ML20141B350

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Monthly Operating Repts for Apr 1997 for Beaver Valley Power Station,Units 1 & 2
ML20141B350
Person / Time
Site: Beaver Valley
Issue date: 04/30/1997
From: David Jones, Legrand R
DUQUESNE LIGHT CO.
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 9705150247
Download: ML20141B350 (10)


Text

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Telephone (412) 393-6000 Nuclear Group hp rt, PA 15077-0004 May 7,1997 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 Report U. S. Nuclear Regulatory Commission Document Control Desk

)

Washington, DC 20555 Gentlemen:

In accordance with Appendix A, Technical Specifications, the Monthly Operating Report is submitted for Unit I and Unit 2 for the month of April,1997.

Respectfully, A-n

/

R. L. LeGrand Division Vice President, Nuclear Operations /

Plant Manager i

DTJ/stp Enclosures cc:

NRC Regional Oflice g

King ofPrussia, PA j

9705150247 970430 POR ADOCK 05000334 R

PDR q 1he s_,e., P,.<ess,o..,s g

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i NARRATIVE

SUMMARY

OF l

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"~

MONTHLY OPERATING EXPERIENCE I

i

- UNIT 1 APRIL 1997.

i April 1 The Unit began the report period shutdown in Mode 5 to continue with repair of the i

through "A" Reactor Coolant Loop Cold Leg Isolation Valve.

April 4

-l i

April 5 Upon satisfactony completion of repairs to the "A" Reactor Coolant Loop Cold Leg

' through Isolation Valve, reactor coolant system heatup began while several issues were I

' April 10 resolved prior to entering Mode 4.

i

. April 11_

Mode 4 was entered at 0313 hours0.00362 days <br />0.0869 hours <br />5.175265e-4 weeks <br />1.190965e-4 months <br /> as plant heatup continued and as preparations were made for entering Mode 3.

April 12 Mode 3 was entered at 1421 hours0.0164 days <br />0.395 hours <br />0.00235 weeks <br />5.406905e-4 months <br /> as plant heatup continued and as preparations were made for entering Mode 2.

l April 13 Mode 2 was entered at 2214 hours0.0256 days <br />0.615 hours <br />0.00366 weeks <br />8.42427e-4 months <br /> and the Reactor was taken critical at 2313 hours0.0268 days <br />0.643 hours <br />0.00382 weeks <br />8.800965e-4 months <br />.

April 14 Mode I was entered at 0328 hours0.0038 days <br />0.0911 hours <br />5.42328e-4 weeks <br />1.24804e-4 months <br />. The Unit was synchronized to the electrical grid at 0711 hours0.00823 days <br />0.198 hours <br />0.00118 weeks <br />2.705355e-4 months <br /> and began power escalation towards 100% output.

April 15 The Unit achieved a nominal value of 100% output at 2115 hours0.0245 days <br />0.588 hours <br />0.0035 weeks <br />8.047575e-4 months <br />.

Aprii 16 The Unit operated at a nominal value of 100% output for the remainder of the report through period.

i April 30 In_ addition to the above, the following events which also occurred during the report period are being reported as required by Technical Specifications.

i April 1 The Automatic Rod Position Deviation Monitor, although still functional, was not i

through considered operable per Technical Specifications.

The limiting condition for April 30 -

. operation as specified in the Technical Specifications was met because the desistions

. 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 />.

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NARRATIVE

SUMMARY

OF l

4

'. MONTHLY OPERATING EXPERIENCE UNIT 1 APRIL 1997 (Continued)

April 14 With the Unit in Mode 2 and the Reactor critical, the Analog Rod Position Indication l

(ARPI) for Control Rod G-3 was declared inoperable at 0001 hours1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> due to reading greater than the Technical Specification limit of 12 steps. In addition, the primary i

detector voltage readings also verified the control rod to be low outside of the 12 step limit. The limiting condition for operation as specified in the Technical

' l Specifications was met because the trippability of the control rod was verified, and the high neutron flux trip setpoint was reduced to 585% of rated thermal power.

Following recalibration of the ARPI for Control Rod G-3, a channel check was performed satisfactorily and Control Rod G-3 was declared c,perable at 0226 hours0.00262 days <br />0.0628 hours <br />3.736772e-4 weeks <br />8.5993e-5 months <br />.

April 15 At 1645 hours0.019 days <br />0.457 hours <br />0.00272 weeks <br />6.259225e-4 months <br />, the Analog Rod Position Indication (ARPI) for Control Rod H-2 was declared inoperable due to reading greater than the Technical Specification limit of 12 steps. In addition, the primary detector voltage readings also verified the control j

rod to be high outside of the 12 step limit. The limiting condition for operation as specified in the Technical Specifications was met because the control rod position was verified to be within the 12 step limit by using the incore movable detectors.

j April 16 Following recalibration of the ARPI for Control Rod H-2, a channel check was performed satisfactorily and Control Rod H-2 was declared operable at 0600 hours0.00694 days <br />0.167 hours <br />9.920635e-4 weeks <br />2.283e-4 months <br />.

i 4

s

AVERAGE DAILY UNIT POWER LEVEL DOCKET NO. 50-334 UNIT BVPS Unit 1 DATE May 2,1997 COMPLETED BY David T. Jones TELEPHONE (412) 393-4962 MONTH April 1997 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net)

(MWe-Net) 1 0

17 823 2

0 18 826 3

0 19 825 4

0 20 826 5

0 21 826 6

0 22 825 7

0 23 826 8

0 24 827

)

9 0

25 827 10 0

26 824 11 0

27 824 12 0

28 824 13 0

29 824 14 209 30 819 j

15 670 31 16 821 l

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 i

DOCKET NO..

