ML20054L162
| ML20054L162 | |
| Person / Time | |
|---|---|
| Site: | FitzPatrick  |
| Issue date: | 07/01/1982 |
| From: | Bayne J POWER AUTHORITY OF THE STATE OF NEW YORK (NEW YORK |
| To: | Vassallo D Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML20054L163 | List: |
| References | |
| RTR-NUREG-0737, RTR-NUREG-737, TASK-1.A.2.1, TASK-2.B.4, TASK-TM JPN-82-56, NUDOCS 8207070211 | |
| Download: ML20054L162 (9) | |
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POWER AUTHORITY OF THE STATE OF NEW YORK 10 CoLUMeus CIRCLE NEW YORK. N. Y. too19 e2123 397 6200 GEORGET BERRY PREteOENT & C e44 E r TRUSTEES OPE n aving otracEn JOHN S. DYSON JOHN W. BOSTON E IDENT ROCEDURES
& PEnronM NCE GEORGE L.lNGALLS VIC E CMal4 MAN JOSEPH R. SCHMIEDER RICH ARD M. F LY N N RES DE Y & CHIEr ROBERT I MILLONZ4 LEROY W. SINCLAIR VtCE PR E le f* E NT FREoERica R. CL ARx JPN-82-56
.SE NIOR C Er riN NCi L July 1, 1982 THOM AS R. FREY SENIOR WICE PAESIDE NT
& GENERALCoweeSEL Director of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, D.C.
20555 Attention:
Mr. Domenic B. Vassallo, Chief Operating Reactors Branch No. 2 Division of Licensing
Subject:
James A.
FitzPatrick Nuclear Power Plant Docket No. 50-333 NUREG-0737 Items I.A.2.1 and II.B.4 Upgraded SRO and RO Training and Training for Mitigating Core Damage
Reference:
1.
D.B. Vassallo (NRC) to L.W.
Sinclair (PASNY) letter dated May 20, 1982, same subject.
Dear Sir:
In response to your request for additional information (Reference 1), regarding NUREG-0737 items I.A.2.1 and II.B.4, the Authority hereby submits the attached information.
A copy of our submittal is being sent to Dr.
R.T.
Liner of Science Applications, Inc. as you requested.
If you or your staff have any further questions, please contact Mr.
J.A.
Gray, Jr. of my staff.
Very truly yours,
/
sc v J) ayn Senior Vi e President Nuclear Generation cc:
attached U
po B207070211 820701 PDR ADOCK 05000333 P
. _. _ ~ _.
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cc:
without attachment Mr. J. Linville Resident Inspector U.S. Nuclear Regulatory Commission P.O.
Box 136 Lycoming, New York 13093 i
Mr.
R.
Barton i
United Engineers and Constructors, Inc.
30 S.
17th Street Philadelphia, PA 19101 4
I cc:
with attachments Dr.
R.T.
Liner Science Applications Inc 1710 Goodridge Drive 7
McLean, Virginia 22102 i
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POWER AUTHORITY OF THE STATE r
OF NEW YORK I
e Response to NRC May 20, 1982 4
Request for Additional Information Regarding NUREG-0737 Items I.A.2.1 and II.B.4 (Upgraded SRO and RO Training, and Training for Mitigating Core Damage)
James A.
FitzPatrick Nuclear Power Plant Docket No. 50-333 Attachment to (JPN 56 )
l July 1,
1982 i
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a 2
General Indoctrination and Training Procedure No.
4,
" Licensed Operator / Senior Operator Replacement Training", dated 8-8-80, Revision 2 is the current revision.
Indoctrination and Training Procedure No.
5,
" Licensed Operator Requalification", dated 9-10-80, Revision 4 is attached as Enclosure 1.
Section A - Requalification Program i
t Question 1 Are the lectures and quizzes on the subject of accident mitigation given to shift technical advisors and operating personnel from the plant manager through the operations chain to the licensed operators?
If they are, would you please provide the titles of the people who are trained and an organization chart which illustrates their posi-tion in the operations chain?
Response
Lectures on the subject of mitigating the consequences of severe core damage have been given to the following personnel:
a.
Resident Manager b.
Superintendent of Power c.
Technical Services Superintendent d.
Radiological & Environmental Services Superintendent f.
Operations Superin*:endent g.
Maintenance Superintendent h.
Instruraent and Control Superintendent i.
Reactor Analyst Supervisor j.
All Staff Licensed Personnel k.
All Station Shift Supervisors (SRO) 1.
All Senior Nuclear Operators (RO) m.
All Nuclear Control Operators (RO)
A plant staff organization chart is attached as Enclosure 2 (Figure 6.2-1 of FitzPatrick's Technical Specifications.)
Question 2 Do the requalification program elements which involve heat transfer, fluid flow, thermodynamics and accident mitigation involve 80 contact hours in each program?
(A contact hour of instruction is a one-hour period in which the course instructor is present or available for instructing or assisting students; lectures, seminars, discussions, problem-solving sessions, and examinations are considered contact periods under this definition.) !
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Response
J The requalification program does not provide for 80 contact hours in each area of heat transfer, fluid flow, thermodynamics or accident mitigation.
a.
