ML20062G844

Monthly Operating Rept for Jul 1982

ML20062G844
Person / Time
Site:	Fort Saint Vrain
Issue date:	08/09/1982
From:	Mcbride L PUBLIC SERVICE CO. OF COLORADO
To:
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ML20062G838	List: ML20062G836 ML20062G844
References
NUDOCS 8208130199
Download: ML20062G844 (8)

Text

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PUBLIC SERVICE COMPANY OF COLORADO FORT ST. VRAIN NUCLEAR GENERATING STATION h

MONTHLY OPERATIONS REPORT NO. 103 July, 1982 i

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3 8208130199 820010 PDR ADOCK 05000267 R PDR

Th ; report contains the highlights of the Fort St. Vrain, Unit No 1, activities operated under the provisions of the Nuclear Re3 slatory Commission Operating License DPR-34. This report is for the month of July, 1982.

1.1 NARRATIVE

SUMMARY

OF OPERATING EXPERIENCE AND MAJOR SAFETY RELATED MAINTENANCE 1.1 Summary The plant operated at 70% power for almost all of the month. Exceptions to this were caused by two spurious trips of 18 circulator from programmed low speed, one of .

which resulted in a hot reheat temperature scram. Recovery was comparatively quick in both cases.

Problems that persist are the introduction of water into the turbine lube oil system and a slight leak of primary coolant into the Rcactor Building, which we have not been able to find.

Shipping of spent fuel, which began in June, continued for -

the entire month of July.

1.2 Operations At the beginning of the month of July, the reactor was operatir.g at about 70% capacity. Generator output was 215 MWa.

Much time and effort was spent during the month of July on the emergency feedwater supplies to the circulator pelton wheels and to backup bearing water. Pressure controllers were tuned, pressure control and safety relief valves were rebuilt.

A July 9 inspection of our #2 auxiliary boiler revealed that a general overhaul is overdue. The boiler will remain shut down until the work can be completed, which is estimated to be the last of August.

Reactor power continued at the 70% level until 1734 hours0.0201 days <br />0.482 hours <br />0.00287 weeks <br />6.59787e-4 months <br /> on July 13. At that time,1B circulator tripped spuriously from programmed low speed. Extensive investigation revealed no cause, so power was reduced to 30%, the circulator was put back in service, and generator output was increased back up to 215 MWe by 0700 hours0.0081 days <br />0.194 hours <br />0.00116 weeks <br />2.6635e-4 months <br /> on July 14.

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On July 15, IB bearing water supply pump tripped on overload. Since the backup bearing water was in service, the circulators continued to operate. 1C bearing water pump automatically started, and plant load remained constant.

On July 16 at 2235 hours0.0259 days <br />0.621 hours <br />0.0037 weeks <br />8.504175e-4 months <br />, 18 circulator again tripped spuriously from programmed low speed. This time, the hot reheat temperature increased enough to cause a reactor scram. Investigation revealed a faulty chip in a relay driver which was replaced.

The reactor was brought critical, and the turbire generator was subsequently synchronized at- 1421 hours0.0164 days <br />0.395 hours <br />0.00235 weeks <br />5.406905e-4 months <br /> on July 17.

Power generation was limited for the balance of the weekend primarily due to high boiler feedwater conductivity. .

Reactor power was increased to 70% on Monday, July 19.

For the balance of July, generation remained constant at about 215 MW, except when reduction was requested by the System Load Dispatcher.

On July 27, it was found that tne 1A helium purification train could not be isolated. Further investigation indicates that HV-2301 is experiencing some leakage past

_ the seat. An investigation of this matter is continuing.

On July 31, recorders were placed in service for meteorological data fed from the new 60 meter tower.

2.0 SINGLE RELEASES OF RADI0 ACTIVITY OR RADIATION EXPOSURE _IN EXCESS OF 10% OF THE ALLOWABLE ANNUAL VALUE None 3.0 INDICATION OF FAILED FUEL RESULTING FROM IRRADIATED FUEL EXAMINATIONS None 4.0 MONTHLY OPERATING DATA REPORT Attached I

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ssue :

on?AT::e cATA RE?T? DOCKET No. 50-267

ATz Aucust 9, 1982 CCMr!. :zo sT L. M. McBride TI:.ZPHONE (101) 7RS ???d CPERAT!Nc STAT"5 soTzs

1. Unit xame: Fort St. Vrain

. 1eporting Period: 820701 through 820721

3. Licensed : hor: sal Pow.r CNt): 842 1 xameptate nating ccro n w.): 342

$. :esign Electrical 24 ting Ofet We): 330 ,

6. %ximae Oependable Capacity (Gross We): 342 .

