ML20042A867

Forwards Monthly Operating Rept for Feb 1982

ML20042A867
Person / Time
Site:	Fort Saint Vrain
Issue date:	03/18/1982
From:	Warembourg D PUBLIC SERVICE CO. OF COLORADO
To:	Gammill W Office of Nuclear Reactor Regulation
References
P-82083, NUDOCS 8203240219
Download: ML20042A867 (2)

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Warch18,1982' 8 \\'"'/

g Fort St. Vrain Unit No. I o

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s Director of Nuclear Resctor Regulation' ATTN:

W. P. Gammill, Chief s

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M Operating Reactors Safeguard Branch Division of Operating Reactars U. S. NucNa., Regulatory Commisrion Washinctar, D.C, 20555

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Ta-ility Operating License No.' DPR-34 Docket No. 50-267

Dear Sir:

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i s s En610 sed please find our Monthly Operations Report fcr the nienth of FetYua'ry, 1982.

s Very truly yours,.

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s Don Warembourg x

s Manager, Nuclear Production s_

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5 C203240219 020318 PDR ADOCK 050C0267

- R PDR

e MONTHLY OPFPATIONS REPORT DISTRIBLit0N Number of Contes De p a rt men t o f E n e r gy - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -

1 (P Latte r)

San Francisco Operations Of fice Attn California Patent Group 1333 Broadway Oakland, California 94612 Dep a r t ne n t o f En e r gy - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -

1 (P Letter)

Mr. Glen A. Newby, Chie f HTR Branch Divist an of Nuclear Power Development Mail Station 8-10 7 Washir gton, D.C.

10543 e

De p a r t meo t o f E;t e r gy - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -

1 (P Letter)

Attn Project PLutager 116 We s t A S t ree t, S uite 460 San Diego, California 92101 Du p a r t me n t o f E ne r gy - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -

1 (P La t t e r)

Technical Information Center P. O. Box 62 Gak Ridge Tannessee 37830 Di re c to r o f Nuc le a r Re a ct o r Re gul a t ion - - - - - - - - - - - - - - - - - - - - -

1 (Original of P Letter)

Attn: William P. Ganmill, Chie f Operating Reactors Safeguard Branch Division of Operating Jeactors Nuclear Regulatory Commission Washington, D.C.

20555 Philadelphia Electric Company 1

Attn Mr. M. J. Cooney 2 301 Market Street Philadelphia, Pennsylvania 18101 F re n th E mb a s s y - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -

1 Attn: Mrs. Duberney 1730 Rhode Island Avenue, NW Suite 1217 Washington, D.C.

20036 colorado Department of Health 1 (P Letter)

Attn:

Mr. Al Hazel 4210 East lith Avenue Denver, Colorado 80220 Mr. Ge o r ge K uz my c z - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -

1 (P Le t te r)

Nuclear Regulatory Connission 7920 Norfolk Avents Be thesda, Maryland 20034

?!r. John T. Collins, Re gional Administ rator 1 (P Le t te r)

Region IV N uc le a r Re gulat o ry Commiss ion 611 Ryan Plaza Drive auite 1000 Arlington, Te xas 76011 Re c o r ds Ce n t e r - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -

1 (? Le t te r)

Institute of Nuclear Powe r Operations 1820 Water Place Atlanta, Georgia 30339 Mr. Richard Phelps, FSV, CA, Site Re p re s e n t a t i ve - - - - - - - - - - - - - - - - 10 (Original of FPLC Lette r, General Atomic Company two copies of FPLC Letter, 16864 Weld County Road 19 1/2 an d one copy o f P Le tte r)

P la tt e ville, Colorado 80651 NRC Resident Site inspector 1 (P Le t te r)

PUBLIC SERVICE COMPANY OF COLORADO FORT ST. VRAIN NUCLEAR GENERATING STATION MONTHLY OPERATIONS REPORT NO. 98 February, 1982 e

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E hi eno3240344 820318 FCH ADOCK 050002

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This report contains the highlights of the Fort St. Vrain, Unit No. 1, activities operatec under the provisions of the Nuclear Regulatory Commission Op4 rating License DPR-34.

This report is for the month of February, 198&.

1.0 NARRATIVE

SUMMARY

OF OPERATING EXPERIENCE AND MAJOR SAFETY RELATED MAINTENANCE 1.1 Summary The loop split work was about 98% complete at the beginning of the month with the remaining items to ce completed by t'e maintenance personnel.

An error in a valve lineup resulted in an inadvertent release of 250 callons of water from the liquid waste system.

Although the water in tne liquid waste receiver was, as was later analy:ed, determined to exceed the Technical Specification limits for a liquid waste release from the receiver, the off-site concentrations of the release were within limits, posing no adverse environmental effect.

The reactor was brought critical for training starts for the license operator candidates on February 15 and 16.

An examiner from the Nuclear Regulatory Commission was on site to conduct the exams.

High primary coolant moisture concentrations required the reactor to be scrammed on February 22.

Two control rods failed to scram at that time and subsequent tests revealed three others exhibitec a tendency to stick.