Initial training in Accident Mitigation - 32 hours3.703704e-4 days <br />0.00889 hours <br />5.291005e-5 weeks <br />1.2176e-5 months <br />.
Mitigation concepts are incorporated into existing lesson plans.
b.
Heat transfer, fluid flow and thermodynamics for requalification are three lesson plans normally presented in a 24-32 hour time frame.
i Question 3 1
Does your requalification program for Reactor Operator and Senior Reactor Operator cover the subjects of heat transfer, fluid flow, and thermodynamics?
If it does, is the coverage to the level of detail spelled out in enclosure 2 of the Denton letter?
Please send a course outline if available.
Response
The requalification program covers the areas of heat transfer, fluid flow and thermodynamics.
Applicable portions in Attachment 2 of the Denton Letter are included.
Find enclosed lesson plans for Heat Transfer, Fluid Flow and Thermodynamics (Enclosures 3,4 and 5)
Question 4 Does your requalification program for Reactor Operator and Senior Reactor Operator cover the subject of using installed plant systems to control or mitigate an accident in which the core is severely damaged?
If it does, is the coverage to the level of detail spelled out in enclosure 3 of Denton's letter?
Please send a course 4
outline if available.
Response
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i The requalification utilized a lesson plan and text prepared by the General Physics Corporation which includes all applicable requirements in Attachment 3 of Denton's Letter.
Find enclosed the Training Report from the Mitigating Core Damage Lesson (Enclosure 6).
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1 Question 5 Does your requalification program for reactor operators and senior reactor operators cover the required training in control manipulations?
If it does, is the coverage to the level or detail and frequency spelled out in enclosure 4 of Denton's letter?
Response
Control manipulations in the requalification program are specified in section 5.5.7 of Indoctrination and Training Procedure No.
5,
" Licensed Operator Requalification,"
(Enclosure 1).
This procedure was revised to incorporate of the Denton Letter.
Section B - Training Program Question 1 The training program for reactor operators (4.5.3.a.2 and 4.5.4.b.l.f)has lectures which appear to cover the subjects of heat transfer, fluid flow and thermodynamics as called out in enclosure 1 of Denton's March 28, 1980, letter. Do these lectures in fact cover this material and is the coverage to the level of detail spelled out in enclosure 2 of the Denton letter?
Please send a course outline if it is different from that used in the requalification program.
Response
The training program for replacement license candidates consists of college accredited fundamental training as outlined below:
i a.
Algebra & Trigonometry 80 Hours i
b.
Geometry & Calculus 40 Hours c.
Chemistry 120 Hours d.
Physics 80 Hours e.
Thermo, Heat Transfer & Fluids 120 Hours f.
Electronics 40 Hours g.
Radiological Safety 80 Hours h.
Nuclear Engineering 120 Hours i.
Nuclear Reactor Safety 32 Hours j.
Instrumentation & Controls 32 Hours This curriculum, developed by Multi-Amp Institute in conjunction with Midlands Technical College, more than satisfies the requirements of Enclosure 1 of the Denton Letter. In addition to the above fundamental training,
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I each candidate receives approximately 40 hours4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br /> of instruction during the review portion of the' training program in plant specific areas of heat transfer, fluid L
flow, thermodynamics and thermal limits.
This 40 hours4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br /> I
utilizes the requalification program lesson plans (Enclosures 3,4 and 5).
Question 2 The reactor operator and senior reactor operator training program (4.5.3.a.10 and 4.5.4.b.l.q) has lectures which appear to address the subject of using installed plant i
systems to control or mitigate an accident in which the j
core is severely damaged.
Do these lectures address the topic and do they cover the subject to the level of detail i
spelled out in enclosure 3 of Denton's letter?
Please send a course outline if it is different from that used in the requalification program.
Response
Mitigation training for license candidates is the same as utilized in the requalification program.
Question 3 t
There is increased emphasis on reactor and plant transients in the reactor operator and senior reactor operator training program (4.5.3.a.ll and 4.5.4.b.l.h).
Does this training deal with both normal transients and abnormal (accident) transients?
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Response
Training for license candidates in the area of opera-tional transients and accident analysis is done in a t
i three step process-a.
Introduction to Emergency Core Cooling Systems j
(during systems training).
b.
Introduction to Transient Analysis (during final I
review phase).
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Normal and abnormal event analysis as outlined in the FSAR and General Electric's Abnormal-Events Analysis text.
Question 4 Please answer question 1 of Section A with respect to i
to your training program.
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Response
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1 Please refer to our response to question 1 of Section A.
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n-6 Question 5 Please answer question 2 of Section A with respect to your training program.
Response
Please refer to our response to question 2 of Section A. is a typical course schedule conducted during the final phase of license replacement training detailing the above topics.
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j LIST OF ENCLOSURES J
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Indoctrination and Training Procedure No. 5,
" Licensed Operator Recualification" (2)
Figure 6.2-1 (Plant Staff Organization)
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Heat Transfer Lesson Plan j
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Fluid Flow Statics and Dynamics Lesson Plan J
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Elementary Thermodynamics Lesson Plan (6)
Requalification Training Report " Mitigating Reactor Core Damage" i
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Selected Course Schedules (Replacement L-icense t
j Training) i r
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