ML20058H407

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Advises That Util Proceeding W/Certain Plant Closure Activities within Existing Licensee Authority
ML20058H407
Person / Time
Site: Fort Saint Vrain Xcel Energy icon.png
Issue date: 11/05/1990
From: Crawford A
PUBLIC SERVICE CO. OF COLORADO
To: Weiss S
Office of Nuclear Reactor Regulation
References
CON-#490-11206 P-90331, NUDOCS 9011150256
Download: ML20058H407 (4)


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P.O. Box 840

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Denver CO 80201 0840 -

W November 5,.1990 M

Fori St. Vrain A. Clegg Crawford y

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Vice P.esident yl P-90331

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.s U. S. Nuclear Regulatory Commission

- ATTN: Document Control Desk Washington _,;D.LC.

20555 ATTN: Mr.-Seymour H. Weiss. Director Non-Power Reactor, Decommissioning and g

iEnvironmental Project Directorate

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Docket No. 50-267 SUBJECTi PLANT CLOSURE ACTIVITIES s

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REFERENCES:

.1) NRC:. Memorandum and

Order, CLI-90-08,.

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~ October 17;.1990 4

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2) NRC; letter, %iss to Crawford, dated May 1, 1990 W

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', ' De~ar Mr. Weiss:

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_ Public Service Company

'of' Colorado (PSC) has' reviewed the guidance provided by :the. NRC in ) Reference :1:.regarding the-propos(d

' ! decommissioning. of the ShorehamLNuclear Power Sution.

Based on;the Ldecision ofuthe Comtrission.thato resumed 'opr ation need not be p;i *

' considered 1as an:Talternative;to" decommissioning,'PSC is proceeding, with certain 1plantM closure. activities'.that -are within -existing, t.i@ jg g'y licensee: authority.J

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n In [ Reference l',

the; NRC: stated.that a licensee: prepar'ng for GQ 2

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decommissioning must.1);conply.with the requirements of:its operating

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license fand,thefregulations appi,1 cable to whatever mode or condition

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,the : plant'might beini at 'a given time and 2) refrain from taking any W_ '

tactionst thatLwould.miterially and demon'strably affect the methrds or

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options:available for decommissioning or that would substantially l

S increaseJ the costs of decommissioning, prior.to NRC. approval of a d decommissioning, plan.

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ihel requirements ef1'the' Fort St. Vrain (FSV) Facility Operating

'LicenseF have."been ! modified to reflect the permanent-shutdown

,L' condition -of. ' the f plant.-

The -NPC modified our Facility Operating i

L. License Not 10PR-34 -via' Confirmatory Order, in Reference 2,-

to prohibit L taking ' the f FSV ~ reactor to criticality and to prohibit a

1 operating;the facil.ity:at any: power level. 'PSC'has implemented this s

10rdsri as /shown 'on th'e attached copies of page; 4 and 5 of the Fort-s

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St. Vrain Facility' Operating License.

The conflicting wording in f,L license: condition.4;tregarding Early Shutdown, has also been deleted.

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P-90331-

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November 5, 1990 A-n~

pursue plant closure activities that are within

- PSC intends' to existing licensee authority, including activities that do not:

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~ Require' a change.to the FSV Technical Specifications or Facility S

' Operating. License (asLshown on the attached pages),

Involve an-unreviewed safety question as defined in 10 CFR 50.59, cL, Limit.the' choice of reasonable decommissioning alternatives W

(i.e.,,SAFSTOR,DECON,.orENTOMB),or.

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.rf Substantially increase the costs of FSV decommissioning.:

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As-'previously stated in-various meetings and. correspondence, PSC does y

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f, not consider. resumed n'uclear' operation an option'for Fort St. Vrain.

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_PSC.will' fully; evaluate contemplated plant closure = activities, I

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Lincluding component removal-and disposal-activities for,the Region-

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-Constraint Devices -and Loop IL(!A':and 'B')_ helium circulators,-and 1

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we.i.ntend.to proceed with these activities in accordance with the cn M.,;

- provisions: of'710 CFRL50.59; Documented: safety evaluations for each

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of Lthese activities,
as swell as-other future'
4 plant closure and t

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component removal activities, iwill zbe available-for NRC review.

Plant closure' ' activities - that ' ' are not. within ' existing licensee

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!authortty will. be ; submitted for ; NRC '! approval, prior to their

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y, w m4 cPSC? Iconsiderst(that the. actions described above are fully in-k

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compliancewith:applicableiregulationsandjlicenserequirements.If

@4 you havetany questions about'the.information; presented herein,;please

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contact'Mr.M.H.(Holmestat1(303)"480L6960(

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o I E LVpryi ruly yours,.