50-334

)

REPORT DATE:

05/02/97 COMPLETED BY: DAVID T. JONES TELEPHONE:

(412) 393-4962

)

QiSRATING STATUS j

1. UNIT NAME: BEAVER VALLEY POWER STATION, UNIT 1
  • Notes
2. REPORTING PERIOD: APRIL 1997
3. LICENSED THERMAL POWER (MWt) :

2652

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 j

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 l

THIS MONTH YEAR TO DATE CUMULATIVE j

11. HOURS IN REPORTING PERIOD:

719.0 2879.0 184079.0

12. NO. OF HRS. REACTOR WAS CRITICAL:

408.8 2262.9 122910.8

13. REACTOR RESERVE SHUTDOWN HOURS:

0.0 0.0 4482.8 j

14. HOURS GENERATOR WAS ON LINE:

400.8 2254.9 120741.5

15. UNIT RESERVE SHUTDOWN HOURS:

0.0 0.0 0.0

16. GROSS THERMAL ENERGY GEN. (MWH):

1023580.0 5879346.0 293153088.5 17 GROSS ELECT, ENERGY GEN. (MWH):

337912.0 1957555.0 94825147.0

18. NET ELECTRICAL ENERGY GEN. (MWH):

314092.0 1841345.0 88702914.0

19. UNIT SERVICE FACTOR: (PERCENT) 55.7 78.3 67.3
20. UNIT AVAILABILITY FACTOR:(PERCENT) 55.7 78.3 67.3
21. UNIT CAPACITY FACTOR (MDC): PCT 53.9 79.0 61.8
22. UNIT CAPACITY FACTOR (DER): PCT 52.3 76.6 59.9
23. UNIT FORCED OUTAGE RATE: (PERCENT) 44.3 21.7 15.1
24. SHUTDOWNS SCHEDULED OVER NEXT SIX MONTHS (TYPE,DATE,AND DURATION OF EACH):

THE UNIT'S 12TH REFUELING OUTAGE IS SCHEDULED TO BEGIN ON 9/5/97 AND LAST FOR

,,,3 5 DAYS.

25. IF SHUT DOWN AT END OF REPORT PERIOD, ESTIMATED DATE 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 SIRTIDOWNS AND POWER REDUCTIONS (22tM4)

Docket No. 50-334 Unit Name BVPS Unit #1 Date May 2,1997 Completed By Dmid T. Jones REPORT MONIH April 1997 T@w (412) 393-4 % 2 No.

Date Typel Duration Reason 2 Method of Licensee System c.

, - =:

Cause A Corrective Action to Prevent (Hours)

Shutting Event Report #

Code 4 radd Recunence Down Reactor 3 4

970401 F

109.8 A

4 N/A CB VALVEX The Unit rematned in cold shutdown to complete repair of a body-to-bonnet flange joint Icak on the "A" Reactor Coolant Loop Cold Leg Isolation Valve.

5 970405 F

209.4 11 9

N/A ZZ 777777 The Unit continued with reactor coolant system heatup and startup activities, resolving several issues prior to entering Mode 4 and prior to sywhronizing to the electncal grid.

h 1

2 3

4 F-Farad Reasorr Meehat Exhibit F-Instructens for Paparahan of Dana Entry S-ScM w A-Equipment Failure (Explain) 1-Manual Shases for I.acensee Event Report (LER) Fine IkMaineenance or Test 2-Manual Saam (NURE0016I).

C-Refueling 3-Automatic Saarn D-Regulatory Restridion 4 Cont'd from Preneus Mesah E4)perator Trainmg & Lacense Exam 5-Reeaction 5

F-A&nnustrative 94)ther Exhibit Il-Same Source G4)pershonal Error (Explain) lI-Other(Explain)

~

NARRATIVE

SUMMARY

OF

-)

. MONTHLY OPERATING EXPERIENCE UNIT 2 h

APRIL 1997 April 1 The-Unit began the report period operating at approximately 59% output to complete repair of the mechanical seal on the "A" Main Feedwater Pump. Following

]

completion of repairs, the Unit began to increase power towards 100% output at 0850 hours0.00984 days <br />0.236 hours <br />0.00141 weeks <br />3.23425e-4 months <br />.' The Unit achieved a nominal value of 100% output at 1755 hours0.0203 days <br />0.488 hours <br />0.0029 weeks <br />6.677775e-4 months <br />.

)

April 2 The Unit operated at a nominal value of 100% output.

