ML17194B670
| ML17194B670 | |
| Person / Time | |
|---|---|
| Site: | Dresden, Byron, Braidwood, Quad Cities, Zion, LaSalle, 05000000 |
| Issue date: | 08/04/1983 |
| From: | Swartz E COMMONWEALTH EDISON CO. |
| To: | Harold Denton Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML17194B671 | List: |
| References | |
| RTR-NUREG-0737, RTR-NUREG-737, TASK-1.A.3.1, TASK-TM 7094N, NUDOCS 8308110106 | |
| Download: ML17194B670 (11) | |
Text
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- e *commonA.th Edison B
One First Na-Plaza, Chicago; Illinois Address Reply to: Post Office Box 767
- Chicago, Illinois 60690 u e August 4, 1983 Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, DC 20555
Subject:
References (a) :
( b) :
( c) :
( d) :
( e) :
( f) :
Dear Mr. Denton:
Dresden Station Units 2 and 3 Quad Cities Station Units 1 and 2 Zion Station Units 1 and 2 LaSalle County Station Units 1 and 2 Byron Station Units 1 and 2 Braidwood Station Units 1 and 2 NUREG-0737 Item I~A.3:1 Revised Licensed Operator Requalification Topical Report NRC Docket Nos. 50-237/249, 50-254/265 50-295/304, 50-373/374, 50-454/455, and 50-456/457* * - - *
- H:
R~ Denton let fer to All OL's and Applicants.dated March 28~ 1980~
D.
G~ Eisenhut letter to All OL's dated May 7, 1980.
D~ L ~ Peoples letter to D.
G~ Eisenhut dated Junel2~ 1980.
- w. F ~ Naughton letter to D. G. Eisenhut dated August 1 ' 1980.
w
~ F. Naughton letter to P: F. Collins dated September 15, 1980.
L. 0. Del George letter to P. F: Collins dated October 29' 1980.
In respons' to the requirements set forth in Refer~nces (a) and (b), References (c) and (d) provided the Commonwealth Edison Company commitments to ihe TMI Action Plan Item I.A.3.1 and provided the revised topical report entitled "REQUALIFICATION PROGRAM FOR LICENSED OPERATORS, SENIOR OPERATORS, AND SENIOR OPERATORS (LIMITED)" for NRC Staff review.
Additionally, References (e) and (f) provided supplemental information
.concerning this matter~
- (
8308110106 830804 I
PDR ADOCK 05000237
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H~ R~ Denton 2 -
v e August 4, 1983 The purpose of this letter is to provide a rev1s1on to our Reference (d) Topical Report for your review and approval.
The changes consist of voluntary revisions based on our experiences gained through Q~A. audits and current guidance on NRC examinations~ Additionally, it is intended that the attached revised Topical Report be applicable to all Commonwealth Edison Stations.
By copy of this letter to Region III, it is requested that the Region participate in review of our. revised requalification program as applicable.
Please address any questions that you or your Staff may have concerning this matter to this office:
One (1) signed original and forty (40) copies of this letter with Attachment are provided for your use.
Very truly yours, E~ Douglas Swartz Nuclear Licensing Administrator Attachments cc:
J. G. Keppler - Region III 7094N Region III Inspectors - D/QC/Z/LS/B/B P. F. Collins -
OLB
- -**-*-U* e COMMONWEALTH EDISON COMPANY May 16, 1983 REQUALIFICATION PROGRAM FOR LICENSED OPERATORS, SENIOR OPERATORS, AND SENIOR OPERATORS (LIMITED)
The following *requalification program is designed to assure station management that all licensed Operators, Senior Operators, and Senior Operators (Limited) maintain a high level of competency.
The program consists of lectures, simulator training, and on-tt~e-job training.
Records shall be maintained and evaluations made of each man's performance.
The Station Superintendent at each Commonwealth Edison Company nuclear power station has delegated to the Training Supervisor responsibility for implementing and-coordinating the requalification program for the station *
. I. Lectures.
Lectures will be given as required by Section IV of this document in the general subject areas listed belo_w.