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A.UleggCrawford

~Vice' President 4

N_uclear Operations q-t i

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Attachment

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.cc: Mr. G. L. Constable, Chief

_ Technical Support Section Division of Reactor Projects

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.'M Mr. J. B. Baird J

Senior Resident Inspector

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Fort St. Vrain J f.

Technical Specifications License Information Enclosure (1) to AEC Letter dated 12/21/73 Confirmatory Order - 5/1/90 Page 4 of 5 yy

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7' D.

This. license shall be deemed to contain and is subject to the conditions apecified in the following Commission regulations

'in -10 CFRM Chapter I:

Part 20, Section 30.34 of Part 30, t

Section 40;41 of Part 40, Sections 50.54 and 50.59 of Part 50, and the appropriate -sections of Parts 70.and 73; is subject to allsapplicable provisions of 'the Act and to the

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rules, regulations, and orders of the Commission now or
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'hereafter fin effect; and is subject to.the additional s

-c'onditions specifi.ed or: incorporated below.

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l(1) Maximum Power Level Y

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The licenseeLiis :prohib ded from taking the. Fort St.

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Vrain reactor to criticality vnd the facility.shall not j

be operated-at anyl power level.

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((2) Technical Specifications' M[!t

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_ TheliTechnical: Specifications contained in Appendices A-A (;"i and'Bkas(revisedthrough_AmendmentNo.77, are hereby

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=incorporat9dlin'the license.

The 1icensee shall operate' J,

'L Lthe!. facilityJ in

,accordance' with :the

. Technical' fg.,

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Specifications.

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!('3)) Physidal Proter. tion" C

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Thet-licensee? shall-fully implement land Fmaintain-in f

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'effect L all f prov'i si.on s t 'ofc ithe-, Commission-approved j

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pphysica Rsecurity,Lguard training and qualification ;and, l

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,n 1 w pursuantL toi provisions:ofithe~ Miscellaneous! Amendments m

safeguards contingency { plans' including amendments made

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andJSearch Requirements revisions';to 10 CFR 73.55 (51'FR9 4

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27817-- land L27822)' Land to the authority of 10 CFR 50.90 :

O T..and.L10llCFRj50'54(p).

xThe". plans,

?which

'contain 1

C ASafeguardsLInformation' protected unders10 CFR 73.21, are k M4

'I entitledf ' "For.t1 5t.. Vrain Security-. Plan',"

with M

W revisions. submitted? through July - 15,--1988;'" Fort St.

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,' O Vrain1 Guard: Training Land-Qualification Plan',"

with 4

M %:4',

y, "revis. ions submitted $through.iFebruary 27, 1987;- and " Fort "jM

-St.qVrain Safeguards! Contingency Plan,":.ith revisions 4

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@, M m i1 submitted through! February ~ 27,'1987. Changes made.in i

v.cordance with.t10-CFR'73';55 !shall, be' implemented in accMdance'withltheschedulesetforth.therein.

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'A Fort St. Vrain b :1c, f r Technical Specifications License Information ni

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Enclosure (1) to AEC 3_

PW Letter dated 12/21/73 6

Confirmatory Order - 5/1/9C q

Page 5 of 5

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- (5) Fire Protection i: +1 The ilicensee.shall implement and naintain in effect all 1 "-

provisions-ofcthe-approved fire-protection program as H

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' described :in. the' Final Safety Analysis Report for the.

facility'and as' approved in the SER' dated May 18, 1989 subject tolthetfollowing. provision:

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. The Llicensee. ma'y make changes to the' approved fire

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protection program without prior _ approval of the Commission 1onlyLif those
changes would not adversely c

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. affect,the' ability sto achieve and' maintain safe

..s uh tdowntin the. event of a-fire.

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This!_ license is} subject. to. all_ Federal,-State,-and local-n,

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standards imposed pursuant:to the requirements of theLFederal.

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4 c JWater? Pollution" Control; Act of '1972.'

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i 13MThis; license Lis. ef fective as;of!the date. of issuance Land shall

,l Lexpire'atmidnight,: Se'ptember?17,J2008.

w; FOR;THE ATOMIC ENERGY. COMMISSION "0RIGIN4LLSIGNED BY:"'

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A;'Giambusso, Deputy Director for li Reactor Projects' Directorate 1ofilicensing l

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~u Attach 6ents:

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App,endices"ALand B.

Technical' Specifications.

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y Date'of: Issuance: Decembe'rL21, 1973'

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