ML20237K211

Monthly Operating Rept for Jul 1987

ML20237K211
Person / Time
Site:	Fort Saint Vrain
Issue date:	07/31/1987
From:	Novachek F, Robert Williams PUBLIC SERVICE CO. OF COLORADO
To:	NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
References
P-87291, TAC-65992, NUDOCS 8708190136
Download: ML20237K211 (9)

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I PUBLIC SERVICE COMPANY OF COLORADO l

i FORT ST. VRAIN NUCLEAR GENERATING STATION i

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MONTHLY OPERATIONS REPORT NO. 162 July, 1987 E

' 8708190136 870731

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PDR ADOCK 05000267 PDR _

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1 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 the month of July,1987.

1.0 NARRATIVE

SUMMARY

OF OPERATING EXPERIENCE AND MAJOR SAFETY RELATED MAINTENANCE On July 2, 1987, the Office of Nuclear Reactor Regulation authorized operation of Fort St. Vrain above 35 percent of full power, not to exceed 82 percent, based on reanalysis of safe shutdown cooling following a 90 minute interruption of forced cooling.

On July 3, 1987,, with the Average Region Outlet Temperature greater than 1200 degrees Fahrenheit, the 10 day grace period for Technical Specification LCO 4.2.10 was entered at 1000 hours0.0116 days <br />0.278 hours <br />0.00165 weeks <br />3.805e-4 months <br /> when primary coolant oxidants exceeded 10 PPM. Oxidants peaked at approximately 26.4 PPM on July 4, and then gradually reduced to approximately 18 PPM. Reactor power was reduced to lower the Average Region Outlet Temperature to less than 1200 degrees l

Fahrenheit at 1852 hours0.0214 days <br />0.514 hours <br />0.00306 weeks <br />7.04686e-4 months <br /> on July 12, thereby exiting the grace l period of LCO 4.2.10.

On July 10, 1987, and again on July 11, 1987, with the reactor l operating at 57 percent power, the group III Loop II steam I generator penetration interspace operating below primary coolant pressure, with and RIS-2264 inoperable, grab samples were not collected fror the Loop II steam generator penetration interspace as required per Technical Specification LCO 4.2.9. This incident occurred as a result of personnel error in combination with a deficient procedure. This incident has beaa investigated and reported to the Nuclear Regulatory Commission in Licensee Event Report 87-017.

d Primary coolant oxidants were reduced to less than 10 PPM on l

July 16. On July 17, reactor power was increased and the Average Region Outlet Temperature exceeded 1200 degrees Fahrenheit at 0230 hours0.00266 days <br />0.0639 hours <br />3.80291e-4 weeks <br />8.7515e-5 months <br />. The 10 day grace period for LCO 4.2.10 was entered

at 1100 hours0.0127 days <br />0.306 hours <br />0.00182 weeks <br />4.1855e-4 months <br /> when the total primary coolant oxidants exceeded i

10 PPM. j l

l On July 22, 1987, at 0012 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, C helium circulator tripped on l Circulator Speed /Feedwater Flow Mismatch. At 0517 hours0.00598 days <br />0.144 hours <br />8.54828e-4 weeks <br />1.967185e-4 months <br />, with. C helium circulator self-turbining, D helium circulator )

automatically tripped on high speed. Loop II secondary flow was 1 manually isolated and reactor power was reduced to less than 2 i percent to recover Loop II. During the Loop II recovery,

- excessive wobble and erratic speed indications were observed on D

, helium circulator. O circulator was shutdown and the Loop II l recovery proceeded on C helium circulator. The turbine generator

[ was synchronized to the grid on July 25, at 0956 hours0.0111 days <br />0.266 hours <br />0.00158 weeks <br />3.63758e-4 months <br />.

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4 l j ,t _ q, i On July;_28, 1987,' , ,a pur'ified herium bil,of approximately 800 ,

i pounds 'per e.?y cevehped in ti+, int esuce on D helium ,.

T:4Micu Specification, 100 d.2.9 required the cirettlator. >

c ,i rea: tor to be rhutdown and depressurized.i.n less than 100 psia 'i^> '

within 24 hours Si nce the leak rate was in excess of 400 pounds l<

per day. The tuttir.e gbnerator was removed from service on l July 29, at 0140 hours0.00162 days <br />0.0389 hours <br />2.314815e-4 weeks <br />5.327e-5 months <br />. A manual reactor shutdown was complet7d*

at 1026 hour0.0119 days <br />0.285 hours <br />0.0017 weeks <br />3.90393e-4 months <br /> 3 Following the reactor shutdown, it was deter ined that D heltum circulator would be replaced. This/eventwillbe .

investigated 'and reported to tr.o duclear Regulatory Commissio Jn , 1 Licensee Event Report 87-018.V t 2.0 SINGLE PELEASES OF RADIOACTIVITY OR RADIATION EXPOSURE IN EXCESS OF IC% OF THE ALLOWABLE AMNUAL VALUE I

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None ,

3.0 INDICATION OF FAILED FUEL RESULTING FROW IRRADIATED FUEL EXAMINATIONS 'i t

None l 4.0 MONTHLY OPERATING DATA REPGRT l

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• ePreATIN CATA RTr0T* DoctET ra. __50-267 dan Auoust 14. 19R7

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! coxrLETED al F. J. Novachek ,

(303) 620-1007 f masonE opExAnn: STAT >s NOTES

a. Unit Name: Fort St. Vrain. Unit No. 1

3. Reporting Period: 870701 throuah 870731

3. Licensed Thermal Power (Wt): 842

6. Nameplate Rating (Cross We): 342

5. Design Electrical Rating (Net We): 330

6. Maxinum Dependable Capacity (Gross We): __342

7. Maximum Dependable Capacity (Net We): 330

8. If Changes occur in Capacity Eatings (Items Nummer 3 Through 7) Since Last Erport. Give Reasons:

None i

9. Power Level To Which Kestricted, If Any (Net Wet: 270.6

10. Reasons f or Restrictions, If Any: Reanalysis of safe shutdown coolino followina a 90 minute interruption of forced coolina.

