ML20082J007

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Monthly Operating Rept for Jul 1991 for Fort St Vrain,Unit 1
ML20082J007
Person / Time
Site: Fort Saint Vrain Xcel Energy icon.png
Issue date: 07/31/1991
From: Block M, Fuller C
PUBLIC SERVICE CO. OF COLORADO
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
P-91266, NUDOCS 9108270081
Download: ML20082J007 (8)


Text

{{#Wiki_filter:, . . _ . . . . -. - , - .. - .. .. . -. 16~ f , e Publ6c Service Public Service' c-- c-- P.o. Boa 840 Ottnv4t. Co 80201- 0B40 16805 WCR 19 1/2, Platteville, Colorado 80651 August 15, 1991 Fort St. Vrain Unit No. 1 P-91266

                                                                                                                     'I U. S. Nuclear Regulatory Commission ATTN: Document Control Desk                                                                           '
               -Washington, D.C. 20555 j

Docket No. 50-267

SUBJECT:

JULY, 1991, MONTHLY DEFUELING OPERATIONS REPORT

REFERENCE:

Facility Operating License Number DPR-34

Dear Sirs:

j Enclosed please find the Monthly Defueling Operations Report for the month of July,1991, submitted per the requirements of Fort St. Vrain Technical Specification AC 7.5.1.

                                                                                                                     ]

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

                 <{Wf (t Charles H. Fuller
               -Manager, Nuclear Production-Fort St. Vrain Nuclear Generating Station CHF:DW/bh Enclosure cc: Regional Administrator, Region IV Mr. J. B. Baird Senior Resident Inspector Fort St. Vrain 8
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4 i l-l- 1 -- PUBLIC SERVICE COMPANY OF COLORADO h - FORT ST. VRAIN NUCLEAR GENERATING STATION a. d- u ic MONTHLY DEFUELING OPERATIONS REPORT NO, 210 L July, 1991' I f

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l . . l l This report contains the highlights of the Fort St. Vrain, Unit No. 1, activities operated under the provisions of the Nuclear Regulatory Commission Operati'g License No. DPR-34. This report is for the month of July, 1991. 1.0 NARRATIVE

SUMMARY

OF OPERATING EXPERIENCE AND MAJOR SAFETY 1l[LXTED MAffit$ NANCE The reactor remained shutdown the entire month of July, 1991, following Public Service Company of Colorado's decision to end nuclear operation at Fort St. Vrain. Preparations for shipping spent fuel are proceeding. Construction of the Independent Spent Fuel Storage Installation (ISFSI) is proceeding. 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

OPERATING DATA REPORT D0tr.ET NO. 50-267 DATE August 15. 1991 COMPLETED BY M. L. lilock 1ELEPHONE (303).620:1313 OPER ATPG ST ATUS NOTE 5

1. Unit harne: Fo tt St. V nin, Unit No. I
2. Reporting Perica: 910701 through 910731
3. Licensed Thennal Power (MWt): 842 4 hameplete Rating (Gross MWe): 342
5. Design Electrical Rating (Net MWe): 330
6. Maximum Dependable Capacity (Gross MWe): 347
7. Maximum Decendable Capacity (Net MWe): 330
8. Changes Occur in Capacity Ratings (items Numoer 3 Througn 7) Since Last Report, Give Reasons:

Nono

9. Fo.er Level To Which Restrictea, If Any (Net Meie): 0,0
10. Reasons for Restrictions, If Any: Fort St. V r rii n censed nunicir oper.;trinn nrt An t u n t 'O. lor 9.

This Month Year To Date Cumulative

11. Hours In Reporting Period 744 5.087 106.43f
12. Numoer Of Hours Reactor Was Critical N/A_ N/A /i0.576.2_
13. Reactor ;eserve Shutdown Hours N/A_ N/A_ N/A 14, nours Generator On-Line N/A N/A 27.777.4
15. Unit Reserve Snutdown Hours N/A N/A N/A
16. Gross Thertnal Energy Generated (MWH) N/A N/A 14.450.651.2
17. Gross Electrical Energy Generated (MWH) N /2L N/A /. 816.834.0
18. Net Electrical Energy Generated (MWH) -1,539 4.240.532
19. Unit Serytce Factor N/A N/A N /2L
20. Lnit Availability Factor N/n N/A N/A
21. Unit Capacity f actor (Using MDC Net) M/A N/A N/A
22. Unit Cacacity factor (Using DER Net) N/A N/A N/A 23, Unit Forced Outage Rate M/A M/A M/A
24. Shutdowns Scheduled Over Next 6 Months (Type, Date, and Duration of Each): Fort St. Vrain ceased nuclonr nnornrion on Auggnt 29. 1989.
25. If Shut Down At End Of Report Period. Estimated Date Of Startup: N/A Forecast Achieved
26. ; nits In test Status (Prior To Commercial Coeration):

INITIAL CRITICAlliY N/A N/A INITIAL ELECTRICITY N/A N/A COMMERCIAL OPERAtl0N N/A N/A i l

AVERAGE DAILY UNIT POWER LEVEL Docket No. 50-267 Unit Fort St. Vrain Unit No. 1 Date Au Completed By [ L. gust Block 15 J 991 Telephone {lUl[I26;i313 Month JULY _ 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 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 0.0 16 0.0 Nuclear Operations at Fort St. Vrain were terminated on August 29, 1989.

