ML19246A674

Monthly Operating Rept for May 1979

ML19246A674
Person / Time
Site:	Fort Saint Vrain
Issue date:	06/01/1979
From:	Gahm J PUBLIC SERVICE CO. OF COLORADO
To:
Shared Package
ML19246A659	List: ML19246A656 ML19246A674
References
MOR-790531-1, NUDOCS 7907060229
Download: ML19246A674 (8)

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PUBLIC SERVICE COMPANY OF COLOPRO FORT ST. VRAIN NUCLEAR GE'IERATING STATION

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MONTHLY OPERATIONS REPORT No. 65 MAi' , 19 79

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298 207 s

2 7907060229

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6 This report .tontains the highlights of the Fort S t. Vrain, Unit No. 1 activi-ties, operated under the provisions of the Nuclear Regulatory Cc==ission Operating License, DPR-34. This report is for the month of May,1979.

1.0 NARRATIVE SDMARY OF OPERATING EXPERIENCE AND MAJOR SAFETY RELATED MAINTENANCE The first refueling of the reactor was co=pleted with an inspection of region 13 core support block. This inspection was perforced at the re-quest of the Nuclear Regulatory Co==ission. The core support block was free of any questionable markings.

RT-523A, Region Constraint Device Handling Test, was co=pleted. Region constraint devices were installed on the core and removed without diffi-culty. Several diagnostic devices were installed to assist in trouble-shooting the core fluctuation problem. A relative motion detector (scratched and pad) was installed in the upper plenus to detect relative motion between region 18 and region 35. Also modified control rod drives with special instrumentation were installed in regions 5 and 35.

Core fluctuation data syste= using the =ultiplexing technique is being installed and checked out.

All three boiler feed pu=ps were disassenbled and were in various stages of repair at the end of this rep rting period.

"C" circulator change out was extended anproxi=ately two weeks when the internal piping was discovered to have a bent scea= inlet baffle plate.

Spare internals assembly was subsequently installed. "C" circulator changeout was co=pleted on May 29, 1979.

The pur=anent two loop du=p modification to the Plant Protective System

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was incorporated and the functional tests revealed that high moisture trips will occur on restoration of pcwer followir.g a loss of bus voltage.

Modification of the dew point =oisture monitor switching module vfll be required to correct the high moisture trips on restoration of power.

The time delay relays which were re=oved from Loop 1 as a te=porary fix will be reinstalled until this problem can be properly evaluated.

The reactor was taken critical at 0340 hours0.00394 days <br />0.0944 hours <br />5.621693e-4 weeks <br />1.2937e-4 months <br /> on May 26, 1979, with a re-activity discrepancy of .002 ap. Following criticality, the reactor was shutdown, and shutdown margin was de=onstrated with the instrumented control rod drives installed and the maximum worth control rod drive with-drawn. The reactor was operated at approximately C.1% power for 18 hours2.083333e-4 days <br />0.005 hours <br />2.97619e-5 weeks <br />6.849e-6 months <br />.

The Control Data co=puter is being upgraded to a new Syste= 17 Control Data computer. The new co=puter utilizes CRT displays and sof t disc packs.

Main turbine generator ovarhaul continues. Dye penetrant checks of the 5

throttle valve seats revealed cracks in the #1, #2, and #3 valve seats.

Considerable difficulty was encountered in removing the throttle valve s ea ts . Co=cercial Machine Wor. from Illinois was contracted to remova 5

them by pulling with hydraulic hand jacks.

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1. 0 NARRATIVE SD0!ARY OF OPERATING E*JERIENCE AND MAJOR S AFETY RELATED MAINTENANCE (centinued)

A total of 61 Technical Specification surveillance tests were completed; 25 were surveillance tcsts, 34 were preventive maintenance operations tests, and two were non-radiological tests.

