ML20210K582

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Monthly Operating Repts for Jul 1997 for Bvps,Units 1 & 2
ML20210K582
Person / Time
Site: Beaver Valley
Issue date: 07/31/1997
From: David Jones, Legrand R
DUQUESNE LIGHT CO.
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 9708190310
Download: ML20210K582 (11)


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$hippingport, PA 15077 0004 August 8,1997 Deaver Valley Power Station Unit 1 - Docket No. 50-334, License No. DPR-66 Unit 2 - Docket No. 50-412, License No. NPF-73 Monthly Operatina Report l

l 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 ofJuly,1997.

Respectfully, j af AE,'h

$;na( . '

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

Plant Manager DTJ/ sip Enclosures p,j W,C 6 7fI p

cc: NRC Regional Ollice King of Prussia, PA 1

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y *he Nuclear Professionals a e , n i fi O

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, ADOCK 05000334-PDR s

. , NARRATIVE

SUMMARY

OF 4

MONTHLY OPERATING EXPERIENCE UNIT 1 JULY 1997 July 1 The Unit began the report period shutdown in Mode 3 to resolve seismic qualification concerns with the main feedwater flow transmitters.

July 2 At 1729 hours0.02 days <br />0.48 hours <br />0.00286 weeks <br />6.578845e-4 months <br />, the Unit began to cooldown to Mode 5 to perform a design change l to the main feedwater flow transmitter control circuitry and for needed modifications l to pipe supports on the excess letdown piping.

July 3 Mode 4 was entered at 0923 hours0.0107 days <br />0.256 hours <br />0.00153 weeks <br />3.512015e-4 months <br /> and Mode 5 was entered at 1830.

July 4 While the Unit remained in Mode 5, a median control selector switch was installed as through a corrective action to resolve the main feedwater flow transmittec:, seismic

- July 28 qualification concerns, and modifications to the excess letdown piping were completed. Additional activities involved repairing and modifying additional pipe supports to the Charging and Volume Control System's normal and excess letdown lines, and also completing modifications to three containment isolation check valves.

July 29 Following completion of the above, the Unit began to heatup and entered Mode 4 at 1649 hours0.0191 days <br />0.458 hours <br />0.00273 weeks <br />6.274445e-4 months <br />.

July 30 The Unit continued to heatup and entered Mode 3 at 0028 hours3.240741e-4 days <br />0.00778 hours <br />4.62963e-5 weeks <br />1.0654e-5 months <br />.

July 31 Mode 2 was entered at 0305 hours0.00353 days <br />0.0847 hours <br />5.042989e-4 weeks <br />1.160525e-4 months <br /> and the reactor was taken critical at 0443 hours0.00513 days <br />0.123 hours <br />7.324735e-4 weeks <br />1.685615e-4 months <br />.

Mode I was entered at 0610 hours0.00706 days <br />0.169 hours <br />0.00101 weeks <br />2.32105e-4 months <br />. The Main Unit Generator was synchronized to the electrical grid at 1059 hours0.0123 days <br />0.294 hours <br />0.00175 weeks <br />4.029495e-4 months <br /> and power was escalated to approximately 30%

output. The Unit remained at approximately 30% output through the end of the report period.

Also note that following entry in Mode 2, the Automatic Rod Control Position Deviation Monitor, although- still functional, was not considered operable per Technical Specifications. The limiting condition for 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 />. In addition, Control Rod H-2 was also considered inoperable. The limiting condition for operation as specified in the Technical Specifications was met by reading the detector primary voltage every four hours.

. . AVERAGE DAILY UNIT POWER LEVEL 4

l

(- ,

DOCKET NO. 50-334

UNIT BVPS Unit l l DATE August 4,1997 l COMPLETED BY David T. Jones l TELEPHONE (412) 3934962 -

l l

MONTli July 1997 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe Net) (MWe Net)

!! 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 0 26' 0 ,

11 0 27 0 12 0 28 0 13 0 29 0 _

14 _,.

0 30 0 15- 0 31 105 16 0 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. -

a OPERATING DATA REPORT DOCKET No.: 50-334 REPORT DATE: 08/05/97 COMPLETED BY: DAVID T. JONES TELEPHONE: (412) 393-4962 OPEPATING STATUS

