ML19305D640
| ML19305D640 | |
| Person / Time | |
|---|---|
| Site: | 05000516 |
| Issue date: | 03/28/1980 |
| From: | Harold Denton Office of Nuclear Reactor Regulation |
| To: | Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML19305D635 | List: |
| References | |
| TASK-1.A.2.1, TASK-2.B.4, TASK-TM TAC-44188, TAC-44189, TAC-44538, TAC-44539, NUDOCS 8004150319 | |
| Download: ML19305D640 (20) | |
Text
,
cMucu k'
UNITED STATES
+
[\\
g NUCLEAR REGULATORY COMMISSION C
WASHINGTON, D. C. 20555 p
MR 2 8 7380 i
AIL POLER REACIOR APPLICANTS AND LICENSEES Gentlemen:
SUBJECT:
QUALIFICATIONS OF REACIOR OPERA'IORS In a letter dated Septanber 13, 1979, we informed you of NRR requirements established as of that date based on our review of the 'IMI-2 accident. to the letter outlined the staff recomnendations concerning inprovements in the area of operator training for your information.
Since that time, the Coandssion has acted on the staff recoamendations.
It is the purpose of this letter to set forth the revised criteria to be used by the staff in evaluating reactor operator training and licensing that can be inplemented under the current regulations and to establish an effective date for their inplementation.
Other criteria that will be established require additional staff work are also addressed.
- However, inplementation dates cannot be provided at this time.
Coamission review in the area of operator training and qualification is continuing and can be expected to result in additional criteria.
Finally, requirements will be established through rule making proceedings.
- details the revised criteria and the effective date for their inplementation.
Your attention is specifically directed to Sections A,
B and C of Enclosure 1 since these call out new criteria that will be implemented in the near future; therefore, your plans regarding training and licensing activities should be prouptly revised to conform to these criteria.
Enclosures 2 and 3 provide guidance for establishing training programs in heat transfer, fluid flow and thernodynamics; and mitigating core damage. details control manipulations for requalification programs.
i Based on our understanding of the industry's reasons for establishing the l
Institute of Nuclear Power Operations and our review of the latest l
revisions to applicable ANSI standards, we believe you share our desire to significantly upgrade the requirements for operations personnel.
8004150 3l9
2-herefore, we urge you to effect the implementation of the criteria as soon as practicable rather than wait for the stated inplementation date.
Also, we urge you to start planning for the long range require-rents so that they nny be rapidly inplenented upon cocpletion of the rule making procedure.
MS$
n Harold R. Denton, Director Office of Nuclear Reactor Regulation Enclosures.
1.
Requirerrents for Reactor Operator Training and Licensing 2.
Training in Heat Transfer, Fluid Flow and %ermodynamics 3.
Training Criteria For Mitigating Core Daruge 4.
Control Manipulations b
ENCIDSURE 1 CRITERIA FOR REACIOR OPERA'IOR TRAINING AND LICENSING A.
Eligibility Requirements to be Administered an Examination.
1.
Fa erience*
Applicants for' senior operator licenses shall have 4 a.
years of responsible power plant experience. Responsible power plant experience should be that obtained as a control room operator (fossil or nuclear) or as a power plant staff engineer involved in the day-to-day 8
activities of the facility, cmmencing with the final year of construction.
A maximum of 2 years power i
plant experience may be fulfilled by academic or related technical training, on a one-for-one time basis. 'Ibo years shall be nuclear power plant experience.
At least 6 nonths of the nuclear power plant experience shall be at the plant for which he seeks a license.
i w
Effective date:
Applications received on or after May 1, 1980.
e
- Precritical applicants will be required to neet unique qualifications designed to acccxmodate the fact that their facility has not yet been in operation.
I l
n.
J
b.
Applicants for senior operator licenses shall have held an operator's license for 1 year.
Effective date:
Applications received after Decenber 1, 1980.
2.
Training a.
Senior operator *:
Applicants shall have 3 renths of shift training as an extra man on shift.
b.
Control room operator *:
Applicants shall have 3 nonths training on shift as an extra person in the control room.
Effective date:
Applications received after August 1, 1980.
c.
Training programs shall be nodified, as necessary, to provide:
1)
Training in heat transfer, fluid flow and therno-dynamics.
