ML20136G374

Monthly Operating Rept for Oct 1985

ML20136G374
Person / Time
Site:	Fort Saint Vrain
Issue date:	10/31/1985
From:	Gahm J, Novachek F PUBLIC SERVICE CO. OF COLORADO
To:	NRC OFFICE OF ADMINISTRATION (ADM)
References
P-85407, NUDOCS 8511220334
Download: ML20136G374 (9)

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PU8LIC SERVICE COMPANY OF COLORADO FORT ST. VRAIN NUCLEAR GENERATING STATION O

MONTHLY OPERATIONS REPORT NO. 141 OCTOBER, 1985 5 k 8511220334 851031 PDR ADOCK 05000267 gh g R PDR

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\3 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 OpR-34. This report is for the month of October, 1985.

1.0 NARRATIVE

SUMMARY

OF OPERATING EXPERIENCE AND MAJOR SAFETY RELATED MAINTENANCE The reactor remained critical throughout the reporting period.

Power was limited to slightly less than 2% until October 16, 1985, while repairs were conducted on the Alternate Cooling Method diesel generator set. On October 16, 1985,. the Alternate Cooling Method diesel generator was declared-_ operable after the successful completion of the surveillance two hour load' test. and power escalation ' began "while maintaining *' reactor dewpoint temperature comfortably below the low level moisture

~ monitor's trip value. On October 18, 1985, a helium circulator bearing watsr system upset occurred while shutting down

. "0" circulator for Environmental Qualification work, and the reactor dewpoint increased to 23 degrees Fahrenheit. Reactor power was decreased from approximately 4% to 2% to reverse the primary coolant moisture content increase. After the short- term moisture level spike, power escalation was resumed. , Sufficient u 5") nuclear steam production was achieved on October 19, 1985, to allow shutdown of the outside auxiliary boiler for minor repairs.

It was left in a standby condition after repair completion. On October 22, 1985, 7.8% power was reached. The Alternate Cooling Method diesel generator unreliable erratic behavior began again on October 23, 1985. .After- extensive troubleshooting by Plant Electricians, Electrical Department experts, System Operations, and outside experts, the diesel / generator was repaired and successfully demonstrated operable on October 30, 1985. On October 30, 1985, the primary coolant moisture level had decreased to the point that the "A" helium circulator was brought to speed to drive additional moisture out of the insulation in the area of the original ingress.

"0" helium circulator tripped on a buffer-mid-buffer signal caused by malfunction of the main drain pressure differential transmitter (p0T-2178-1) on October 23, 1985. A test to troubleshoot this problem will be run after the reactor is shutdown for Environmental Qualification modifications.

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h O The "C" turbine driven boiler feed pump was placed in operation for pre-boiler recirculation on October 14, 1985, in order to

' clean up the feedwater prior to establishing feedwater flow

[ through the steam generators. The pump came up very smoothly with minimal vibration detected. Feedwater cleanup was completed on October 15, 1985, and normal feedwater was placed on both '

steam generator economizer-evaporator-superheater sections. The "A" turbine driven boiler feed pump was placed in service October 31, 1985, to obtain vibration data. It also came up very smoothly and was left in operation. "C" turbine driven boiler feed pump was then shutdown.

2.0 SINGLE RELEASES OF RADI0 ACTIVITY OR RADIATION EXPOSURE IN EXCESS' 0F 10*; 0F THE ALLOWABLE ANNUAL VALUE_ . -

None 3.0 INDICATION OF FAILE0 FUEL RESULTING FROM IRRADIATED FUEL EXAMINAf!ONS None 4.0 MONTHLY OPERATING DATA REPORT f,3

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Attached I

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• Page 1 sf 1 orrum:C DAu arroar - Docutt so. 50-267 4 Dart Novomher- 7; l orc; ComtrtD sr Frank J. Novachek trttraout (303) 785-2224 Cr!RATINC $7AT*J5

1. voit x..es' Fort St. Vrain ,

2. mer2rtinsreriod: 851001 through 851031

3. ' Licensed Ther=al Fever (Wt): 842

4. - Nameplate Rating (Cross 5*e): 342

5. Design Electrical Racing (Net We): 330

6. Maximum Dependable Capacity (Cross We): _342

7. Maxiou:n Dependable Capacity (Net We): _ - 330 . -

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8. .If Changes occur in capacity Ratints -(Itees Nu25er 3.;hrough 7) Since tast Report.-Cive Reasons:,- "c- 3- >_u;

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9. rower Level To 1hich Restricted, If Any pet We): 280 ,

10. Reasons for Restrictions, l' Any: Per comitment_to_ the NRCJong term anentien

_ahove 85% power _DERding completion of B-0 startup testing.

This !both Year to Data Cumulative

11. nours in reportins reriod 745 7.296 55.561

12. neter of wouEs seacte r va. Critical 649.9_ 162.8 . 27.914.2

13. neactor Reserve shutdova nour. 0.0 0.0 0. 0 _

is, nours cenerator on-tin. 0.0 0.0 -

0.0

15. rnst Reserve shutdova nour. 0. 0 _. 0.0 0. 0 --

16. cross neral Energy cenerat.d (s,t> 24,311.6_ 24,421.1 9,886,135.5

17. Crcss Electrical Energy cenerated (tf.fil) OA 0.0 0.n ta. ret neetrical enersy cenerated (su) -3,668 -25,206 -2.902.752

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19. caft service raeter . 0.0_ 0.0 _33.2

20. tatt Avat1 ability ractor 0.0 0. 0 __ 3 3 . 2__

21. rnit capacity ractor (tsing Mac set) 0.0_ 0.0_ 15.8

22. twit Capecity rector (usins Dtr. set) 0.0 0.0 15.8 _

23. Unit rorced Outas. Rat. 100.0_ 100.0_ SLL.

4 shuidevne scheduled over x xt 6 fonths (Type. Date, .nd Duration or cach): NRC~ ordered

_ November 15. 1985 through November 30, 1985.

