ML20133F483

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Monthly Operating Repts for Dec 1996 for Beaver Valley Power Station Unit 1 & 2
ML20133F483
Person / Time
Site: Beaver Valley
Issue date: 12/31/1996
From: David Jones, Noonan T
DUQUESNE LIGHT CO.
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 9701140217
Download: ML20133F483 (11)
v • d • e


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Telephone (412) 393-6000 O. Box 4 Shippingport. PA 15077-0004 January 8,1997 Beaver Valley Power Station Unit 1 - Docket No. 50-334, License No. DPR-66 Unit 2 - Docket No. 50-412, License No. NPF-73 Monthly Operating Reoort U. S. Nuclear Regulatory Commission Document Control Desk Washington, D.C. 20555 Gentlemen:

In accordance with Appendix A, Technical Specifications, the Monthly Operating Repod is submitted for Unit I and Unit 2 for the month of December,1996.

Respectfully, T. P. Noonan Division Vice President, Nuclear Operations /

Plant Manager DTJ/ sip Enclosures j cc: NRC Regional OfIice King of Pnissia, PA / V) 9701140217 961231 /

PDR ADOCK 05000334 R PDR The Nuclear Professionals l

1

. 1 NARRATIVE SUh1 MARY OF MONTHLY OPERATING EXPERIENCE UNIT 1 DECEMBER 1996 December i The Unit operated at a nominal value of 100% output.

through December 26 December 27 At 2040 hours0.0236 days <br />0.567 hours <br />0.00337 weeks <br />7.7622e-4 months <br />, the Unit began a power reduction to approximately 84% output to clear the "C" Waterbox of the Main Unit Condenser for repair of a tube leak. An output of approximately 84% was achieved at 2220 hours0.0257 days <br />0.617 hours <br />0.00367 weeks <br />8.4471e-4 months <br />.

December 28 Following clearing of the "C" Waterbox for repair of a tube leak, a return to full power was commenced at 0130 hours0.0015 days <br />0.0361 hours <br />2.149471e-4 weeks <br />4.9465e-5 months <br />. The Unit achieved a nominal value of 100%

output at 0400 hours0.00463 days <br />0.111 hours <br />6.613757e-4 weeks <br />1.522e-4 months <br />. However, due to rising hotwell temperaturn because of the clearance on the "C" Waterbox, output was reduced to approximately 96.5% at 1015 hours0.0117 days <br />0.282 hours <br />0.00168 weeks <br />3.862075e-4 months <br /> to stabilize Condenser hotwell conditions.

December 29 Following satisfactory repair of the tube leak, a return to full power was commenced at 0340 hours0.00394 days <br />0.0944 hours <br />5.621693e-4 weeks <br />1.2937e-4 months <br />. A nominal value of 100% output was achieved at 0500 hours0.00579 days <br />0.139 hours <br />8.267196e-4 weeks <br />1.9025e-4 months <br />.

December 30 The Unit operated at a nominal value of 100% output for the remainder of the report through period.

December 31 In addition to the above, the following events which also occurred during the report period are being reported as required by Technical Specifications.

December 17 The Automatic Rod Position Deviation Monitor, although still functional, was not through considered operable per Technical Specifications. The limiting condition for December 31 operation as specified in the Technical Specifications was met because the deviations between the indicated rod positions were verified to be within their 12 step limits by obtaining analog / digital rod positions at least once every 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

December 27 The Analog Rod Position Indication (ARPI) for control rod H-2 was declared

, through inoperable at 2230 hours0.0258 days <br />0.619 hours <br />0.00369 weeks <br />8.48515e-4 months <br /> due to reading greater than the Technical Specification limit December 28 of 12 steps. Actual rod position was verified to be within the 12 step limit by obtaining primary detector voltage readings. After the ARPI returned to within 12 steps following a surveillance test, control rod H-2 was declared operable at 0300 hours0.00347 days <br />0.0833 hours <br />4.960317e-4 weeks <br />1.1415e-4 months <br />.

AVERAGE DAILY UNIT POWER LEVEL DOCKET NO. 50-334 UNIT BVPS Unit i DATE January 3,1997 COMPLETED BY David T. Jones TELEPHONE (412)393-4962 MONTH December 1996 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net) (MWe-Net) 1 822 17 825 2 828 18 831 3 826 19 829 4 827 20 831 5 828 21 832 6 826 22 833 7 829 23 827

8. 829 24 831 9 825 25 834 10 823 26 834 ,

11 820 27 819 12 818 28 784 j 13 824 29 818 l 14 829 30 832 l l

15 827 31 831 16 -825 INSTRUCTIONS On this form, list the average daily unit power level MWe-Net for each day in the reporting month.

