ML17138B598
| ML17138B598 | |
| Person / Time | |
|---|---|
| Site: | Susquehanna  |
| Issue date: | 11/20/1980 |
| From: | Tedesco R Office of Nuclear Reactor Regulation |
| To: | Curtis N PENNSYLVANIA POWER & LIGHT CO. |
| References | |
| NUDOCS 8012040617 | |
| Download: ML17138B598 (13) | |
Text
NOY 20 1980 Docket Nos.:
50-387 and 50-388 Mr. Norman W. Curtis Vice President - Engineering and Construction Pennsylvania Power and Light Company Two North Ninth Street Allentown, Pennsyl vania 13101
Dear Mr. Curtis:
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Subject:
Susquehanna Steam Electric Station,, Units Nos for Additional Information 1 and 2 - Request As a result of our review of your application for operating licenses for the Susquehanna Steam Electric Plant, we find that we need additional information in the area of operator licensing.
The specific information required is listed in the Enclosure.
If you desire any discussion or clarification of,ttie,iiiformation requested, please contact R.
M. Stalk, Licenqing Project,thnager, (301-,492-7238).
Sincerely,
'Original signed by Robort L, Tedcsco Encloqqre:
I As stated cc w/encl.'.
See next page Robert L. Tedesco, Assistant Director for. Licensing Division of Licensing OFFICE SURNAME DATEI.
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4U.S. GOVERNMENT PRINTI G OFFICEi 1979'289'369
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Mr. Norman W. Curtis Vice President
- Engineering and Construction Pennsylvania Power and Light Company 2 North Ninth Street Al 1 entown, Pennsyl vani a 18101 CC:
Mr. Earle H. Mead Project Engineering Manager Pennsylvania Power 8 Light Company 2 North Ninth Street Allentown, Pennsylvania 18101 Jay Silberg, Esq.
- Shaw, Pittman, Potts 5
Trowbridge 1800 M Street, N.
W.
Washington, D.
C.
20036 Hr. William E. Barberich, Nuclear Licensing Group Supervisor Pennsylvania Power 5 Light Company 2 North Ninth Street Al 1 entown, Pennsyl vania 18101 Edward M. Nagel, Esquire General Counsel and Secretary Pennsylvania Power 5 Light Company 2 North Ninth Street Allentown, Pennsylvania 18101 Bryan Snapp, Esq.
Pennsylvania Power 8 Light Company 2 North Ninth Street Allentown, Pennsylvania.
18101 Robert M. Gallo Resident Inspector P.
0.
Box 52 Shickshinny, Pennsylvania 18655 John L.;;Anderson Oak Ridge National Laboratory Union Carbide Corporation Bldg. 3500, P. 0.
Box X
Oak Ridge, Tennessee 37830 Gerald R. Schultz, Esq.
Susquehanna Environmental Advocates PE 0, Box 1560 Wikes-Barre,'ennsylvania 18703 Mr. E.B. Poser Project Engi,neer Bechtel Power Corporation P. 0.
Box 3965 San Francisco, California 94119 Matias F. Travieso-Diaz, Esq.
Shaw, Pittman, Potts 5
Trowbridge 1800 M Street, N.
W.
Washi'ngton, D.
C.
20036 Dr. Judith H. Johnsrud Co-Director Environmental Coalition on Nuclear Power 433 Orlando Avenue State College, Pa 16801 Hr. Thomas M. Gerusky, Director Bureau of Radiation Protection Department of Environmental Resources Comnonwealth of Pennsylvania P. 0.
Box 2063 Harrisburg, Pa 17120 Ms. Colleen Marsh Box 538A, RDb'4 Mountain Top, PA 18?07 Hrs. Irene Lemanowicz, Chairperson The Citizens Against Nuclear Danagers P. 0.
Box 377 RDgl
- Berwick, PA 18503 Mr. J.W. Millard Project MAnager Hail Code 394 General Electric Company 175 Curtner Avenue San Jose, California 95125
P 4
Attachment A
SSES must commit to following the guidance of Section 5.5.2 of ANSI N18.1-1971 in the training conducted for replacement personnel
I L,
441.12 (Item II.a.4 of NUREG-0694)
The staff requires that the applicant develop a program to ensure that all operating personnel are trained in the use of installed plant 'systems to control or mitigate an accident in which the core is severely damaged.
