ML20210S126

Issue 2 to Training Procedure - Licensed Operator Requalification

ML20210S126
Person / Time
Site:	Fort Saint Vrain
Issue date:	02/12/1987
From:	Willford S PUBLIC SERVICE CO. OF COLORADO
To:
Shared Package
ML20210S100	List: ML20210S096 ML20210S126 ML20210S143
References
TAC-64747, TP-LR, TP-LR-I02, TP-LR-I2, NUDOCS 8702170567
Download: ML20210S126 (34)

Text

TP-LR Issue 2 0SerVICO*

Public FORT ST. VRAIN NUCLEAR GENERATING STATION Page 1 of 30 PUBLIC SERVICE COMPANY OF COLORADO TITLE: TRAINING PROCEDURE - LICENSED GPERATOR REQUALIFICATION RESPONSIBLE FOR

[G d b UT!iORIZED Oc EF TlVE g[iaw EDRC 711 FEB - 51987 TE UMBER (S) bl v

FORMi01372 22 3642

TP R Enclosura 2 Issue 2

@\\/v/ ServlC9" Public FORT ST VRAIN NUCLEAR GENERATING STATION Page 2 of 30 Y

PUBUC SERVICE COMPANY OF COLORADO TABLE OF CONTENTS Page 1.0 PURPOSE....................................................... 3 2.0 APPLICABILITY................................................. 3 3.0 GENERAL REQUIREMENTS...........................................

3 4.0 LICENSED OPERATOR REQUALIFICATION COURSE.......................

5-

5.0 REFERENCES

15 6.0 ATTACHMENTS.................................................. 15 7.0 COMMITMENTS.................................................. 16 t

l FORM (D)372 22-3643

TP-LR Issue 2 j

) PUD llC.

FORT ST. VRAIN NUCLEAR GENERATING STATION Page 3 of 30 D/ SGIVlC9'

-PUBLIC SERVICE COMPANY OF COLORADO 1.0 PURPOSE l

• 1. • 7.2*#*

To make training available for Licensed Reactor Operator and Licensed Senior Reactor Operator individuals M l

maintain currency of their NRC license in accordance with l

10 CRF 55 Appendix A.

2.0 APPLICABILITY This training procedure applies to all personnel who hold an NRC Reactor Operator or Senior Reactor Operator's license.

3.0 GENERAL REQUIREMENTS 3.1 Responsibilities l

3.1.1

• 1. • 7.3*#*

The Supervisor of Operator Training is responsible for the supervision and administration of the Licensed Operator Requalification Program.

Training records will be maintained in accordance l

with Training Management Procedure (TMP) 1.2 as l

required by Section 5, Appendix A of 10 CFR Part l

55.

3.1.2 The Training Instructors so designated by the Supervisor of Operator Training in accordance with TMP 1.4 shall be responsible for implementation, coordination, and documentation of the Licensed Operator Requalification Program.

3.1.3 The Departmental Supervisor of the trainee shall allocate sufficient time for completion of the training program.

3.1.4 The trainee is responsible for the completion of assigned course / text material in the allotted time interval.

3.2 Experience Requirements 3.2.1 There are no experience requirements for the Licensed Operator Requalification Program.

3.3 Education Requirements 3.3.1 High School diploma or GED Certificate.

FORM (on372 22-3643

TP-LR Enclosura 2 Issue 2 (N Public FORT ST.- VRAIN NUCLEAR GENERATING STATION Page 4 of 30

) $9fVIC98' PUBLIC SERVICE COMPANY OF COLORADO 3.4 Training Requirements 3.4.1 All personnel will have had to satisfactorily complete either the Reactor Operator training program or the Senior Reactor Operator training program and currently' hold an NRC Reactor Operator or Senior Reactor Operator license.

l 3.5

• 1. • 7.4*#*

Waiver Requirements 3.5.1 Instructors will be excused from those lectures, quizzes, and examinations which they have prepared, reviewed or presented.

l 3.5.2 Individuals who conduct operating / oral I

examinations shall be excused from taking said l

examinations.

l 3.5.3 Individuals who review the annual requalification l

written and oral examination shall be excused from l

taking said examinations providing an oral l

evaluation is conducted every two years.

l 3.5.4 Instructor involvement in preparation, review l

and/or conduct of the annual written and oral l

examinations shall be rotated so that each l

instructor will be required to take a written and I

an oral examination during each two year period.

l The written and oral examinations need not be l

taken during the same requalification year.