7. I'.azimus Oependable Capacity Or.c se): 330

3. If Changes occur in Capacity Racings (Items Number 3 Through 7) Since Laac Report, cive lessons:

None

9. rever L. vel o which an tereced, is any Cr e se): 231

13. zauons for nostricerons, :f Any: NRC restriction of 70T, oendina resolution of temoerature fluctuations.

This Month Tear to Date Camulative -

u. aours in a. porting period 744 5.087 27.048 1:. aunber oc sours nuecer vu Critient 737.0 2,723.5 17.301.9

13. ancear a...rv. shutdown sours 0 0 0

24. sours c n.racor on-Lin. 716.3 1.824.9 11.733.2

13. Cnic daserve Shutdovu Yours 0 0 0

16. cross Ther=al en.rsy c.n. rated (wa) 402.306.4 1.006.816.6 5.940.761.4

17. crou cl.ctrical to.rar c.n. rated (wa) 145,313 331.460 2.022.816

, 13. s t ti.ctrical zo.r:7 c.n rated (wn) 136,256 295,518 1,849,777

19. nic s.rvic. ractor 96.3 35.9 43.4

0. Cait Availa'oility Factor 96.3 35.9 43.4

n. unic Capac.ey raetor (esins anC 3.t> 55.5 17.6 20.7

2. Cnic Capacity Factor (Using OE1 Net) 55.5 17.6 20.7

23. Unic Forced Outage Rate 3.7 16.9 11.A

4. shutdowns scheduled over x.xe 6 nonths (Typ., sat., and curation or each): 821201 throuch 091714 -

! surveillance t?stira - 336.0 hours0 days <br />0 hours <br />0 weeks <br />0 months <br />

3. If Shut Ocn.n at End of Report ?eriod Estimated Oate of Startup: N/A

25. Coita In T.se Status (?rior to Com:nercial Op. ration): Tcrecast Achieved

x:nAt Can:CA:.:n N/A N/A

n:AI. ::.:C nCnT N/A N/A C:w.rzC:At cersAnCx  % VA

TSP-3 Attachment-3A AVERAGE DAILY UNIT POWER LEVEL Issa 2 Page 1 or, 1 Docket No. 50-267 Unic Fort St. Vrain Date Aucust 9, 1982 Completed 3y 1 M. McArida Telephone (303) 785-2224 Month July. 1982 DAY AVERAGE DAILY POWER LEVEL DAY AVERACE DAILY POWER LEVEL..'

(We-Net) (.We-Nat) 1 200.3 17 18.5 2 200.9 18 68.7 3 199.7 19 194 A 4 200.6 20 204.4 5 200.7 21 201.4 6 200.6 22 199.1 7 200.7 23 194.9 3 200.5 24 201.8 9 200.4 25 201.3 10 200.4 26 201.1 11 200.3 27 202.1 12 199.5 28 198.8

! 13 171.7 29 199.7 l

14 186.4 30 190.9 15 200.0 31 191.5 16 82.6

• Genarator on line but no net generation.

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2. Scheduled data 'cr naz: :sfueli=g shu: dows. Oc::bar 1.1983

3. Scheduled data for sstar= .

'ollcwi=r sfue11:2. I w e-;.e 5 ton?

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1. Will sf-= :p :: :ssump:1:n of ,,'

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=5*-* specifica"c= cha=ge or other liestse a==ad-ev.:? Yes T.5 answer is yes, wha , in tenersi. #_11 -dese be? Use of tvoe H-451 grachite.

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=i=a whacher a=7 cc nriawed safa:7 ques ier.s are associated i vi:h the e s :sicad (Isfa sece 10C71 Sec"_c= 50.591 ? ,

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5. Scheduled da:s(s) for submi::1=g proposed lies sing ac:1c= a=d ~

l surocr-ing i=.fer=a 2:=. Not scheduled at this ti=e: to be deter =ined.

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RE7UEI,I:iG I:170RMATI0ti (C0!ITIITUED) i

9. The projected date of the " 1992 under Agreements AT(04-3)-633 and last refueling that can be ' DE-SC07-79ID01370 between Public Service discharged to the spent fuel i Company of Colorado, . General Atomic pc.o1 assuming the present l Company, and DOE.*

licensed cacacitv. I

• The 1992 estimated data is based on the understanding that spent fuel discharged during the term of the Agreements will be stored by DOE.at the Idaho Chemical Processing Plant. The storage capacity has evidently been sized to accomodate eight fuel segments. It is estimat.ed that the eighth fuel segment will be discharged in 1992.

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