1. UNIT NAME: BEAVER VALLEY POWER STATION, UNIT 1
  • Notes *
2. REPORTING PERIOD: JULY 1997 * *
3. LICENSED THEPJ4AL POWER (MWt): 2652 * *
4. NAMEPLATE RATING (Gross MWe)t 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. REAEONS FOR RESTRICTIONS, IF ANY: N/A THIS MONTH YEAR TO DATE CUMULATIVE
11. HOURS IN REPORTI'*O FER*0ni 744.0 5087.0 186207.0
12. NO. OF HRS. REACTOR WAS CRITi~3L: 19.3 3675.7 124323.6
13. REACTOR RESERVE SHUTDOWN Hotaf: 0.0 0.0 4482.8 14 HOURS GENERATOR WAS ON LINE: 13.0 3660.4 122147.0
15. UNIT RESERVE SHUTDOWN HOURS: 0.0 0.0 0.0
16. GROSS THERMAL ENERGY GEN. (MWH): 11589.0 3559902.0 296833644.5
17. GLOSS ELECT. ENERGY GEN. (MWH): 2478.0 3163653.0 96031245.0 '
18. NET ELECTRICAL ENERGY GEN. (MWH): -12342.0 2963843.0 89825412.0
19. UNIT SERVICE FACTOR: (PERCENT) 1.7 72.0 67.3
20. UNIT AVAILABILITY FACTOR: (PERCENT) 1.7 72.0 67.3
21. UNIT CAPACITY FACTOR (MDC) : PCT 0.0 71.9 61.8
22. UNIT CAPACITY FACTOR (DER) : PCT 0.0 69.8 59.9 23.' UNIT FORCED OUTAGE RATE: (PERCENT) 98.3 28.0 15.5
24. SIF.1TDOWNS SCHEDULED OVER NEXT 'X MONTHS (TYPE,DATE,AND DURATION OF EACH):

THE UNIT'S 12TH REFUELING OUTAGE r. 3 BEEN RESCHEDULED TO BEGIN ON 9/27/97 AND LAST FOR 45 DAYS.

25. IF SHUT 1>OWN AT END OF REPORT PERIOD, ESTIMATED DATE OF STARTUP:
26. UNIT 9 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

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Docket No. 50-334 l UNIT SHUTDOWNS AND POWER REDUCT10NS (220%) ,

Unit Name BVPS Unit #1 Date August 4,1997 Compicted By Dasid T. Jones REPORT MONT11 July 1997 Tc'-y--e (412)393-4 % 2 -

No. Dase Typel Duratsos Reason 2 Method of f acensee System Component Cause & Correcthe Action to Present (Hours) Shutting , Event Report # Code 4 Code 5 Recurrence  ;

Dous Reactor 3 8 970701 F 189.0 F 4 1-97-015 CH INSTRU The Unit remained shutdoun and cooled dann to Mode 5 to resoht sersauc qualdication concerns with the main feednter flow transmitters. A naah=

control selector switch nas i.estalled to resohe this issue.

9 970708 F 139.0 B 9 N/A CG PIPEXX The Unit remamed shutdoun in Mode 5 to conctete modifications to sestral pipe supports on the excess letdown pipang.

10 970714 F 41.0 B 9 N/A SD VALVEX The Unit remained shutdown in Mode 5 to compicte moddicauons to three containment isolauon check uhts.

11 970716 F 34.3 H 9 N/A ZZ 777777 The Unit e startup actnitics in preparauon for entering Mode 4.

l s 2 3 4 F-Forced Reasant hkead. FMt F * - -- for Preparassan ofDoes Esery S.Sciuduled A.T , - Fadure(Explain) I-klammel sheets tw 1xensee Ems Repat(11R) File B41amme.sance er Test 2-klanual Screen (Nt'REGO161) caeruchng ?c- - Scrasa D.aes hnory aes=xtion 44:am 4 rnum Pr== Esaiah F Operusar Tramung & ticense Emani S-Redactane S F-Aeimrusershve 94Mer Ext:stus H-Sann Seurte GOpermisonal Erm %)

H4mur(Explaan)

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UNIT SHUIDOWNS AND POWER REDUCI1ONS (220%) Dociet No. 50-334 .

Unit Name BVPS Usut #I Daec August 4.1997 Cosapicted BT Dmid T. Jones REPORTMONTH July 1997 Telephoac (412)393-4 % 2 -

Typel Duration Reasce2 Method of th Systent C- == Came & Correcthe Action to Present No. - Date .

(Hours) Shutting Estat Report # Codc4 Codc5 Recurrence Donin Reactor 3 12 970717- F 285.5' B 9 N/A CG PIPEXX The Unit remassed shutdoun in Mode 5 to cosapicte sestral other pipe suppost repaars/moddicassons in the Chenescal &

Volume Control 3S m normal and excess lendomu le 13 970729 F 42.2 H 9 N/A ZZ 777777 The Unit comupleted startup acthities and returned to a nominal cusput of 100*i I 2 3 4 F-Forced Reasaur h8ednest Edines F4mentmas fer Prayerseman of Dess Imwy S-Sciwdmied ASW Fasiuse(Empiesm) 145mmuni sheses for txemmer Event Report (11R) File B4sh or Test 245ammet Scrusa (Nt_REOGl61)

C-Redselsig 3 ,*- Screen .

