BVY-97-098, Monthly Operating Rept for Jul 1997 for Vermont Yankee Nuclear Power Station

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Monthly Operating Rept for Jul 1997 for Vermont Yankee Nuclear Power Station
ML20210J755
Person / Time
Site: Vermont Yankee Entergy icon.png
Issue date: 07/31/1997
From: Maret G, Wallin G
VERMONT YANKEE NUCLEAR POWER CORP.
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
BVY-97-098, BVY-97-98, NUDOCS 9708190039
Download: ML20210J755 (6)
v • d • e


Text

s

  • VEllMONT YANKEE NUCLEAP. POWER COltPOllATION s

/

(~ P.O. Box 157. Governor Hunt Road j i Vernon, Vermont 05354-0167

< (802) 257 7711

.:X.1 l

August 11,1997 BVY-97-098 United States Nuclear Regulatory Commission ATrN: Document Control Desk Washington, D.C. 20555

Reference:

(a) License No. DPR-28 (Docket No. 50-271)

In accordance with section 6.7.A 3 of the Vermont Yankee Technical Specifications, submitted herewith is the hionthly Statistical Report for the Vermont Yankee Nuclear Power Station for the month of Julv.1997.

Sincerely, VERMONT YANKEE NUCLEAR POWER CORPORATION Gregory A. hinret Plant hianager cc: USNRC Region I Administrator USNRC Resident Inspector - VYNPS USNRC Project hianager - VYNPS ,

9708190039 970 31 PDR ADOCK 050 0271 R PDR i

4 i

VERMONT YANKEE NUCLEAR POWER STATION MONTIILY STATISTICAL REN)RT 97 07 FOR TiiE MONTH OF JULY 1997 Figure II DP 0411 Rev. 7 Page 1 of 1

OPERATING DATA REPORT l

. DOCKET NO.50-271 DATE 970810 COMPLETED BY G.A. WALLIN TELEPHONE (802)258-5414 OPERATING STATUS A. Unit Name Vermont Yankee

2. Reporting Period: July
3. Licensed Thermal Power (MWt):1593
4. Nameplate Rating (Gross MWe) : 512
5. Design Electrical Rating (Net MWe) : ill
6. Maximum Dependable Capacity (Gross MWe) : 525
7. Maximum Dependable Capacity (Net MWe): Ela
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): N/A
10. Reasons for restrictions, if any: N/A This Month Yr-to-Date Cumulative

'11. Hours in-Reporting Period 744.00 5087.00 215471.0.2

12. Number Of Hours Reactor was Critical 744.00 4781.39 179748.05
13. Reactor Reserve Shutdown Hours 0.00 0.00 0.00
14. Hours Generator On-Line 744.00 4750.00 176423.00
15. Unit Reserve Shutdown Hours 0.00 0 . 0 0 __ 0.00
16. Gross Thermal Energy Generated (MWH) 1179362.50 7536423.90 265183557.30
17. Gross Electrical Energy Generated _ 393111.00 2573587.00 88625009.00
18. Net Electrical Energy Generated (MWH) 370663.00 2461111.00 84277000.00
19. Unit Service Factor 100.00 93.40 81.00
20. Unit Availability Factor 100.00 93.40 81.00
21. Unit Capacity Factor (Using MDC Net) 97.70 94.90 76.60
22. Unit Capacity Factor (Using DER Net) 95.40 92.70 75.10
23. Unit Forced Outage Rate 0 . 0 0 __ 5.02 4.62
24. Shutdowns scheduled over next 6 months (Type, Date, and Duration of Each: N/A
25. If shut down at end of report period, estimated date of ctartup: N/A
26. Units In Test Status (prior to commercial operation) : N/A Forecast Achieved INITIAL CRITICALITY INITIAL-ELECTRICITY COMMERCIAL OPERATION VYDPF 0411.01 (Sample)

DP 0411 Rev. 7 Page 1 of 1 RT No. 13.F01.19F

AVERAGE DAILY UNIT POWER LEVEL e

. DOCKET NO. 50-271 UNIT Vermont Yankee DATE 970810 l

COMPLETED BY G.A. WALLIN TELEPHONE (802)258-5414 MONTH July l -DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL 1

(MWe-Net) (MWe-Net) l

1. 458 17. 479
2. 492 18. 488
3. 492 19. 502
4. 502 20. 503
5. 506 21, 507
6. 504 22, 508
7. 498 23, 505
8. 495 24, 503
9. 494 25. 502
10. 498 26. 501
11. 500 27. 495
12. 505 28, 493
13. 504 29. 502
14. 498 30. 502 15, 501 31. 500 16, 509 INSTRUCTIONS:

On_this format,. list the average daily unit power level in MWE-Net for'ench day in the~_ reporting month. Compute to the nearest whole-m3gawatt.

VYDPF 0411.02 (Sample)

DP 0411 Rev. 7 Page 1 of 1 RT No. 13.F01.18V

UNIT SHUTDOWNS AND POWER REDUCTIONS .

