ML20141N945

Monthly Operating Rept for Feb 1986

ML20141N945
Person / Time
Site:	Fort Saint Vrain
Issue date:	02/28/1986
From:	Gahm J, Novachek F PUBLIC SERVICE CO. OF COLORADO
To:	NRC OFFICE OF ADMINISTRATION (ADM), NRC OFFICE OF INSPECTION & ENFORCEMENT (IE)
References
P-86197, NUDOCS 8603180311
Download: ML20141N945 (8)

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PUBLIC SERVICE COMPANY OF COLORADO FORT ST. VRAIN NUCLEAR GENERATING STATION MONTHLY OPERATIONS REPORT NO. 145 February, 1986 e

3 8603180311 960228 3 PDR ADOCK 05000267

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i 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 I the month of February, 1986.

l 1.0 NARRATIVE

SUMMARY

OF' OPERATING EXPE3IENCE AND MAJOR SAFETY RELATED MAINTENANCE

- Permission to operate at up to thirty-fise percent power was received from the Nuclear Regulatory Commission on February 7, 1986. Emergency condensate to both loops economizer-evaporator-

superheater sections and pre-boiler recirculation with "C" Boiler Feed Pump were established on February 11, 1986, in preparation ,

for startup. The pre-critical sur veillance tests were. completed and the reactor was taken~ critical at 1332 hours0.0154 days <br />0.37 hours <br />0.0022 weeks <br />5.06826e-4 months <br /> on February 14, 1986. Power was slowly increased and feedwater was put on the economizer-evaporator-superheater sections to gradually raise the '

PCRV temperature as moisture levels allowed.. A peak power level of 1.5% power was reached on February 28, 1986.

- Spent fuel shipping activities continued.

The alternate cooling method diesel generator battery changeout and battery charger repair was completed on February 19, 1986.

The surveillance test was successfully run and the unit was declared operable.

The, quarterly and semi-annual preventive maintenance was completed on standby emergency diesel units K-9203X and K-9204X. '

Work is continuing on the Environmental Qaalification (EQ)

Program. As much work as is possible at the current time on all four helium circulators has been completed, with the remainder on hold for parts procurement. As of February 28, 1986, approximately forty-six percent of the Environmental Qualification Station Service Requests (SSR's) generated to date have been completed.

2.0 SINGLE RELEASES OF RADIOACTIVITY OR RADIATION EXPOSURE IN EXCESS OF-10% OF THE ALLOWABLE ANNUAL VALUE None

' 3.0 INDICATION OF FAILED FUEL RESULTING FROM IRRADIATED FUE_L EXAMINATIONS

, None 3

4.0 MONTHLY OPERATING OATA REPORT .

! Attached -

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, :si. j Attgenmer.t= 31 inue a rese 1 of 1 errun= DA A uror zo:::n so. 50-267 34n March 10.1986

( ces:.znD :: Frank J. Novachek

r zrnm (303) 785-2224 ext. 201 ,

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1. cast name Fort St. Vrain ,

. . Reporting Period: 860201 throuah 860228

3. Licanad mesa: Power (Et): 842 4 Easeplate Rating (crees We): 342 l 3. Desiga zlectrical Rating (Net We): 330

6. Maxime Dependable capasiry (cross We): 342

( ~7. Maziams Dependable capacity 0;et We): 330 l

s. If changes occur is Capetity 34 tings (Itaae Number 3 Through 7) Since Last Report, cive Reasones l

! None l .

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9. Fawr Level Te *.tiah Restricted. If Any C:et We): 115.5  !

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10. sansens for au trittiens. It Any: Limited to 35% oower oendina enmnletion of l Ervironmental Qualification l

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• hia heath Taar to Date C o miative

11. seurs ta me,ersias Period 672.0 1.416.0 58.441.0

j. 1:. ===ur et tsun n=eter vu critical 346.5 346.5 28.42 Q

13. auetar neeerve madeva :teure 0.0 0.0 0.0,

24. news comuur on-:.ine 0.0 0.0

• 18.468.0 l

is. rait suern mtdeve nevre 0.0 0.0 0.0 l 16. ' creu mraal taersy cenerstad car) 1.97A 0 1.974.0 _

9.897.057.2  !