Compute to the nearest whole megawatt.

OPERATING DATA REPORT DOCKET NO.: 50-334 REPORT DATE: 01/03/97 COMPLETED BY: DAVID T. JONES TELEPHONE: (412) 393-4962 OPEP.ATING STATUS 2 1. UNIT NAME: BEAVER VALLEY POWER STATION, UNIT 1

  • Notes
  • i 2. REPORTING PERIOD: DECEMBER 1996 * *
3. LICENSED THERMAL POWER (MWt): 2652 *
  • 1
4. NAMEPLATE RATING (Gross MWe) ; 923 * *
5. DESIGN ELECTRICAL RATING (Net MWe): 835 * *
6. MAX. DEPENDABLE CAPACITY (Gross MWe): 860 * *
7. MAX. DEPENDABLE CAPACITY (Net MWe): 810 * * * * * * * * * * * * * *
8. IF CHANGES OCCUR IN CAPACITY RATINGS SINCE LAST REPORT, GIVE REASONS:
9. POWER LEVEL TO WHICH RESTRICTED, IF ANY (Net MWe): None
10. REASONS FOR RESTRICTIONS, IF ANY: N/A 7

THIS MONTH YEAR TO DATE CUMULATIVE

11. HOURS IN REPORTING PERIOD: 744.0 8784.0 181200.0
12. NO. OF HRS. REACTOR WAS CRITICAL: 744.0 7196.1 120647.9
13. REACTOR RESERVE SHUTDOWN HOURS: 0.0 0.0 4482.8
14. HOURS GENERATOR WAS ON LINE: 744.0 7134.5 118486.6

, 15. UNIT RESERVE SHUTDOWN HOURS: 0.0 0.0 0.0

16. GROSS THERMAL ENERGY GEN. (MWH) : 1959481.0 18351680.0 287273742.5
17. GROSS ELECT. ENERGY GEN. (FGE) 648890.0 6053575.0 92867592.0
18. NET ELECTRICAL ENERGY GEN. (MWH): 614370.0 5694745.0 86861569.0
19. UNIT SERVICE FACTOR: (PERCENT) 100.0 81.2 67.2
20. UNIT AVAILABILITY FACTOR:(PERCENT) 100.0 81.2 67.2
21. UNIT CAPACITY FACTOR (MDC): PCT 101.9 80.0 61.5
22. UNIT CAPACITY FACTOR (DER) : PCT 98.9 77.6 59.7
23. UNIT FORCED OUTAGE RATE: (PERCENT) 0.0 6.0 15.0 d 24. SHUTDOWNS SCHEDULED OVER NEXT SIX MONTHS (TYPE,DATE,AND DURATION OF EACH);
25. IF SHUT DOWN AT END OF REPORT PERIOD, ESTIMATED DAT" OF STARTUP:
26. UNITS IN TEST STATUS (PRIOR TO COMMERCIAL OPERATION) :

FORECAST ACHIEVED INITIAL CRITICALITY N/A N/A INITIAL ELECTRICITY N/A N/A COMMERCIAL OPERATION N/A N/A

UNIT SilUTDOWNS AND POWER REDUCTIONS (22t&) Docket No. 50-334 Unit Name BVPS Umt #I -

Date January 3.1997 Completed By David T Jones ,

REPORT MONTil December 19% Telephone (412)393-4 % 2 Date Typel Duration Reason 2 Method of Licensec System Component Cause & Corrective Action to Prevent No Shutting Event Report # Cedc4 Codc5 Recurrence (llours)

Down Reactor 3 None v

I L

i i

l 3 4 1 2 kletimd. Exlubit F-Instructwns for Preparation of Data Faary F-Forced Reason:

I-h!anual Slwets for Iicernee twent Report (1.FR) Fde S-Scheduled A-Equipment Fadure (Explain) ll-htamtenance or Test 2-htanual Scram (NUREG0161).

C-Refuelmg 3-Automatic Scram thRegulatory Restricthm 4 Cont'd. from Previous hionth E operator Traimng & t.icense Exam 5-Reduction 5 F-Administrative 94hlwr Exhdwt Il-Same Source G4)perational Error (Explam)

Il4xhcr (Explam)

NARRATIVE

SUMMARY

OF MONTHLY OPERATING EXPERIENCE UNIT 2 4

DECEMBER 1996 December 1 The Unit began the report period in Mode 3 while preparations for entering Mode 2 through continued during startup from the sixth refueling outage. A 48 hour5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> delay in startup l

. December 2 activities occurred while in Mode 3 to troubleshoot and repair leakage past a Reactor Vessel Head Vent System isolation valve.

