B34 NOANSI 2.573 B35 NOANSI 2.573 B36 NOANSI 2.573 B38 NOANSI 2.573 B39 NOANSI 2.573 B42 NOANSI 2.573 B43 NOANSI 2.573

e -urry Monthly Operating Report No. 94-12 Page 18 of 19 FUEL HANDLING UNITS 1 & 2 MONTH/YEAR: December, 1994 New or Spent Numberof

  • New or Spent Fuel Shipment Date Stored or Assemblies Assembly ANSI Initial Fuel Shipping Number Received e!r Shiement Number Number Enrichment Cask Activi!X ISFSI CASTORX/33 (Continued) 12/14/94 33 845 NOANSI 2.573 NIA 848 NOANSI 2.573 849 NOANSI 2.573 852 NOANSI 2.573 S02 LMOOTG 2.606 S04 LMOOTJ 2.606 sos LMOOlZ 2.606 S07 LMOOTP 2.606 sos LMOOlX 2.606 S09 LMOOTT 2.606

. * -Surry Monthly Operating Report DESCRIPTION OF PERIODIC TEST(S) WHICH WERE NOT COMPLETED No. 94-12 Page 19 of 19 WITHIN THE TIME LIMITS SPECIFIED IN TECHNICAL SPECIFICATIONS MONTH/YEAR: December, 1994 None During the Reporting Period

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