ML19261D475

Monthly Operating Rept for Apr 1979

ML19261D475
Person / Time
Site:	Fort Saint Vrain
Issue date:	04/30/1979
From:	Gahm J PUBLIC SERVICE CO. OF COLORADO
To:
Shared Package
ML19261D473	List: ML19261D472 ML19261D475
References
NUDOCS 7906190302
Download: ML19261D475 (9)

Text

PUBLIC SERVICE COMPANY OF COLORADO FORT ST. VRAIN NUCLEAR GENERATING STATION MONIHLY OPERATIONS REPORT NO. 64 AP RIL, 1979 2307 263 i

5 i

7 9061005Q29

This report contains the highlights of the Fort S t. Vrain, Unit No. 1 activi-ties, operated under the provisions of the Nuclear Regulatory Commission Operating License, DPR-34. This report is for the month of April,1979.

1.0 NARRATIVE

SUMMARY

OF OPERATING EXPERIENCE AND MAJOR SAFETY RELATED MAINTENANCE Refueling shutdown is progressing on schedule. The six regions scheduled for refueling have been completed. Fuel test elements have been placed in Region 27, Region 24, Region 30, Region 22, and Region 25. The PGX graphite sa=ple in the layer 12 reflector elements have also been placed in those five regions. An inspection of the Region 13 core support block is planned. A test of the installation of the region constraint devices was performed on Region 18 for the purpose of identifying any problems prior to the scheduled installation of region constraint devices later this year. Following co=pletion of the region constraint device test, the stylus block for the scratcher assembly was inserted into Region 18.

The modified control rod drive work was completed with one modified drive placed in Region 35 and one placed in Region 5.

The main turbine generator overhaul completion date of May 4,1979, is reported by General Electric to have slipped to iby 24, 1979. This new completion date could pose real problems for attaining power operation by June 1,19 79.

Installation of C-2103 (helium circulator) continues.

The main condenser eddy current testing indicated wall thinning and/or leaks in 648 tubes. Plugging of the tubes is in progress.

Cleaning of the circulating water cooling tower has been completed.

Loop 1 and Loop 2 secondary coolant piping, valve, and control system over-haul was completed in April and both loops are receiving flow from the condensate system at this time.

System 91 (hydraulic oil system) overhaul and system modification were essentially completed by April 25, 1979, and these systems are now being returned to service. The additional auxiliary boiler was placed in ser-vice on April 5,1979, and final testing was completed during this report period.

Attached is a su= mary, by department, of outage activities completed.

2.0 SINGLE RELEASES OF RADIOACTIVITY OR RADIATION EXPOSURE IN EXCESS OF 10% OF THE ALLOWABLE ANNUAL VALUE None g 3.0 INDICATION OF FAILED FUEL RESULTING FROM IRRADIATED FUEL EXATNATIONS 2

None 3

2307 264

4.0 MONTELY OPERATING DATA REPORT Attached 2307 265 0

i s

E

A summary of outage completion is as follows: ,

DEPARTMENT TOTAL NUMBER NUMBER OF ACTIVITIES OF ACTIVITIES COMPLETED  % COMPLETE 8 4 50 Computer Services

.:119 82 Electrical 145 75 Engineering 117 88 46 43 93 General Atomic 39 General Electric 41 16 7 37 Health Physics 19 MAINTENANUE 521 456 88 Overall 78 General items 264 206 232' 232 100 Refueling 25 18 72 Circulator 234 189 81 OPERATIONS 4 2 50 QUALITY ASSURANCE 114 86 75 RESULTS 23 19 83 STORES 42 32 76 TECH SERVICES 3 2 67 TRAINING ll 4 36 WAREMBOURG ,

TOTAL 1,328 1,067 80%

overall average 2307 26,6

e?IRAns: cATA RI? cts occzr: No. 50-267 An 790601 coe .t:t3 si J. W. Cahe

.tra xz (303) 785-2253 c?r3A ns: s:A rs sons

. :: : same: Fo rt S t. Vrain, Unit No. 1

. a por:ing P.:iod: 790501 to 790531

3.  :. ice-sed n :nal rover ose): 842

e. samepla:e aa:ing Gross We): 302

3. Design Ele ::ical Rating (Net !Ge): 330

6. W r' m m Dependable capaci:7 (: rosa We): 34 2

7. Maxt=um Dependable Capa:1:7 (Ne: We): 330 S. If changes 0 :ur in Capacity Racings G:e=s Nu=ber 3 3:ough 7) Since !.as: Repo rt , :ive Reasons:

None

9. Power Level to '.thich Res::1:ted. If Any (se: !Se): 231

10. Raasor.s f:: Res::ie: ions, if Any: Nuclear Regulaterv Co ission restriction (700 cending resolution of certain Final Safety Analysis Report and Technical Soecification bases dis crep ancies. This unit is in the power ascension chase of startuo testin2.