This behavio-has been attributed to high moisture concentrations in the primary coolant.

Further testing has revealed that all rods are now operable.

The high moisture levels required that the vessel be evacuated as a means of removing the residual moisture.

This operation was in progress at month's end.

1.2 Operations The completion of the shutdown maintenance items continue 1

with about 98% of the loop split modification work done.

There are several significant items to be completed by plant maintenance personnel before startup.

Arrangements were finali:ed with the Nuclear Regulatory l

Commission to conduct the training start portion of the e

licensed operator exam on Feoruary 15.

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The purified helium header was put in service on February 1 to facilitate cleanup of tne primary coolant through the purification system.

Loop 1 helium circulators are now a

operating, using tne new cross connect to the Loop 2 dryer.

An error in a valve lineuo following a liquid waste release resulted in about 250 gallons being inacvertently released to the cooling tower blowcown lines from 1A liquid waste receiver.

This IA receiver nad not been previously sampled for release.

The subsecuent analysis on the receiver revealed that the Tecnnical Specification limit for liquid waste discharge had been exceeded, but that permissible concentrations off site had not been exceeded.

This was reported to the Nuclear Re.gulatory Commission per our reporting requirements as a "significant event."

Loop 2 circulators were put in service on February 15 following completion of the loop split modification.

A test of this new equipment is being performed by the Results Department.

a The main cooling tower was filled on February 7, but leaking basin drain valves required draining the tower.

The cold weather caused significant freezing problems in the pumps and isolation valves, but on February 11, the circulating water system was put in service. A vacuum was also estaolisned on tne condenser after the turbine steam seal system was made operable.

We also began making-up water to the condensate storage tanks from a rented portable cemineralizer system on February 11.

This will allow filling and draining the condensate /feedwater system several times to restore the secondary coolant chemistry to the quality required for normal plant operation.

Tne reactor was brought critical on February 11 for I

practice starts for the license operator candidates in l

preparation for the actual examination. Monte Davis, a Nuclear Regulatory Commission Examiner, was on site February 15 and 16 to conduct the actual reactor start portion of the license operator exam.

He also administered a senior licensed coerator exam to Marty Block while he was l

here.

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The major overhaul of the alternate cooling method diesel generator was complete on February 20, and the re-assembly i

of the 18 diesel generator was finished on February 22.

e The semi-annual Surveillance Test of the turbine trip and 3

loss of all outsice electrical power was completec on

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February 22.

This was the last Surveillance Test that 3

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s required a plant shutdown.

It is now anticipated the next scheduled outage will be in October rather than May.

A spurious trip of the plant protective system dewpoint moisture monitors caused a scram and a Loop 2 shutdown with a

steam / water dump.

The reactor had previously been operating at 1% power.

The reactor was again critical five hours later following an investigation into the cause.

High primary coolant moisture began presenting a problem in meeting the Tecnnical Specification limit of less than a 67 degrees fahrenheit dewpoint, and we entered an LCO 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> grace period on February 21.

An, expected upset in the circulator auxiliaries during the loss of outside electrical power Surveillance Test introduced some acditional moisture and further increased the moisture indications.

The reactor was manually scrammed on February 22 per the Technical Specifications because we were unable to meet the specified maximum dewpoint of 67 degrees fahrenheit.

Two control rods failed to scram on February 22, and subsequent tests revealed there were three additional rods that exhibited a tendency to stick in the full-out position. A program was initiated to exercise both the orifices and rods once per shift.

By February 23, all of the rods were operating properly.

We are continuing with a control rod drive exercise program to demonstrate operability.

The high moisture levels in the core is the probable cause of the erratic and sticking operation of the rods.

We continued to evaluate the extent of the high primary coolant moisture problem and our ability-to remove the moisture via the purification system until February 27.

The lack of a definite trend in moisture prompted the decision to pumo down and evacuate the vessel through the purge vacuum pumps.

This procedure had been used successfully in the past to remove large quantities of moisture.

The evacuation is now in progress.

There have been several discussions with Proto-Power and Engineering about the modifications made during the loop split and several of the conclusions are as follows:

1)

Investigation should be made into closing either the -3 valves or new 600 series valves during a circulator trip to avoid venting gas from the surge tank.

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2) Several changes to the System Operating Procecures have been made to describe how to vent the surge tank, if

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required, and how to keep from overpressurizing the surge tank.

3) The buffer supply and return flow element calibration or any measurement error is much more obvious in the new system and will require increased attention.

4) The helium dryers appear to perform satisfactorily et reduced pressures.

E)

Investigations are underway to determine if a new valve from the cryer discnarge to the PCRV is required.

6) A replacement trim for PCV-2367 i' raquired before the system's performance in the transfer from System 23 to System 24 can be optimized.

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 e3 t-)

• 3P-3 Attacament-18 Issue 2 Page 1of I cenartse un unar

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50-267 urz 820305 ccMytzna 3T I.. M. McBride

rttriicre 785-2224 ornAn c Sn

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OTIS 1.

Unit same:

Fort St. Vrain 2.

Reportins Period:

820201 through 820228 3.

