ML19332F983

Summarizes 891130 Meeting W/Util Re Util Planned Change in Licensed Operator Requalification Training Program During Defueling & Decommissioning Activities.Attendance List & Handout Encl

ML19332F983
Person / Time
Site:	Fort Saint Vrain
Issue date:	12/12/1989
From:	Collins S NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
To:	Crawford A PUBLIC SERVICE CO. OF COLORADO
References
NUDOCS 8912200002
Download: ML19332F983 (8)

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In' Reply ReferrTo:

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Docket: - '. 50-267f r,

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~Public Service Company of__ Colorado

• ATTN: 'A.-Clegg Crawford,.Vice President a*

Nuclear Operations 4

P.O. Box 840

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. Denver, Colorado - 80201-0840 '

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m Gentlemen:

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SUBJECT:

PRESENTATION ON' LICENSED OPERATOR REQUALIFICATION TR'AINING-DURINGt f

DEFUELING AND DECOMMISSIONING g

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'On Thursda 30,:1989, representatives ofLPublic Service Company of

-Colorado (y,NovemberPSC). met with Region:IV staff to'discussiplanned changes in "o

licensedLoperator requalification training program during-defueling and

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decommissioning activities at the Fort St. Vrain Nuclear Generating.

~ Station ~(FSV). The attendees-at this meetingfare. listed in Enclosure 1.

The.

' material presented byJPSC11s attached as

Enclosure:

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- During the meeting, 'it was noted that.other facilities that have faced long-term activities not involving l power operatinn may be a good information source for J

PSC?when planning futurc~ changes. 'An example is Three Mile Island Unit 2.

j lAlso attendees agreed,that. modifications to the current training program will

-be in accordance with the accredited, systems approach based methodology - If accreditation.is lost then it could require that PSC submit a< detailed requali-f16ation program for-revi_ew and approval by the NRCb j

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LFinally, i.t was noted that the nature of,the program necessary is being

>partia11y'controllet by' decisions.about the decommissioning path adopted.

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isLexpected that this will be further resolved in early 1990..

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If you have;any questions,' please feel free to contact J. L. Pellet, Chief,

- Operator _ Licensing Section, at (817)860-8159.

1 Sincerely, j

Odginalsionod ay:-

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Thomas P.Gwyre Samuel J. Collins, Director Division of Reactor Projects 7

Enclosures:

(asstated)

• RIV:C:0LS 4D:DRS

DRP JLPellet/lb LJCallan SJCollins 112/05/89 12/06/89

/S./f/89

• Previously concurred =

891'200002 891212 2

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PubliciserviceCompanyofColorado 1 1

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>cc w/ enclosures:

'Public Service Company of Co%rado e

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, ATTN:'<D.'W. Warembourg..Ma-ager Nuclear Engineering D1 vision:

1 P.O. Box 840 c.

Denver. Colorado 80201-0840-GA' International Services Corporetion Fort St. Vrain~ Services.

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' ATTN:- David Alberstein, Manager.

P.O. Box 85608 N

San Diego. California 92138

-j Public Service Company of Colorado

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ATTH: Charles H. Fuller. Manager i

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. Nucleir Production and Station i

Manager 3

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16805 Weld County Road;19-1/2

'Platteville, Colorado 80651 ~

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PublicServiceCdmpanyof' Colorado ATTN:- H. LL Breys Manager. Nuclear Licensing.and Resource j; g, Mahagement Division q

p P.O. Box 840 -

Denver. Colorado '80201-0840 i

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'Public' Service' Company of Colorado ATTN:

P.' F. Tomlinson, Manager j

m; l f Ouality Assurance Division s

16805 W1d County Road 19-1/2 e,

Platteville. Colorado 80651-Public Service Company of Colorado-

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L ATTN:

D. D. Hock President and l.

Chief Executive Officer m

P 05 Box 840-

. Denver. Colorado' 80201-0840 O

lL Fublic Service Company of Colorado f

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~ ATTN:

Lammitment Control Program Coordinator

2420 W.' 26th Ave. Suite 100-D Denver Colorado 80211

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l Public Service Company of Colorado j

.Y; gi relley, Standfield & 0'Donnell i

ATTN:. Mr. J. K. Tarpey Public Service Company Building Room 900 550 15th Street. -

Denver, Colorado 80202:

Chairman t

l Board of County Comissioners i

e1 'of Weld County,, Colorado

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'Greeley, Colorado 80631

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Regional Representative.

Radiation Programs..

1 Environmental Protection Agency

c. o 1 Denver Place 999 18th. Street. Suite 1300.

Denver, Colorado 80202-2413 Department of Health AT7't Robert M. Ouillen, Director

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Radiation Control Division 4210 East lith Avenue Denver, Colorado 80220 Colorado Public btilities Comission 1

i ATTN:

Ralph Teague, P.E.'