17. creu nutrial smersy ca.eused (Wa> 0.0 0.0 3.890.254.0 1s. s.t rieurial zaersr cemented (Wu)

-2.988.0 -6.019.0 2.890.254.0 '

19. tait sorvin raster . 0.0 0.0 31.6

l. 20. : sit Antiabi11er retter ,

0.0 0.0 31.6 l 21. tait' cepecity rester (reins HDc set) 0.0 0.0 15.0

. rait capacity rester (Usins Dtx set) 0.0 0.0 15.0

23. Cait rersed estage Rata 100.0 100.0 59.9 i

• 4 Shutdevas Scheduled Over Next 6 Naths (Type. Date, and Duration of Sach): None l

t:  :!. :t mt Deva a sad of aeport peri e. ratia ted :ste of start p N/A '

26. (' pits In Test Status (Prior te co usertial operation): raresset Achieved

- mun cunen:n N/A N/A l Istna ttzen:cm N/A N/A co.esac:a erruncz -

N/A N/A

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. . . Ts?-3 Attachment-3A AVERACI DAILY CiIT POWER LEVEL Issue 2 Page 1 of 1 ,

Docket No. 50-267 Unic Fort St. Vrain I Da a Ma,.ch in 1ons Completed By Frank J. Novachek i Telephone (303) 785-2224 ext. 201 Month DAY AVERACI DAILY POWER LEVEL DAT AVERACI DAILY POWER LEVEL. ,

(MWe-Net) (.We-Ne t)

~

1 0.0 17 0.0 2 O.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 28 0.0  ;

13 O.0 29 N/A [

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14 0.0 30 N/A 15 0.0 31 N/A 16 0.0 ,

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• Generator on line but no net generation.

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>=xte mi. 50-267 ,

. must amw. - Fort St. Vrain

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anes March 10, 1986 .

i ca ristra av Frank J. Novachek .

nron ensin February,1986 trurumme (303) 785-2224 ext. 201 ename or

! SIIIFTTRIIC 1

Mass 5T57936 f3491101F3ff me. marz vvre annation asAsam asActua Iza f omic f,mc p ast AND CBERECilVE ACTIpgi in r_styrNT RFIWRafm x 85-00:851108 F 176.0 hr D Z N/A ZZ ZZZZZZ Environmental Qualification 86-001860207 F 173.5 hr G 4 N/A CF FCV Inadvertently left closed valve Liready lineup perfonned.

Shut-down k

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REFUELING INFORMATION I I I l 1. Name of Facility Fort St. Vrain Unit No.1 l l l l 2.' Scheduled date for next l l l refueling shutdown. October 1, 1987 l l l l 3. Scheduled date for restart l November 1, 1987 l l following refuelina. l l l l l l 4. Will refueling or resumption ofl No l l operation thereafter require a l. l l technical specification change l l l or other license amendment? I l

1 I l i l If answer is yes, what, in l ---------------- l l general, will these be? l l l l l l' If answer is no, has the reload l l l fuel design and core configura-l l l tion been reviewed by your l l l Plant Safety Review Committee l No l l to determine whether any unre- l l l viewed safety questions are l l 3 l associated with the core reload l l l (Reference 10 CFR Section l l

• l 50.59)? l l l l l l If no such review has taken l 1986 l l place, when is it scheduled? I l l l l l S. Scheduled date(s) for submit- l l l ting proposed licensing action l ---------------- l l and supporting information. l l

l l l 6. Important licensing considera- l l l tions associated with refuel- l l l ing,.e.g., new or different l l l fuel design or supplier, t ire- l ---------------- l l viewed design or performance l l analysis methods, significant l l l changes in fuel design, new l operating procedures.

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7. The number of fuel assemblies l l (a) in the core and (b) in the l a) 1482 HTGR fuel elements l l spent fuel storage pool. I b) 94 spent fuel elements l

i l REFUELING INFORMATION (CONTINUED)

l. r l l l ' l 8. .The present licensed spent fuell l pool storage capacity and the l h l size of any increase in -l. Capacity is limited in size to l

l. licensed storage capacity that.l about one-third of core l

'l has been requested or is l (approximately 500 HTGR elements).l l planned,' in number of fuel l No change is planned. I l assemblies. I l

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- l 9. The projected date of the last l 1992 under Agreements AT(04-3)-633l l . refueling that can be dis- l and DE-SC07-79ID01370 between l l ' charged to the spent fuel pool l Public Service Company of l

-l assuming the present licensed l Colorado, and General Atomic l l capacity. l Company, and DOE.* l l

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 l evidently been sized to accommodat'e eight fuel segments. It is l estimated that-the eighth fuel segment will be discharged in 1992.

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O PublicService Companyof Colorado 16805 WCR 19 1/2, Platteville, Colorado 80651 March 14, 1.986 Fort St. Vrain Unit No. 1 P-86197 Office of Inspection and Enforcement ATTN: Document Control Desk U. S. Nuclear Regulatory Commission Washington, D.C. 20555 Docket No. 50-267'

SUBJECT:

Monthly Operations Report For February, 1986

REFERENCE:

Facility Operating License No. DPR-34

Dear Sir:

Enclosed, please find the Monthly Operations Report for the month of February, 1986.

If you have any questions, please contact Mr. Mike Holmes at (303) 480-6960.

Sincerely, d.d.kb b]

J. W. Gahm N

Manager, Nuclear Produc+'on Enclosure cc: Mr. R. D. Martin Regional Administrator, Region IV JWG:djm T* .rE2y

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