L-98-178, Monthly Operating Repts for Aug 1998 for Bvps,Units 1 & 2. with

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Monthly Operating Repts for Aug 1998 for Bvps,Units 1 & 2. with
ML20197C874
Person / Time
Site: Beaver Valley  FirstEnergy icon.png
Issue date: 08/31/1998
From: Brandt R, David Jones
DUQUESNE LIGHT CO.
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
GL-97-02, GL-97-2, L-98-178, NUDOCS 9809140268
Download: ML20197C874 (6)
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Telephone (412) 39}-6000 puc'*a;jaa og L-98-178 Shippingport. PA 15077-0004 September 4,1998 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 NRC Generic Letter 97-02, " Revised Contents of the Monthly Operating Report", and Unit I and 2 Technical Specification 6.9.1.6, the " Monthly Operating Report" is submitted for Unit 1 and Unit 2 for the month of August,1998.

Respectfully,

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R. D. Brandt Division Vice President, Nuclear Operations Group and Plant Manager i g DTJ/slp h(

Enclosures cc: NRC Regional Office King ofPrussia, PA 7 ,7 r n s 's

{ , The Nuclear Professionals 9809140268 980831 PDR ADOCK 05000334.

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.- UNIT SHUTDOWNS DOCKET NO. 50-334 UNIT NAME BVPS Unit #1 DATE September 2,1998 COMPLETED BY David T. Jones TELEPHONE (412) 393-4962 REPORTING PERIOD: Auaust 1998 No. Date Type Duration Reason Method of Cause / Corrective Actions F: Forced (Hours) (1) Shutting s: scheduled Down (2) Comments 14 980801 F 253.2 H 4 The Unit remained shutdown in Mode 5 to complete resolution of Technical Specification compi.ance issues.

15 980811 F 102.1 G 3 The Unit experienced an automatic reactor trip due to a low "A" steam Generator level coincident with a steam flow greater than feed flow mismatch. Approximately 2%

hours prior to the trip, a steam flow channel had failed and needed to have its associated bistables tripped in accordance with Technical Specifications. With this bistable tripped, a 25% steam generator level would result in a reactor trip.

(Normal low level trip is 15%.) During transfer from the "A" bypass feedwater regulating valve to the 'A' main feedwater regulating valve, the steam generator level felt to 25% coincident with the steam-feed flow mismatch due to the tripped bistable for the failed channel, and resulted in the reactor trip.

9 (1) Reason (2) Method A Equipment Feture(Eglein) 1 Manuel 8 MeWenance or Test 2 ManuelTrip/Screm c Refusung 3 - Andomstic Trip / scrum D RegulatoryRestricean 4- centinuelion E operator Training / Ucenes Eneminellen 5 Other(Eginin)

F - Administratlwe G operousnelError(Eglein)

H Other(Eglein)

SUMMARY

The Unit began the nport period shutdown in Mode S. Following resolution of all Technical Specification compliance issues, the Unit began startup and entered Mode 4 at 2133 hours0.0247 days <br />0.593 hours <br />0.00353 weeks <br />8.116065e-4 months <br /> on 08/06/98. Mode 3 was entered at 0629 hours0.00728 days <br />0.175 hours <br />0.00104 weeks <br />2.393345e-4 months <br /> on 08/07/98. On 08/11/98, Mode 2 was entered at 0603 hours0.00698 days <br />0.168 hours <br />9.970238e-4 weeks <br />2.294415e-4 months <br />, the reactor was taken entical at 0715 hours0.00828 days <br />0.199 hours <br />0.00118 weeks <br />2.720575e-4 months <br />, Mode 1 was entered at 0921 hours0.0107 days <br />0.256 hours <br />0.00152 weeks <br />3.504405e-4 months <br />, and the Unit was synchronized to the electrical grid at 1313 hours0.0152 days <br />0.365 hours <br />0.00217 weeks <br />4.995965e-4 months <br />.