IMtegninkrv Restrichen 44ema'd. fraum Previases kicush ,

E% Training & Ixemme Emmse 5-Redacon 3 F.Ashmmamersanw 94 Mar Edubit H-senne sawce Gopersesamel Error (Emplems)

H4Mier(Empimin)

NARRATIVE

SUMMARY

OF MONTi{LY OPERATING EXPERIENCE 4

UNIT 2 JULY 1997 July 1 The Unit operated at a nominal value of 100% output.

July 2 With unusually warm and humid atmospheric conditions present, incremental load through reductions to approximately 98.5% output were commenced at 1729 hours0.02 days <br />0.48 hours <br />0.00286 weeks <br />6.578845e-4 months <br /> to July 4 stabilize Condenser Hotwell conditions due to the heat transfer capability of the Cooling Tower being slightly below design. Once conditions in the Condenser Hotwell had improved, the Unit was returned to full power at 0248 hours0.00287 days <br />0.0689 hours <br />4.100529e-4 weeks <br />9.4364e-5 months <br />.

July 5 The Unit operated at a nominal value of 100% output, through July 9 l

l July 10 The Unit operated at a nominal value of 100% output until 1135 hours0.0131 days <br />0.315 hours <br />0.00188 weeks <br />4.318675e-4 months <br /> when a l power reduction was commenced due to high seal leakoff flow on the "C" Reactor l Coolant Pump. The Main Unit Generator output breakers were opened and the Unit l was taken offline at 1945 hours0.0225 days <br />0.54 hours <br />0.00322 weeks <br />7.400725e-4 months <br />. Mode 2 was entered at 2008 hours0.0232 days <br />0.558 hours <br />0.00332 weeks <br />7.64044e-4 months <br /> and Mode 3 l

was entered at 2046 hours0.0237 days <br />0.568 hours <br />0.00338 weeks <br />7.78503e-4 months <br />.

July 11 The plant continued to cooldown to Mode 5 to permit repair of both the "A" and "C" Reactor Coolant Pump seals. Mode 4 was entered at 1337 hours0.0155 days <br />0.371 hours <br />0.00221 weeks <br />5.087285e-4 months <br />.

July 12 Mode 5 was entered at 0117 hours0.00135 days <br />0.0325 hours <br />1.934524e-4 weeks <br />4.45185e-5 months <br />.

July 13 The Unit remained in Mode 5 while repair of the "A" and "C" Reactor Coolant Pump through seals continued.

July 20 July 21 Following completion of repairs, the Unit began to heatup and entered Mode 4 at 1722 hours0.0199 days <br />0.478 hours <br />0.00285 weeks <br />6.55221e-4 months <br />.

July 22 The Unit continued to heatup and entered Mode 3 at 0620 hours0.00718 days <br />0.172 hours <br />0.00103 weeks <br />2.3591e-4 months <br />.

July 23 Mode 2 was entered at 0044 hours5.092593e-4 days <br />0.0122 hours <br />7.275132e-5 weeks <br />1.6742e-5 months <br /> and the reactor was taken critical at 0224 hours0.00259 days <br />0.0622 hours <br />3.703704e-4 weeks <br />8.5232e-5 months <br />.

Mode I was entered at 0752 hours0.0087 days <br />0.209 hours <br />0.00124 weeks <br />2.86136e-4 months <br />. The Main Unit Generator was synchronized to the electrical grid at 1248 hours0.0144 days <br />0.347 hours <br />0.00206 weeks <br />4.74864e-4 months <br /> and a return to full power was commenced.

4

.- NARRATIVE

SUMMARY

OF i

MONTHLY OPERATING EXPERIENCE UNIT 2

JULY 1997 l

l (Continued) 1 July 24 A nominal output of 100% was achieved at 1700 hours0.0197 days <br />0.472 hours <br />0.00281 weeks <br />6.4685e-4 months <br />.

July 25 The Unit operated at a nominal value of 100% output.

through July 26

- July 27 With unusually warm and humid atmospheric conditions present, incremental load reductions to approximately 96.5% output were commenced at 1342 hours0.0155 days <br />0.373 hours <br />0.00222 weeks <br />5.10631e-4 months <br /> to stabilize Condenser Hotwell conditions due to the heat transfer capability of the Cooling Tower being slightly below design.

July 28 Once conditions in the Condenser Hotwell had improved, 'the Unit was returned to full power at 0332 hours0.00384 days <br />0.0922 hours <br />5.489418e-4 weeks <br />1.26326e-4 months <br />.

