ML20138C307

Monthly Operating Rept for Sept 1985

ML20138C307
Person / Time
Site:	Fort Saint Vrain
Issue date:	09/30/1985
From:	Gahm J, Novachek F PUBLIC SERVICE CO. OF COLORADO
To:	NRC OFFICE OF ADMINISTRATION (ADM), NRC OFFICE OF INSPECTION & ENFORCEMENT (IE)
References
P-85365, NUDOCS 8510220407
Download: ML20138C307 (9)

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0; PUBLIC SERVICE COMPANY OF COLORADO FORT ST. VRAIN NUCLEAR GENERATING STATION 1

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l MONTHLY OPERATIONS REPORT I

NO. 140 l

September, 1985 o

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i This report contains the highlights of. the Fort St. Vrain, Unit No. 1, activities operateu under the provisions of the Nuclear 4 Regulatory Commission Operating License DPR-34. This report is for the month of September, 1985.

1.0 NARRATIVE

SUMMARY

OF OPERATING EXPERIENCE AND MAJOR SAFETY

'RELATED MAINTENANCE Shutdown moisture removal continued.

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Condensate was placed on both economizer-evaporator-superheater sections of the steam generators September 11, 1985, isolated September 19, and reestablished on September 23, awaiting Nuclear Regulatory Commission approval to'startup.

Permission to startup to 8% power was received on September 30, 1985; criticality was attained at 2347 hours0.0272 days <br />0.652 hours <br />0.00388 weeks <br />8.930335e-4 months <br /> the same day.

Under the new interpretation of reporting requirements of 10CFR50.72, Non-Emergency Four Hour Reports were made to the Nuclear Regulatory Commission for Rod Withdrawal Prohibits received during start-up, training starts and low power operation.

O As part of the conditions for start-up release, revised procedures for manually establishing liner cooling, depressurizing, and inserting reserve shutdown were developed, and all operators received special training on -these revised procedures.

A two man -Nuclear Regulatory Commission Radiological Emergency Response Plan Audit Team vas on site during this period. Four of the five shift crews walked through a Nuclear Regulatory ,

Commission developed scenario simulating an offsite release with no outside assistance available due to inclement weather, receiving high marks from the Nuclear Regulatory Commission ~at the exit interview.

Alternate cooling method diesel / generator problems occurred while

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running the unit for freeze protection. Electricians, Maintenance, and Woodward Governor continued to troubleshoot.

This has been a hold for greater than 2% power ' operation through this period.

Region 34 control rods could not be powered in while running a ten inch rod drop surveillance. The Electricians cleaned the

, elay contacts and the rod: were successfully retested. This did i -not affect. control rod operability or scram capability.

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Appendix R procedure development was essentially completed this during period and Operator walkdown of the procedure continues.

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I.. 2.0 SINGLE -RELEASES OF RADIOACTIVITY OR RADIATION EXPOSURE IN EXCESS l OF 10% OF THE ALLOWABLE ANNUAL VALUE--

1 None .

3.0 INDICATION- 0F FAILED FUEL RESULTING FR0 IRRADIATED FUEL EXAMINATIONS None 4.0 MONTHLY OPERATING DATA REPORT Attached f

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• e At t ach man t-33 Issue 2 OPERATINC DATA REPORT DOCKET NO. 50-267 l DATE October 8, 1985 COMrtETED af Frank Novachek TELEPHONE (303) 785-2224

'i; OPERATING STATUS NOTES

1. Unit Name: Fort St. Vrain

2. Reporting Period: 850901 through 850930

3. Licensed Thermal Power (Wt): 842 i

4. Nameplate Rating (Cross We): 342

5. Design Electrical Rating (Net We): 330

6. Maximum Dependable Capacity (Cross We): 342 l 7. Maximum Dependable Capacity (Net We): 330

8. If Changes Occur in Capacity Ratings (Items Number 3 Through 7) Since Last Report, Give Reasons:

None t

9. Power Level To Which Restricted, If Any (Net Ws): 280 lo. Reasons for Restrictions, If Any: Per commitment to the NRC. lona term ooeration above 85% power pending completion of B-0 Startuo Testing.

