ML20030C825

Monthly Operating Rept for May 1981

ML20030C825
Person / Time
Site:	Fort Saint Vrain
Issue date:	08/19/1981
From:	Gahm J PUBLIC SERVICE CO. OF COLORADO
To:
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ML20030C822	List: ML20030C821 ML20030C825
References
NUDOCS 8108280212
Download: ML20030C825 (9)

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MDNTHLT OPERATIONS REPORT DISTRIBUTION Nurber o f Copies Depa r t men t of Energy - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - 1 (P Letter)

San Francisco Operations Of fice Attn: California Patent G ro up 1333 Broadway Oakland, California 94612 Department of Energy - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - 1 (P Letter)

MJ. Glen A. Newby, Chief HTR Branch Division of Nuclear Power Development ite ' Station B-107 ashingten. D.C.

20h45 Departmeat o f E ne r g y - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - 1 (P Letter)

Atta: P roj ec t "an age r 110 West A Street. Suite 460 San Diego, Cali f o rnia 72131 De pa r t me n t o f E ne r gy - - - - - - - - - - - - - - - - - - - - -

---

1 (P Letter)

Tecnnical Information Center P. O.

Box 62 Oak Ridge, Tenne ssee 37830 Di rec to r o f Nuclea r Reac to r Re gula tion - - - - - - - - - - - - - - - - - - - - - - 1 (Original P Letter)

Attn: William P. Gamn111. Chief Operating Reactors Safequard Branch Division of Operating Reactors S. Nuclear Regulatory Commission Washington, D.C.

20535 ThildCelphia Elec t ric CoLpany 1

Attn:

M. J. Cooney 2301 Market Street Philadelphia, Pennsylvania 18101 F re n c h E mba s s y - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - 1 Attn:

Mrs. Dube rney 1730 Rhode Island Avenue, NW Suite 1217 Washington, D.C.

20036 Colo rado Department of Henith 1

(P Letter)

Attn: Al H azel 4210 East lith Avenue Denver, Colorado 30220 Mr. Bill Lavalee ----

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1 (P Letter) hcietr Safety Analysis Center 34L2 Hillview Avenue P.

J. 3ax 1)412 Pala Alta, Calif ornia 94303 Mr. Richard Phelps --------------------------------10 (Original of FDLO plus Fri, CA, hite 2 Copies of FPLC plus Representative L Copy of P Letter)

Generst Atemic Company P.

T 30x 426 Platteville, Colorado 4'65L NRC Resident Site Inspector ------------------ ------

---1 (P Letter) 8108280212 810819 PDR ADOCK 05000267 R

PDR

i PUBLIC SERVICE COMPANY OF COLORADO FORT ST. VRIAN NUCLEAR GENERATING STATION l

f MONTHLY OPERATIONS REPORT

\\

N0. 89 iMY, 1981 i

l l

l

l This report contains the highlights of the Fort St. Vrain, Unit No. 1, activities operated under the provisions of the Nuclear Regulatory Commission Operating License DPR-34.

This report is for the month of May, 1981.

1.0 NARRATIVE

SUMMARY

OF OPERATING EXPERIENCE AND MAJOR SAFETY RELATED MAINTENANCE 1.1 Summary At the beginning of the month, the reactor was at 70%

power, with a turbine generator load of 230 MW.

On May 4, reactor power was reduced to ?S%, and the turbine generator was taken off line to establish new setpoints for the turbine runback circuitry and feedwater program.

On May 13, a turbine trip from high vibration resulted in a reactor scram.

The reactor remained shutdown for the rest of the month.

1.2 Ooerations At the beginning of the month, the reactor was operating at 70% power witn a turbine generator load of 230 MW.

Backup bearing water was secured on May 2, due to the erratic operation of PV-21105 which damaged safety valves V-21168-1 and -2.

Reactor power was reduced to 28% on May 4 to enable establishing new setpoints of the turbine ruriback circuitry and feedwater programs with the turbine off line.

The turbine was rolled at 2120 hours0.0245 days <br />0.589 hours <br />0.00351 weeks <br />8.0666e-4 months <br /> on May 4, and was synchronized to the system at 0829 hours0.00959 days <br />0.23 hours <br />0.00137 weeks <br />3.154345e-4 months <br /> on May 5.

The

~

reactor was returned to 69.5% power with a turbine generator load of 223 MW.

Power was raised to 80% on May 13 for test RT-500K.

A core temperature redistribution was observed while increasing power. General Atomic Company is analyzing data taken during this redistribution period.

At 1334 hours0.0154 days <br />0.371 hours <br />0.00221 weeks <br />5.07587e-4 months <br /> on May 13, the turoine was automatically tripped from a high vibration sign 7l.

The transient caused a "two loop trouble" scram at 1349 hours0.0156 days <br />0.375 hours <br />0.00223 weeks <br />5.132945e-4 months <br />.

Loop 1 was automatically shutcown.

Loop 2 remained in service.

At 1445 hours0.0167 days <br />0.401 hours <br />0.00239 weeks <br />5.498225e-4 months <br />, the Reactor Building was evacuated because

.i of airocrne activity.

The source was traced to the low I

pressure separator.

The airborne activity reached 4.5E-9.

as compared to a maximum permissible concentration of 3.0E-9.

No measurable activity was detected in the Reactor Building exhaust filtering system.

The reactor remained shutdown for the rest ~of the month.

Inspection of the turbine blading revealed that the staking pins of two turbine blading stabilizer blocks were missing from the shrouding of the north end of the low pressure turbine, and several other stabilizer blocks were loose.

On May 20, the decision was r.ade to remain shutdown for refueling of the reactor and il helium circulator change-out.