3.6 Instructor Qualification 3.6.1 The instructors so designated by the Supervisor of Operator Training shall meet the instructional skills qualifications as defined by the TP-TI, Training Procedure-Training Instructor.

3.6.2

• 1. • 7.1*#*

The instructors so designated by the Supervisor of Operator Training shall possess a current NRC Senior Reactor Operator License or a current NRC Instructor Certification.

l FORM (D)372 22 3643 i

T P -i.R Issue 2

[ \\ Public -

FORT ST. VRAIN NUCLEAR GENERATING STATION Page 5 of 30

,D ServlC9' 1

PUBUC SERVICE COMPANY OF COLORADO l

3.6.3 The instructors so designated by the Supervisor of l

Operator Training to teach Licensed Operator l

Requalification should stand one (1) eight (8) l hour shift per month as a licensed operator in l

order to maintain their technical proficiency.

l Guest lecture instructors are exempt from this I

requirement.

4.0 LICENSED OPERATOR REQUALIFICATION COURSE 4.1 Length of Course 4.1.1 The requalification program will be conducted on a two (2) year cycle. Each requalification cycle will be divided into two parts: the first designated requalification year one (1) and the last designated requalification year two (2).

4.1.2 Each requalification cycle will commence on June 1 of each year and conclude on May 31 of the following year.

4.1.3 The classroom / lab portion of the Licensed Operator Requalification Program will commence the first week after Labor Day and end May 31 of the following year. Normally the classroom / lab portion will be on a six (6) week rotating basis with the exception of June, July, and August (due to vacation scheduling).

4.1.4 The classroom / lab portion of requalification training normally consists of 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> of formal lectures in either the classroom or lab and two (2) hours devoted to plant tours or study time.

1)

The classroom / lab will be of an estimated length of eighty (80) instructional hours each yearly cycle but in no case less than sixty (60) hours per yearly cycle.

ii)

The Licensed Requalification Program instructional hour may consist of any of the following activities:

lectures, seminars, discussions, problem-solving sessions, quizzes, examinations, drills, laboratory exercises, films, videotapes, and individual study.

FORM (D)372 22 3643 1

TP-LR Encicsure 2 Issue 2 P. Public FORT ST. VRAIN NUCLEAR GENERATING STATION Page 6 of 30 k

SerViCO*

- PUBUC SERVICE COMPANY OF COLORADO 4.1.5 Operations Seminars shall be utilized during the classroom / laboratory portion to review LER's, 01AG material, and any significant information so that each licensed operator and senior operator is cognizant of facility design changes, procedure changes, and facility license changes.

4.1.6 On shift review In order to ensure that any procedural changes, Technical Specifications changes, plant modifications, and LER's which take place during those months when operations seminars are not held, on-shift review of the material may be held.

l NOTE:

• 1. • 7.5*#*

Timely review of changes to facility l

design, procedure or license shall be accomplished l

in accordance with SOAP-4, Plant Operations Shift l

Turnover Procedure.

4.2 Course Content The Licensed Operator Requalification Training Program shall consist of the following but will not be limited to the following:

4.2.1 Classroom a.

Principles and theory of nuclear power plant operations b.

Thermodynamics, heat transfer, and fluid flow c.

Plant systems design (including safety and emergency systems) 1)

Plant protective systems 11)

Engineered safety systems i

I FORMtD)372 22 3643

TP-LR Issue 2 i

]'s Public FORT ST. VRAIN NUCLEAR GENERATING STATION Page 7 of 30

)SerVICO' PUBUC SERVICE COMPANY OF COLORADO d.

Instruments and controls e.

Procedures 1)

Normal 11)

Abnormal l

111) Emergency iv)

Administrative l

NOTE: All abnormal and emergency l

procedures shall be reviewed on a l

two year cycle.

f.

Radiological control g.

Technical Specification - all technical specifications will be covered on a two-year cycle h.

Topics identified by a Training Needs Survey, Form 0 - 20 l

1.

Mitigating Core Damage l

j.

Mitigation of Accidents l

NOTE:

Station Manager is also required to meet l

this commitment.

l k.

• 1. • 7.10*#*

Applicable portions of l

Title 10, Chapter 1, Code of Federal l

Regulations l

4.2.2

• 1. • 7.6*#*

Laboratory / Task Training l

4.2.2.1 Over the two year requalification l

period, all licensed individuals shall l

be evaluated on the performance of l

manipulations listed in Step 4.2.3.

l Tasks must be performed or simulated by l

walkthrough with a member of the l

Training Staff or qualified individuals l

as defined by TP-TI.