2)
Training in the use of installed plant systems to control or mitigate an accident in which the core is severely damaged.
l 3)
Increased emphasis on reactor and plant transients.
l
- Precritical applicants will be required to meet unique qualifications designed' to accomodate the fact that their facility has not yet been in e
. Effective date:
Present programs have been modified in response to Bulletins and Orders. Revised programs should be submitted for OLB review by August 1,1980.
d.
Training center and facility instructors who teach systens, integrated responses, transient and simulator courses shall demnstrate their cocpetence to NRC by successful completion of a senior operator examination.
Effective date:
Applications should be submitted no later than August 1,1980 for individuals who do not aircady hold a senior operator license.
e.
Instructors shall be enrolled in appropriate requal-ification programs to assure they are cognizant of current operating history, problems, and changes to procedures and administrative limitations.
Effective date:
Programs should be initiated 'ay 1, 1980.
Programs should be submitted to OLB for review by August 1, 1980, i
3.
Facility Certifications Certifications completed pursuant to Sections 55.10(a)(6) and 55.33a(4) and (5) of 10 CFR Part 55 shall be signed by the highest level of corporate management for plant operation l
(for exaaple, Vice President for Operations).
L k_
A
Effective date:
Applications received on or after thy 1, 1980.
B.
NRC Examinations 1.-
Increased Scope o! Examinations a.
A new categcry shall be added to the operator written examination entitled, " Principles of Heat Transfer and Fluid Mechanics."
b.
A new category shall be added to the senior operator written examination entitled, "Iheory of Fluids and Thermodynamics."
c.
Time limits shall be inposed for completion of the written examinations:
1.
Operator:
9 hours1.041667e-4 days <br />0.0025 hours <br />1.488095e-5 weeks <br />3.4245e-6 months <br />.
2.
Senior Operator:
7 hours8.101852e-5 days <br />0.00194 hours <br />1.157407e-5 weeks <br />2.6635e-6 months <br />.
d.
The passing grade for the written examination shall be 80%
overall and 70% in each category.
e.
All applicants for senior operator licenses shall be required to be administered an operating test as well as the written examination.
f.
Applicants will grant permission to NRC to inform their facility management regarding the results of the exam-inations for purposes of enrollment in requalification programs.
Effective date:
Examinations. administered on or after thy 1, 1980 for items a. through e.
Applications received on or after May 1,1980 for Iten f.
C.
Requalification Programs 1.
Content of the licensed operator requalification programs shall be nodified to include instruction in heat transfer, fluid flow, thermodynamics and mitigation of accidents involving a degraded core.
Effective date: May 1, 1980.
2.
The criteria for requiring a licensed individual to participate in accelerated requalification shall be nodified to be consistent with the new passing grade for issuance of a license 80%
overall and 70% each category.
Effective date:
Concurrent with the next facility administered annual requalification examination after the issue date of this letter.
3.
Programs should be podified to require the control manipulations listed in Enclosure 4.
Normal control manipulations, such as plant or reactor startups, nust be performed.
Control man-ipulations during abnormal or emergency operations nust be walked through with, and evaluated by, a nember of the~ training staff at a mininum.
An appropriate sinulator may be used to satisfy the requirements for control manipulations.
Effective date: Prograns nodified by August 1,1980.
Renewal applications received after November 1,
1980 nust reflect compliance with the program.
D.
Ione Range Criteria and/or Requirements
'Ihe following require additional staff wrk and/or n21emaking prior to their implementation.
1.
Qualifications a.
Shift supervisors shall have an engineering degree or equivalent qualifications.
b.
Senior operators shall have successfully completed a course in appropriate engineering and scientific subject equal to 60 credit hours of college level subjects.
2.
Training a.
All applicants shall attend simulator training programs.
Required control manipulations and exercises to be performed shall be the same for
" cold" and ' hot" applicants.
b.
Eligibility requirements shall be developed for instructors, in addition to that listed in A.2 above.
I 3.
NRC Fxuninations a.
NRC shall administer the certification examinations that are presently administered at the conclusion of the off-site portion of the cold training programs.
1 b.
All applicants shall be required to be administered a sinulator examination in addition to the written exam-inations and plant oral tests.
c.
NRC shall administer the requalification program annual examination.-
l l
4 Reaualification Programs All licensees shall ' participate in sinulator programs as part of the requalification programs. Control manipulations shall be performed pursuant to Enclosure 4.
I 1
r
.[
t l
O f
i i
l l
ENCIDSURE 2 TRAINING IN HEAT TRANSFER, FLUID Film AND 'IFERM0 DYNAMICS 1.