25. If thut Devn at End of Report Period. Estinated Date of Startups _N/A

26. L' nits la *est $:stus (Frict to Co-ceretal Operation): rotecast Achieved IN!71At CRITICALITT N/A N#

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• N/A -

1 sit 1At. ntC u ct:T N/A N e m RC m. ort m Cs N/A N/A _

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• . . Att ech nent-3A

.' AVERAGE DAILY UNIT POWER LEVEL Issue 2

, g Do cke t No. 50-267 Unit _Fo7t St. Vrain s Date ' November 7,1985_

Completed By Frank J. Noyachek Telephone (303) 785-2224 '_

lbnth QC10ber DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MRe-Net) (MWc-Ne t)

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-- ._ ,.g 1 0.0 -n :4 _ _ _.17 --0.0 _

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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 28 0.0 13 0.0 29 0.0 14 010 30 0.0 15 0.0 31 0.0 16 0.0

^ Generator on line but no net generation.

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lease 2 , ,,

UNIT SIIVrlundNS AND l*GdER RCJ4JhJtd ,- 'e

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L A' ' InexeT No. 5'0-267 uNtT Mane Fort St. Vrain ,.

nATs - November 7.1985 coerl.zTen nT Frank J. Novachek ar.roitT tenu -October ,

Tet.cnmNe (303)'785-2224

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tuniniu or __

sittTTTING

, DNN 5T5TDI COIR 0tir.NT No. DATE TTFE DURATLON RrASON REACTOR I.ER I CUDC CDDE CAlfSK AND CURRECTIVE ACTION 10 rREST.t37 RECURRIJ8CE

,85-002851001 F 38.0 Hrs A 2 85-020 5A FC0 Loss of both auxiliary boilers.

5A . LC0 Repaired auxiliary boilers

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- - REFUELING INFORMATION 1- l l l 1. Name of Facility l Fort St. Vrain Unit No. 1 l l l l l 2. ' Scheduled date for next l l l refueling shutdown. l April 1, 1987 l  ;

I l l l 3. Scheduled date for restart l May 1, 1987 l l following refueling. 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? l l_.____.__._.

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l. If answer:is yes, what cing ;1l l

- - - - 8 l' general, will these be? I l l- l l l .If answer is no, has the reload l l l fuel design and core configura-l l l

l tion been reviewed by your l l l l Plant Safety Review Committee l No l l l to determine whether any unre- l l l viewed safety questions are l ~

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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 1985 l l place, when is it scheduled? l l l l l .

l 5. Scheduled date(s) for submit- l l l l ting proposed licensing action ,1 ---------------- l l l and supporting information. l l 1, 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, unre- l ---------------- l l viewed design or performance l l l analysis methods, significant l l l changes in fuel design, new l l l operating procedures. ., l

'l , l l 7. The number of fuel assemblies L l l (a) in the core and (b) in the l a) 1482 HTGR fuel elements l l spent fuel storage pool. I b) 137 spent fuel elements l

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. ~ REFUELING INFORMATION (CONTINUED) ,

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l l l l l 8. The present licensed spent fuell l l pool storage capacity and the l l 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 l has been requested or is -

l (approximately 500 HTGR elements).-l ~

L, l planned, in number of fuel l No change is planned. l l assemblies. l l l l l l 9. .The projected date of the last l 1992 under Agreements AT(04-3)-633l

._. . refueling that can be dis '.-- l and DE-SC07-791001370--between = -lc, =.= =  ;.

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• charged to the spent. fuel pool-l. Public Service Companysof;1nt- r :;l:::_ : ..

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-l assuming the present'licehsed l Colorado, and General ' Atomic ""-l' " -4 l capacity. I Cor,ipany, and 00E.* l l

• The 1992 estimated date is based on the understanding that spent fuel l

discharged during the term of the Agreements will be stored by DOE at L the Idaho Chemical Processing . Plant.-- The storage capacity has l- evidently been. sized to.-accommodate -eight fueln segments. =-It is .::. .

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

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Public Service ~ - . , * .

Company of Colorado 16805 WCR 19 1/2, Platteville, Colorado 80551 November 14, 1955 Fort St. Vrain Unit No. 1 P-55407 Office of Inspection and Enforcement ATTN: Document Control Desk U. S. Nuclear Regulatory Commission Washington, D.C. 20555 Docket No. 50-267 I

SUBJECT:

Monthly Operations Report For October, 1935

REFERENCE:

Facility Operating License No. OPR-34

Dear Sir:

Enclosed, please find the Monthly Operations Report for the month of October, 1985.

Sincerely, l

J. W. Gahm Manager, Nuclear Production Fort St. Vrain Nuclear Generating Station l Enclosure I

cc: Mr. Robert D. Martin Regional Administrator, Region IV JWG:djm qi