FoRMID)372 22 3643

TF-LR.

Enclosura 2 Issue 2

("N Public FORT ST. VRAIN NUCLEAR GENERATING STATION Page 8 of 30 hService*

PUBLIC SERVICE COMPANY OF COLORADO l

4.2.2.2 If an individual simulates a task by l

walkthrough, performance of the task i

will be evaluated by use of the Job l

Performance Measure (JPM) for the l

specific task. Completion of the l

simulated tasks shall be documented on a l

Reactor Manipulations Sheet (From 0-11).

l 4.2.2.3 If an individual has actually performed l

or supervised the performance of a task l

satisfactorily, the individual will be l

given credit for performing the task.

l Performance of the task is satisfactory l

if the actions of the operator during i

the task are within procedural l

requirements and will be documented on l

Form 0-11, Page 1.

The actual event is l

summarized on Event Description, l

Form 0-11, Page 2, and attached to the l

Reactor Manipulation Sheet (From 0-11),

l Page 1.

If additional training needs l

are identified as a result of the event l

or the performance of the task is i

unsatisfactory, Form 0-11 (both pages) l shall be submitted with a Training i

Development Request (TDR) for evaluation l

by the Operator Training Unit.

4.2.3 Control Manipulations

• a)

Reactor startup with observable temperature feedback

• b)

Reactor shutdown with observable temperature feedback

• c)

Manual manipulation of steam generator and/or feedwater controls during startup and shutdown.

• d)

Reactor power change of 10*.' or greater where load change is performed with load limit control or where flux, temperature, or circulator speed t

control is on manual.

e)

Moisture inleakage i

f)

Reactor scram i

g)

Loop shutdown h)

Circulator trip FORM (D)372 22 3643

IP-LR Issue 2

/

Public FORT ST. VRAIN NUCLEAR GENERATING STATION Page 9 of 30 (g' Service

• PUBUC SERVICE COMPANY OF COLORADO 1)

. Abnormal power j)

Main turbine emergencies k)

Extended loss of active core cooling 1)

Abnormal radioactivity m)

Fire n)

Radiological alert or radiological emergency o)

Earthquake p)

Loss of instrument air header q)

Loss of hydraulic power r)

Loss of instrument bus s)

Loss of a DC bus t)

Steam leak or inadvertent opening of a main or hot reheat steam relief valve u)

Loss of access to Control Room These manipulations must be performed on an annual basis; all other manipulations shall be performed at least once per two year cycle.

4.3 Evaluation 4.3.1 The successful completion of the Licensed Operator Requalification Program shall be based on the following criteria:

4.3.1.1 Review of Required Reading Satisfactory performance is based upon return of OIAG distributed reading material and evidence of review to the Training Section. The review of required reading shall be documented on Form 0-12.

FOAM 101372 22 3643

_. _ _ _ _ _... ~. _.. _ _ _,, _ - _ _ _ _, _ _ _ _.., _ _. - _ _ _ _ _ _ _ _ _ _ _ _. _ _, _ _ _. _. _. _. _ _. _. _ -. _. _ _ _ _..

TP-LR Issue 2

/

PUDllC FORT ST. VRAIN NUCLEAR GENERATING STATION Page 10 of 30 (j SerVICO' PUBLIC SERVICE COMPANY OF COLORADO 4

4.3.1.2 Performance on Unit Examinations Satisfactory performance is based upon scores of greater than or equal to 80%

on unit examinations administered in the l

requalification year.

Failure of 4 unit examinations will require consultation with the individual, the Supervisor of Operator Training, and the individual's supervisor.

Failure of an additional 2 l

unit examinations (6 total) constitutes failure of this criterion. Performance on U.11t Examinations shall be documented on Form 0-17.

l

• 1. • 7.7*#*

It is the responsibility of 1

the student to attend another l

requalification rotation or self study I

to achieve a score of greater than or l

l equal to 80% on all unit examinations.

4.3.1.3 Attendance at Requalification Training Satisfactory performance is based upon attendance of at least 80% of the lecture series. Attendance shall be l

documented on Form 0-15 and summarized l

on Form 0-18.

All missed lectures must be made up. Missed lectures shall be documented on Form 0-16.