December 3 Following leak repair of the Reactor Vessel Head Vent System isolation valve, Mode

-2 was entered at 0846 hours0.00979 days <br />0.235 hours <br />0.0014 weeks <br />3.21903e-4 months <br />. The Reactor was taken critical at 1045 hours0.0121 days <br />0.29 hours <br />0.00173 weeks <br />3.976225e-4 months <br />. At 1708 hours0.0198 days <br />0.474 hours <br />0.00282 weeks <br />6.49894e-4 months <br />, startup physics testing was halted to permit shutdown of the Reactor and

> cooldown of the plant to 400F for additional Reactor Vessel Head Vent System leakage testing and troubleshooting. Mode 3 was entered at 1735 hours0.0201 days <br />0.482 hours <br />0.00287 weeks <br />6.601675e-4 months <br /> following a manual reactor trip to shutdown the reactor. At 2316 hours0.0268 days <br />0.643 hours <br />0.00383 weeks <br />8.81238e-4 months <br />, a Reactor Coolant System temperature of approximately 400F was achieved.

December 4 The Unit remained in Mode 3 at 400F for additional leakage testing and through troubleshooting of the Reactor Vessel Head Vent System. As a result of earlier December 5 injection ofleak repair material into an upstream Reactor Vessel Head Vent System isolation valve, the "A" Reactor Vessel Head Vent System hand control valve could not be cycled completely and required repair.

December 6 The Unit began a cooldown to Mode 5 at 0228 hours0.00264 days <br />0.0633 hours <br />3.769841e-4 weeks <br />8.6754e-5 months <br /> to enable repair of the "A" Reactor Vessel Head Vent System hand control valve. Mode 4 was entered at 0925 hours0.0107 days <br />0.257 hours <br />0.00153 weeks <br />3.519625e-4 months <br /> and Mode 5 was entered at 1543 hours0.0179 days <br />0.429 hours <br />0.00255 weeks <br />5.871115e-4 months <br />.

December 7 The Unit remained in Mode 5 while repair of the "A" Reactor Vessel Head Vent  ;

through System hand control valve continued. In addition, repair of the "B" Reactor Vessel l December 12 Head Vent System hand control valve and replacement of associated piping was added to the work scope due to contamination from the leak repair material injected into the upstream isolation valve and piping.

December 13 Following successful repair and testing of the Reactor Vessel Head Vent System l valves, the Unit began to heat up and entered Mode 4 at 1742 hours0.0202 days <br />0.484 hours <br />0.00288 weeks <br />6.62831e-4 months <br />. Mode 3 was entered at 2315 hours0.0268 days <br />0.643 hours <br />0.00383 weeks <br />8.808575e-4 months <br />.

December 14 The Unit remained in Mode 3 while preparations for entering Mode 2 continued.

December 15 The Unit entered Mode 2 at 0125 hours0.00145 days <br />0.0347 hours <br />2.066799e-4 weeks <br />4.75625e-5 months <br />. The Reactor was taken critical at 0326 hours0.00377 days <br />0.0906 hours <br />5.390212e-4 weeks <br />1.24043e-4 months <br />. Mode 1 was entered at 2130 hours0.0247 days <br />0.592 hours <br />0.00352 weeks <br />8.10465e-4 months <br />.

NARRATIVE

SUMMARY

OF MONTHLY OPERATING EXPERIENCE UNIT 2 DECEMBER 1996 (Continued)

December 16 The Main Unit Generator was synchronized to the electrical grid at 0606 hours0.00701 days <br />0.168 hours <br />0.001 weeks <br />2.30583e-4 months <br /> completing the Unit's sixth refueling outage. At 1720 hours0.0199 days <br />0.478 hours <br />0.00284 weeks <br />6.5446e-4 months <br />, a load reduction was commenced prior to removing the Unit from service to permit planned Turbine overspeed trip testing. The Turbine was tripped at 1930 hours0.0223 days <br />0.536 hours <br />0.00319 weeks <br />7.34365e-4 months <br /> to support the planned Turbine overspeed trip test. During the Turbine overspeed trip test, the Unit ,

experienced a circuit card component failure in the Turbine Throttle Valve / Governor Valve transfer circuit.

December 17 Following an acceptable Turbine overspeed trip test and repair and successful Turbine Throttle Valve / Governor Valve transfer, the output breakers were closed and the Unit was synchronized to the electrical grid at 0642 hours0.00743 days <br />0.178 hours <br />0.00106 weeks <br />2.44281e-4 months <br />. Output was then escalated to approximately 27% for fuel preconditioning.

