ML20054F803
| ML20054F803 | |
| Person / Time | |
|---|---|
| Site: | Yankee Rowe |
| Issue date: | 06/11/1982 |
| From: | Kay J YANKEE ATOMIC ELECTRIC CO. |
| To: | Crutchfield D Office of Nuclear Reactor Regulation |
| References | |
| TASK-1.A.2.1, TASK-2.B.4, TASK-TM FYR-82-56, NUDOCS 8206170343 | |
| Download: ML20054F803 (7) | |
Text
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YANKEE ATOMIC ELECTRIC COMPANY 1671 Worcester Road, framir.gham, Massachusetts 01701 rTa 82-56
,Yauxes Juae 11. 1982
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United States Nuclear Regulatory Commission Washington, D. C. 20555 Attention:
Mr. Dennis M. Crutchfield, Chief Operating Reactors Branch Ho. 5
References:
(a) License No. DPR-3 (Docket 50-29)
(b) USNRC Letter to YAEC, dated May 7, 1982
Subject:
Request for Additional Information: TMI Action Plan Items I.A.2.1 and II.B.4
Dear Sir:
In response to Reference (b), the following information has been prepared and corresponds by number to each of your six requests:
1.
The referenced lectures outlined cover in detail the subject of heat transfer, fluid flow and thermodynamics as prescribed in Denton's March 28, 1980 letter. The specific material covered is outlined in Attachment I.
2.
The referenced lectures outlined cover in detail the subject of using installed plant systems to control or mitigate an accident in which the core is severely damaged.
The material is presented in a sequence that would parallel the evolution of an event that leads to severe core damage. The course outline is as follows:
l
- Introduction - Section 1
- Core Cooling Mechanics - Section 2
- Potentially Damaging Conditions - Section 3
- Recognizing Core Damage - Section 4 l
- Hydrogen Hazards During Severe Accidents - Section 5
- Radiation Monitoring - Section 6 The section on Core Cooling Mechanics emphasizes the various mechanisms available to the operator in cooling the core under both steady state and accident conditions. Heat transfer processes important in removing core decay heat are described with emphasis on fluid transport through the
/
prieary system, i.e., natural circulation.
h() t[ b 8206170343 820611 PDR ADOCK C5000029 P
United States Nuclear Regulatory Commission June 11, 1982 Attention:
Mr. Dennis M. Crutchfield, Chief Page 2 Section 3 - Fotentially Damaging Conditions provides details of specific plant behavior during abnormal events. A spectrum of transients and accident scenarios are presented to develop skills in accident mitigation.
In addition to addressing accident mitigation, emphasis is placed on potentially hazardous conditions that could lead to inadequate core cooling and, eventually, severe core damage.
In Section 4, we first consider the existence of core damage. A discussion is presented on how the response of the incore and excore nuclear instrumentation might be used to ascertain whether or not core damage has occurred. Factors af fecting the reliability and potential failure of instrumentation associated with critical parameters are de sc ribed. Alternative means of determining values in the event of instrument failures are presented.
The laat two sections (5 and 6) present potential hazards associated with a damaged core.
These include the consequences of transferring small quantities of radioactive Ifquid outside containment, hydrogen gas generation, and radiation hazards associated with a damaged core.
3.
Lectures and, where appropriate, quizzes on the subject of accident mitigation have been given to Shift Technical Advisors and Operations personnel from the Plant Manager through the operations chain to the Ifcensed operators. A list of titles of who was trained and quizzed along with an organization chart is enclosed in Attachment II.
4.
As a minimum 80 :ontract hours are involved in training and requalification programs covering heat transfer, fluid flow, thermodynamics and accident mitigation.
A breakdown of the hours is as follows:
Initial Operator Training Program
- Accident Mitigation - 40 hours4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br />
- llent Transfer, Fluid Flow and Thermodynamics - 120 hours0.00139 days <br />0.0333 hours <br />1.984127e-4 weeks <br />4.566e-5 months <br /> Operator Retraining Program
- Accident Mitigation - 40 hours4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br />
- IIcat Transfer, Fluid Flow and Thermodynamics - 40 hours4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br /> 5.
There is increased emphasis on reactor and plant transients, both normal and abnormal, as a result of Denton's March 28, 1980 letter.
The required control manipulations are given during a two-year cycle on a simulator and plant walk-throughs are conducted during training and retraining programs.
United Stetos Nuclect R.2gulatory Cc=ziesicn June 11, 1982 Attention:
Mr. Dennis M. Crutchfield, Chief Page 3 6.
In compliance with Item II.B.4 we have developed a Mitigating Core Damage Training Manual. The manual is divided into six sections as follows:
Section Number Title / Description Training Hrs.
1.0 Introduction 1
2.0 Core Cooling Mechanics 3
3.0 Potentially Damaging Conditions 8
3.1 Transients & Accidents 3.2 LOCA 8
4.0 Recognizing Core Damage 4
4.1 Incore 4.2 Excore 4
4.3 Vital Instrumentation 4
5.0 Hydrogen Hazards During Severe Accidents 2
5.1 Gas Generation 5.2 Chemistry 2
6.0 Radiation Monitoring 4
In addition each licensed operator receives 20 hours2.314815e-4 days <br />0.00556 hours <br />3.306878e-5 weeks <br />7.61e-6 months <br /> of simulator sessions per year and 20 hours2.314815e-4 days <br />0.00556 hours <br />3.306878e-5 weeks <br />7.61e-6 months <br /> of simulator classroom sessions per year.
We trust this information is satisfactory; however, if you have any further questions, please contact us.
Very truly yours, YANKEE ATOMIC ELECTRIC COMPANY
. Kay Senior Engineer - Licensing JX/ kip
HEAT TRANSFER, FIBID FIlW AND 'DEIMXWNAMICS Outline of Topics Terrperature Mass and Weight Voltane, Density, Specific voltane Pressure Pressurizer Invel Indication Energy and Wrk Specific Heat 4
i lleat Required to Change Teperature Tmperature Equilibrium i
licat Transfer Fate Delta T as a Measure of Power Mass Flow Rate 'Ihrough a Pipe Power, Efficiency PmPS Net Positive Suction licad ifydraulic florsepower Pmp Iaws Natural Circulation Types of IIcat Transfer i
Overall IIcat Transfer Saturation l
Iatent Heat,IIcat of Fusion-ONB 1
Ilot Channel Factors Steam Quality, Percent bbisture, Void Fraction Enthalpy Enthalpy of a Mixture Entropy Carnot cycle bbllier Diagram Throttling Process i
Pressurizer Behavior Steam Cycle Efficiency 4
ATT70MNI' I l
Page 1 of 2
'Ihe following is a list by titles of those trained in Mitigating Core Darrage in 1981:
Cortpleted Entire Program with Quiz Plant Superintendent Assistant Plant Superintendent Training Manager Manager - Plant Operations Manager - Plant Chemistry Manager - Beactor Engineering Manager - Fadiation Protection Manager - Plant Maintenance Manager - Technical Services Assistant Manager - Plant Operations Senior I & C Engineer Senior Maintenance Engineer Senior Instructor Operations Engineer Nuclear Engineer I & C Supervisor Maintenance Supervisor Shift Supervisor Control Poom Operators Note: This list represents the M.C.D. training given by title in 1981. Due to a realignment in organizational structure the Technical Director position was not filled until the last quarter; therefore, that position was not trained in 1981.
ATTAONENT II
Page 2 of'2
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