This Month Tear to Date Cu:nulative i n. sours in Reporting Period 744 5.087 70.872

12. Nu:eer of sours aeactor was critical 682.4 2.392.4 32.930.2

13. Reactor Reserve Shutdown Ecurs 0.0 0.0 0.0

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14. nour Generator on-Line . 597.1 1.811.7 21.366 4._

l 15. unit a serve Shutdown Boars 0.0 _

0.0 0.0

16. Cross Thermal Energy Generated (WH) 248.206.R 576.546.1 10.841.945.9

17. Cross Electrical Energy Generated (WH) 91.227.0 189.789.0 3J;23.785.0

18. Net Electrical Energy Generated (WB) R4_273_O 163_3Q7_O 3.1I1.677_O

19. Unit Service Factor 80.3 35.6 30.1 t

20. Unit Availability Tactor 80.3 35.6 3 0 .1_____ j l 21. Unit capacity Factor (Using MDC Net) 34.3 9.7 13.3 {

1 l 22. Unit Ca acity factor (1' zing DER Net) 34.3 9.7 13.3 I 23. unit rorces outare Rate 19.7 64.4 62.7 i ,

! 24. Shutdovcs Scheduled over Next 6 lbnths (Type. Date, and Duration of Each): RpDlaro O helium '

cirenlator. R70A01. 1732 hours0.02 days <br />0.481 hours <br />0.00286 weeks <br />6.59026e-4 months <br />

25. If Shut Down at End of Report Period. Estinar.ed Date of Startup: ,,$6ptember 21. 19R7

26. Units In Test Status (Prior to Cor::mercial operaticn): rotecast Achieved innAt cRmerl.in N/A N/A InnAt rucmcm N/A N/A comEnc:AL orExancs N/A N/A

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AVERA3E' DAILY UNIT POWER LEVEL Docket No, 50-267 Unit Fort St. Vrain Unit No. 1 Date August 14, 1987 Completed Ey F. J. Novachek Telephone (303) 620-1007 Month JULY DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net) (MWe-Net) 1 90.1 17 145.7 2 91.8 18 177.4 l 3 142.2 19 191.6 4 164.4 20 198.5 5 163.2 21 216.8 6 164.5 22 16.5 7 171.5 23 0.0 8 169.2 24 0.0 9 172.6 25 33.6 10 174.3 26 85.8 11 173.9 27 127.4 12 134.4 28 123.1 13 105.7 29 0.0*

14 104.5 30 0.0 15 101.8 31 0.0 16 96.8

• Generator on line but no net generation.

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1 REFUELING INFORMATION I l l l 1. Name of Facility 1 Fort St. Vrain Unit No. 1 l l l l l 2. Scheduled date for next l l l refueling shutdown. I October 15, 1988 l l l l l 3. Scheduled date for restart l December 15, 1988 l l following refueling. l l l l l l 4. Will refueling or resumption ofl No l

! operation thereafter require a l l l technical specification change l l l or other license amendment? I l l l l l If answer is yes, what, in l ---------------- l i general, will these be? l l l l l l If answer is no, has the reloadj 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 l associated with the core reload l l l (Reference 10 CFR Section l l l 50.59)? I l l 1 l l If no such review has taken l 1987 l l place, when is it scheduled? l l l l l l 5. Scheduled date(s) for submit- l l l ting proposed licensing action j ---------------- l l and supporting information. l l l l l l 6. Important licensing considera- l l ,

I 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 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) 0 spent fuel elements l ,

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e REFUELING INFORMATION (CONTINUE 0) l I I l 8. The present licensed spent fuell l l pool storage capacity and the l l j 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).1 l planned, in number of fuel l No change is planned. l l assemblies. l l 1 I l 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-SC07-791001370 between l l charged to the spent fuel pool l Public Service Company of I l assuming the present licensed l Colorado, and General Atomic l l capacity. l Company, and DOE.* 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 the Idaho Chemical Processing Plant. The storage capacity has evidently been sized to accommodate _ eight fuel segments. It is estimated that the eighth fuel segment will be discharged in 1992.

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l O Public Service ~ Company of Colorado i

16805 WCR 19 1/2, Platteville, Colorado 80651 August 14, 1987 Fort St. Vrain

. Unit No. I l P-87291

I l U. S. Nuclear Regulatory Commission I i

ATTN: Document Control Desk Washington, D.C. 20555 i Docket No. 50-267 I

SUBJECT:

MONTHLY OPERATIONS 1 REPORT FOR JULY,1987

REFERENCE:

Facility Operating License No. DPR-34

Dear Sir:

Enclosed, please find the Monthly Operations Report for the month of i July, 1987.  !

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

Sincerely, hv' R. O. Williams, Jr.

Vice President, Nuclear Operations Enclosure cc: Mr. J. E. Gagliardo U.S. NRC, Region IV >

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