The training program shall be completed prior to Full Power Operation and shall include the following topics:
(1)
Incore Instrumentation (a)
Use of fixed or movable incore detectors to
'etermine extent of core damage and geometry changes.
(b)
Use of'hermocouples in determining peak temper-atures; methods for 'extended range readings; methods for direct readings at terminal junctions.
(2)
Excore Nuclear Instrumentation NIS (a)
Use of NIS for determination of void information; void location basis for NIS response as a function of core temperatures and density changes.
(3)
Vital Instrumentation I
(a)
Instrumentation response in an accident environment; failure sequence (time to failure, method of fail-ure); indication reliability (actual vs indicated level),
(b)
Alternative methods for measuring flows, pres-
- sures, levels, and temperatures.
(i)
Determination of pressurizer level if'-all level transmitters fail.
(ii) Determination of letdown flow with a clogged filter (low flow)
(iii) Determination of other Reactor Coolant System parameters if the primary method of measurement has failed.
(4)
Primar Chemistr 4
(a)
Expected chemistry results with severe core damage; consequences of transferring small quantities of liquid outside containment; importance of 'using leak tight systems.
(b)
Expected isotopic breakdown for core damage; for clad damage.
(c)
Corrosion effects of extended immersion in primary water; time to failure.
I t
(5)
Radiation Monitorin (a)
Response
to Process and Area Monitors to severe damages; behavior of detectors when saturated;.
method for detecting radiation readings by direct measurement at detector output (overanged detector);
expected accuracy of detectors at different loca-tions; use of detectors to determine extent of core damage.
(b)
Methods of determining dose rate inside contain-ment from measurements taken outside containment.
(6)
Gas Generation (a)
Methods o'f HZ generation during an accident; other sources of gas (Xe, Kr); techniques for venting or disposal of non-condensibles.
(b)
H2 flammability and explosive limit, sources of 0~ in containment or Reactor Coolant System.
The operating personnel who receive this training must include the Station Superintendent, his assistant, Shift Technical Advisors, licensed operators, and all other members of the operating staff whose skills would be utilized during degraded core conditions.
Chemistry, Health Physics, and ICS personnel should receive training in those areas applicable to their duties,
441.13 (Item I.A.2.3, of NUREG-0694)
(1)
Training instructors who teach
- systems, integrated responses, transients and simulator courses shall successfully complete a
SRO examination.
(2)
Instructors shall attend appropriate retraining programs that address, as a minimum, current operating history, problems and changes to procedures and administrative limitations.
In the event an instructor is a licensed SRO, his retraining shall be the SRO requalification program.
441.14 (Item I.A.2.1 of NUREG-0694)
(1)
Applicants for SRO license shall have 4 years of responsible power plant experience, of which at least 2 years shall be nuclear power plant experience (including 6 months at the specific plant) and no more than 2 years shall be academic or related technical training.
(2)
Certifications that operator license applicants have learned to operate the controls shall be signed by the highest level of corporate management for plant operation.
(3)
Revise training-programs,to include training in heat transfer, fluid flow, thermodynamics, and plant transients.
(1)
Applicants for operator licenses will be required to T
grant permission to the NRC to inform their facility management regarding the results of examinations.
(2)
Content of the licensed operator requalification pro-gram shall be modified to include instruction in heat
. transfer, fluid flow, thermodynamics, and mitigation of accidents involving a degraded core.
('3)
The criteria for requiring a licensed individual to participant in accelerated requalification shall be modified to be consistent with the new passing grade for issuance of a license.
(4)
Requalification programs shall be modified to require specific reactivity control manipulations.
Normal control manipulations, such as plant or reactor start-
- ups, must be performed.
Control manipulations during abnormal or emergency operations shall be walked through and evaluated by a member of the training staff.
An appropriate simulator may be used to satisfy the requirements for control manipulations.