ML20039G065
| ML20039G065 | |
| Person / Time | |
|---|---|
| Site: | Beaver Valley |
| Issue date: | 03/11/1981 |
| From: | Dunn C DUQUESNE LIGHT CO. |
| To: | NRC OFFICE OF MANAGEMENT AND PROGRAM ANALYSIS (MPA) |
| Shared Package | |
| ML20039G066 | List: |
| References | |
| NUDOCS 8201150245 | |
| Download: ML20039G065 (4) | |
Text
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ThLS Duquesna Lifit 43S S.am Avenue 77'"'
March 11, 1981 t'7!lJ i
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- So Beaver Valley Power Station, Unit No. 1 Docket No. 50-334, License No. DPR-66
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6-hlS Monthly Operating Report
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United States Nucicar Regulatory Commission Director, Of fice of Management Information & Program Control Washington, D. C.
20555 Gentlemen:
In accordance with Appendix A, Technical Specifications, the Monthly Operating Report is suimitted for the month of February, 1981.
Very truly yours,
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C. N. Dunn Vice President, Operations Enclosures e
cc:
NRC Regional Office, King of Prussia, PA P. Higgins, Prime Movers Committee
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i DUQUESNE LIGHT COMPANT Beaver Valley Power Station NARRATIVE
SUMMARY
OF MONTHLT OPERATING ~ EXPERIENCE - JANUARY 1981 Jcnuary 1 Station in Operational Mode 4 at 950 PSIC'and 337F.
Heat-up of the reactor coolant system was in progress.
Entered Operational Mode 3 at 0152 hours0.00176 days <br />0.0422 hours <br />2.513228e-4 weeks <br />5.7836e-5 months <br />.
Jcnuary 2 Station in Operational Mode 3 at 200 PSIG and 541F.
Heat-up through of the reactor coolant system was in progress and the prerequisites Jcnuary 5 for reactor criticality were being completed.
At 2000 hours0.0231 days <br />0.556 hours <br />0.00331 weeks <br />7.61e-4 months <br />, a small packing leak developed on the 13 loop bypass flow isolation valve (1RC-45].
This leak could not be stopped. At 0303 hours0.00351 days <br />0.0842 hours <br />5.009921e-4 weeks <br />1.152915e-4 months <br /> on January 3, a station cooldown to Operational Mode 5 was begun.-
The Station entered Operational Mode 4 at 0940 hours0.0109 days <br />0.261 hours <br />0.00155 weeks <br />3.5767e-4 months <br /> and Operational Mode 5 at 1535 hours0.0178 days <br />0.426 hours <br />0.00254 weeks <br />5.840675e-4 months <br />.
Containment vacuum was broken at 1630 hours0.0189 days <br />0.453 hours <br />0.0027 weeks <br />6.20215e-4 months <br /> and RCS depressurization was begun at 2010 hours0.0233 days <br />0.558 hours <br />0.00332 weeks <br />7.64805e-4 months <br />.
The packing leak on (1RC-45] was repaired and the packing on other similar valves were checked and adjusted as necessary by 1220 hours0.0141 days <br />0.339 hours <br />0.00202 weeks <br />4.6421e-4 months <br /> on January 4.
Filling the pressurizer was begun immediately and a steam bubble was established by 0300 hours0.00347 days <br />0.0833 hours <br />4.960317e-4 weeks <br />1.1415e-4 months <br /> on January 5.
Drawing the containment vacuum was begun _at 0550 hours0.00637 days <br />0.153 hours <br />9.093915e-4 weeks <br />2.09275e-4 months <br />.
January 6 Station in Operational Mode 5 at 317 PSIG and 153F.
Heat-up_
of the reactor coolant system was in progress. At 0255 hours0.00295 days <br />0.0708 hours <br />4.21627e-4 weeks <br />9.70275e-5 months <br />, with the RCS temperature at 180F, further heat-up was delayed to correct reactor coolant pump seal problems. Heat-up was resumed at 0650 hours0.00752 days <br />0.181 hours <br />0.00107 weeks <br />2.47325e-4 months <br /> and the Station entered Operational Mode 4 at 1213 hours0.014 days <br />0.337 hours <br />0.00201 weeks <br />4.615465e-4 months <br />.
At 1555 hours0.018 days <br />0.432 hours <br />0.00257 weeks <br />5.916775e-4 months <br />, the Company Engineering Department informed the Station of a pipe-whip-restraint deficiency at the main steam line non-return valves and an RCS'cooldown to Operational Mode 5 was begun to repair the restraints.
Jcnuary 7 Stationfin Operational Mode 4 at 390 PSIG and 300F.
RCS" pressure was being maintained at less than 400 PSIG and RCS temperature was being maintained between 300F and 325F during main steam line restraint repairs.
At G745 hours, the Residual Heat Removal system was isolated and an increase of RCS pressure to 900 PSIG was commenced.
Jcauary 8 Station in Operational Mode 4 at 870 PSIG and 323F.
At 1040 hours0.012 days <br />0.289 hours <br />0.00172 weeks <br />3.9572e-4 months <br /> the 1A main feedwater stop-check isolation valve
[MOV-FW-156A] was declared. inoperable because the gear drive housing was discovered cracked.