2.0 SINGLE RET. EASES OF RADIOACTIVITY OR RADIATION i POSURE IN EXCESS OF

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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

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ema- s: 0A A Rn cR- occ: so. 50-267

A:: 790501 _ _ _

~?:. :: 3: J . L' . Gahn

L:7z:s: /30 9 785-2253 cms-~n: s:Am

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1.  ::.i: sa e: _ Fo rt S t. Vrain, Unit No. 1

2. Repor:iss Period: 790401 to 790430

3. Li:e: sed 'her=al ?over ($t); 842

s. Nansplate Rating ("r:ss We): 342 i I

3. ce sig: Ele::rical ?.s:1:g Cie: Se): 330 i I

6. Mar'=u::t cependable Capacity (cr:ss We): 342  ;

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7 Mar =un .)ependable Capaci:7 (se: We): 330 t

5.  !! .'ha ges 0::ur in Capaci y Aa:isgs (!:::s Nu=ber 3 Through 7) Since Las Report, cive Reasons:

hone -

9. ?over :.evel To Which Restricted, If Any (Net We): 231

10. Reasces f:: Re s tri:: ices, if Any: Nuclear Regulatorv COFission res triction (70%) cending resolution of certain Final Safety Analvsis Recort and Technical Specificacion bases discrecancies. This unit is in power ascension chase of startuo tes ting.

• his Month Year :o Da:e C=ala:ive

n. sours 1: Reper:is; Perice 719 2,379 - - - - - - -

1:. susee et smurs Raa::e: vas c ::::2; 0.0 789.4 14,263.1

13. Rea::or zase:re shu:dev: acurs 0. 0 0.0 0.0

n. acurs ::euerata: ::.t.1:e 0.0 665.3 8,507.9

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15. t=:: Reserve shu:eovr. sours 0.0 0.0 0.0

16.  :::ss her=a; :ergy cetera:ed ($s) 0 313,069 3,516,067 17  :::ss ne:::1:a; ergy ce: era:ed ($u) 0 109.852 1.058.122

3. se

ne::r.:a 7.=e :g r cetera:ee ($3) 0 101,177 952,628

19. ::1: se .:e Ta ::: N/A N/A N/A

20.  ::1: Ava11ab ni:7 Ta:: r N/A ';/ A N /A

21. L:.1: "aoa:::- Tac::r ( sing MDC se:) N/A N/A N/A

22.  ::it. ca;a:1:v ra:::: (Usi:g :IR set) N/A N/A ';/ A

23.  : 1: T:::ed cutage F.a:e N/A N/A N/A 2.. Shu: doves 5:ce:uled Over Nex: 6 M:::as (Me. ca:e, and Ourati Of Iact):

Refueline, 2 79, '+ Months

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23. *f 3hu: =cv: a: I:s Of ?acar: ?eriod, Is:::ated Ca:e af 5:ar:ue: b-1 /c.

26.  :::s :: Tes: 5 :a tus ??:10: :: " ==ercia; 0: erat ::) : 7: e:as: A:hieved

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• UNIT NAttE fo rl S t. YraIn, OnIl No.

narE 790501 n ern ny J. W. Galim Rt t' ORT Ik) Nill Spr11 h urHONE (303) 785-2253 fu;1thott UF SilHIllNG IM MN SYSTril et ttfi't)N EN r IN ) . liA I E !Y l'E l# URAL lON REASON HEACIOR I.FR # Oil >E OlliE (ZtlSE Anis CURRt:CIIVE ACTION 10 l'R E V r.N I Rf CtfitRINt E 79-04 790201 F 719 A 4 79-03/03-1.-0 till Pllf 3'XX Excessive gland leakage on "11" boiler feed pump concu: rent with inoperable "C" bo ile r feed pump necessitated cont rolled reactor shutdown on Feb-rua ry 1, 19 79, pe r I.m 4. 3. 2.

Scheduled reactor shutdown for re-fuellug was clianged f rom March 1, 1979, to Feb ruary 1, 19 79. Thus shutdown number 79-04 has e x ten deil tlirough February, fl.irch, and Ipril, 1979.