The minimum time requirement for review of subject areas A through G shall be 40 hours4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br /> over the one year requalification cycle.
A.
Principles of Nuclear Power Plant Operation and Fundamentals of Thermodynamics, Heat Transfer, and Fluid Flow
- Lectures shall include review of reactor kinetics, control rod worths, reactivity coefficients, reactor anci flow transients, core damage mitigation concepts, fuel; safety limits, thermal limits and DNB considerations.
B.
Plant Design Including Safety and Emergency Systems Lectures shall include review of plant operating characteristics during normal and abnormal operating conditions, analyzed transients, and accidents.
Incidents and abnormal occurrences at Edison stations and at other utilities shall also be reviewed.
C.
Instruments and Contr,ols Lectures shall include review of the operation and control of the reactor. prot~ctic;?n systems,,j>lant,instrum~?tation, emergency core and containment cooling systems; c'ore damage m~tigation sy~tems, eng1neered s~feg~aras, and other related piant systems.,.
0436A/0044A/l 05/83
D.
- --**U-9 Procedures - Normal, Abnormal, Emergency and Radiological Control Lectures shall include review of normal, abnormal, and emergency procedures, including fuel handling procedures.
Federal and company radiation exposure limitations, control methods, monitoring equipment and waste disposal systems.
E.
Administrative Procedures, Conditions and Limitations Lectures shall include review* of administrative procedures,.security procedures, quality assurance procedures, station emergency plan implementation procedures, and facility license (including technical specifications).
F.
Plant Modific.ations Lectures shall *provide UP"'.'to-date information concerning system design changes, instrument setpoint changes, wiring modifications, and any other plant modifications implemented during the most recent requalificatio.n interval.....
G.
General Information Lectures shall include, as appropriate, information on upcoming outages and other events of operational significance.
II. Simulator Training A.
Each Operator or Senior Operator shall spend a minimum of three full days per year at a training simulator which has the characteristics of the plant for which be is licensed.
During this time he shall perform operating functions under simulated normal, abnormal, and emergency conditions.
B.
Control manipulations performed on the training simulator.may be used toward.satisfying the requirements of Section III of this document.
III.
On-the-Job Training A.
Each licensed Operator shall manipulate plant controls during the term of his license.
Each Senior Operator shall manipulate plant controls or direct the activities of individuals performing plant control manipulations during the term of his license.
Such plant control manipulations shall include those commensurate with the plant evolutions listed in Attachment A of this document on an annual (once in every calendar year) or bi-annual (orice in every two calendar years) basis, as indicated.
0436A/0044A/2 05/83
B.
- c.
- --U--*
e Credit for control manipulations performed or supervised on a given unit shall be given to a licensed Operator or Senior Operator who has performed or supervised such control manipulations on a training simulator or on a different unit, provided that such simulator or different unit has operating characteristics and control and instrumentation arrangements.similar to those of the given unit.
Stations shall maintain a system to record plant control manipulations by Operators or supervision of plant control manipulations by Senior Operators.
The system may consist of a log kept by the individual or an authenticated list of qualifying manipulations extracted from the unit log, or simulator record of manipulations.
D.
Each licensed Operator and Senior Operator shall review facility design changes, procedure revisions, and facility license changes so as to remain cognizant of these changes.
Each licensed Operator and Senior Oper~tor shall review abnormal and emergency procedures on a regularly scheduled basis.
Stations shall maintain a system to accomplish these reviews, including documentation to substantiate
- accomplishment of the reviews~
E.
Senior Operators (Limited) are responsible for review of design changes, procedure revisions, facility design changes and abnormal and emergency procedures which are applicabie to their area of responsibility.
Stations shall maintain a system to accomplish these reviews including documentation to substantiate accomplishment of the reviews.
IV. Evaluation A.
Annual written examinations shall be given to licensed Operators and Senior Operators to determine their knowledge of subjects covered in the requalif ication program, to ~rovide a basis for evaluating their knowledge of abnormal and emergency procedures, and to determine areas in which retraining is needed.
Examinations shall be given on the Operator and Senior Operator.level.