Basic Properties of Fluids and Matter.
'Ihis section should cover a basic introduction to matter and its properties.
'Ihis section should include such concepts as tmperature neasurements and effects, density and its effects, specific weight, buoyancy, viscosity and other properties of fluids.
A working knowledge of steam tables should also be included.
Energy novement should be discussed including such fundamentals as heat exchange, specific heat, latent heat of vaporization and sensible heat.
2.
Fluid Statics.
'Ihis section should cover the pressure, temperature and volume effects on fluids.
Franple of these parametric changes should be illustrated by the instructor and related calculations should be performed by the students and discussed in the training sessions.
Causes and effects of pressure and temperature changes in the various components and systems should be discussed as applicable to the facility with particular enphasis on safety significant features.
'Ihe characteristics of force and pressure, pressure in liquids at rest, principles of hydraulics, saturation pressure and temperature and subcooling should also be included.
3.
Fluid Dynamics.
'Ihis section should cover the flow of fluids and such concepts as Bernoulli's principle, energy in noving fluids, flow measure theory and devices and pressure losses due to friction and orificing.
Other concepts and terms to be discussed in this section are NPSH, carry over, carry under, kinetic energy, head-loss relationships and two phase
flow fundamentals. Practical applications relating to the reactor coolant system and steam generators should also be included.
4.
Heat Transfer by Conduction, convection and Radiation.
This section should cover the fundanentals of heat transfer by conductions. This section should include discussions on such concepts and terms as specific heat, heat flux and atomic action. Heat transfer characteristics of fuel rods and heat exchangers should be included in this section.
This section should cover the fundamentals of heat transfer by con-vection. Natural and forced circulation should be discussed as applicable to the various systems at the facility. The convection current patterns created by expanding fluids in a confined area should be included in this section. Heat transport and fluid flow reductions or stoppage should be discussed due to steam and/or noncondensible gas formation during normal and accident conditions.
This section should cover the fundamentals of heat transfer by thermal radiation in the form of radiant energy. The eletromagnetic energy emitted by a body as a result of its temperature should be discussed and illustrated by the use of equations and sanple calculations. Conparisons should be made of a black body absorber and a white body enitter.
5.
Change of Phase - Boiling.
This section should include descriptions of the state of matter, their inherent characteristics and thernodynamic properties such as enthalpy and entropy.
Calculations should be performed involving steam quality and void fraction properties.
The types of boiling should be discussed as applicable to the facility during norm 1 evolutions and accident conditions.
6.
Burnout and Flow Instability.
'Ihis section should cover descriptions and nechanisms for calculating such terms as critical flux, critical power, D:3 ratio and hot channel factors.
' Ibis section should also include instructions for preventing and nonitoring for clad or fuel damage and flow instabilities.
Sample calculations should be illustrated by the instructor and calculations should be perforced by the students and discussed in the training sessions. Methods and procedures for using the plant computer to determine quantitative values of various factors during plant operation and plant heat balance determinations should also he covered in this section.
l l
7.
Reactor Heat Transfer Limits.
'Ihis section should include a discussion of heat transfer limits by examining fuel rod and reactor design and limitations.
'Ihe basis for the limits should be covered in this section along with recocrended ruthods to ensure that limits are not approached or exceeded.
'Ihis section should cover discussions of peaking factors, radial and axial power distributions and changes of these factors due to the influence of other variables such as noderator temperature, xenon and control rod position.
! a
Suggested
References:
Collier, J. G. Convection Boiling and Condensation.
New York:
McGraw-Hill, 1972.
~
Eckert, E. R. G. and Drake, R.
M., Jr. Analysis of Heat and Mass Transfer.
New York: McGraw-Hill, 1973.
El-Wakil, M. M. Nuclear Heat Transport. Scranton, PA:
Internr.tional, 1971.
Gebhart, B.
Heat Transfer.
2nd ed. New York: McGraw-Hill, 1971.
- Mooney, D.
Mechanical Engineering Thermodynamics.
Prentice Hall, 1953.
I
^-
ENCLOSURE 3
'IRAINING CRITERIA FOR MITIGATING CORE DA!iAGE A program is to be developed to ensure that all operating personnel are training in the use of installed plant systems to control or mitigate an accident in which the core is severely damaged.
'Ihe training program should include the following topics.
A.
Incore InstruTentation 1.
Use of fixed or novable incore detectors to determine extent of core dann and gecmtry changes.