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.. UNIT SHUTDOWNS DOCKET NO. 50-334 UNIT NAME BVPS Unit #1 DATE September 2,1998 COMPLETED BY David T. Jones TELEPHONE (412) 393-4962 REPORTING PERIOD: Auaust 1998 a

SUMMARY

(continued):

With the Unit at approximately 24% output, an automatic reactor trip occurred at 1512 hours0.0175 days <br />0.42 hours <br />0.0025 weeks <br />5.75316e-4 months <br /> on 08/11/98. The reactor trip occurred due to a low "A" steam generator level coincident with a steam flow greater than feed flow mismatch. Earlier at 1240 hours0.0144 days <br />0.344 hours <br />0.00205 weeks <br />4.7182e-4 months <br />, a steam flow channel had failed and needed to have its associated bistables tripped in accordance with Technical Specifications. With this bistable tripped, a 25% steam generator level would result in a reactor trip. (Normal low level trip is 15%.) During transfer from the "A" bypass feedwater regulating valve to the "A" main foodwater regulating valve, the steam generator level fell to 25% coincident with a steam-feed mismatch due to the tripped bistable for the failed channel, and resulted in the reactor trip. Tiw Unit was subsequently stabilized in Mode 3.

( Following compietion of corrective actions and analysis of the reactor trip, Mode 2 was entered at l 2040 hours0.0236 days <br />0.567 hours <br />0.00337 weeks <br />7.7622e-4 months <br /> on 08/14/98. However, due to a procedural conflict, all control rods were fully inserted at 2153 hours0.0249 days <br />0.598 hours <br />0.00356 weeks <br />8.192165e-4 months <br /> and Mode 2 was exited. Followng resoluton of the pvocedural conflict, Mode 2 was re-entered at 0537 hours0.00622 days <br />0.149 hours <br />8.878968e-4 weeks <br />2.043285e-4 months <br /> on 08/15/98. Also note that followmg each entry into Mooo 2 as r$am==M above, the Automatic Rod Control Position Deviation Monitor, although still functonal, was not l considered operable per Technical Specifications. The limiting condition for operation as speafied in i the Technical Specifications was met because the deviations between the indicated rod positens were verified to be within their 12 step limits by obtaining analog / digital rod posations at least once every 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

As startup continued on 08/15/98, the reactor was taken enbcal at 0654 hours0.00757 days <br />0.182 hours <br />0.00108 weeks <br />2.48847e-4 months <br />, Mode 1 was entered at 1019 hours0.0118 days <br />0.283 hours <br />0.00168 weeks <br />3.877295e-4 months <br />, and the Unit was synchronized to the electrical grid at 2115 hours0.0245 days <br />0.588 hours <br />0.0035 weeks <br />8.047575e-4 months <br />. An output of approximately 28% was achieved at 0557 hours0.00645 days <br />0.155 hours <br />9.209656e-4 weeks <br />2.119385e-4 months <br /> on 08/16/98, however, power escalation could not l continue until steam generator chemistry was within specifications. Following satisfactory steam generator chemistry results, esca;ation to approximately 50% output was begun at 1210 hours0.014 days <br />0.336 hours <br />0.002 weeks <br />4.60405e-4 months <br /> on 08/16/98. An output of approximately 48% was achieved at 1416 hours0.0164 days <br />0.393 hours <br />0.00234 weeks <br />5.38788e-4 months <br /> on 08/16/98, and output was held at that power level while a quadrant power tilt ratio calculation was performed. Escalation to full power was resumed at 2124 hours0.0246 days <br />0.59 hours <br />0.00351 weeks <br />8.08182e-4 months <br /> on 08/16/98. An output of approximately 95% output was achieved at 1715 hours0.0198 days <br />0.476 hours <br />0.00284 weeks <br />6.525575e-4 months <br /> on 08/17/98 to allow for a secondary heat balance to be performed. A nominal output of approximately 100% was achieved at 0100 hours0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br /> on 08/18/98. The Unit continued to operate at a nominal value of 100% output for the remainder of the report period.

