ML20205H045

Monthly Operating Rept for Jul 1986

ML20205H045
Person / Time
Site:	Fort Saint Vrain
Issue date:	07/31/1986
From:	Gahm J, Novachek F PUBLIC SERVICE CO. OF COLORADO
To:	NRC OFFICE OF ADMINISTRATION (ADM), NRC OFFICE OF INSPECTION & ENFORCEMENT (IE)
References
P-86519, NUDOCS 8608190695
Download: ML20205H045 (7)

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PUBLIC SERVICE COMPANY OF COLORADO FORT ST. VRAIN NUCLEAR GENERATING STATION MONTHLY OPERATIONS REPORT NO. 150 j July,1986 l

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860819069S 860731 PDR ADOCK 05000267 1 R PDR g;o . l

e 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,1986. , l 1.0 NARRATIVE

SUMMARY

OF OPERATING EXPERIENCE AND MAJOR SAFETY ,

RELATED MAINTENANCE The reactor remained shutdown during the entire month of July for Environmental Qualification modifications. Environmental Qualification modifications on Loop II are complete except for testing. Modifications on Loop I will proceed when Loop II testing has been completed.

Three items were identified requiring reports to the Nuclear Regulatory Commission: LER 86-020, Re-analysis of Steam Generator Cooling with Firewater Following 90 Minute Loss of Forced Cooling, LER 86-021, Single Failure Points Identified in Firewater Cooling Flow Paths, and LER 86-022, Effects on 480V Essential Switch Gear Due to Loss of DC Bus 1.

Security improvements appear to be on schedule.

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 i

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De s.e: No. 50-267 U01: Fort St. Vrain Unit 1 Date August 8, 1986 ce=cleted By F. J. Novachek Telephone (303) 620-1007 M0:h July,1986 DAT A*2Pa0I DA**.T PO*w'ER LEVEL DAY AVEFaGI DA*LT P7a'EF.

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4 TSP-3 Attachment TSP-3C '

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• Page 1 of 1 UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO. 50-267 UNIT NAME Fort St. Vra i n Un i t No . 1 DATE Aueust 6. 1986

< COMPLETED BY Frank J. Novechek TELEPHONE f3031 620-1007 .

REPORT MONTH July. 1986 I 1 l MEIHOO OF 1 l 1 SHUTTING l CAUSE AND CORRECTIVE ACTION 1 -

) i I . 1 TO PREVENT RECURRENCE l 2

~l NO. l DATE . REASON DOWN LER # ISYSTEM COMPONENT TYPE l DURATION REACTOR CODE CODE 1 I I I I i 186-03 860701 F lI 744 hr D 1 N/A ZZ l ZZZZZZ Environmental Quellrication l l 1 l l modifications 1

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REFUELING INFORMATION I I I l 1. Name of Facility i Fort St. Vrain Unit No. 1 l l 1 l l 2. Scheduled date for next l l l refueling shutdown. I March 1, 1988 l l l l l 3. Scheduled date for restart l June 1, 1988 l l following refueling. I l l l l

14. Will refueling or resumption ofl No l l operation thereafter require a l l l technical specification change l l l

l or other license amendment? l l l l l 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 l associated with the core reload l l l (Reference 10 CFR Section l l l 50.59)? I l l l l l l If no such review has taken l 1986 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 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 i

l l l spent fuel storage pool. I b) O spent fuel elements l .

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REFUELING INFORMATION (CONTINUED)

I 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 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-SC07-791D01370 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 accommodate eight fuel 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 80651 August 14, 1986 Fort St. Vrain Unit No. 1 P-86519 Office of Inspection and Enforcement ATTN: Document Control Desk U. S. Nuclear Regulatory Commission Washington, D.C. 20555 Docket No. 50-267

SUBJECT:

Mont.hly Operations Report For July,1986

REFERENCE:

Facility Operating License No. DPR-34

Dear Sir:

Enclosed, please find the Monthly Operations Report for the month of July, 1986.

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

Sincerely, Y . Gahm

'/ J.

Manager, Nuclear Production

.. Fort St. Vrain Nuclear Generating Station Enclosure

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

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