- 1.
The annual examinations may be given as one exlµllination or as a set of two examinations.
If given as a set of two examinations,
.these examinations shall be given within a three-month period.
- 2.
An Operator or Senior Operator achieving a grade of 80% or greater in any examina~i9n. :subj~ct i~ not required to attend a lecture on that subject.
1.-
0436A/0044A/3 05/83
I
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,..U e
- 3.
An Operator or Senior Operator receiving a grade of less than
- 80% on any exainiriation subject shall attend a lecture on that subject.
- 4.
An Operator or Senior Operator who receives an overall grade of less than 80% on the annual written examination, or a grade of less than 70% in any examination subject, shall demonstrate competence to continue to perform his license duties by participating in and completing an accelerated requalification program.
The following procedure shall be followed:
- a.
If the Operator or Senior Operator is to continue license duties past 14 days, while enrolled in accelerated retraining, an oral examination shall be administered within 14 days of after determining the need for accelerated requalification.
- b.
If the Operator or Senior Operator is removed from license duties or completes the accelerated retraining within 14 days,. the. oral exam is.not require_d ~.*
- c.
If the Operator or Senior Operator demonstrates that he can operate the plant safely in the oral examination, he may be permitted.to continue to perform license duties while participating in the accelerated requalification program *.
- d.
If the Operator or Senior Operator fails to demonstrate that he can operate the plant safely during the oral examination, he shall be relieved of license duties until he has *completed the aceelerated requalificationprogram.
- e.
The accelerated requalification program shall address all subject areas wherein the Operator or Senior Operator received an exam grade;of less than 80%.
- f.
The Operator or Senior Operator shall be considered to have completed accelerated requalif ication only after he has been re-examined and has attained an overall examination grade not less than 80%, with a grade of not less than 70%
in any examination subject.
B.
- If a licensed individual prepares, grades, or reviews the annual examination, the licensed individual need not take the examination.
This exclusion shall. extend to only three individuals at each station.
These three individuals shall participate in all other phases of the operator requalification program.
0436A/0044A/4 05/83
I
- c.
_-----u e A quiz shall be administered upon completion of lectures in each of the subject areas* specified in Section I, paragraphs A through G, of this document.
Any individual whose attendance at such lectures is required under the provisions of Section IV of this document, and who receives a grade of less than 80% on the quiz, shall receive additional training.
D_.
An oral examination shall be administered at least once during each two year license interval to all licensed operators.
This examination may consist of an oral review to determine the operator's knowledge of normal and emergency procedures and equipment or an oral review of an operator's performance conducted after a reactor startup, shutdown, or emergency.
The oral exam-ination shall be administered by a licensed member of the training staff or other licensed supervisor.
E.
Evaluations shall be made by supervisors and/or training staff member, including vendors, of the performance and competency of licensed operators during actual or simulated abnormal and emergency conditions.
F.
An annual review shall be made by Station Management of each licensee's performance in Section IV A through Section IV D and a determination shall be made concerning the licensee's qualification to continue in his assigned duties and the need for retraining or accelerated retraining.
V.
Traini?g for Senior Operators (Limited) - Fuel Handlers A.
Senior Operators (Limited) when required by examination results shall attend lectures as designated in Section I appropriate to fuel handling operations.
Lectures_ considered appropriate for fuel handlers in Section I are as follows:
- 1.
Review of terminology, reactor theory, rQd worth, core loading physics, and calculations.
- 2.
Review of federal and company radiation exposure limitations, control methods, monitoring equipment, waste disposal systems when pertaining to the fuel pool systems, calculations for exposure dose, and shielding.
- 3.
Fuel handling procedures.
- '-I 0436A/0044A/5 05/83
- 4.
-~---u
- The Ge'n:ra *.
g Station Emergency Plan and
- items directly related to fuel**handling indicated. in the do-cuments listed in this series.
- 5.
Plant modifications directly or indirectly related to the performance and maintenance of fuel handling operations or equipment.
- 6.
FSAR transients, operating experience, incident review related to fuel handling.
- 7.