2.
Use of thernoccuples in determining peak temperatures; methods for extended range readings; methods for direct readings at terminal junctions.
3.
Methods for calling up (printing) incore data from the plant computer.
B.
Excore Nuclear Instrumentation (NIS) 1.
Use of NIS for determination of void formation; void location basis for NIS response as a function of core tetiperatures and density changes.
C.
Vital Instrucentation 1.
Instrumentation response in an accident environment; failure sequence (time to failure, nethod of failure); indication reliability (actual vs indicated level).
2.
Alternative nethods for nuasuring flows, pressures, levels, and tenperatures.
a.
Detemination of pressurizer level if all level transmitters
- fail, b.
Determination of Ictdown flow with a clogged filter (low floa).
c.
Detemination of other Reactor Coolant System parameters if the primary method of neasurement has failed.
D.
Primary Chemistry 1.
Fxpected chemistry results with severe core damages consequences of transferring smil quantities of liquid outside containment: inportance of using leak tight systems.
2.
Fxpected isotopic breakdoan for core damages for clad damage.
3.
Corrosion effects of extended imersion in primary waters time to failure.
E.
Radiation ibnitoring 1.
Response of Process and Area Ibnitors to severe damages behavior of detectors when saturated nethod for detecting radiation readings by direct reasurement at detector output (overranged detector); expected accuracy of detectors at different locations; use of detectors to determine extent of core damge.
2.
Methods of determining dose rate inside containment from neasurerents taken outside contalment.
s i
F.
Gas Generation 1.
Methods of g generation during an accidents other sources of gas (Xe, Ke): techniques for venting or disposal of non-condensibles.
2.
g flannability and explosive limits sources of 0 in containment or 2
t 1
f l
5 6
e e
i 1
l i l I
I
DCDSL'RE 4 00.VBOL !WIIPUIATIONS The following control manipulations and plant evolutions where applicable to the plant design are acceptable for meting the reactivity control manipula-tions required by Appendix A, Paragraph 3.a. of 10 CFR Part 55. The starre' items shall be performed on an annual basis all other item shall be performed on a two-year cycle.
Ikmever, the requalification programs shall contain a ccnnitment that each individual shall perform or participate in a ecmbination of reactivity control manipulations based on the availability of plant equipment and systems.
'Ihose control manipulations which are not performed at the plant may be perforned on a simulacor. The use of the Technical Specifications should be muimized during the simulator control manipulations.
Personnel with senior licenses are credited with these activities if they direct or evaluate contro1~ manipulations as they are performed.
PWR/B'a/HIUR
- (1)
Plant or reactor startups to include a range that reactivity feedback from nuclear heat addition is noticeable and heatup rate is established.
(2)
Plant shutdown.
- (3)
Manual control of steam generators and/or feedwater during startup and shutdom.
(4)
Boration and or dilution during power operation.
- (5)
Any significant ( > 10%) power changes in manual rod control or recirculation flow.
l (6)
Any reactor pcwr change of 10% or greater where load change is performed with load limit control or where flux, temperature, er speed control is on nanual (for HIUR).
- (7)
Toss of coolant including:
1.
significant RR steam generator leaks 2.
inside and outside primary contairrent 3.
large and smil, including leak-rate determination 4
saturated Reactor Coolant response (RR).
(8) loss of instrumnt air (if sinulated plant specific).
(9)
Ioss of electrical power (and/or degraded power sources).
- (10)
Ioss of core coolant ficw/ natural circulation.
(11)
Ioss of condenser vacu m.
(12)
Ioss of service water if required for safety.
(13)
Ioss of shutdown cooling.
(14)
Ioss of cmponent cooling system or cooling to an individual component.
(15)
Loss of penm1 feedwater or norm 1 feedwater system failure.
- (16)
Ioss of all feedwater (norm 1 and emrgency).
(17)
Ioss of protective system channel.
(18) itispositioned control rod or rods (or rod drops).
(19)
Inability to drive control rods.
(20)
Conditions requiring use of energency boration or standby liquid control systen.
(21)
Fuel cladding failure or high activity in reactor coolant or offgas.
(22)
'Ihrbine or generator trip.
(23)
Fh1 function of autor.atic control system (s) which affect reactivity.
.(24) tialfunction of reactor coolant pressure / volume control system.
(25)
(26) ifain steam line break (inside or outside containment).
(27) tbclear instrumntation failure (s).