Bis Mench Tear to Oa:. Cu::alative

11. sou s in Repor:ing ? :134 744 3,623

. su.sa : af sours a a::o as criminal 28.3 817.7 14,291.4

13. Reac:o: Raserve shu:down sours 0. 0 0. 0 0.0

14. aours cecarator on-:.ine 0.0 665.3 8,507.9

13. Uni: Rese:i. shutdown sours 0.0 0. 0 0.0

16. ;ross ner=aJ Inergy Generated (ws) 23 313,092 3,516,090 17-  ::ess ne==1 cal Energy cene:: ed (ws) 0 109,852 1,058,122 is. see nec= tea Energy Geners:ed (sa) 0 101,177 952,628

19. Uni: service rac:or N/A N/A N/A

20. :ni: Avanabili:7 rae:or N/A N/A N/A

1. :ni: capa:1:7 rae:or (tsing :cc se:) N/A N/A N/A

22. Oni: :apact:v racts: Gsing :IR see) N/A N/A N/A

23. Oni Forced Outage Rate N/A N/A N/A

4. Shu: downs Scheduled Over sex: 6 Mon:hs (Type Date, and Duration of Iach):

Shutdown for Refueling on 2-1-79

23. If Shu: Down a: Ind of Repor: Period, Estimated 04:e of S:artup: 6-15-79

26. Uni:s in res: S tatus (Prio: :o co::=er:ial @ era: ion): Forecas: Achieved 2307 267

c :A:. Onn:A:.:n 740201 740131

cnA:. ::. : 22 m 7612 761211

eca :A:. :Pr3An:3 --

e

UNIT SHUllgNS[ANJ) fpfR _RMN[WNS

,oc,Kr rai, 50-267 _ _ __--____--. -

18 NIT NAttE For t S t. Vrain,_ Unit No. 1 imis 790601 rotrtElta nY .1. W. Cah m REPORT PRINIll May_, 1979 Tritreamn _13031_785-2253 NElHOD OF SHurTING -l IM MN SYSIEn OlttrONEN T DA1E TYPE LER #

-NO. - - - - DURATIO.N --

- - - - REAS_ON--

--- - - -REACTOR - - , . ,O_)DE _0)DE _-.

- --cAU- - - -C..URR.EC1 S E AND -- -- I V.E _ACT tO. N.10 .l*R. EVtW I RtX:URR.PM. E .-.

79- 04 790201 F 744 A 4 79-03/03-1.-0 1111 PUMPXX Excessive gland leakage on "II" boiler i feed pump concurrent with Inoperable  !

"C" boiler feed pump necessitated ,

controlled reactor shutdown on Feb-ruary 1, 1979, pe r 1,W 4. 3.2.

Scheduled reactor shutdown for re-fueling was changed f rom March 1, 1979, to February 1, 1979. Thus shutdown number 79-04 has extended through February, March, April, and May, 1979. .

f N I-u o (

N N

CF CD

SUMMARY

Plant shutdown for scheduled refueling and turbine generator overhaul entire month.

l L

AVERAGE DAILY IJNIT POWER LEVEL Docket No. 50-267 Uni: For: S t. Vrain, Uni: No. 1

, Da:e 790601 Co=pleted By J. W. Gahm t elephone (303) 785-2253 Month May, 1979 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY ?OWER LEVIL (We-Ne:) (M;ie-Ne t) 1 0 17 0 2 0 la 0 3 0 19 0 4 0 '0 0 5 0 0 21 6 0 0 22 7 0 23 0 8 0 24 0 9 0 25 0 10 0 26 0 11 0 27 0 12 0 0 28 13 0 29 0 14 0 30 0 15 0 31 0 16 0 2307 269

• Generator on line bur no ne: generation.

RETJE:.ING INFORMA* ION

1. Na=e of Facili:v. Fo rt S t. Vrain. Unit No. 1

2. Scheduled da:e for nex: refueling shutdown. February 1,1979

3. Scheduled date for restart followine refueline. June 1,1979 4 Will refueling or resu=p:1on of operation thereafter require a technical specifica: ion change or other license a=end=ent? Yes*

If answer is yes, what, in To facilitate insertion of eight fuel general, vill these be? test elements.

If answer is no, has the reload

• NOTE: If Technical Specification change fuel design and core configura- approval if not received from Nuclear tion been reviewed by your Plan: i Regulatory Co==ission in time for re-Saf ety Review Cc==it:ee :o de:er- fueling, then the answer :o #4 is NO, and

=ine whether any unreviewed the reload fuel and graphite design have safety questions are associa:ed oeen reviewed.

with the core reload (Reference i 10CFR See:1on 50.59)? I If no such review has taken olace, when is it scheduled? I

5. Scheduled date(s) for sub=1::ing proposed licensing action and suceortine information. Januarv 9. 1978

6. I=portan: licensing considera- Eight test fuel ele =en ts to allow:

tions associated with refueling, e.g., new or different fuel de-

1) Different fuel particle design, sign or supplier, unreviewed i

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

nethods, significant changes in f uel design, new opera:ing pro-cedures.

7. The nu=ber of fuel asse=blies a) 1482 HTGR fuel elements.

(a) in the core and (b) in the seen: fuel storage cool. b) 245 spent HTGR fuel elements. l

3. The present licensed spent fuel Capacity is limited in size to about one pool s:orage capaci:y and :he third of core (approximately 500 HTGR si:e of any increase in licensed elements). No change is planned.

storage capaci:y tha: has been reques:ed or is planned, in nu=ber of fuel asse=blies.

2307 270

RE-TELING INyOPJiATION (CONTINCD)

9. The projected date of the 1986 under the Three Party Agreement (Con-las: refueling tha: can be tract AT (04-3)-633) between DOE, Public discharged to the spen fuel Service Co=pany of Colorado (PSCo), and pool assu=ing the presen: Genera *1 Atocic Company.

• licensed ca:acitv.

• The 1986 date is based on the understanding that spent fuel 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=ical Processing Plant (ICPP ) . The s:orage capacity has evidently been sized to acconodate fuel which is expected to be discharged during the eight year period covered by the Three Party Agreement.

2307 271 O