July 29 The Unit operated at a nominal value of 100% output for the remainder of the report through period.

July 31

^

, ' ,- ' AVERAGE DAILY UNIT POWER LEVEL

, . DOCKET NO. 50-412 UNIT BVPS Unit 2 DATE August 4,1997 COMPLETED BY David T. Jones TELEPHONE (412) 393-4962 MONTH July 1997 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DA1!.Y POWER LEVEL (MWe-Net) (MW -Net)

=l 815 17 0 l- -2 809 18 0 3 805 19 0

-- 4 823 20 0 i 829 21 -0

-- 6 823 22 __

0 7 822 23 114-8 816 24 634 9- 819 25- -815-10 659 26- 815 0 27- 795 12 0 28 808

'13 0 29 824 14 -0 30 827 15 0- 31 822 16 0 INSTRUCTIONS -

l 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. "

4 a

o- ,

OPERATING DATA REPORT COCKET No.: 50-412 REPORT DATE: 08/05/97 3 COMPLETED BY: DAVID T. JONES TELEPHONE: (412) 393-4962 OPERATING STATUS

1. UNIT NAME: BEAVER VALLEY POWER STATION, UNIT 2
  • Notes *
2. REPORTING PERIOD: JULY 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 RATINOS 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 CUM'LATIVE
11. HOURS IN REPORTING PERIOD: 744.0 5087.0 85070.0
12. NO. OF HRS. REACTOR WAS CRITICAL: 450.4 4316.1 72037.1
13. REACTOR RESERVE SHUTDOWN HOURS: 0.0 0.0 0,0
14. HOURS GENE 2ATOR WAS ON LINE: 439.0 4278.3 71543.0
15. UNIT RESF' AVE SHUTDOWN HOURS: 0.0 0.0 0.0
16. GROSS THERMAL ENERGY GEN. (MWH)- 1115985.0 10951889.0 178163732.0 ,
17. GROSS ELECT. ENERGY GEN. (MWH). 362406.0 3620509.0 58116932.0
18. NET ELECTRICAL ENERGY GEN. (MWH): 338939.0 3421606.0 54910202.0
19. UNIT SERVICE FACTOR: (PERCENT) 59.0 84.1 84,1
20. UNIT AVAILABILITY FACTOR: (PERCENT) 59.0 84,1 84,1
21. UNIT CAPACITY FACTOR (MDC) : PCT 55.6 82.0 78.4
22. UNIT CAPACITY FACTOR (DER) : PCT 54.5 80.5 77.2
23. UNIT FORCED OUTAGE RATE: (PERCENT) 41.0 15.9 5.2
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

. o~

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  • UNIT SHUTDOWNS AND POWER REDUCTIONS (220%) Docket No. 50-412 " ,.

Uma Nane BVPS Unit #2 Date August 4,1997 Completed By ;IMid T. Jones l "I

REPORT MONni Julv1997 TQ.s. e (412)393-4 % 2 -

No. Date Typel Darauon Reason 2 ' Method of Licensee System Component Cause & Correctin Acuon to Pment (Hours) Shutting Event Report # Code 4 Codc5 Recurrence Down Reactor 3 12 970710 F 0 B 5 N/A CB PUMPXX - The Unit began a forced shutdown due to high seal leakoff flow on the "C* Reactor Coolant Pump.

13 ' 970710 F 305.0 'B 1 N/A CB PUMPXX The Unit was taken off-line and cooled down to Mode 5 to repair the seals on both the "A" and "C" Reactor Coolant Pumps. The cause for.the seal leakage was determined to be particulate nuterial deposited on the seals due to internal bypass ihm through the seal injection filter. This condition was corrected and the seals were replaced. The "B" Reactor Coolant Pump seal was not substantially affected and showed imprmement aAer the filter was corrected. This seal will be replaced during the . upcoming 7th refueling outage in the Spring of 1998.

14 970723 F '0 H 9 N/A ZZ 777777 The Unit completed startup activities and returned to a nominal output of 100%.

I 2 3- 4 Reason- hieshod; Exhann F-bueracteous fw Preparasson of Data Enary ..

F-Forced A-Equeraarm Failure (Explain) 1-htaemal Shrees for Lacensee Event Report (LER) Fde S-Sdieduled Ikhtaimenance er Test 2-nfanual Scram (Nt3tE00161).

C-Referisig 3-Autonistic Sanse .

. D-Regulasary Restritiost 4Com'd. froun Press klasah E4. Wor Training A U wnse Exarn 5-Reduction 5 l F-Adrninistrathe 94eer Exhitut H-Sanne Source l- 0-Operational Error (Explain)

' II4hher(Explain)

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