ML20092F425
ML20092F425 | |
Person / Time | |
---|---|
Site: | Beaver Valley |
Issue date: | 08/31/1995 |
From: | David Jones, Noonan T DUQUESNE LIGHT CO. |
To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
References | |
NUDOCS 9509180175 | |
Download: ML20092F425 (11) | |
Text
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Shippingport. PA 15077-0004 September 8,1995 Beaver Valley Power Station i Unit 1 - Docket No. 50-334, License No. DPR-66 Unit 2 - Docket No. 50-412, License No. NPF-73 Monthly Ooeratine Reoort l
U. S. Nuclear Regulatory Commission Document Control Desk Washington, D.C. 20555 Gentlemen:
In accordance with Appendix A Technical Specifications, the Monthly Operating Report is submitted for Unit 1 and Unit 2 for the month of August,1995.
Respectfully, f
. P. Noonan Division Vice President, Nuclear Operations /
Plant Manager DTJ/ sip Enclosures cc: NRC Regional Office King of Prussia, PA 2CC138 w ,
The Nuclear Professionals 9509180175 950831 PDR p/,
ADOCK 05000334 R PDR .
I
NARRATIVE
SUMMARY
OF MONTHLY OPERATING EXPERIENCE UNIT 1 AUGUST 1995 August 1 The Unit operated at a nominal value of 100% output.
through August 16 August 17 The Unit continued to operate at a nominal value of 100% output until 1051 hours0.0122 days <br />0.292 hours <br />0.00174 weeks <br />3.999055e-4 months <br /> when a reduction in output was commenced due to decreasing condenser vacuum. Output was reduced to approximately 99% while repairs were completed on a broken instrument air line to an auxiliary steam regulating valve which regulates auxiliary steam to the condenser air ejectors.
The Unit was restored to a nominal value of 100% output at 1300 hours0.015 days <br />0.361 hours <br />0.00215 weeks <br />4.9465e-4 months <br />.
August 18 The Unit continued to operate at a nominal value of 100% output until 2053 hours0.0238 days <br />0.57 hours <br />0.00339 weeks <br />7.811665e-4 months <br /> when a controlled shutdown was commenced due to reactor coolant system pressure boundary leakage on the socket weld of a vent valve on the "A" reactor coolant pump seal bypass piping.
4 August 19 The Unit was removed from the electrical grid when the output breakers were oxned at 0034 hours3.935185e-4 days <br />0.00944 hours <br />5.621693e-5 weeks <br />1.2937e-5 months <br />. Mode 3 was entered at OL32 hours and Moc'e 4 was entered at 1641 hours0.019 days <br />0.456 hours <br />0.00271 weeks <br />6.244005e-4 months <br /> while the Unit continued to cooldown to Mode 5.
August 20 The Unit entered Mode 5 at 0233 hours0.0027 days <br />0.0647 hours <br />3.852513e-4 weeks <br />8.86565e-5 months <br />.
August 21 The Unit remained in Mode 5 while repair of the weld leak at through the vent valve on the "A" reactor coolant pump seal bypass August 24 piping was completed. Additional permanent repairs of leaks on l the "A" main steam header, the "B" and "C" steam generator manways and the main unit turbine were also completed during (
this time period.
August 25 The Unit remained in Mode 5 unt11110 hours when Mode 4 was I entered. Mode 3 was entered at 2131 hours0.0247 days <br />0.592 hours <br />0.00352 weeks <br />8.108455e-4 months <br />. (
August 26 The Unit remained in Mode 3 while preparations for entering
, Mode 2 continued.
