ML20214E049

Monthly Operating Rept for Apr 1987

ML20214E049
Person / Time
Site:	Fort Saint Vrain
Issue date:	04/30/1987
From:	Novachek F, Robert Williams PUBLIC SERVICE CO. OF COLORADO
To:	NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
References
P-87190, NUDOCS 8705210618
Download: ML20214E049 (9)

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PUBLIC SERVICE COMPANY OF COLORADO

,i FORT ST. VRAIN NUCLEAR GENERATING STATION

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MONTHLY OPERATIONS REPORT NO. 159 .

i April, 1987 E

8705210618 870430

PDR ADOCK 05000267

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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 April 1987.

1.0 NARRATIVE

SUMMARY

OF OPERATING EXPERIENCE AND MAJOR SAFETY RELATED MAINTENANCE Loss of Outside Electric Power tests were successfully conducted during the month of April.

On April 2 and April 3, 1987, the reactor scram circuitry was actuated a total of three times on Wide Range Channels III and V neutron flux rate of change high due to electrical noise. These events were reported to the Nuclear Regulatory Commission in Licensee Event Report 87-010.

On April 6, 1987, the Nuclear Regulatory Commission authorized the restart of Fort St. Vrain, not to exceed 10 percent of full power until written approval to operate up to 35 percent of full power was provided'from Region IV.

i On April 11, 1987, an unplanned Loop I shutdown occurred. On April 14, 1987, an unplanned Loop II shutdown occurred. These events are being investigated and reported to the Nuclear Regulatory Commission in Licensee Event Report 87-011. .

On April 16, 1987, during a Quality Assurance audit of Fort St.

Vrain Technical Specification surveillance procedures, it was discovered that functional test procedures for Gaseous and Liquid .

Effluent Radiation Monitors were deficient. This event is being investigated and reported to the Nuclear Regulatory Commission in Licensee Event Report 87-012.

The reactor was taken critical on April 17, 1987, at 1029 hours0.0119 days <br />0.286 hours <br />0.0017 weeks <br />3.915345e-4 months <br />.

On April 17, 1987, with the reactor operating at approximately l

0.8 percent power, it was determined that primary coolant flow was below the minimum allowable value established in Technical Specification LC0 4.1.9. This event is being investigated and reported to the Nuclear Regulatory Commission in Licensee Event Report 87-013.

i On April 27, 1987, written authorization from Region IV was received to operate the reactor up to 35 percent of full power.

Steam generator " boil-out" was accomplished on April 29, and the l . turbine generator was placed on line at 2130 hours0.0247 days <br />0.592 hours <br />0.00352 weeks <br />8.10465e-4 months <br /> on April 30.

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2.0 SINGLE RELEASES OF RADI0 ACTIVITY OR RADIATION EXPOSURE IN EXCESS OF 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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? Court.atto at F. J.'Novachek Tatsruour (303) 620-1007

orsa4TIMG STATUS notas

1. Unit Names- ' Fort St. Vrain.' Unit No. 1

2. asportins Persod: 870401' throumh 870430 3'. Licensed therms 1 Feuer (st): 842

4. Nameplace natias (Gross we): - 342

$. nasign Electrical nating (Not we): 330

'6. Maximum Dependable Capacity (Gross we): 342 4 7. Maximum Dependable Capacity-(met me):: 330

' 8. .If Changes Occur in Capacity Eatings (Items Number 3 Through 7) Since Last Report, Give Reasonst

< , None

9. ~ Fower Level To Which Restricted, If Any (Net me): 115.5

10. Raasons for Restrictions, If Any: Per conunitment to the Nuclear Renulatory Connniaston.

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' do not operate above 35% until anoroved by the NRC.'