2.0 S NGLE 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 IRRADIATION FUEL EXAMINATIONS None 4.0 MONTHLY OPERATING OATA rep 0RT Attached 4

f

CPE?AT NC san RI? ORT DOCIET No.

50-267 DATE _ 810601 CcurLI:zo sY J. W. Gahm T" ZPHONE (303) 785-2224 egenT:sc_ snTm

cTzs 1.

cnit Name:

Fort St. Vrain

. asporting Period:

810501 through 810531 3.

Licensed normal Pever OSit):

842 6.

Nameplace nating (Gross We):

342

" sign Electrical being (Nec 2Sie):

330 3.

a 6.

!'me= Dependable Cagac.ity (Gross We):

342 7.

%rh= Dependable Capacity (Nee :si 330 3.

If Changee Occur in t;apacity Ratin.

' eas Numt.or 3 nrough 7) Since Last asport, Jive asasone:

None 9.

Power Level To Which testricted. If Any (Net SSie):

231 Nuclear Regulatarv Co % sien restriction 70% pending

10. Reasons for Restrie:1ons, If Any:

resolution of temperature fluctuations.

nis Mosch Tear :o Deca Camilatira 744 3.623 16,826 11.

sours in Reporting Period

. Number of sours wetor van Critical 301.8 2.665.5 11.800 1

13. Reaccor saserve shuca.m aours 0.0 0.0 0.0 14.

sours cewrator on-Line 285.9_

2.131.5 7.824.8

15. Uni Reserve shutdown sours 0.0 0.0 0.0

16. cross normal Energy cenerated (> sin) 170.909.3 M 02.586.8 3.810.679.6 j

17. crose Electrical Inergy ceneraced Osia) 64.706 400.445 1.272.239 is. Nec necerical Energy cenerated Oers) 59.092 369.305 1.168.606 l

19. Onic 3ervice Factor 18. 4 %.

58.8%

46.5%

18.4%

58.Si 46.5%

i

20. Unic Availabilisy Factor

1. Unic Capacity Factor (Using 2CC Nec) 24.TT 10.9%

21.0%

22. tnic Capacity Factor (Using OE1 Nec) 24.15 10.9%

21.0%

l

23. Unit Forced Oucage Race m

15 95 37.0%

26. 3hutdowns Scheduled Over Next 6 ! baths (Tyre Oate, an Juration of Each):

Maintenance / modification shutdown Seotember 1.

1981 lasting four months.

July 20, 1981 25.

If shuc cova at tad of zapor: Period, Isciseced Oece or startup:

26. Unics In rest status (Prior to Cosmarcial Operacion):

Forecasc Achieved N/A N/A

NIT nL C2:T:CALITT N/A N/A

st-:AI. E:.ZCUICCT m e CnL OPERAT:cs N/A N/A

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AVERAGE DAILY UNIT POWER LEVEL Docket No.

50-267 Unit Fort St. Vrain Date 810601_

Completed By J. W. c.,hm Telephone (101) 78s_2224 Month w

y.

1981 a

DAY AVERAGE DAILY POWER LEVEL DAY AVERAGd DAILY POWER LEVEL (MWe-Net)

(MWe-Net) 1 215.8 17 0.0 2

215.4 18 0.0 3

214.6 19 0.0 4

143.3 20 0.0 5

109.2 21 0. ',

6 211.9 22 0.0 7

217.1 23 0.0 8

919.1 24 0.0 9

217.8 25 0.0 10 217.8 26 0.0 11 217.8 27 0.0 12 218.4 28 0.0 13 124.7 29 0.0 14 0.0 30 0.0 15 0.0 31 0.0 16 0.0

• Generator on line but no net generation, i

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REFUELING INFORMATION 1.

Name of Faciliev.

Fort St. Vrain Unit No. 1 2.

Scheduled date for next refueling shutdown.

May 20. 1981 3.

Scheduled date for restart following refueling.

July 20. 1981 4.

Will refueling or ruumption of operation thereafter require a technical specification chanta or other license amendm;snt?

No If answer is yes, what, in general, will these be?

If answer is no, has the reload fuel design and core configura-tion been reviewed by your Plant Safety Review Cocmittee to deter-mine whether any unreviewed safety questions are associated with the core reload (Reference i

10CFR Section 50.59)?

{

Yes If no such review has taken place, when is it scheduled?

5.

Scheduled date(s) for submitting proposed licensing action and suoporting information.

6.

Important licensing considera-tions associated with refueling, Peripheral fuel elements changed from thin thorium buffer to thick thorium e.g.,

new or different fuel de-buffer.

sign or supplier, unreviewed design or performance analysis methods, significant changes in fuel design, new operating pro-cedures.

7.

The number of fuel assemblies a) 1482 HTGR fuel elements.

(a) in the core and (b) in the spent fuel storage cool.

b) 10 spent HTCR fuel elements S.

The present licensed spent fuel Capacity is limited in size to about one-pool stor:ge capacity and the third of cor's (approximately 500 HTGR size of any increase in licensed elements).

No change is planned, storage capacity that has been requested or is planned, in nud er of fuel asse=blies.

REFUELING INFORMATION (CONTINUED) 9.

The projected date of the 1986 under the Three Party Agreement (Con-last refueling that can be tract AT (04-3)-633) between DOE, Public discharged to the spent fuel Service Company of Colorado (PSCo), and pool assuming the present General Atomic Company.*

licensed capacitv.

l l

• The 1986 date is based on the understanding that spent fuel discharged during the term of the Three Party Agreement will be shipped to the Idaho National Engineering Laboratory for storage by DOE at the Idaho Chemical Processing Planc (ICPP). The storage capacity has evidently been sized to accomodate fuel which is expected to be d.ischarged during the eight year period covered by the Three Party Agreement.

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