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6 OPERATING DATA REPORT DOCKET NO.: 50-334 UNIT NAME: BVPS UNIT #1 REPORT DATE: 09/02/98 COMPLETED BY: DAVID T. JONES TELEPHONE: (412) 393-4962 1a. REPORTING PERIOD: AUGUST 1998

  • Notes *
1. . DESIGN ELECTRICAL RATING (Net MWe): 835 *
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2. MAX. DEPENDABLE CAPACITY (Net MWe) : 810 *
  • THIS MONTH YEAR TO DATE CUMULATIVE 3a. HOURS IN REPORTING PERIOD: 744.0 5831.0 195791.0
3. NO. OF HRS. REACTOR WAS CRITICAL: 409.1 688.8 126351.0
4. SERVICE HOURS GENERATOR ON LINE: 388.7 629.2 124102.7
5. UNIT RESERVE SHUTDOWN HOURS: 0.0 0.0 0.0
6. -NET ELECTRICAL ENERGY GEN. (MWH): 284155.0 410339.0 91268922.0
7. GROSS ELECT. ENERGY GEN. (MWH): 311795.0 459489.0 97608685.0

- 8. GROSS THERMAL ENERGY GEN. (MWH) : 973181.0 1441406.0 301711210.5

9. UNIT AVAILABILITY FACTOR (%): 52.2 10.8 64.9
10. UNIT CAPACITY FACTOR (MDC) (%): 47.2 8.7 59.6
11. UNIT FORCED OUTAGE RATE (%): 47.8 89.0 18.7 i

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, . j UNIT SHUTDOWNS I DOCKET NO. 50 412 UNIT NAME BVPS Unit #2 DATE September 2,1998 COMPLETED BY David T. Jones TELEPHONE (412) 393 4982 REPORTING PERIOD: Auaust 1998 l No. Date Type Duration Reason Method of Cause / Corrective Actions F: FM (Hours) (1) Shutting s: scheduled Down (2) Comments L

( 11 980801 F 744.0 H 4 The Unit remained shutdown in Mode 5 to continue with resolution of Technical Specification compliance issues i

(1) Reneen (2) Method ,

l A. Equipmerd Fellure (Eginin) . 1 Manual j s Maintenance er Test 2. Manual Trip / scram .

C Refuelin0 3 Ademstic Trip / scram l D. Regulatory Restriction 4 Continuation j E Operater Training / Unense Emmminellen 5. Other (Emplain)

F . Administruthe G OperationalError(Emplain)

H Other(Empimin)

SUMMARY

l The Unit remained shutdown in Mode 5 for the entire month of August 1998.

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OPERATING DATA REPORT r . .

DOCKET NO.: 50-412 UNIT NAME: BVPS UNIT #2

( REPORT DATE: 09/02/98 l COMPLETED BY: DAVID T. JONES l

1 TELEPHONE: (412) 393-4962 1a. REPORTING PERIOD: AUGUST 1998

  • Notes *
1. DESIGN ELECTRICAL RATING (Net MWe): 836 * *
2. MAX. DEPENDABLE CAPACITY (Net MWe) : 820 THIS MorTH YEAR TO DATE CUMULATIVE 3a. HOURS IN REPORTING PERIOD: 744.0 5831.0 94574.0
3. NO. OF HRS. REACTOR WAS CRITICAL: 0.0 0.0 75344.5
4. SERVICE HOURS GENERATOR ON LINE: 0.0 0.0 74849.4 5.- UNIT RESERVE SHUTDOWN HOURS: 0.0 0.0 0.0
6. NET ELECTRICAL ENERGY GEN. (MWH) : 0.0 0.0 57647298.0 i I
7. GROSS ELECT. ENERGY GEN. (MWH): 0.0 0.0 61001672.0
8. GROSS THERMAL ENERGY GEN. (MWH): 0.0 0.0 186886473.0
9. UNIT AVAILABILITY FACTOR (%): 0.0 0.0 79.1
10. UNIT CAPACITY FACTOR (MDC) (%) : 0.0 0.0 74.0
11. UNIT FORCED OUTAGE RATE (%): 100.0 100.0 11.9 i

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