ML20072D760

Forwards Response to 830208 Request for Addl Info Re NUREG-0737,Items I.A.2.1, Upgrading Reactor Operator & Senior Reactor Operator Training Qualifications & II.B.4, Training for Mitigating Core Damage

ML20072D760
Person / Time
Site:	Hatch
Issue date:	03/14/1983
From:	Beckham J GEORGIA POWER CO.
To:	Stolz J Office of Nuclear Reactor Regulation
References
RTR-NUREG-0737, RTR-NUREG-737, TASK-1.A.2.1, TASK-2.B.4, TASK-TM NED-83-167, TAC-44166, TAC-44167, NUDOCS 8303210427
Download: ML20072D760 (7)

Text

Georgia Power Company 333 Piedmont Avenue Atbnta, Cecrgia 30308 Telephor:e 404 526-7020 Mading Address' Post Office Box 4545 bm Atlanta. Gecrga 30302 Georgia Power IN "#N"O'6CIC 605 J. T. Beckham, Jr.

Vce President and General Manag '

NED-83-167 Nuclear Generation March 14, 1983 Mr. John F. Stolz, Chief Operating Reactors Branch #4 Division of Licensing U. S. Nuclear Regulatory Commission Washington, D. C. 20555 mC DOCKETS 50-321, 50-366 OPERATING LICENSES DPR-57, NPF-5 EDWIN I. HATCH NUCLEAR PLANT UNITS 1 & 2 ADDITIONAL INFORMATION REGARDING NIREG-0737 ITEMS I.A.2.1.4 AND 11.6.4 Gentlemen:

Your letter of February 8, 1983, transmitted a request for, additional information regarding NUREG-0737, Items I. A.2.1.4 (Upgrading of RO and SRO Training) and II.B.4 (Training for Mitigating Core Damage).

Enclosed are our responses to that request.

Should you have further questions regarding Itsns I. A.2.1.4 or II.B.4, please contact this office.

Yours very truly, 0 k lh J. T. 8 kham, Jr.

PDR/blm Erclosures xc:

H. C. Nix G. BoCKhold D. F. Moore P. Bennett (General Physics Corp.)

J. P. O'Reilly (NRC-Region II)

Senior Resident Inspector

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ENCLOSURE I

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RESPONSE TO. REQUEST FOR~ ADDITIONAL INFORMATION REGARDING UPGRADED RO APO SRO TRAINING AND-TRAINING

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' FOR~ MITIGATING ~ CORE-DAMAGE - MJREG-0737 ITEMS -I. A.2.1.4 and II.B.4

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lQUESTIONfl-y.,

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Describe in detail how the material' required by Enclosure 2 of the March a m>

728,'.1980fletter from Harold.R. Denton to all power reactor applicants and:. licensees.L concerning. qualifications of reactor operators.is iincorporated :into the Phase I and iII sections' of your Criteria for Reactor Operator' Training and Licensing..

RESPONSE 1 During L0perator. Licensing School-Phase.I (Easic License Preparation),

y 4

the following. subjects are introduced:

Thermodynamics Fluid Mechanics and Heat ' Transfer

Energy' Transfer Systems Forms of Energy ,

Enthalpy.

First Law of Thermodynamics :

Second Law of Thermodynamics

~

Phases of Matter 1 Steam Tables-Power Plant Cycles Basic Fluid Flow Relationship Bernoulli's Equation Fluid Friction Modes of Heat ~ Transfer Conduction Convection-Radiation Boiling Heat Transfer 4 During Phase.III (Basic Technology) of the same school, the ~ following

+

subject matter is taught:

Thermodynamics Energy Transfer Systens Properties'of Working Fluids Forms of Energy -

Work and" Heat Energy' and Power Equivalences 1

Enthalpy First Law of Thermodynamics Applications of the General Energy Equation

-Second Law of Thermodynamics Phases of Matter Phase Diagrams Page 1 4

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Mya Om RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION REGARDING UPGRADED R0 AND SRO TRAINING APO TRAINING FOR MITIGATINC CORE DAMAGE - NUREG-0737 ITEMS I.A.2.1.4 and II.B.4 (Continued)

Thermodynamics (Continued)

Steam Tables Use of Saturated Steam Tables Use of Superhmted Steam Tables Liquid Heat Capacity Mollier Diagram Types of Power Cycles Power Cycle Refinements Elements of Power Cycles Power Cycle Efficiency Overall Plant Efficiency Sample Analysis of a Nuclear Power Plant Fluid Mechanics Basic Fluid Flow Relationship Units of Fluid Flow Laminar and Turbulent Flow Continuity of Flow Bernoulli's Equation Fluid Friction Evaluation Head Loss From Friction Evaluating Head Added by Pumps Measuring Fluid Flow Rate Two Ph8se Fluid Flow Heat Transfer Modes of Heat Transfer Fundamentals of Heat Transfer Conduction Convection Boiling Heat Transfer Combined Heat Transfer Reactor Heat Transfer BWR Core Operational Considerations and Limitations Thermal Limits Minimum Critical Power Ratio Linear Heat Generation Rate Average Planar Linear Heat Generation Rate QUESTION 2 As above for Enclosure 3 to Denton's letter of March 28, 1980.

t Page 2 700775

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L RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION Georgia Power REGARDING UPGRN)ED R0 AND SRO TRAINING AND TRAINING L

FOR MITIGATING CORE DAMAGE - NUREG-0737 ITEMS I.A.2.1.4 and II.B.4 (Continued)

I l

RESPONSE 2 l

During Operator Licensing School Phase IV (Reactor Technology), the following subjects are introduced:

Severe Core Damage Accident.