UNtT SHUTDOWNS AND POh'ER REDUCT IONS

  • DOCKET NO. 50-267 _

UNIT NAME Fort St. Vra in Unit No d DATE Auqust 15. 1991 COMPLETED BY M. L. f3 f ock TELEFHONE [JplL610-TJ13 0 REPORT MONTH LULY. 1991 i i i i 1 I i i 1 '!PETHou Ori j 1 j j CAUSE AND CORRECTIVE ACTION i i i i ISHUTTING l I i 1 LER # l SYSTEM 8 COMPONENT l TO PREVENT RECURRENCE I i NO. I DATE l TYPE! DURATION 1 REASCN I l DO'WN l REACTOR 1 BCODE_ lCODE I i l l  ! I I i l i i i  ! 6 l 1 N/A 1 N/A I N/A l Nuclea r Operations were terminated on I 189-091 910701 i F I! 744.0 1 F i 1 1 j i i l August 29. 1989, see LER 89-018. I l 1 ( i I I ( i 1 I I  ! I I 1 1 I I I I i  !  ! i I I i l I I I I I i i i i 1 1 I i 1 I i I I I I I I I i i l i I i 1 1 I I i 1 i i l I I I I I i i i 1 i i i l I i i i i i i i i I I I s 1 I i ) 1 I I I I i  !  ! I i  ! i  ! I I  !  ! i I l I i  ! I

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         .                                                     Docket No. 50-267 Unit Fort St. Vrain Unit No, 1 Date August 15, 1991 i

l CompletedTelephone By [M. L. Block @l_6_20-1313 REFUELING INFORMATION l I i l 1. Name of Facility __] Fort St. Vrain Unit No. 1 l l 1 l l 2. Scheduled date for next l None, no further refueling at l l refueling shutdown. I FSV is expected, j l I l 1 3. Scheduled date for restart 1 N/A l l following refueling. l l l l I l 4. Will refueling or resumption ofl N/A 1 I operation thereafter require a l l l technical specification change l l 1 or other license amendment? [ l l l I l If answer is yes, what, in l ---------------- l l general, will these be? I l l l l l If answer is no, has the reload l l l fuel design and core configura-l i i tion been reviewed by your i l I Plant Safety Review Committee l N/A l l to determine whether any unre- l l l viewed safety questions are { i l associated with the core reloadj l l (Reference 10 CFR Section 1 i 1 50.59)? I i i 1 1 1 If no such review has taken l N/A 1 l place, when is it scheduled? I ___

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I I l l 5, Scheduled date(s) for submit- l l l ting proposed licensing action 1 ---------------- l l and supporting information. l l l l l 1 6. Important licensing considera- l l l tions associated with refuel- l l 1 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. I _ l 1 I I l 7. The number of fuel assemblies l l 1 (a) in the core and (b) in the I a) 1024 HTGR fuel elements l l spent fuel storage pool. l td 458 HTGR fuel elements l

i

                                              . ._                                      REFUELING'INFORMATION(CONTINUED)                            [

I 1 . I i

                                                   - l 8. The present licensed spent fuell Current capacity-is limited in                    -l    .[

l . pool storage capacity and the l size to about one-third of core, l -{ l size of any increase in l 504 HTGR elements. Construction l  ;

                                                   -l         licensed storage capacity that I of an Independent Spent Fuel-                  l    'i l        has been requested or is                 l Storage Installation (ISFSI)         l
l. planned, in number of fuel ] with a capacity of 1620 FSV HTGR l _
                                                   -l         assemblies.                       _      l_ elements is proceeding
  • _l l l 1 I l 9. The projected date of the last l No further refueling is  ! .

l refueling that can be dis- l anticipated at Fort St. Vrain. l -i

                                                   - l .. charged to the spent fuel pool l                                                l     ;
l assuming the present licensed l l l l capacity. l l j
                                                          .The Independent Spent Fuel Storage Installation (ISFSI) will be                          f capable of storing the entire FSV core.(1482 HTGR fuel elements) with                    !

storage space for an additional 138 HTGR fuel elements.  !

                                                     **    Under Agreements AT(04-3)-633 and DE-SC07-791001370 between Public                       l Service Company-of Colorado, General Atomic Company, and DOE, spent                      i fuel discharged during the defueling process will be stored by DOE at                    !

the, Idaho Chemical Processing Plant. The storage capacity is-  ! presently limited to eight fuel segments. It is estimated that the  ! eighth fuel segment will be discharged in 1992. . Discussions  ! concerning the disposition of ninth fuel segment are in progress with .l DOE. Nuclear Operations at Fort St. Vrain were terminated August 29, -} 1989. i t

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