August 27 The Unit remained in Mode 3 until 1028 hours0.0119 days <br />0.286 hours <br />0.0017 weeks <br />3.91154e-4 months <br /> when Mode 2 was entered. The reactor was taken critical at 1122 hours0.013 days <br />0.312 hours <br />0.00186 weeks <br />4.26921e-4 months <br />. Mode 1 was entered at 1542 hours0.0178 days <br />0.428 hours <br />0.00255 weeks <br />5.86731e-4 months <br />. The Unit was synchronized to the i electrical grid at 1727 hours0.02 days <br />0.48 hours <br />0.00286 weeks <br />6.571235e-4 months <br /> and power escalation was !
commenced.
l
NARRATIVE
SUMMARY
OF
, MONTHLY OPERATING EXPERIENCE UNIT 1 AUGUST 1995 (Continued)
August 28 At 0134 hours0.00155 days <br />0.0372 hours <br />2.215608e-4 weeks <br />5.0987e-5 months <br />, power escalation was halted at approximately 59%
output due to the quadrant power tilt ratio (QPTR) exceeding technical specification limits. A reduction to below 50 %
output was commenced at 0238 hours0.00275 days <br />0.0661 hours <br />3.935185e-4 weeks <br />9.0559e-5 months <br />. An output of a@roximately
- 49% was achieved at 0324 hours0.00375 days <br />0.09 hours <br />5.357143e-4 weeks <br />1.23282e-4 months <br />. Fen 1= tion to full power was resumed at 0650 hours0.00752 days <br />0.181 hours <br />0.00107 weeks <br />2.47325e-4 months <br /> following a satisfactory QPTR. The Unit achieved a nominal value of 100% output at 1825 hours0.0211 days <br />0.507 hours <br />0.00302 weeks <br />6.944125e-4 months <br />.
August 29 The Unit operated at a nominal value of 100% output for the through remainder of the report period.
August 31 Y
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l AVET'4CS r#sT E INIT POWER IEVEL DOCKET NO. 50-334 BVPS Ikilt 1 9
(NIT DATE Sept. 5, 1995 OCMPLETED BY David T. Jones TELEPfONE (412) 393-7553 l
1(NIH Atnust 1995--
DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL
() tie-Net) G;% 200) 1 813 17 817 2 813 38 763 3 804 19 0 4 817 20 0 5 804 21 0 6 800 22 0 7 813 23 0 8 821 24 0 l 9 817 25 0 1
10 817 26 0 i 11 804 27 5 12 804 28 600 13 796 29 808 14 808 30 821 15 813 31 808 16 798 INSIPUCTIONS On this fam, list the average daily unit power level Itie-Net for each day in the repotting month. OcepurA to the nearest Mole megawatt.
i .
. OPERATING DATA REPORT DOCKET No.: 50 334 REPORT DATE: 09/06/95 COMPLETED BY: DAVID T. JONES TELEPHONE: (412) 393-7553 OPERATING STATUS
- 1. UNIT NAME: BEAVER VALLEY POWER STATION, UNIT 1 Notes
- 2. REPORTING PERIOD: AUGUST 1995
- 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
- 8. IF CHANGES OCCUR IN CAPACITY RATINGS SINCE 1AST 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 CUMUIATIVE
- 11. HOURS IN REPORTING PERIOD: 744.0 5831.0 169487.0
- 12. NO. OF HRS. REACTOR WAS CRITICAL: 541.2 4125.3 110682.1
- 13. REACTOR RESERVE SHUTDOWN HOURS: 0.0 0.0 4482.8
- 14. HOURS GENERATOR WAS ON LINE: 535.1 4053.8 108591.5
- 15. UNIT RESERVE SHUTDOWN HOURS: 0.0 0.0 0.0
- 16. GROSS THERMAL ENERGY GEN. (MWH): 1381737.0 10412280.0 261739346.5 !