December 18 The Unit remained at approximately 27% output for fuel preconditioning.

December 19 Following completion of a core flux map, a load increase towards approximately l 70% output was commenced at 0109 hours0.00126 days <br />0.0303 hours <br />1.802249e-4 weeks <br />4.14745e-5 months <br />.

December 20 An output of approximately 67% was achieved at 1027 hours0.0119 days <br />0.285 hours <br />0.0017 weeks <br />3.907735e-4 months <br />.  ;

December 21 The Unit remained at approximately 67% output for fuel preconditioning.

December 22 Following completion of a core flux map, a load increase towards approximately 90% output was commenced at 1500 hours0.0174 days <br />0.417 hours <br />0.00248 weeks <br />5.7075e-4 months <br />.

December 23 An output of approximately 87% was achieved at 0100 hours0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br />.

December 24 Following completion of a calorimetric test, a load increase towards approximately 100% output was commenced at 0940 hours0.0109 days <br />0.261 hours <br />0.00155 weeks <br />3.5767e-4 months <br />. At 1755 hours0.0203 days <br />0.488 hours <br />0.0029 weeks <br />6.677775e-4 months <br />, the power increase was halted because a maximum output of approximately 93% could only be achieved due to the planned "B" Separator Drain Receiver Drain Pump overhaul still in progress.

December 25 The Unit remained at approximately 93% output for the remainder of the report through period while repair of the "B" Separator Drain Receiver Drain Pump occurred December 31 offsite.

Y AVERAGE DAILY UNIT POWER LEVEL DOCKET NO. 50-412 UNIT BVPS Unit 2 DATE January 3,1997 COMPLETED BY David T. Jones TELEPHONE (412)393-4962 MONTH December 1996 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL .

(MWe-Net) (MWe-Net) 1 0 17 80 2 0 18 137 3 0 19 209 4 0 20 453 5 0 21 561 6 0 22 599 7 0 23 727 8 0 24 761 9 0 25 793 10 0 26 783 11 0 27 786 12 0 28 781 13 0 29 786 14 0 30 793 15 0 31 792 16 32 INSTRUCTIONS On this form, list the average daily unit power level MWe-Net for each day in the reporting month.

Compute to the nearest whole megawatt.

I

a OPERATING DATA REPORT DOCKET NO.: 50-412 REPORT DATE: 01/03/97 COMPLF.TED BY: DAVID T. JONES TELEPHONE: (412) 393-4962 OPERATING STATUS

1. UNIT NAME: BEAVER VALLEY POWER STATION, UNIT 2
  • Notes *
2. REPORTING PERIOD: DECEMBER 1996 *' *
3. LICENSED THERMAL POWER (MWt) : 2652 *
  • 4.. NAMEPLATE RATING (Gross MWe): 923 * *
5. DESIGN ELECTRICAL RATING (Net MWe): 836 * *
6. MAX. DEPENDABLE CAPACITY (Gross MWe) : 870 * *
7. MAX. DEPENDABLE CAPACITY (Net MWe): _820 **************
8. IF CHANGES OCCUR IN CAPACITY RATINGS SINCE LAST REPORT, GIVE REASONS:
9. POWER LEVEL TO WHICH RESTRICTED, IF ANY (Net MWe): None
10. REASONS FOR RESTRICTIONS, IF ANY: N/A THIS MONTH YEAR TO DATE CUMULATIVE
11. HOURS IN REPORTING PERIOD: 744.0 8784.0 79983.0 )
12. NO. OF HRS. REACTOR WAS CRITICAL: 411.4 6239.2 67721.0 i l
13. REACTOR RESERVE SHUTDOWN HOURS: 0.0 0.0 0.0 i
14. HOURS GENERATOR WAS ON LINE: 365.2 6170.1 67264.7
15. UNIT RESERVE SHUTDOWN HOURS: 0.0 0.0 0.0
16. GROSS THERMAL ENERGY GEN. (MWH) : 718725.0 15387840.0 167211843.0
17. GROSS ELECT. ENERGY GEN. (MWH): 232495.0 5063094.0 54496423.0
18. NET ELECTRICAL ENERGY GEN. (MWH): 208959.0 4769073.0 51488596.0
19. UNIT SERVICE FACTOR: (PERCENT) 49.1 70.2 84.1
20. UNIT AVAILABILITY FACTOR:(PERCENT) 49.1 70.2 84.1
21. UNIT CAPACITY FACTOR (MDC) : PCT 34.3 66.2 78.2 I

l 22. UNIT CAPACITY FACTOR (DER) : PCT 33.6 64.9 77.0 l 23. UNIT FORCED OUTAGE RATE: (PERCENT) 47.4 18.4 4.4

24. SHUTDOWNS SCHEDULED OVER NEXT SIX MONTHS (TYPE,DATE,AND DURATION OF EACH):

i l

l

25. IF SHUT DOWN AT END OF REPORT PERIOD, ESTIMATED DATE OF STARTUP:

I 26. UNITS IN TEST STATUS (PRIOR TO COMMERCIAL OPERATION):