4.3.1.4 The Requalification Review Panel will evaluate all individuals who aid not complete the above 3 criteria, and determine if the individual shall be eligible to take the annual oral and written exams.

4.3.2 Performance on Annual Licensed Operator (R0/SRO) oral and written requalification examinations.

4.3.2.1 All individuals who have satisfactorily completed the above criteria shall be administered an annual oral and written requalification examination, l

FORM lD)372 22 3643

TP-LR Enclosurs 2 Issue 2 (Q{ service

• Public FORT ST. VRAIN NUCLEAR GENERATING STATION Page 11 of 30 PUBUC SERVICE COMPANY OF COLORADO 4.3.2.2 Satisfactory performance on the written examination is based upon scores of greater than or equal to 80% overall and greater than or equal to 70% on all sections.

Satisfactory performance on the Oral Examination is based on a score of satisfactory on the examination. The successful completion of the written and oral examinations constitute the successful completion of the Requalification Program. The Requalification Review Panel will review the results of the examinations to ensure satisfactory completion, which will result in the award of the Licensed Operator bonus.

4.3.2.3 The oral examination will be given on an individual basis by a team of two (2) or l

more qualified instructors as defined in l

TP-TI.

l 4.3.2.4

• 1. • 7.8*#*

At least two Reactor Operator l

and two Senior Reactor Operator written l

requalification examinations shall be l

prepared and administered during each l

requalification year. These l

examinations will be broad based and l

similar in format to NRC administered l

examinations.

4.3.3 Failure Criteria 4.3.3.1 In the event that the individual does not successfully complete the annual written and/or oral examinations, the individual will be removed from licensed duties.

4.3.3.2 The Requalification Review Panel will evaluate all individuals that have failed the written and/or oral examinations and determine if the individual shall be eligible to retake the applicable examination.

FORM (0)372 22 3643 i

i

TP-LR Issue 2 19 Public FORT ST. VRAIN NUCLEAR GENERATING STATION Page 12 of 30 h service

• Pusuc sanvsca COMPANY OF COLORADO 4.3.3.3 If the individual is deemed eligible to retake the examination, he will be placed in an Accelerated Requalification Program. Upon completion of this program, the individual will take a reexamination. Successful completion of the second attempt will result in the award of the Licensed Operator bonus.

In the event that this second attempt is not successful, the Requalification Review Panel will determine eligibility for a third attempt, based on a review of the individual's performance to date on all requalification criteria.

4.3.3.4 If the Requalification Review Panel determines the individual is eligible for a third attempt and the individual is successful on the third attempt, the bonus will not be awarded due to the fact that the Station has lost the use of the individual for licensed duties for an inordinate period of time.

However, the individual will be permitted to resume license duties.

4.3.3.5 Those individuals that fail on their third attempt, those individuals who were deemed not eligible to take the annual written or oral requalification exam, or those individuals who are not eligible for a reexamination shall have their license deactivated.

4.3.4 Program Evaluations l

4.3.4.1 Program Evaluations shall be given to a l

sample group of trainees at the completion of each rotation.

l 4.3.4.2 A Training Need Survey (Form 0-20) shall be given to the trainees two (2) months after the completion of the Requalification Year.

l FORM t01372 22 3643

TP-LR Issue 2 QPublic (C/ SGTVICO' FORT ST. VRAIN NUCLEAR GENERATING STATION Page 13 of 30 PUBLIC SERVICE COMPANY OF COLORADO 4.4 Requalification Review Panel 4.4.1 Quorum 4.4.1.1 The Requalification Review Panel shall consist of the Supervisor of Operator Training, the Superintendent of Operations, the Superintendent of Training and the Station Manager.

4.4.1.2 The individual's immediate supervisor shall be part of the Review Panel when evaluation of an individual is required.

4.4.2 Duties 4.4.2.1 The Requalification Review Panel shall review the results of the individual examination to ensure satisfactory completion.

l 4.4.2.2

• 1. • 7.9 The Requalification Review Panel will evaluate all individuals who have demonstrated unsatisfactory performance of the Licensed Requalification Program and determine eligibility to continue in the program.

l The following criteria shall be used for l

the evaluation of an individual's l

eligibility to continue in the program:

l a.

The individual's performance on l

the job as evaluated in accordance l

with SMAP-20, Procedure for l

Supervisor Responsibilities and l

actual reactor manipulation as per l

Section 4.2.2.3 of this procedure.

l b.

The individual's performance in l

previous requalification training.

l c.