f This Month Year to Date Cumulative

11. Hours in Reporting Pe'riod 720 6.551 54.186

12. Number of Hours Reactor Was Critical 0.2 67.9 27,219.3

13. Reactor Reserve Shutdown Hours 0.0 0.0 0.0

14. Hour. Generator On_t.ine 0.0 0.0 18,468

15. Unit Reserve Shutdown Hours 0.0 0.0 0.0

16. Cross Thermal Energy Generated (WH) 0.0 0.0 9.861.823.9

17. Cross Electrical Energy Generated (WH) 0.0 0.0 3.248.594

18. Net Electrical Energy Generated (WH) -3,065 -21,538 2.906.420

19. Unit Service Factor 0.0 0.0 33.7

20. Unit Availability Factor 0.0 0.0 33.7

21. Unit Capacity Factor (Using MDC Net) 0.0 0.0 16.1

22. Unit Capacity Factor (Using DER Net) 0.0 0.0 16.1

23. Unit Forced Outage Rate 100.0_ 100.0 55.3

24. Shutdewns Scheduled Over Next .6 Months (Type, Date, and Duration of Etch): None

25. If Shut Down at End of Report Period, Estimated Date of Startup: October 1. 1985

26. Units In Test Status (Prior to Commercial Operation): Forecast Achieved

IT:AI. CnITICAun N/A N/A I::rTIA:. ELEcn:C:n N/A N/A Co mERCIAL OPERATION N/A N/A L- - _ _ _ _ - - - - - - - - - - - - - - _- -

TSP-3 Att ach ment-3A AVERAGE DAILY UNIT POWER LEVEL lss ue 2 p

Docket No. 50-267 Unit Fort St. Vrain #1 Date October 8, 1985 Completed By Frank Novachek Telephone (303) 785-2224 bbath September, 1985 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (FMe-Net) (FMe-Ne t) 1 0.0 17 0.0 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 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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At t achmen t-3C Issue 2

• Page 1 of 1 UNIT SHUTDOWNS AND POWER REDUCTONS .

UNIT NAME Fnrt St_ Vrain #1 DATE Octo:er 8, 1985' COMPLETED BY Frank Novachek REPORT MONTH 5eptember, 1985 TELEPuCNE (303) 785-2224 METIl0D OF SIIUTTING DOWN SYSTEM COMPONENT N. DATE TYPE DURATION REASON REACTOR LER # CODE CODE CAUSE AND CORRECTIVE ACTION TV PREVENT RECURRENCE 85- 350724 F 719.8 G 3 50-267/85-012 AB XXXXXX Primary Coolant Cleanup 001 f

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REFUELING INFORMATION l 1 l l 1. Name of Facility l Fort St. Vrain Unit No. 1 l l .

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'l 2. Scheduled date for next l l l refueling shutdown. I April 1,1987 l l ..

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-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 l l 1

-l If answer is yes, what, in l ---------------- l l general, will these be? l l 1 .

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 a.re l l 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 1 -

l l l 5. 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 de sign or suppl ier, 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. I 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) 137 spent fuel elements l h _ _

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REFUELING INFORMATION (CONTINUED) 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 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. I i l l 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-SC07-79ID01370 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 00E.* 1 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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16305 WCR 19 1/2, Platteville, Colorado 80651 October 11, 1985 Fort St. Vrain Unit No. 1 P-85365 Office of Inspection and Enforcement ATTN: Document Control Desk U. S. Nuclear Regulatory Comn'ssion Washington, D.C. 20555 ,

Docket No. 50-267

SUBJECT:

Monthly Ope. rations Report For September, 1985

REFERENCE:

Facility Operating License No. DPR-34

Dear Sir:

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

Sincerely, l / J. W. Gahm l Manager, Nuclear Production Fort St. Vrain Nuclear l Generating Station Enclosure cc: Mr. John T. Collins JWG:djm h

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