1580 Logan Street OLI Denver, Colorado; 80203-U.S. Nuclear Regulatory Comission I

I-ATTN:

Senior Resident Inspector '

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.P.O. Box 640 l

Platteville, Colorado 80651

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U.S. Nuclear Regulatory Commission ATTN:

Regional Admin _istrator, Region IV 611 Ryan Plaza Drive, Suite 1000 y

Arlington.. Texas 76011 bec to DMB.(IE42) 7 bec distrib. by RIV:

o R. D.: Martin Resident Inspector L,

SectionChief(DRP/B)

ProjectEngineer(DRP/B) l DRSS-FRPS J. L. Pellet MIS System E. Himes-L

_ K. Heitner, NRR Project Manager (MS:

13-D-18)

L RIV File DRS (Reading File)

N DRP LFMB - Facilities Section L

L. Miller, TTC l

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J MEETING ON OPERATOR LICENSING REOUALIFICATION ATTENDANCE LIST l

November 30. 1989

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Public Service Company i

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. F. J. Borst

-Ken Einic David C. Goss M. E. Deniston Nuclear Regulatory Commission

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J. L. Pellet J. E. Whittemore T. F. Westerman

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i Nuclear Regulatory Commission, OLB T. L. Szymanski-

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FORT ST. VRAIN F;

LICENSE REOUALIFICATION TRAINING-DEFUELING 4

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,w, FORT ST. VRAIN LICENSE REOUALIFICATION TRAINING DEFUELING On August 29, 1989, Public Service Company Exectaive Management announced that Fort St. Vrain (FSV) would cease operation and start defueling and decommissioning.

The licensed operator's job has changed significantly because of this announcement of the End-of-Operations. Recognizing this change in job scope, the FSV Nuclear Training Department has begun the process to determine the reactor operator's (RO) job scope and adjust the license requalification training i

program accordingly. This will be accomplished by following the Training Administrative Procedures at FSV, which are based on a systems approach to r

training. The following items outline the response by FSV Training Department

-to the' change to defueling at FSV:

VERIFICATION OF INITIAL TASK LIST On October 26, a meeting was attended by training instructors and two plant operators-(an'R0 and a senior reactor operator (SRO)). The purpose of the meeting was to review the complete initial task list and deselect n

the tasks relating to power operation.

JOB SURVEY The revised task list was compiled and then distributed to each licensed operator during the second rotation of the licensed requalification program. The operators filled out the job survey and turned it in for data entry..

TASK SELECTION When data entry is completed, a task selection committee will meet to select the appropriate tasks based upon the information supplied by the operators. This is scheduled for the first week in December. The defueling licensed requalification program will be based upon the resulting task list.

TASK ANALYSIS Some task analysis may be needed for any new tasks that are identified by the above process. We expect to be able to use most of the existing analysis in tae program. As new procedures are developed for defueling, we will continue to adjust the task analysis by using the training development request (TDR) process.

. CURRICULUM DESIGN A new training setting matrix will be the result of the above process.

This matrix will be titled " Licensed Requalification-Defueling," and will contain the selected tasks that the licensed operators will receive training on during defueling. Training instructors will review all learning objectives and tests, and ad',ust these as necessary.

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i L Based on the above process, it is expected that many tasks will no longer require training. These deselected tasks will be dropped from the training program, but will remain.in the files for future reference.

Examples of these

~ deselected tasks would be related to the following:

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Reactor s/u and s/d Turbine ' generator s/u and s/d Reactivity manipulations (ones based on power operation)

' :1 Any tasks related to plant systems which are removed from service permanently Tasks relating to procedures (A0Ps, S0ps, E0Ps, etc..) which are no 1

longer applicable The transition of the license requalification program from one based on j

requirements for an operating plant to one based on requirements for a plant in defueling conditions must be planned carefully. The following is an L

outline of topics to be covered-in the 1989-90 License Requalification Program 1

at FSV.

I 1.

Maintenance of Safety Limit 3.1 (Fuel Particle Integrity)

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1 A.

Core Thermal Power 1.

Measurement L

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Review of Theory and Operation of Nuclear l

Instrumentation 1

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Core Configuration Changes l

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Shutdown Physics l

b.

Effects of Dumy Blocks l

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Spent Fuel Removal Operations

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Technical Specifications B.

Core Helium Flow Rates l

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Measurement a.

Circulator Inlet b.

Average Core Outlet Temperature 2.

Circulator l

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Available Flowpaths i

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Technical Specifications l

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t p-II. Control of Radioactive Materials Onsite J

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PCRV Integrity l

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PCRV Cooling l

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Penetrations 3.

Defueling L

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Techncial Specifications

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n B.

. Reactor Building Integrity 1.

Reactor Building HVAC 2.

Reactor Plant Exheust System 3.

Technical Specifications C.

Fuel Handling Related Systems s

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General Radiological Concerns 1.

Documentation 2.

Radiation Limits 3.

Conteinment Methodologies' III. Emergency Preparedness

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A.

Radiological Emergency Response Plan B.

Emergency Operating Procedures a

Since defueling will generate new procedures and philosophies, these will also be incorporated into the license requalification program as they are needed.

The information presented in subsequent requal years (90-91 and 91-92) will a

l' depend lupon task analysis and plant conditions, but will always be based on a i

systems approach to operator training. There are license training instructors whom are presently involved in several defueling topics of interest such as:

Lthe defeuling safety analysis, administrative defueling procedure planning.

and the fire protection plan.. This information is presented to the licensed L

operators during requal in order to keep them informed of all aspects of defueling that are related to their job.

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'The nuclear training department at FSV will continue to provide quality L'

. training for licensed R0 and licensed SR0' individuals to maintain currency of l

their NRC license in accordance with 10 CFR 55.

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