The need for the individual's l

license.

FORMIDI372 22 3123

TP-LR Issue 2

( 'TPublic FORT ST. VRAIN NUCLEAR GENERATING STATION Page 14 of 30

\\j $9fVICG*

PUBUC SERVICE COMPANY OF COLORADO 4.4.2.3 The Requalification Review Panel, with the exception of the Station Manager, shall review on an annual basis the overall Licensed Requalification Program. This review process is intended to identify any program weaknesses.

A.

Any section on the annual Requalification written examination which has an overall average of less than 80% shall be covered during the next requalification cycle on the first or second rotation.

B.

Any overall demonstrated weaknesses in a category on the annual requalification oral examination shall be covered during the next requalification cycle on the first or second rotation. A demonstrated weakness shall be defined as an unsatisfactory response in a category by 20% of the individuals tested.

C.

A report documenting any overall weaknesses of the Licensed Requalification Program shall be submitted for review to the Station Manager.

4.5 Accelerated Requalification Program 4.5.1 Based on unsatisfactory performance in any area of the Licensed Requalification Program, licensed individuals shall be directed to attend an accelerated requalification program.

Completion of the accelerated requalification program shall be documented on Form 0-10 and Form 0-14.

4.5.2 The accelerated requalification program shall be tailored to the needs of the individuals based on the demonstrated weakness of the individual.

4.5.3 The Supervisor of Operator Training shall approve the accelerated requalification program prior to implementation of the program.

FORM 101372 22 3643

__ _.. ~. _.. _. _. _ _. _

TP-LR Enclosura 2 Issue 2 O Public FORT ST. VRAIN NUCLEAR GENERATING STATION Page 15 of 30

.(/

$9fVIC9' PUBUC SERVICE COMPANY OF COLORADO

5.0 REFERENCES

5.1 PPC-85-2630 Letter from F. Borst to J. Gahm, Dated July 2, 1985 l

5.2 Training Management Procedures l

5.3 Training Procedure - Training Instructor l

5.4 10 CFR 55, Appendix A l

5.5 10 CFR 50.54 l

5.6 Title 10, Chapter 1 Code of Federal Regulations l

5.7 Station Manager Administrative Procedures 20 l

5.8 Superintendent of Operation Administrative Procedures 4 l

5.9 P-86506 l

5.10 P-87049 l

5.11 G-86659 l

5.12 P-83366 6.0 AZ ACHMENTS 6.1 Form 0 Licensed Requalification Review 6.2 Form 0 Licensed Operator Training Report, Reactivity Manipulations 6.3 Form 0 Operating Infor.aation Assessment Group Transmittal Form 6.4 Form 0 Accelerated Review Record 6.5 Form 0 Attendance Sheet l

6.6 Form 0 Makeup Sheet l

6.7 Form 0 Licensed Requalification Grade Summary Log l

6.8 Form 0 Licensed Requalification Attendance Summary Log l

6.9 Forn 0 Licensed Requalification Program Review l

6.10 Form 0 Training Needs Survey FORM (D)372 22 3843

TP-LR Issue 2

/

Public FORT ST. VRAIN NUCLEAR GENERATING STATION Page 16 of 30 C) Service

• rusuc seRVEE COMPANY OF COLORADO 7.0 COMMITMENTS The step (s) and section(s) listed below may not be deleted without issuance of comparable controls.

The procedure itself, if initiated as a result of commitment corrective action, may not be deleted without issuance of comparable controls.

7.1 Step 3.6.2 is a result of Commitment Log Item 1322.

l 7.2 Section 1 is a result of Commitment OB 1480:01 l

7.3 Step 3.1 is a result of Commitment in P-86506 l

7.4 Section 3.5 is a result of Commitment in P-87049 l

7.5 Step 4.1.6 Note is a result of Commitment in P-87049 l

7.6 Step 4.2.2 is a result of Commitment in P-87049 l

7.7 Step 4.3.1.2 is a result of Commitment in P-86506 l

7.8 Step 4.3.2.4 is a result of Commitment 08:1545A:01 and l

08:1480:03 j

l 7.9 Step 4.4.2.2 is a result of Commitment P-87049 l

7.10 Step 4.2.1k is a result of Commitment QDR87-001.

4 1

i FORMIol372 22 3M3

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TP-LR Form 0-10 (QPublic$/ Service

• FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 2 rusuc senvece couramy or cotonaoo Page 17 of 30 l

LICENSED OPERATOR REQUALIFICATION REVIEW l Name:

l Job Classification:

l Requalification Period:

to l I.