Core Damage a)

Detection b)

Varification Methods I

c)

Damage Assessment l

Core Gases a)

Swmm b)

Effects of Cooling l

c)

Elimination and/or Control of Gases d)

Hydrogen Hazard Critical Instrumentation During Accident a)

Pressure i

b)

Temperature c)

Level d)

Radiation e)

Alternate Methods of Evaluation Radiation Hazard a)

Location b)

Monitoring Instrument Response c)

Radiological Emergency Plan Vulnerable Operating Conditions a)

Offsite Power Losses b)

Onsite Power Losses c)

Inoperative Plant Equipment Core Cooling Mechanics a)

Flow Paths Normal b)

Alternate Cooling Methods c)

Cooling Mode Selection

-QUESTION 3 Describe the program that has been provided to assure that instructors are cognizant of current operating history, problens, and changes to procedures and administrative limitations.

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Georgia Power-RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION REGARDING UPGRADED R0 AND SRO TRAINING AND TRAINING FOR MITIGATING CORE DAMAGE - NUREG-0737 ITEMS I.A.2.1.4 and II.B.4 (Continued)

RESPONSE 3 Operational Experience Assessment Reports are prepared monthly by the Plant E. I. Hatch Engineering Department and sent to all plant personnel who hold either a Reactor Operator or Senior Reactor Operator's License and all members of the training department who teach plant systems or integrated plant response.

These reports are a one month summary of pertinent operating experience information which typically consist of:

A narrative descirption of significant events on each unit A description of Licensee Event Reports A summary of Desfgn Change Requests Amendments to Technical Specifications A description of pertinent SOERs/SERs and Notepad items which are relevant to Plant Hatch Scram reports A listing of all procedures revised.

QUESTION 4 If subcontractors (i.e.,

General Physics, NUS, etc.) are used to supplenent your training staff, what actions have you taken to assure that they meet the requirements of A.2.d, A.2.e, C.2, and C.3 of to Denton's letter of March 28, 1980.

RESPONSE 4 All subcontracted instructors who teach systems, integrated responses, transient and simulator courses have been certified at the SR0 level by General Physics Corporation.

General Physics Corporation provides letters of certification for applicable instructors to Georgia Power Company stating that each individual is certified and maintains certification by participation in the General Physics requalification program.

The NRC has recently committed to administer SRO examinations to vendor personnel and General Physics Corporation, in cooperation with Georgia Power Company, has made plans for NRC certification of these t

instructics.

These plans were submitted by Georgia Power Company te the l

Director, O. vision of Licensing, Darrell G. Eisenhut, in a letter dated February 18, 1983, a copy of which is attached as enclosure 2 to this letter.

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K SPONSE TO REQUEST.FOR ADDITIONAL'IWORMATION

REGARDING UPGRADED R0 Am SRO TRAINING AFD TRAINING IFOR MITIGATING CORE DAMAGE - MJREG-0737pITEMS I.A.2.1.4 and II.B.'4 -

(Continued)'

tGeorgia PowerA:.

-QUESTION 5.

Item II.B.4 of NUREG-0737 requires that managers and technicians in the Instrumentation and Control, Health Physics and Cher11stry Departments shall receive - training commensurate with their responsibility in mitigating core damage.. Describe in detail the program to provide this training / retraining to managers and technicians in the I&C,' Health

. Physics,- and Chmistry Departments.

RESPONSE.5 Mitigating-Core Damage training for HP-Chemistry managers and technicians is accomplished through programs conducted for mmbers of the. Radiological Emergency Team 'of which the technicians of the HP-Chem

-department are members.. This training is conducted annually for each of

' these menbers ' as 'part - of ~ the training <for. the annual energency drill.

Training for I&C technicians necessary to~ assist in~ core -damage conditions is accomplished through their routine on-the-job training as part of their routine duties. '

An excerpt from procedure hbp-291, Radiological Emergency Team (RET)'

Training follows as an outline of training provided for Radiological'

' Emergency Team members.

TRAINING The training program for-instructing and qualifying personnel who will

. implement radiological energency response plans includes practical drills and demonstration of individual ability as ' well as classroom instruction.

Initial training is followed by. annual retraining.

A description of the specialized training for various categories of emergency personnel is described below.