- 17. GROSS ELECT, ENERGY GEN. (MWH): 447940.0 3415490.0 84441457.0 '
- 18. NET ELECTRICAL ENERGY GEN. (MWH): 417930.0 3202690.0 78926594.0
- 19. UNIT SERVICE FACTOR: (PERCENT) 71.9 69.5 65.9
- 20. UNIT AVAIIABILITY FACTOR:(PERCENT) 71.9 69.5 65.9
- 22. UNIT CAPACITY FACTOR (DER): PCT 67.3 65.8 58.1 -
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- 23. UNIT FORCED OUTAGE RATE: (PERCENT) 28.1 5.7 15.8 l
- 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 I
l UNIT SHUTDOWuS AND POWER REDUCT10ms (t20%) Docket No. 50-334 .
Unit Name SVPS Unit 81 l Date sect. 5. 1995 l
l Completed By David T. Jones REPORT MONTH Aunust 1995 Telephone (412) 393-7553 Method of Licensee Cause & Corrective i Duration shutting Event System Component Action to No. Date Type 1 (mours) Reason 2 Down Reactor 3 Report # Code 4 Code 5 Pre =ent Recurrence l
t
[
10 950819 F 208.9 A 1 1-95-006 CI VALVEX A controlled shutdown was made to repair reactor coolant systas pressure boundary testage on the socket weld of a vent valve on the "A" reactor coolant pump seat bypass piping.
1 2 3 4 F-Forced Reason: Method: Exhibit F-Instructions for S-Scheduled A-Equipment Falture (Emplain) 1-Manual Preparation of Data Entry Sh w s B-Maintenance or Test 2-Manual Scree for Licensee Event Report (LER) Tile C-Refueling 3-Automatic Scree (NUREG0161).
D-Regulatory Restriction 4-Cont'd. from Previous Month E-Operator Training & License Exas 5-Reduction 5 F-Adelnistrative 9-Other Exhibit H-Same Source.
G-Operational Error (Explain)
H-Other (Explain)
e i NARRATIVE
SUMMARY
OF
. MONTHLY OPERATING EXPERIENCE
! UNIT 2 AUGUST 1995 August 1 The Unit operated at a nominal value of 100% output.
through
) August 8 l August 9 The Unit continued to operate at a nominal value of 100% output until 2345 hours0.0271 days <br />0.651 hours <br />0.00388 weeks <br />8.922725e-4 months <br /> when a planned reduction in output was
' commenced to remove the "B" separator drain receiver drain pump from service for maintenance.
- August 10 An output of approximately 89% was achieved at 0140 hours0.00162 days <br />0.0389 hours <br />2.314815e-4 weeks <br />5.327e-5 months <br />. The i Unit remained at approximately 89% output while maintenance on the "B" separator dram receiver drain pump continued.
1 August 11 Following completion of maintenance on the "B" separator drain l receiver drain ~ pump, power escalation was commenced at 2050 hours0.0237 days <br />0.569 hours <br />0.00339 weeks <br />7.80025e-4 months <br />. The Umt achieved a nommal value of 100% output at 2230 hours0.0258 days <br />0.619 hours <br />0.00369 weeks <br />8.48515e-4 months <br />.
t i August 12 With unusually warm atmospheric conditions present, incremental load reductions to a minimum output of approximately 95% were commenced at 1330 hours0.0154 days <br />0.369 hours <br />0.0022 weeks <br />5.06065e-4 months <br /> to stabilize condenser hotwell conditions. Once conditions in the condenser hotwell began to improve, output was incrementally increased and a nominal value of 100% output was achieved at 2115 hours0.0245 days <br />0.588 hours <br />0.0035 weeks <br />8.047575e-4 months <br />.
j August 13 The Unit continued to operate at a nominal value of 100% output until 1033 hours0.012 days <br />0.287 hours <br />0.00171 weeks <br />3.930565e-4 months <br /> when a reactor trip due to a generator /turbme trip occurred. The plant was subsequently stabilized in Mode l
- 3. The generator trip was determined to be caused by a loss of main umt generator exciter field due to a grounded field 1
current resistor.