ORAL AND WRITTEN REQUALIFICATION EXAMINATION PREREQUISITES l

A.

DIAG Reading Completed l

B.

Unit Examination Satisfactory l

C.

Attendance Satisfactory l

Examination Prerequisites Completed l

Supervisor, Operator Training l

Review Panel Evaluation Approval l

(If required) l Supervisor, Operator Training l II.

EXAMINATION PERFORMANCE l

Written Examination Grades l

R0 Section I SRO Section V l

R0 Section II SRO Section VI l

R0 Section III SRO Section VII l

R0 Section IV SR0 Section VIII l

Overall Overall l

Oral Examination Grade (Sat /Unsat) l Review Panel Review Completed l

Supervisor, Operator Training FOMM101372 22 3H3

IP-LR Encicsure 2 Form 0-10 8['~,Npyhll3 FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 2 Service

• rusuc senvoca comramy or cotonaoo Page 18 of 30 l III. SECONO EXAMINATION l

This section is to be completed if individual failed written or l

oral examination l

A.

Review Panel Approval l

to take retest.

l Supervisor, Operator Training l

B.

Accelerated Requalification l

Completed.

.l Supervisor, Operator Training l

C.

Examination Performance l

Written Examination Grades l

R0 Section I SRO Section V l

R0 Section II SR0 Section VI l

R0 Section III SRO Section VII l

R0 Section IV SRO Section VIII l

Overall Overall l

Oral Examination Grade (Sat /Unsat) l Review Panel Review Completed l

Supervisor, Operator Training FORM (D)372 22 3843

TP-LR~

Enclosura 2 Form 0-10 O Public FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 2 hService*

resuc senvece couramy or cotonam Page 19 of 30 l IV.

THIRD EXAMINATION l

A.

Review Panel Approval to l

take third examination.

l Supervisor, Operator Training l

B.

Examination Performance l

Written Examination Grades l

R0 Section I SR0 Section V l

R0 Section II SRO Section VI l

R0 Section III SR0 Section VII l

R0 Section IV SRO Section VIII l

Overall Overall l

Oral Examination Grade (Sat /Unsat) l Review Panel Review Completed l

Supervisor, Operator Training i'

FoRMIDl372 22 3043

7:

i

("D Public _

FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 2 Form 0-11

\\

)Servl30*

Pusuc sanwes comeAmy or cotonAno Page 20 of 30 FORT ST. VRAIN GENERATING STATICN LICENSED OPERATOR TRAINING REPORT Reactivity Manipulations No: RM Date:

Shift: 12-8 8-4 4-12 o Actual Manipulation (fill out both pages) o Simulated Manipulation (use only page 1)

TYPE MANIPULATION: [ CHECK APPROPRIATE 80X(ES)]

• 1. o Reactor startup with observable temperature feedback

• 2. o Reactor shutdown with observable temperature feedback

• 3. o Manual manipulation of steam generator and/or feedwater controls during startup and shutdown

• 4. c Reactor power change of 10% or greater where load change is performed with load limit control or where flux, temperature, or circulator speed control is manual.

5. o Moisture inleakage

6. o Reactor scram

7. o Loop shutdown

8. o Criculator trip

9. o Abnormal power change

10. o Main turbine emergencies

11. o Extended loss of active core cooling

12. o Abnormal radioactivity

13. o Fire

14. o Radiological alert or radiological emergency

15. o Earthquake

16. o Loss of instrument air header

17. o Loss of hydraulic power

18. o Loss of instrument bus

19. o Loss of a DC bus

20. o Steam leak or inadvertent opening of a main or 50t reheat stem relief valve

21. o Loss of access to Control Room

• These manipulations must be pe'rformed on an annual basis; all other manipulations shall be perforemd on a two year cycle at a minimum.