SUMMARY

OF INITIAL EFERGENCY TRAINING Dose E.P. and Assessment RET Repair & C.A.

and Inst. and Procedure (1)

P.A.G. (2) RET (3) Analysis (4)

Emergency Director x

x TSC Manager x

x

. EOF Manager x

x x

OSC Manager x

Security Manager x

Dose Assessment Manager x

x x.

x

-Support Coordinator x

Dose Assessment Staff x

x x

x i

Communicators / Recorders x

OSC/TSC/ EOF / Remaining Staff x

Hatch RET x

x x

Offsite RET x

x When Called Page 5

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RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION

~REGARDING UPGRADED R0 APO SRO TRAINING AND TRAINING

.FOR MITIGATING CORE DAMAGE - NUREG-0737 ITEMS I. A.2.1.4 cnd II.B.4 (Continued)

= Georgialbwer A NOTES 1.

Includes Procedures and Plan overview, Summary of offsite agency response (for the top three position),

and Procedures HP-4866 (Corrective Actions) and Fff-4812 (Emergency Exposure Guides).

'2.

Includes Procedures HNP-4852 (Offsite Dose Calculations) and HP-4854 (Protective Action Guides).

3.

Includes RET Procedures and specialized training.

Certain aspects of the HNP-RET program will not be given to offsite staff.

These topics include:

First

Aid, Respiratory Protection, and Fire Protection Training, (needed for in-plant entry).

These will be given to offsite staff on an "as needed" basis.

4.

This training includes the following:

a.

Portable H.P.

Instruments (survey & frisking) for Hatch RET plus Offsite staff when called.

H.P. staff may receive credit for their routine plant activities.

b.

External Survey Team for Hatch RET plus offsite staff when called.

c.

Air isotopic analysis for permanent Hatch HP's with Chemistry assist.

d.

Post Accident Sampling for permanent Hatch Chemistry technicians with W assist.

QUESTION 6 Describe the training in primary chmistry that is provided in your operator training program for mitigating core damage as required by to Denton's letter of March 28, 1980.

RESPONSE 6 The Hatch training department has reviewed the requirements of the Denton letter and has included in the license training program the basic chemistry training determined necessary for operator understanding of changes relating to core damage occurring both from failure by corrosion as well as other damage mechanisms.

In this training, the following topics relating to chemical changes are covered:

'1)

General Corrosion 2)

Temperature & Radiation Effects on Corrosive Properties 3)

Chloride Stress 4)

Control of Chlorides in Moderator l

5)

Tech Spec Requirments l

6)

Release of Radioactive Materials to Environs During LOCA-DBA 7)

Emergency Plan conditions & Implementation 8)

Equipment used to detect moderator chemistry changes.

Page 6 700175

u ENCLOSURE 2 L

E Georgia Power Powerf OefterAt; Ort DJOJf tmerit NED-83-106 February 23, 1983 l

Mr. Darrell G. Eisenhut, Director Division of Licensing Office of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission Washington, D..C.

20555 V

NRC DOCKETS 50-321, 50-366 l

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OPERATING LICENSES DPR-57, NPF-5 EDWIN I. HATCH NUCLEAR PLANT UNITS 1, 2 l

NRC DOCKETS 50-424, 50-425 CONSTRUCTION PERMITS CPPR-108, 109 l

ALVIN W. V0GTLE NLCLEAR PLANT, UNITS 1, 2 OPERATOR LICENSING EXAMINATION SITE VISIT REQUIREMENTS THROUGH DECEMBER 1985 (GENERIC LETTER 83-01 DATED JANUARY ll, 1983)

Genti men:

In response to the subject letter, Georgia Power Company (GPC) requests NRC staff site visits to conduct operator licensing / instructor examinations l

through February 1986 on the following schedule:

Catecory of Examination:

(1) Initial (cold) license examinations for. units applying for operating licenses.

(2) Initial license examinations to extend licenses to a second, identical unit after initial licensing.

(3) Examinations to support certification of utility employees as Instructors.

(4) Examinations to support certification of individuals who are not utility splayees, but who are under contract to instruct licensed operators.

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(5) Examinations for initial licensing of - personnel at operating facilities or for upgrading a license from the Reactor Operator level to the Senior Operator level.

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Mr. ' Darrell G. Eisenhut, Director Division of Licensing Office of Nuclear Reactor Regulation February 23, 1983 Page Two toiBER OF EXAMINATIONS PROPOSED GPC BY CATEGORY DATE PLANT.

1 2

3 4

5 5

SRO RO 02/28/83 Hatch 8

6 05/23/83 Hatch 4

5 2

07/25/83 Vogtle 5

5 09/26/83 Hatch 4

5 11 11/14/83 Vogtle.

4 2

02/20/84 Hatch \\

2 2

8 3

04/16/84 Hatch 1

5 12 06/84

. Hatch 1

2 3

17 07/84 Vogtle 4

2 09/84 Hatch 14 12/84 Vogtle 3

1 07/85 Hatch 1

2 8

07/85 Vogtle 3

1 12/85 Hatch 15 02/86 Vogtle 80 If the tRC is not able to support our requested schedule, please respond to this office as soon as possible.

Very trul*/ yours,

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L. T. Gucwa Chief Nuclear Engineer G8/mb xc:

J. T. Beckham, Jr.

D. O. Foster H. C. Nix, Jr.

M. Manry J. P. O'Reilly (NRC-Region II)

Senior Resident Inspectors 700775 E_