- August 14 Following removal of the resistor ground, reactor startup was commenced and Mode 2 was entered at 1334 hours0.0154 days <br />0.371 hours <br />0.00221 weeks <br />5.07587e-4 months <br />. The reactor was taken critical at 1453 hours0.0168 days <br />0.404 hours <br />0.0024 weeks <br />5.528665e-4 months <br />. Mode 1 was entered at 1652 hours0.0191 days <br />0.459 hours <br />0.00273 weeks <br />6.28586e-4 months <br />.
August 15 The Unit was synchronized to the electrical grid at 0114 hours0.00132 days <br />0.0317 hours <br />1.884921e-4 weeks <br />4.3377e-5 months <br /> and power escalation was commenced.
August 16 The Unit achieved a nominal value of 100% output at 0300 hours0.00347 days <br />0.0833 hours <br />4.960317e-4 weeks <br />1.1415e-4 months <br />. With unusually warm atmospheric conditions present, incremental load reductions to a minimum output of
, approximately 95% were commenced at 1340 hours0.0155 days <br />0.372 hours <br />0.00222 weeks <br />5.0987e-4 months <br /> to stabilize condenser hotwell conditions.
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NARRATIVE
SUMMARY
OF I . MONTHLY OPERATING EXPERIENCE l UNIT 2 AUGUST 1995 (Continued) i 2
August 17 Once conditions in the condenser hotwell began to improve, i
output was incrementally increased and a nominal value of 100%
output was achieved at 0038 hours4.398148e-4 days <br />0.0106 hours <br />6.283069e-5 weeks <br />1.4459e-5 months <br />.
j l August 18 The Unit operated at a nominal value of 100% output.
through August 28 August 29 The Unit continued to operate at a nominal value of 100% output until 1653 hours0.0191 days <br />0.459 hours <br />0.00273 weeks <br />6.289665e-4 months <br /> when a reduction in output to approximately 92% was commenced to remove the "B" first point heater from service in order to repair the "B" first point heater normal level control valve. Following completion of removal of the "B" first poinc heater from service, power escalation was commenced at 2023 hours0.0234 days <br />0.562 hours <br />0.00334 weeks <br />7.697515e-4 months <br /> while repair work on "B" first point l heater normal level control valve continued. The Unit achieved
' a nominal value of 100% output at 2215 hours0.0256 days <br />0.615 hours <br />0.00366 weeks <br />8.428075e-4 months <br />, however, a loss of approximately 30 MWe occurred due to the first point heater being unavailable.
l August 30 The Unit continued to operate at a nominal value of 100%
output, however, a loss of approximately 30 MWe continued to occur due to the first point heater being unavailable.
]
j August 31 The Unit continued to operate at a nominal value of 100%
+ output, however, a loss of approximately 30 MWe continued to
! occur due to the first point heater being unavailable.
i Following completion of repairs on the "B" first point heater normal level control valve, the first point heater was returned i Maximum electrical output was
- to service at 1135 hours0.0131 days <br />0.315 hours <br />0.00188 weeks <br />4.318675e-4 months <br />.
a subsequently restored, however, a slight load reduction to approximately 97% occurred while returning the heater to service. At 1508 hours0.0175 days <br />0.419 hours <br />0.00249 weeks <br />5.73794e-4 months <br />, output was reduced to approximately j 95% to support post maintenance testing of the "C" atmospheric 2
steam dump valve. At 2045 hours0.0237 days <br />0.568 hours <br />0.00338 weeks <br />7.781225e-4 months <br />, the "C" atmospheric steam i dump valve was returned to service and escalation to full power
- operation commenced. As of the end of this report period, the Unit was at approximately 98% output.
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. AVERAGE DAILY WIT POWER LEVEL DOGET NO. 50-412 INIT BVPS thit 2 DATE Sept. 5, 1995 CQfLEIED BY David T. Jarias TELERDIE (412) 393-7553 PONIH Auaust 1995 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL i
('"i %t) G"% lbt) 1 815 17 814 2 814 18 815 3 811 19 814 4 813 20 815 5 820 21 816 __
6 .