)

through -

' April 12 l

April 13 At 0302 hours0.0035 days <br />0.0839 hours <br />4.993386e-4 weeks <br />1.14911e-4 months <br />, the Unit began to decrease output to approximately 39% to evaluate a steam leak at the manway on the Moisture Separator Drain Receiver Tank for possible leak repair. An output of approximately 39% was achieved at 0612 hours0.00708 days <br />0.17 hours <br />0.00101 weeks <br />2.32866e-4 months <br />.

April 14 The Unit remained at approximately 39% output while preparations for leak repair of the manway on the Moisture Separator Drain Receiver Tank continued.

4 April 15 The Unit began to increase power towards 100% output at 1145 hours0.0133 days <br />0.318 hours <br />0.00189 weeks <br />4.356725e-4 months <br />. The Unit achieved a nominal value of 100% output at 2125 hours0.0246 days <br />0.59 hours <br />0.00351 weeks <br />8.085625e-4 months <br />.

I April 16 The Unit operated at a nominal value of 100% output.

through April 30 l

i I

AVERAGE DAILY UNIT POWER LEVEL DOCKET NO. 50-412 UNIT BVPS Unit 2 DATE May 2,1997 COMPLETED BY David T. Jones TELEPHONE (412) 393-4962 MONTH April 1997 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net)

(MWe-Net) 1 657 17 836 2

833 18 836

-3 830 19 836 4

827 20 835 5

826 21 835 6

822 22 836 7

837 23 836 8

838 24 836 9

838 25 835 10 836 26 836 11 833 27 833 12 829 28 834 4

13 381 29 835 14 271 30 829 15 461 31 16 832 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.

s OPERATING DATA REPORT DOCKET NO.:

50-412 REPORT DATE:' 05/02/97 COMPLETED BY: DAVID T. JONES TELEPHONE:

(412) 393-4962 OPERATING STATUS

1. UNIT NAME: BEAVER VALLEY POWER STATION, UNIT 2
  • Notes 2.

REPORTING PERIOD: APRIL 1997 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 DA'!2 CUMULATIVE

11. HOURS IN REPORTING PERIOD:

719.0 2879.0 82862.0

12. NO. OF HRS. REACTOR WAS CRITICAL:

719.0 2401.7 70122.7

13. REACTOR RESERVE SHUTDOWN HOURS:-

0.0 0.0 0.0

14. HOURS GENERATOR WAS ON LINE:

719.0 2375.3 69640.0 if.' UNIT RESERVE SHUTDOWN HOURS:

0.0 0.0 0.0

16. GROSS THERMAL ENERGY GEN. (MWH):

1788741.0 5980776.0 17319151P.0

17. GROSS ELECT. ENERGY CEN. (MWH):

592250.0 1986841.0 56483'.64.0

18. NET ELECTRICAL ENERGY GEN. (MWH):

561678.0 1874129.0 5336273.0

19. UNIT SERVICE FACTOR: (PERCENT) 100.0 82.5 84.0
20. UNIT AVAILABILITY FACTOR:(PERCENT) 100.0 82.5 84.0 l

21.' UNIT CAPACITY FACTOR (MDC) : PCT 95.3 79.4 78.2

22. UNIT CAPACITY FACTOR (DER): PCT 93.4 77.9 77.0
23. UNIT FORCED OUTAGE RATE: (PERCENT) 0.0 17.5 4.9
24. SHUTDOWNS SCHEDULED OVER NEXT SIX MONTHS (TYPE,DATE,AND DURATION OF EACH):
25. IF SHUT DOWN AT END OF REPORT PERIOD, ESTIMATED DATE 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 i

1 I

UNIT SHUTDOWNS AND POWER REDUCTIONS (22(W.)

Docket No. 50-412 Unit Name BVPS Unit #2 Date May 2,1997 l

Completed Dy _ David T. Jones REPORT MONTE April 1997 Telephone (412)393-4 % 2 No.

Date Typel Duration Reason 2 Method of Ixensee S)Mem Component Cause & Corrective Action to Prevent (Hours)

Shutting Ewnt Report #

Code 4 Code 5 Recurrence Down Reactor 3 10 970401 F

0 B

4 N/A CH PUMPXX While operating at approximately 59%

output, the Unit completed repair of the anechanical seal on the "A" Main Feedwater Pump.

11 970413 F

0 B

5 N/A HH IUEXCH The Unit reduced output to approximately 39% to evaluate and leak repair a steam leak on the manway of the Moisture Separator Drain Receiver Tank.

I 2

3 4

l F-Forced Rea m Medmod; FM F-Insermsons for 7.v

_ of Desa Entry l

S-Sche M ed AF,

^ Failure (Emplain) 1.u-a h for I-Evuen Reyest (IIR) Film B-h or Tem 2-Manuel Sassa (NUREOGI6th C-Refueleg 3-Ameamsenc Sean D-Reguissary Resencium 4-Cess'd. fress Prewsmus Messh E4perusar Training & license Exam 5 Rhan 5

F.Ashannessrssive 9-Other Fm H-Bamse Searce G4-

" Error (Explam)

Il-Other(Explain)

_ - _