Plan instrumentation, systems, and engineered safeguards related to fuel handling operations or vessel internals.
- 8.
Open lectures such as a briefing prior to refuel operations.
B.
Senior Operators (Limited) shall participate in special reviews of fuel handling procedures in preparation for refueling or receipt or shipment of fuel.
Senior Operators (Limited) are responsible for review of des1gn changes, procedure revisions, facility design changes, and abnormal and emergency procedures as described in Paragraph III E.
C~
Senior Operator~ (Limited) are not required to participate in simulator traini~g.
D.
The knowledge and performance of Senior Operators (Limited) in fuel handling operations shall be evaluated in accordance with Section IV.
VI. Licensed Personnel Not Actively Performing the Function of an Operator or Senior Operator A.
Absence from station duties due to illness, or other causes for a period of four months or longer.
The licensee shall be enrolled in an accelerated retraining program and must satisfactorily complete an annual examination and evaluation by station management prior to assuming license duties *
. *B.
Assigned at the*station but not performing duties of an Operator or Senior Operator as defined in.10 CFR 55 Paragraph 55.4.
The licensee shall mainta.in license elgibility by participation in
. and satisfactory completion of the requalification program.
Licensed Operators and Senior Operators shall be assigned applicable license duties at least eight hours each year in addition to the regular retraining requirements.
0436A/0044A/6 05/83
u e
- 1:.....
VII.
Schedules A.
-- B.
llle requalif ication program shall be conducted continuously for two years with the possible exception of the three-month swmner vacation period.
llle lecture series shall be conducted on a continuous basis during the periods when licensed personnel are relieved of shift duties and are unavailable for scheduled classes.
Each lecture shall be repeated as necessary to afford licensed personnel the opportunity to meet lecture requirements as determined by the written examination evaluation.
Lectures should not normally be scheduled during the months of June, July, and August due to the minimum availability of shift personnel during this prime vacation period *.
VIII.
Records A.
llle training Supervisor shall maintainrecords of the tra1n1ng progress for each man in the requalification program to include as a minimum:
- 1.
Written evaluation examination, answer key, answers given by licensee,. and grade for each man.
- 2.
Results of evaluation required in this procedure Section IV.C, IV.D, and IV.E.
- 3.
Records of procedure review, facility design changes, procedure changes, facility license change review, and plant manipulations required in Section III.
0436A/0044A/7 05/83
ATTACHMENT A u e The following plant evolutions shall be performed on an annual basis pursuant to the requirements of paragraph III A.
- 1.
Plant or reactor 8 tart up, to the point of adding measurable heat.
- 2.
Manual control of steam generator level or feedwater flow during startup or shutdown.
- 3.
Any change in power of greater than 10%, using manual rod control, recirculation flow, or chemical control.
- 4.
Loss of forced core flow; natural circulation conditions.
- 5.
Loss of all feedwat~r, both normal and emergency.
- 6.
Loss of coolant, including:
- a.
leaks of both large and small sizes
- b.
leaks both inside and outside primary containment
- c.
significant steam generator leaks (PWR only)
- d.
determination of leak rate The following plant evolutions shall be performed on a bi-annual basis pursuant to the requirements of paragraph III A.
- 1.
Plant shutdown.
- 2.
- 3.
Turbine or generator trip.
4~
Main steam line break.
- 5.
- 6.
Loss of normal feedwater.
- 7.
Loss of shutdown cooling.
- 8.
Component malfunction due to loss of cooling.
- 9.
Required activation of emergency boration or standby liquid control *.
- 10. Control rod drive mechanism failure.
- 11. Increase in coolant or offgas activity indicative of fuel failure.
0436A/0044A/8 05/83
\\
ATTACHMENT A (continued)
- 12. Mispositioned control rod or bank.
- 13. Loss or degradation of electrical power source.
- 14. Loss of protective system channel.
- 15. Malfunction of nuclear instrumentation.
-U e
- 16. Malfunction of automatic control system affecting reactivity.
- 17. Malfunction of reactor water level control or coolant volume control.
0436A/0044A/9 05/83