819 22 826 7 818 23 816 8 824 24 821 828 I 9 825 25 l
10 736 26 822 11 741 27 820 1 I
803 28 816 l 12 13 338 29 802 14 0 30 793 15 425 31 788 16 802 INSIRUC1' INS
. On this form, list the average daily unit power level ) tie-Net for each day in the 1.wLirq month, Otzguta to the nearest @ le megawatt. ,
1 l
S OPERATING DATA REPORT DOCKET NO.: 50-412 REPORT DATE: 09/06/95 COMPLETED BY: DAVID T. JONES TELEPHONE: (412) 393-7553 OPERATING STATUS
- 1. UNIT NAME: BEAVER VALLEY POWER STATION, UNIT 2 Notes
- 2. REPORTING PERIOD: AUGUST 1995
- 3. LICENSED THERMAL POWER (MWt): 2652
- 4. NAMEPIATE 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 CHANCES OCCUR IN CAPACITY RATINGS SINCE LAST REPORT, GIVE REASONS:
- 9. POWER LEVEL TO WHICH RESTRICTED, IF ANY (Net MWe): None j
- 10. REASONS FOR RESTRICTIONS, IF ANY: N/A THIS MONTH YEAR TO DATE CUMUIATIVE
- 11. HOURS IN REPORTING PERIOD: 744.0 5831.0 68270.0
- 12. NO. OF HRS. REACTOR WAS CRITICAL: 715.7 4728.3 58552.8
- 13. REACTOR RESERVE SHUTDOWN HOURS: 0.0 0.0 0.0
- 14. HOURS GENERATOR WAS ON LINE: 705.3 4688.0 58165.6
- 15. UNIT RESERVE SHUTDOWN HOURS: 0.0 0.0 0.0
- 16. GROSS THERMAL ENERGY GEN. (MWH): .1825932.0 11780829.0 144302151.0
- 17. GROSS ELECT. ENERGY GEN. (MWH): 593739.0 3875560.0 46927353.0
- 18. NET ELECTRICAL ENERGY GEN. (MVH): 561482.0 3664856.0 44339861.0
- 19. UNIT SERVICE FACTOR: (PERCENT) 94.8 80.4 85.2
- 20. UNIT AVAILABILITY FACTOR:(PERCENT) 94.8 80.4 85.2
- 22. UNIT CAPACITY FACTOR (DER): PCT 90.3 75.2 77.7 -
- 23. UNIT FORCED OUTAGE RATE: (PERCENT) 5.2 0.8 2.8
- 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
l <.
UNIT SHUTDOWNS AND POWER REDUCTIONS (t204) Docket No. 50-412 +.
Unit Name gWPS Unit 82 Date Seot. 5. 1995 Completed By David T. Jones -
REPORT NOIITH Aunust 1995 Telephone (412) 393-7553 Method of Licensee Cause & Corrective Duration shutting Event Systee Component Action to No. Date Typel (Nours) Reason 2 Down Reactor 3 Report # Code 4 Code 5- Prevent Recurrence i
8 950813 F 38.7 A 3 2-95-006 NA GENERA A reactor trip occurred due to a generator / turbine trip caused by a toss of the main unit generator exciter field due to a grounded fletd current resistor. The resistor ground was removed and the Unit was returned to fuit power operation.
1 2 3 4 F-Forced Reason: Method: Exhibit F-Instructions for 5-Scheduled A-Equipment Failure (Explain) 1-Manual Preparation of Data Entry Sheets 5-Maintenance or Test 2-Manual scree for Licensee Event Report (LER) File C-Refue1Ing 3-Autoestic Scram (NUREG0161).
D-Regulatory Restr'ction 4-Cont'd. from Previous Month E-Operator Traintry & License Emma 5-Reduction 5 F-idelnistrative 9-Other Exhibit H-Same Source.
G-Operational Error (Explain)
H-Other (Explain)
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