At 1850 hours0.0214 days <br />0.514 hours <br />0.00306 weeks <br />7.03925e-4 months <br />, both Low Head Safety Injection (LESI) Pumps were declared inoperable when they did not meet the Operational Surveillance Test (OST) acceptance criteria.
The recirculation flow test line was discovered to have frozen.
f-
.s NARRATIVE
SUMMARY
OF MONTHLY OPERATING EXPERIENCE - JANUARY 1981 (continued)
January 9 Station in Operational Mode 4 at 920 PSIG and 321F.
RCS was through being =aintained in the hot shutdown condition pending repairs January 10 to [MOV-FW-156A] and adding insulation to the LHSI Pump test line.
At 1445 hours0.0167 days <br />0.401 hours <br />0.00239 weeks <br />5.498225e-4 months <br /> the LHSI pumps were declared operable after satisfactory completion of the surveillance tests, At 2l00 hours, [MOV-FW-156A] was operable and RCS heat-up was coc=enced at 2127 hours0.0246 days <br />0.591 hours <br />0.00352 weeks <br />8.093235e-4 months <br />.
The Station entered Operational Mode 3 at 2320 hours0.0269 days <br />0.644 hours <br />0.00384 weeks <br />8.8276e-4 months <br /> with the RCS heat-up in progress.
Jenuary 11 Station in Operational Mode 3 at 2235 PSIG and 545F.
The reactor through start-up was co==enced at 1441 hours0.0167 days <br />0.4 hours <br />0.00238 weeks <br />5.483005e-4 months <br />.
The reactor was critical January 12 at 1535 hours0.0178 days <br />0.426 hours <br />0.00254 weeks <br />5.840675e-4 months <br /> and the main unit was synchronized at 0147 hours0.0017 days <br />0.0408 hours <br />2.430556e-4 weeks <br />5.59335e-5 months <br /> on January 12.
January 13 Station in Operational Mode 1 at nominal 88% reactor power.
Jcnuary 14 Station in Operational Mode 1 at nominal 99% reactor power.
through January 20 January 21 Station in Operational Mode 1 at nominal 98% reactor power.
Power level was reduced to 95% because of high backpressure in the main condenser.
Electric power output varied slightly with =ain condenser performance.
Jcnuary 22 Station in Operational Mode 1 at nominal 97% reactor power.
An E=ergency Preparedness Plan alert was declared at 0430 hours0.00498 days <br />0.119 hours <br />7.109788e-4 weeks <br />1.63615e-4 months <br /> due to a high-high radiation alarm on the leak collection areas exhaust gas radiation monitor [RM-VS-105], which automatically diverts the discharge through the =ain filter banks.
The maxi =um off-site gaseous releases did not exceed 3% MPC.
The alert was terminated at 0848 hours0.00981 days <br />0.236 hours <br />0.0014 weeks <br />3.22664e-4 months <br />.
The apparent cause was gas accu =ulation in the pipe trenches being released into the main building space when the trench cover blocks were removed January 23 Station in Operational Mode 1 at nominal 98% reactor power.
Jccuary 24 Station in Operational Mode 1 at nominal 99% reactor power.
The I
through power level was reduced to 64% at 2050 hours0.0237 days <br />0.569 hours <br />0.00339 weeks <br />7.80025e-4 months <br /> to re=ove the main January 26 condenser section A from service for a tube cleenliness inspection.
Condenser section A was returned to service at 0830 hours0.00961 days <br />0.231 hours <br />0.00137 weeks <br />3.15815e-4 months <br /> on January 25 and section B was re=oved from service for inspection when the circulating water outlet isolation valve for section B l
could not be opened.
The power level was further reduced to 46%
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- NARRATIVE
SUMMARY
OF MONTHLY OPERATING EXPERIENCE - JANUARY 1981 (continued) at 1615 hours0.0187 days <br />0.449 hours <br />0.00267 weeks <br />6.145075e-4 months <br /> on January 26 in order to shut down the 1C Cooling Tower Pump to reduce the pressure on the valve.
Power level was increased to 74% at 1840 hours0.0213 days <br />0.511 hours <br />0.00304 weeks <br />7.0012e-4 months <br /> with two (lA and 1D) cooling tower pumps in service.
The 1C Cooling Tower Pump was placed into service at 2023 hours0.0234 days <br />0.562 hours <br />0.00334 weeks <br />7.697515e-4 months <br /> and the power level was increased to 93% by 2220 hours0.0257 days <br />0.617 hours <br />0.00367 weeks <br />8.4471e-4 months <br />.
Power level was reduced to 90% at 2232 hours0.0258 days <br />0.62 hours <br />0.00369 weeks <br />8.49276e-4 months <br /> due to high condensate te=peratures.
January 27 Station in Operational Mode 1 at nominal 90% reactor power.
through Maintaining the condenser vacuum / turbine backpressure was the January 29 major operational difficulty and some adjustment of power level was required to retain proper station operating conditions.
January 30 Station in Operational Mode 1 at nominal 94% reactor power.
At through 7043 hours0.0815 days <br />1.956 hours <br />0.0116 weeks <br />0.00268 months <br />, cocmenced reducing power level to 59% to perform January 31 main condenser inspection and =aintenance.
MAJOR SAFETY-RELATED MAINTENANCE - JANUARY 1981 1.
The gear housing for the =otor-operated 1A main feedvater isolation valve [MOV-FW-156A] was replaced af ter the housing was found to be cracked.
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