Licensed Thornal Power (WC):

842 4.

Nameplate Rating (Grose We):

342 3.

Design Electrical Rating Clet We):

330 e.

Pa=1== Dependable Capacity (ctose We):

342-7.

Marim= cependable capacity (Net we):

330 S.

If changee occur in capacity Racings (Ices Number 3 through 7) Since Last Report, cive Reasons:

Nona 9.

Power Level To *.litch Restricted, If Ar.f (Not we):

231

10. Reasons far Restrictions, If any:

NRC restriction of 70% pending resolution of temperature fluctuations.

This Month Year to Data cumalative

11. nours in amporting Period 672.0 1.416.0 23.377

u. sumoer of sours saector ves critical 101.9 101.9 14,680.3

u. Reactor s eerve shutdown sours 0.0 0.0 0.0 14.

nours cenerator on-Lin.

0.0 0.0 9,908.3

13. Unit Reserve shutdown aours 0.0 0.0 0.0

16. cross Thersal Energy cenerated ossu) 0.0 0.0 4,933,944.8

17. cross tieetrical Emersr Generseed (ws) 0.0 0.0 1,691,356

13. set tiectrical znersy cenerated (w a)

-2.627

-4.577 1.549,682

19. Unit Service Factor 0.0 0.0 42.4

23. Unit Availability Factor 0.0 0.0 42.4

21. Unit capacity Factor (Using :@C Net) 0.0 0.0 20.1

22. Unit capacity Factor (Using OER set) 0.0 0.0 20.1

23. cnit Forced outage Kate O_O O_O 14.0

26. shutdowns Scheduled over next 6 Mantas (Type. Date, and Duration of raca):

March 1, 1982 through vmh 91.

tog? (50a_O hen) for.mintenance outage l

23. If shut Down at End of Report Period. Estimated Oate of Startups hrch 22. 1982

06. Units In Test Status (7tior to Coennercial operation):

Forecast

.uhieved

xI:n; cz:n CAL::Y N/A N/A Ixt:ut EL c z:cnr N/A N/A ccxmcut cPtsAnes N/A N/A

ISP-3 Actachment-3A I

AVERAGE DAILY UNIT POWER LEVEL

!ss a 2 Page 1 of 1 Dockee No.

50-267 Unit Fort St. Vrain Date 820305 Complaced By L. M. McBride Telephone 785-2224 Month February, 1982 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL..

(MWe-Nec)

(MWe-Net) 1 0.0 17 0.0 2

0.0 18 0.0 3

0.0 19 0.0 4

0.0 20 0.0 5

0.0 21 0.0 6

0.0 22 0.0 7

0.0 23 0.0 8

0.0 24 0.0 9

0.0 25 0.0 10 0.0 26 0.0 11 0.0 27 0.0 12 0.0 2S 0.0 13 0.0 29 N/A 14 0.0 30 N/A 15 0.0 31 N/A 16 0.0

• Generator on line but no net generacion.

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Name of 7ac111:-r.

?ce-5:. Vrsis Uni: No. I 2.

Scheduisd data for nex: refueling shutdown.

Oc:cher 1, 1983 3.

Scheduled data for :sstar.

followise -sfueli=r.

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Will :sfueling or wumption of i

operacion =sraad:ar :squ1== a

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= Wt specification change or other licsuse amendment?

Yes L' answer is 7es, wt at, is tenersi, vill hese be?

Use of type H-451 graohite.

L' answer is om, has the reload fuel design and cara c=nfign=a-

1on been :sriswed by your Plan:

Saf ety Raviar Conni::ae to de:ar-s1=s whscher a=7 un=sviewed safec7 questicas are associa ad w1:h the cars raload (latersace 10C72 See:1on 50.59)?

~f no such :sview ham taken elace. when i.s 1: schedu. lad?

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Scheduled data (s) for submi::1sg proposed lies =s1=g ac:1on a=d su-nrer-1=g i=fo n a don.

Not scheduled at this time: to be determined.

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• =por:an: 11:sns1=g c:.nsiders-

1cus associa:ad ri h sfueling, e.g., new or d"ersne fuel de-sign or suppliar, Naviewed design oe ;erfc:rance analysis me: hods, sig=1ficant changss is fual design, saw operat1=g pr:-

endurss.

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ne number of fuel assemblias 1482 COR fuel ela=en:s (a) is :he cara and (b) 1=

2.GR fuel ele =en:s 50 spen

.,.,e sven:,n e., s:crase ecol.

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~he prssent.1.1 caused span: 'ual pcol storage capac1:7 and :he Capact:7 is li=1:ad is si:e to abou: one-i sice of a y 2crasse i= licensed

hird of ecre (approx 1=a:a17 500 COR I

storsgo capac1:7 :ha: has been elemen:s). No ch2=gs is pla==ed.

raquestad or is planned, in

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REFUELING INFORMATION (CONTINUED) 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

. pool assuming the present l Company,andDOE.*

licensed capacity.

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• The 1992 estimated date 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 estimated that the eighth fuel segment will be discharged in 1992.

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