ML20128K293

Monthly Operating Rept for June 1985

ML20128K293
Person / Time
Site:	Fort Saint Vrain
Issue date:	06/30/1985
From:	Gahm J, Novachek F PUBLIC SERVICE CO. OF COLORADO
To:	NRC OFFICE OF ADMINISTRATION (ADM), NRC OFFICE OF INSPECTION & ENFORCEMENT (IE)
References
P-85240, NUDOCS 8507240085
Download: ML20128K293 (9)

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

1 4 MONTHLY OPERATIONS REPORT NO. 137 June, 1985

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N 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 June,1985.

1.0 NARRATIVE

SUMMARY

OF OPERATING EXPERIENCE AND MAJOR SAFETY RELATED MAINTENANCE Helium Circulator "1C" was pulled, and new internals were installed. Problems were experienced with the new bolts, but the problems were resolved, and the circulator was reinstalled.

All major valve work was completed with the exception of HV-2224, HV-2251 and HV-31119.

Vacuum was established on June 30, 1985. On June 18, 1985, the annual Radiological Emergency Response Plan exercise was conducted. Official results have not yet been received from the

. Nuclear Regulatory Commission.

All control red drive work has been completed including testing.

The CR0 secondary cover plates are on. All non-essential

, . equipment has been removed from the Fuel Deck.

t-The electro hydraulic control system work was completed. The system has been flushed and returned to service. All hydraulic valves associated with this system have been calibrated and flushed.

Numerous problems were experienced when returning the recirculators to service after modification work. Results personnel have found the cause of the problem, which is being repaired.

Procedures for interim measurements called for due to Appendix R are in the process of being written and will be implemented prior to startup.

Operations continued training on shift for the new control rod drive operability Technical Specifications and the Four Minute Steam Pipe Rupture (environmental qualification) issue.

Proposals to rewrite the System Operating Procedures. were received, and a contract was awarded. This work should begin on August 1, 1985 and be completed by December 31, 1985.

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2.0 SINGLE RELEASES OF RADIOACTIVITY OR RADIATION EXPOSURE IN EXCESS OF 10% OF THE ALLOWA8LE ANNUAL VALUE None 1 3.0 INDICATION OF FAILED FUEL RESULTING FROM IRRADIATED FUEL EXAMINATIONS None 4.0 MONTHLY OPERATING DATA REPORT Attached i

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_Orru m e CAn M OET DOCKET NO. 50-267 nan July 8, 1985 co m .z n o :T Frank Novachek m zrnour (303) 785-2224 OPERATUc $!Atts son $

2, e,te 3,,, Fort St. Vrain .

2. Reportins reriod: 850601 through 850630

3. uceu.c Thermal roar out): 842 4 s apiste Ratins (cross we): 342

5. omisa traetrical Racins olet me): 330

6. ww-- Dependable capacity (crose we): 342

7. me-- nopendable capacity met we): 330

s. If Changes occur in capacity Retinse (Items Number 3 Throush 7) Since last Report, cive Reasons:

9. rower Level To Wieh Restricted, if Any Olet me): 280

10. amm ons for mostrictions, it any: Per commitment to NRC, long term operation above 85% power pending completion of 80 startup testing.

This Month Year to Date Cumistive n . nours in neporttas Peri g 720 4,343 52,608 27,151.4

12. zumber or nours seactor ves crisie.1 0.0 0.0 ,

-13. R = eter Reserve Shutdown Bour. 0.0 0.0 0.0

14. nours cenerator on-u.e 0.0 0.0 18,468

15. unit Resern Shutdown Ecurs ___

0.0 0.0 0.0

16. cross Thermal Enersy Generated (w E) 0.0 0.0 9,861,714.1

17. cross Electrical Energy cenerated Oeft) 0.0 0.0 3,248,594 is. set nectrical meerer cenerated OsrE) -2,035 -12,282 2,915,676

19. unit S'ervice ractor 0.0 0.0 35.1

20. unit Avanabuity raetor 0.0 0.0 35.1

21. mit capacity rector (usins une me) 0.0 0.0 16.8

22. mit cap. city rector (usins arm mt) 0.0 0.0 16.8

23. mit rareed outase mate 100.0 100.0 52.7

24. Shutdowns Scheduled Over Best 6 Months (Type, Date, and Duration of Each): 850701 through 850801, 744 hours0.00861 days <br />0.207 hours <br />0.00123 weeks <br />2.83092e-4 months <br />

25. If Shut navn at zad or neport retted. Estimated once or Startup: Auoust 1. 1985 4

26. units In Test Status (Prior to commercial Operation): rorecast Achieved immAL CHUCAun N/A N/A mTuL zucmcm N/A N/A comrRcuL ortnATras N/A N/A

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. Attcchment-3A AVERAGE DAILY UNIT POWER LEVEL Icaue 2

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Docket No. 50-267 Unit Fort St. Vrain Date July 8, 1985 l l

Completed By Frank Novachek i i Telephone (303) 785-2224

& nth June, 1985 .

DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (We-Net) (We-Nec) 1 0.0 17 0.0 2 '0.0 _

18 0.0 .

3 0.0 19 0.0 4 0.0 20 0.0 0.0 21 0.0

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..-- 0.0 22 - . _ .0.0 . . _ . .. _ . . _ _ _ _ _ _

7 0.0 23 0.0

. & -- - - 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 _ _ _ o,0 30 0.0

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15 0.0 31 N/A

_ _ 16 0.0 l____.

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• Generator on line but no not generation.

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!  !  ; ... _50-267 .

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, l uni? Nans Fort St. Vrain t

. I DAT: July 8.1985 -

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'-  ! C0eri.rren of Frank Novachek I i

, nurenT unwrN June, 1985 tai.ErNON: (303) 785-2224  !

i DE1 HOD OF j ii SNUTTINC Donal SYSTEn C0090NENT 4

.} 10 0 . DATE TTFE IIURATION REA5011 FEACTOR 125 f CODE (DDE CAUSE AND CORRECTIVE ACTION 10 rREVENT RECURRENCE

i 84-006 840601 F 720 A 3 50-267/84-008 AA JC Control Rod Refurbishment and .

.:' 50-267/85-002 AB BLO Circulator Bolting Changeout ll '

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REFUELING INFORMATION

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i l l 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. l January 1, 1987 l l l l l 3. Scheduled date for restart l February 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 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 I

n. 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 .. .

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l ting proposed licensing action l ---------------- l l and supporting information. l l l l l L6. . Important licensing considera- l '

l tions associated with refuel- l l l ing, e.g., new or different 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

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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 e

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REFUELING INFORMATION (CONTINUED) i -

1 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 l (approximately 500 HTGR elements).l l planned, in number of fuel l No change is planned. l l assemblies. l l 1 1 I l 9. The projected date of the last i 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. I Company, and DOE.* 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 evidently been sized to accomodate eight fuel . segments. It is estimated that the eighth fuel segment will be discharged in 1992.

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O PublicService ... . .

Company of Colorado 16805 WCR 19 1/2, Platteville, Colorado 80651 July 12, 1985 Fort St. Vrain Unit No. 1 P-85240 Office of Inspection and Enfo-cement ATTN: Document Control Desk U. S. Nuclear Regulatory Commission Washington, D.C. 20555 Docket No. 50-267

SUBJECT:

Monthly Operations Report For June,1985

REFERENCE:

Facility Operating License No. DPR-34

Dear Sir:

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

Sincerely,

/ J. W. Gahm Manager, Nuclear Production Fort St. Vrain Nuclear Generating Station JWG:dr Enclosure cc: Mr. John T. Collins d ,

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