Personnel involved:

Actual manipulation of controls Name Joo Title Actual manipulation of controls Name Job Title Supervise manipulation of controls i

Name Job Title j

Supervise manipulation of controls Name Job Title EVALUATION BY IMMEDIATE SUPERVISOR, TRAINING INSTRUCTOR OR PLANT MANAGEMENT j

o Satisfactory a Unsatisfactory Comments:

i i

S/

l Job Title Date ponesaosm at asas

TP-LR Form 0-11

'[;-

Pubii3 -

FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 2

\\

Servl3C#

Pusuc sanvecs comPAmy or cotonAco Page 21 of 30 EVENT DESCRIPTION Initiating Event:

Result of Initiating Event:

Narrative Summary of Events (use back of paper if necessary):

i d

h Training Needs Identified as a Result of this Event:

1 TOR Required (Contact Operation Training Unit) i Signature, Title Date 1

FORM 101372 22 3843 j

IP-LR Enc 1csure 2 Form 0-12 TD'3 Public FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 2 blSerVICO' PusuC ssRVICE COMPANY OF COLORADO Page 22 of 30 j'

OPERATING INFORMATION ASSESSMENT GROUP l

TRANSMITTAL FORM l Department OIAG Number:

l Date l Please review the attached information with appropriate members of I your department, have them sign below and return this transmittal l form to the Training Department l

l l

l l

l l

l l

l l

l l

Completion due by Review completed l

Date l

l Signature / Department Supervisor FORMID)772 22 3843

TP-LR Form 0-14 (QPublic

' FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 2 Q SerVICO*

PusuC ssRVICE COMPANY OF COLORADO Page 23 of 30 l_

ACCELERATED REVIEW RECORD l Name Title Date Assigned l A.

Reason for Accelerated review:

l 1.

( )

Annual Written Exam Failure Grade l

Date Taken l

2.

( )

Other (specify):

l B.

Review Assignment:

l C.

Recommendation for Re-Exam l

Accelerated review program certified complete l

l Date Signature, Licensed Operator l

l Date Signature, Supervisor of Operator Training l D.

Makeup Examination Results:

l Written examination Grade Date FORM 101372 22 3843

~

c y.

'A TP-LR :'

.a Form 0-15

/'7'; Public FORT ST. VRAIN NUCLEAR GENERATING STATION issue 2

,C)$9fVIC9'

.m PUBUC SERVICE COMPANY OF COLORAcc Page 24 of 30 I FORM 0-15 Rotatipn~#

Week #:

1 PSC l

FORT ST. VRAIN d

i TRAINING DEPARTMENT i.

l LICENSED REQUALIFICATION ATTENDANCE LOG c ll

~

l LESSON PLAN NUMBER:

DATE:

/ -

l LESSON PLAN TITLE:

INSTRUCiOR:

1 ASSOCIATED REACTIVITY MANIPULATION:

~

l

,f Il PRINT l.

SIGNATURE l

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Public FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 2

$9tVIC9' PUBUC SERVICE COMPANY OF COLORADO Page 28 of 30 LICENSED REQUALIFICATION PROGRAM REVIEW I.

Annual Requalification Written Examination Review A.

Reactor Operator Examination Categories Category Overall Grade Average

1. Principles of Nuclear Power Plant Operation, Thermodynamics, Heat Transfer, and Fluid Flow

2. Plant Design including Safety and Emergency Systems

3. Instruments and Controls

4. Procedures - Normal, Abnormal, Emergency, and Radiological Control B.

Senior Reactor Operator Examination Catagories Category Overall Grade Average

5. Theory of Nuclear Power Plant Operation, Fluids, and Thermodynamics

6. Plant Systems Design, Control, and Instrumentation

7. Procedures - Normal, Abnormal, Emergency, and Radiological Control

8. Administrative Procedures, Conditions and Limitations II. Sections of the examination which require training in the next requalification cycle in the first or second rotation (overall average less than 80%).

FORMID1372 22 3643

TP-L; Form 0-19

,p Public FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 2 LJ' Service

• Pusuc senvece comeamy or cotonano Page 29 of 30 I

III. Sections of the requalification oral examination which require training in the next requalification cycle in the first or second rotation (unsatisfactory by 20% of indivic'uals tested).

IV. Comments:

V.

Review by:

Supervisor of Operator Training

. 0 ate Superintendent of Training Date Superintendent of Operations Date i

FORM (Ol372 22 3643

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Tp-LR Form 0-20

@ ServlCO' Public FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 2 PUBLIC SERVICE COMPANY OF COLORADO Page 30 of 30 NAME TRAINING NEED SURVEY The following list of topics are taught in the Operator Requalification programs.

Review these topics and in the space below, identify, in detail, what specific portions of these topics you need most for additional training or review. The results of this survey, along with a variety of other inputs, will be utilized to determine the Requalification program selections. Asterisk (*) items identify License topics only.