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l S UMf fAl(Y : I'lan t shutdown for scheduled re f uell'ng and turb ine generato r ove rhaul ent i re nv>n th.

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AVERAGE DAILY CIT POWER LEVEL Do cket No. 50-267 Unit Fort S t. Vrain. Uni: No. 1 Date 790501 Co=pleted By J. W. Gahm Telephone (303) 785-2253 Month April DAY AVERAGE DAILY ?0'JER LEVEL DAY Ai?. RAGE DAILY POWER LEVEL

(.We-Ne t ) (rJe-Net) 1 0 17 0 2 0 18 0 3 0 19 0 4 0 20 0 5 0 21 0 6 0 22 0 7 0 2 0 3 0 24 0 9 0 25 0 10 ' O 26 0 11 0 27 0 12 0 23 0 13 0 29 0 1

4 0 ,

so 0 15 0 31 N/A 16 0

• Genera:or en line but no ne: genera: ion.

298 212

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1. Na=e of Facili:v. Fort St. Vrain- Uni No. 1

2. Scheduled date for nex: refueling shutdown. Feb rua ry 1, 19 7C

3. Scheduled date for restart following refueline. June 1,1979

4. ' Jill refueling or resu=p ion of operatica thereafter require a ,

technical specification change  !

or other license a=end=ent ? { Yes*

l If answer is yes, what, in To facilitate ins ertion of eight fuel i general, vill these be? es t ele =en ts.

I If answer is no, has the reload l

• NOTE: If Technical Specification change fuel design and core configura- approval is no t received fro Nuclear tion been reviewed by your Plan: Regula tory Cc==1ssion in time for re-Saf ety Review Co==1 :ee to deter- ! fueling, then the answer to #4 is N0, and

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=ine whether any unre iewed the reload fuel and graphite design have

! safety questions are associated l

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been reviewed.

I with :he core reload (Reference

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10CFR See:1,n 50.59)? I i

u l If no such review has :aken l clace, when is it scheduled?

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i 5. Scheduled date(s) for sub=1::ing

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' l j proposed licensing action and

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i succortinc infor ation. i Janua rv 9. 1978

$ .

i I 6.  !=portan licensing considera- Eight test fuel ele =ents to allow:

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l tions associated with refueling, e.g., new or differen: fuel de-l 1) Different f uel particle design. ,

! sign or supplier, unreviewed '

design or perfor=ance analysis { 2) To qualify near isotropic graphite. '

, =ethods, significan: changes in i f uel design, new opera:ing pro-l cedures. {

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7. The nt=ber of fuel asse=blies l a) 1432 HIGR f ..el ele =ents. ',

(a) in the core and (b) in '

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ne scen: ruel s: ora 2e cool. b) 245 spen: HTGR fuel elements. '

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5. The present licensed spent fuel Capacity is 11=ited in size to about one i

l pool storage capaci:y and the third of core (approxi=a tely 500 HTGR  :

sice of any increase in licensed ele =en ts ) . No change is planned. '

storage capacity that has been i

requested or is planned, in i og

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nu=cer or

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.ue,_ asse= sties.

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Pl.EING IhTCPJMTION (CONH'17.D)

9. The projected date of the l 1986 under the Three Party Agreement (Con-

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last refueling that can be tract AT (04-3)-633) berween DOE, Public discharged to the spent fuel l Service Co=pany of Colorado (PS Co) , an d pool assu=ing the present General Atomic Company.

• licensed caracitv.

• The 1986 date is based on the unders tanding that spent f uel discharged during the ter= of the Three Party Agreement will be shipped to the Idaho National Engineering Laboratory for storage by DOE at the Idaho Che=1 cal Processing Plant (I CPP ) . The storage capacity has evidently been sized to accomodate fuel which is expected to be discharged during the eight year period covered by the Three Party Agreement.

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