REPORT MONTH JULY tVt m NO 50-271 UNIT NAME Vermont Yankee DATE 970810 I COMPLETED BY G.A. Wallin l TELEPHONE (802)258-5414 1

- )

1 2 3 4 5 No. Date Type Duration Reason Method of License System Component Cause and Correct ** t (hours) Shutting Event Code Code Action to Preven-Down Report # Recurrence Reactor 97-06 970701 S 0.00 B,H* 4 N/A RB CONROD Turbine Bypass Valve, Power MSIV Full Closure Reduction Tests and a Rod Pattern Exchange.

97-07 970717 S 0.00 B,H* 4 N/A RB CONROD Scram Solenoid Pilot Power Valve replacenents, Reduction Single Rod Scram Testing, and a Rod Pattern Adjustment.

1 F: Forced 2 Reason: 3 Method: 4 Exhibit G- Instructions S: Scheduled A-Equipment Failure (Explain) 1 - Manual for Preparation of Data B-Maintenance or Test 2 - Manual Scram Entry Sheets for License C-Refueling 3 - Automatic Scram Event Report (LER) File D-Regulatory Restriction 4 - Other (Explain) (NITREG 0161)

E-Operator Training and License Examination 5 Exhibit I - Same Source F-Administrative G-Operational Error (Explain)

  • H-Explain - Rod Pattern Exchange / Adjustment VYDPF 0411.03 (Sample)

DP 0411 Rev. 7 Page 1 of 1 L

DOCKET No. 50-271 DATE 970810 COMPLETED BY G.A. WALLIN i

TELEPHONE (802)258-5414 REPORT MONTH Julv l

SUMMARY

OF OPERATING EXPERIENCES l Hiahliohts l

l Vermont Yankee operated at 99.5% of rated thermal power for the month.

Gross electrical generation was 393.111 MWHe or 96.8% design electrical ecpacity.

Oneratina Summary Tho following is a chronological description of plant operations including other pertinent items of interest for the month:

At the beginning of the reporting period the plant was operating at 21.61 of rated thermal power.-

970701 At 0042 hours4.861111e-4 days <br />0.0117 hours <br />6.944444e-5 weeks <br />1.5981e-5 months <br />, initiated a power reduction to perform Turbine Bypass Valve Testing, MSIV Full Closure Test, Rod Pattern Exchange. (See Unit shutdowns and Power Reductions) 970701 At 0220 hours0.00255 days <br />0.0611 hours <br />3.637566e-4 weeks <br />8.371e-5 months <br />, at 75% power began Turbine Bypass Valve Test.

970701 At 0230 hours0.00266 days <br />0.0639 hours <br />3.80291e-4 weeks <br />8.7515e-5 months <br />, completed Turbine Bypass Valve Test and reduced power to 68%.

970701 At 0250 hours0.00289 days <br />0.0694 hours <br />4.133598e-4 weeks <br />9.5125e-5 months <br />, began MSIV Full Closure Test.

970701 At 0300 hours0.00347 days <br />0.0833 hours <br />4.960317e-4 weeks <br />1.1415e-4 months <br />, completed MSIV Full Closure Test.

970701 At 0330 hours0.00382 days <br />0.0917 hours <br />5.456349e-4 weeks <br />1.25565e-4 months <br />, started Rod Pattern Exchange.

970701 At 0455 hours0.00527 days <br />0.126 hours <br />7.523148e-4 weeks <br />1.731275e-4 months <br />, completed Rod Pattern Exchange.

970701 At 0515 hours0.00596 days <br />0.143 hours <br />8.515212e-4 weeks <br />1.959575e-4 months <br />, began a return to full power.

970717 At 1915 hours0.0222 days <br />0.532 hours <br />0.00317 weeks <br />7.286575e-4 months <br />, initiated a power reduction to perform Scram Solenoid Pilot Valve replacements, Single Rod Scram Testing and Rod Pattern Adjustment. (See Unit Shutdowns and Power Reductions) 970717 At 2008 hours0.0232 days <br />0.558 hours <br />0.00332 weeks <br />7.64044e-4 months <br />, began first Scram Solenoid Pilot Valve replacement.

970717 At 2152 hours0.0249 days <br />0.598 hours <br />0.00356 weeks <br />8.18836e-4 months <br />, performed Single Rod Scram Testing following first Scram Solenoid Pilot Valve replacement.

970717 At 2215 hours0.0256 days <br />0.615 hours <br />0.00366 weeks <br />8.428075e-4 months <br />, began second Scram Solenoid Pilot V31ve replacement.

970717 At 2336 hours0.027 days <br />0.649 hours <br />0.00386 weeks <br />8.88848e-4 months <br />, performed Single Rod Scram Testire ?ollowirp s,.cond Scram Solenoid Pilot Valve replacement.

970717 At 2341 hours0.0271 days <br />0.65 hours <br />0.00387 weeks <br />8.907505e-4 months <br />, began Rod Pattern Adjustment.

970718 At 0004 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />, following Rod Pattern Adjustment, began a retarn to full power.

At the end of the reporting-period the plant-was operating at 99.9% of rated thermal power.

VYDPF 0411.04 (Sample)

DP 0411 Rev. 7 Page 1 of 1 RT No. 13.F01.18X

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