Cumulative This Month Year to Date

11. ~ Hours in Reporting Period - 719 2.879 68.664-325.5 2

325.5 30.863.3

12. Number of Hours Reactor Was Critical 0.0 0.0 0.0

13. . Reactor Reserve Shutdown Hours -

14. Hours Generator On-Line ~2.5 ' 2. 5 19.557.6 0.0 0.0 0.0

- 15. Unit Reserve Shutdown Bours

16. cross Thermal Energy Generated (HWH) 15 ~.018. 3 15.018.3 10.280.418.1 i' 17. ~ Cross Electrical Energy Generated (MWH) 143.0 143.0 3.334.139.0 i' 18. Het Electrical Energy Generated (wH) 0.0 0.0 2.938.347.0 0.3 0.0 28.5

19. Unit Service Factor l 20. Unit Availability Tactor 0.3 0.0 28.5

21. Unit Capacity Factor (Using HDC Net) 0.0 0.0 13.0

- 22. Unit Capacity Factor (Using DER Net) 0.0 0.0 13.0

23. Unic Forced Outage Rate 99.7 99.9 64.5 i-i

24. ' Shutdowns Scheduled Over Next 6 !bnths (Type, Date, and Duration of Each): Shutdown to less than_

i 2% for valve repairs. 870610, 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />.

( ' 25. If' Shut Down at End of Report Period. Estimated Date of Startup: N/A I Achieved

26. Units in Test Status (Prior to Cornercial Operation): Forecast l-I IsITIAL CRITICALITY N/A N/A t ~

f INITIAL ELEC RICIIT N/A N/A ComCIAL OPERATIcx N/A N/A

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AVERAGE DAILY UNIT POWER LEVEL

- Docket N).~ 50-267 Unit Fort St. Vrain Unit No. 1 Date May 15, 1987 Completed By F. J. Novachek Telephone (303) 620-1007 Month APRIL DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net) (MWe-Net) 1 0.0 17 0.0 2 0.0 18 0.0 I

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

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13 0.0 2S 0.0 14 0.0 30 0.0*

15 ~0.0 31 N/A 16 0.0

• Generator on line but no net generation.

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UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO. 50-267 UNIT NAME Fort St. Vra in Unit No. 1-DATE May 15. 1987~

' COMPLETED BY Frank J. Novachek TELEPHONE (3031 620-1007 REPORT MONTH APRIL. 1987 i

METHOD OF l SHUTTING CAUSE AND CORRECTIVE ACTION I NO. DATE TYPE DURATION REASON DOWN LER # SYSTEM COMPONENT TO PREVENT RECURRENCE l REACTOR CODE CODE l 86-03 870401 F 127.0 hr D 1 N/A ZZ ZZZZZZ Envi ronmental Quellrication J

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' ZZ 777777 NRC restriction to less than 10 percent 87-01 870406 N/A 504.0 hr D N/A N/A 8'5.5 hr N/A N/A ZZ 777777 Rise to power 87-02 870427 N/A H I i i

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- REFUELING INFORMATION I -

l l l 1. Name of Facility i Fort St. Vrain Unit No. 1 l l l l l 2. Scheduled date for next l l l refueling shutdown. I November 1, 1988 l l l 1 l 3. Scheduled date for restart l January 1, 1989- 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 l l 1 l If answer is yes, what, in l ---------------- l l general, will these be? I [

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 viewed safety questions are l l l associated with the core reloadj [

l (Reference 10 CFR Section l l l 50.59)? I l ___ __ _ __

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l If no such review has taken l 1987 l l place, when is it scheduled? l l l l 1 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 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 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 s.-

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REFUELING INFORMATION (CONTINUED) l I I 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 has been requested or is I (approximately 500 HTGR elements).l l olanned, 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)-6331 l refueling that can be dis- 'I and DE-SC07-79I001370 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 6

• 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 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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Grubiicservice- ==

16805 WCR 19 1/2, Platteville, Colorado 80651 I

May 15, 1987 Fort St. Vrain Unit No. 1 P-87190 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 APRIL, 1987

REFERENCE:

Facility Operating License No. DPR-34

Dear Sir:

Enclosed, please find the Monthly Operations Report for the month of April, 1987.

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

Sincerely,i s

R. O. Williams, Jr.

Vice President, i Nuclear Operations l l

Enclosure cc: Mr. R. D. Martin, Regional Administrator, Region IV R0W:djm 7

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