TOPICS EXAMPLES Plant modifications Specific CN's Plant procedures Administrative, Radiological, Emergency Technical Specifications Non-Radiological, PCRV Problems in Job Performance Errors, Difficulties with Equipment operation Specific System or component concerns Sample sink, Feed pumps, Regen

• Plant system design reviews Plant protective system, Plant safety systems

• Instrument and controls Flow monitoring, automatic actions

• Reactor theory, heat transfer

• Fluid flow, thermodynamics

• Plant control manipulations Normal and casualty situations:

Main turbine emergencies, loop shutdown, reactor startup, feedwater controls Plant Fundamentals Plant, math, science, chemistry, safety, electricity, plant cycle Reviewer Comments:

i 1

FORM (D)372 22 3843

i ADDITIONAL INFORMATION FOR THE SPECIAL SENIOR LICENSED OPERATOR REQUALIFICATION PROGRAM We have identified these portions of the TP-SSLO (Enclosure 4) which address your specific concerns as follows:

Lectures NRC CONCERN:

Procedures should include those normal, abnormal, and emergency procedures related to fuel handling.

PSC RESPONSE:

TP-SSLO, Sections 4.2.1 and 4.2.3 TP-SSLO, Section 4.1.3.1(0)

NRC CONCERN:

There are no lectures which include Technical Specifications applicable for fuel handling.

PSC RESPONSE:

TP-SSLO, Section 4.1.3.1(0)

NRC CONCERN:

There are no lectures for applicable portions of Title 10, Chapter 1, Code of Federal Regulations.

PSC RESPONSE:

TP-SSLO, Section 4.1.3.1(0) l

Enclosurs 3 On-the-Job / Additional

.;ining NRC CONCERN:

There are.no provisions for review of abnormal and. emergency procedures on a regularly scheduled basis.

PSC RESPONSE:

TP-SSLO, Sections 4.1.3.2c, 4.2.1, and 4.2.3 NRC CONCERN:

Fuel handling manipulations appear to be limited to practice before actual in-core fuel handling. There are no provisions for simulated exercises or other forms of practice.

PSC RESPONSE:

TP-SSLO, Sections 4.1.3.2, 4.2.1, 4.2.2, 4.2.3, and 4.3.4.1 11 7

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Enclosura 3 Evaluations NRC CONCERN:

There is no methodology nor passing criteria for performance evaluations.

PSC RESPONSE:

TP-SSLO, Sections 4.3.2 and 4.3.4.4d NRC CONCERN:

There are no accelerated training criteria for unsatisfactory performance evaluations.

PSC RESPONSE:-

TP-SSLO, Section 4.3.4.4 NRC CONCERN:

There appear to be no records for performance evaluations.

PSC RESPONSE:

TP-SSLO, Attachment 6 NRC CONCERN:

There appears to be no formal retraining or reexamination if licensed personnel do not satisfy passing criteria son written examinations.

Reexamination appears to be limited to an oral examination.

PSC RESPONSE:

TP-SSLO, Sections 4.3.1, 4.3.4.4, and 4.3.5 General Comments NRC CONCERN:

The Requalification Program does not appear to provide for continuing training or practice to maintain proficiency at any time after the scheduled refueling or the annual Requalification Training.

PSC RESPONSE:

SSLO's are permanently assigned to the refueling deck under the direction of the Reactor Maintenance Supervisor and perform licensed duties throughout the year. Therefore, 55.31(e) does not normally apply.

NRC CONCERN:

Return to duty programs PSC RESPONSE:

TP-SSLO, Section 4.3.4.5(b)

NRC CONCERN:

With regard to retraining, if an individual does not achieve quiz scores of greater than 80%, the program requires review of lesson plan material as the method of remedial assignments. The program should also include examination evaluation and tutorial sessions as determined by the instructor and the Training Supervisor.

PSC RESPONSE:

When a student does not receive a passing grade on an examination, he is given an opportunity to review the material that was provided.

The examination is also reviewed with an instructor and the student signs the cover sheet stating that he has reviewed the examination with the instructor and has been informed and understands the correct answers to any questions he may have missed.

He then has the responsibility of preparing himself for the reexamination using the materials and the test review. The instructor will be available to assist the student in answering any questions regarding the make-up, administer the reexamination, and provide tutorial sessions as determined necessary by the instructor and the Training Supervisors.

This exam review process provides an evaluation of examinations, and when coupled with the Training Department Request (TDR) System as described in TMP 4.1, allows for a continuing evaluation of individual knowledge.

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