FORECAST ACHIEVED INITIAL CRITICALITY N/A N/A l INITIAL ELECTRICITY N/A N/A 1

COMMERCIAL OPERATION N/A N/A

-+. - -

e

UNIT SilUTDOWNS AND POWER REDUCTIONS (220%) Docket No. 50-412 Unit Name BVPS Unit #2 Date January 3,1997 Completed By David T. Jones ,

REPORT MONTil December 1996 Telephone (412)393-4 % 2 No. Date Typel Duration Reason 2 Method of Licensec System Component Cause & Corrective Action to Prevent Shutting Event Report # Codc4 Codc5 Recurrence (llours)

Down Reactor 3 14 961201 S 8.0 C 4 N/A RC FUELXX Continued with previously planned startup activitics related to the Unit's sixth refueling outage.

15  % I201 F 48.0 A 9 N/A CA VALVEX A delay in startup activitics occurred to permit troubleshooting and repair of leakage past a Reactor Vessel licad Vent System isolation valve. The valve was injected with leak repair material.

16  % I203 S 9.1 C 9 N/A RC FUELXX Continued with previously planned startup activities related to the Unit's sixth refueling outage.

17  % I203 F 274.3 B/A 1 2- % 003 CA VALVEX Manually tripped the Reactor and cooled down to 400F to permit additional Reactor Vessel IIcad Vent S3 stem leakage testing and troubleshooting.

Procccded to cool the plant to cold shutdown to enable repair / replacement of the A and B Reactor Vessel licad Vent System hand control valves and piping.

i 2 3 4 htethod. Exhibit F-Instructims fir Preparatkm of Data i ntry F-lined Reason A49npment Failure (Explam) I htanual Shects fir I.neensee Event Repsut (Et:R) ble S-kheduled ll-Alaintenance tr Test 2-klanual Scram (Nt 'RI Go t61).

C-Refuctmg 3-Aukanatee scram D-Regulattry Restrictim 44'ont'd frtwn Prevunas hionth E-Operat r Traming & I icense Exam 5-Reductkm 5 F-Admmistrative SOthea- Exluhit II-Fame Source G-Operatumal Frnr (Explain)

Il4 kher (Explain)

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. . . - . ~= . - - . -

UNIT SilUTDOWNS AND POWER REDUCTIONS (220%) Docket No. 50-412

~ '

Unit Name BVPS Umt #2 Date January 3,1997 Completed By Das id T. Jones -

REPORT MONTil December 1996 Telephone (412)393-4 % 2 Date Typel Duration Reason 2 Method of 1.icensee System Component Cause & Corrective Action to Prevent No Shutting Event Report # Code 4 Codc5 Recurrence (llours)

Down Reactor 3 26.7 C 9 N/A RC FUELXX Continued with and completed pres nously 18 961215 S planned startup activitics related to the Unit's sixth refueling outage.

19 961216 S 6.0 B 9 N/A IIA TURBIN The Unit was removed from service to permit Turbine overspeed trip testing (the Reactor remained critical).

961217 F 6.7 A 9 N/A IIA INSTRU During Turbine overspeed trip testing, a 20 circuit card component failure occurred in the Turbine Throttic Valve / Governor Valve transfer circuit. The circuit was repaired and the Unit was returned to service to complete power escalation testing subsequent to the Umt's sixth refueling outage.

3 4 I 2 kletin! Eslutut F-Instructiuns liw Preparation of Data Entry F-Fisced Reason.

1-klanual Sheets for licensee bent Reptut G.ER)l'ile S-schethiled A-Equipment Failure (Explain) tl-klaintenance or Test 2-htanual Scram (Nt'REGul61).

C-Refuchng 3-Automatic scram D-Regulatory Restrictum 40mit'd. frorn Previous hionth 5-Reductawi 5 E-Operator Traimng & 1icense Exam F-Administrative 94 kher Edubit Il-Same source ,

G-operatwnal Fnor (Explain)

Il-Other (Explain)

_ .- , . - - - - - .

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