UNITED STATES OF~ AMERICA NUCLEAR REGULATORY COMMISSION BEFORE THE ATOMIC SAFETY AND LICENSING APPEAL BOARD In the Matter of LONG ISLAND LIGHTING COMPANY Docket Nos. 50-516
)
50-517 (Jamesport Nuclear Power Station, Units 1 and 2)
CERTIFICATE OF SERVICE I hereby certify that copies of "NRC STAFF STATUS REPORT", dated April 11, 1980, in the above-captioned proceeding, have been served on the following, by deposit in the United States mail, first class, or, as indicated by an asterisk through deposit in the Nuclear Regulatory Commission's internal mail system, this lith day of April,1980.
- Dr. W. Reed Johnson Dr. E. Leonard Cheatum Atomic Safety and Licensing Appeal Route #3, Box 350A Board Watkinsville, Georgia 30677 U.S. Nuclear Regulatory Comission Washington, D. C.
20555 Edward J. Walsh, Jr., Esq.
Long Island Lighting Company
- Richard S. Salzman, Esq.
250 Old County Road Atomic Safety and Licensing Appeal Mineola, New York 11501 Board U.S. Nuclear Regulatory Comission W. Taylor Reveley, III, Esq.
Washington, D. C.
20555 Hunton & Williams P. O. Box 1535
- Sheldon J. Wolfe, Esq.
Richmond, Virginia 23212 Atomic Safety and Licensing Board U.S. Nuclear Regulatory Comission Mr. A. E. Kintigh i
Washington, D. C.
20555 Vice President-Generation New York State Electric & Gas Co.
Mr. Ralph S. Decker 4500 Vestal Parkway East Route 1, Box 190D Binghampton, New York 13902 Cambridge, Maryland 21613 Environmental Protection and Hon. Peter Cohalan Progress Comittee Suffolk County Executive Local 25, I. B. E. W.
County Executive / Legislative Bldg.
Box 997 1
Veteran's Memorial Highway 41 Pinelawn Road l
Hauppauge, New York 11788 Melville, New York 11746 l
David H. Gilmartin, Esq.
l Suffolk County Attorney County Executive / Legislative Bldg.
Veteran's Memorial Highway Hauppauge New York 11788
, Joel Blau, Esq.
Jeffrey E. Stockhola, Esq.
Frederick H. Lawrence, Esq.
New. York State' Dept. of Public Service Huber, Magill, Lawrence The Governor Nelson A. Rockefeller and Farrell Empire State' Plaza 99 Park Avenue Albany, New York 12223 New York, New York 10016 Dr. Caryl R. Granttham Ira Lee Zebrak, Esq.
Co-Chairman, Concerned Citizens Huber, Magill, Lawrence of Suffolk County and Farrell Box 550 99 Park Avenue Jamesport, New York 11947 New York, New York 10016 Ms. Jean H. Tiedke Dr. Arthur Tamplin Box 1103 c/o Natural Resources Defense Southold, New York 11971 Council 917 - 15th Street, N.W.
Dr. Harris Fischer Washington, D. C.
20005 Suffolk County Department of Environmental Control
- Atomic Safety and Licensing 1324 Motor Parkway
)
f Hauppauge, New York 11787 f ucl r Regulatory Commission U.
Irving Like, Esq.
Washington, D. C.
20555 Reilly and Like 200 West Main Street
- Atomic Safety and Licensing P.O. Box 218 Board Panel Babylon, New York 11702 U.S. Nuclear Regulatory Commission Washington, D. C.
20555 Mrs. Laetitia deK. Bradley 144 Quaker Path
- Docketing and Service Section Setauket, New York 11733 Office of the Secretary U.S. Nuclear Regulatory Comission Ms. Shirley L. Bachrach Washington, D. C.
20555 Box 1054 Southold, New York 11971 Jeffrey Cohen, Esq.
Deputy Commissioner and Counsel Ms. Adelaide Flatau New York State Energy Office 30 Dartmouth Road cy 1
Shoreham, New York 11786 ye at a
Albany, New York 12223 William C. Chapek Box 997 Melville, New York 11746 Joseph C. Gramer, Esq.
425 Broadhollow Road M
Melville, New York 11746
' Bernard M. Bordenick Counsel for NRC Staff Carl G. Dworkin, Esq.
Senior Attorney for Energy New York State Department of Environmental Conservation 50 Wolf Road Albany, New York 12233