ML19327A530
| ML19327A530 | |
| Person / Time | |
|---|---|
| Site: | Farley  |
| Issue date: | 07/29/1980 |
| From: | Clayton F ALABAMA POWER CO. |
| To: | Schwencer A Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 8008060333 | |
| Download: ML19327A530 (3) | |
Text
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Alabama Power Company 600 North 18th Street Post Office Bo:: 2641 Crmingham, Al bams 35291 Telephone 205 323-5341 k
h
~
Alabama Power S"o o ce r sid nt
'"* S" **"'* 85"
July 29, 1980 Director Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission Washington, D. C.
20555 Attention: Mr. A. Schwencer TMI-2 ACTION PLAN ITEM JOSEPH M. FARLEY NUCLEAR PLANT - UNIT 2 Gentlemen:
As requested'by the NRC staff, Alabama Power Company submits the enclosed information regarding item II.B.4.
If you have any questions concerning these items, please advise.
Yours very truly, h f C$n%
F. L. Clayton,' Jr.
BDM/rt Enclosure cc: Mr. R. A. Thomas Mr. G. F. Trowbridge Mr. L. L. Kintner Mr. W. H. Bradford SoeI s
II
-8008060 s'33 g
II.B.4 TRAINING FOR MITIGATING CORE DAMAGE Request Provide a program description for the Farley Nuclear Plant mitigating core damage training program.
Response
FNP will develop a training program to instruct all licensed operating personnel in the use of installed systems, including systems that are not engineered safety features, and instrumentation to monitor and control accidents in which the core may be severely damaged. The training program will include the following topics:
A.
Incore Instrumentation (3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br />) 1.
Use of fixed or movable incore detectors to determine extent of core damage and geometry changes.
2.
Use of thermocouples in determining peak temperatures; methods for extended range readings; methods for direct readings at terminal junctions.
3.
Methods for calling up (printing) incoie data from the plant computer.
B.
Excore Nuclear Instrumentation (NIS) (3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br />) 1.
Use of NIS for determination of void formation; void location basis for NIS response as a function of core temperatures and density changes.
C.
Vital Instrumentation (3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br />) 1.
Instrumentation response in an accident environment; failure sequence (time to failure, method of failure); indication reliability (actual vs. indicated level).
2.
Alternative methods for measuring flows, pressures, levels, and temperatures, a.
Determination of pressurizer level if all level transmitters
- fail, b.
Determination of letdown flow with a clogged filter (low flow).
c.
Determination of other Reactor Coolant System parameters if the primary method of measurement has failed. l
D.
Primary Chemistry (3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br />) 1.
Expected chemistry results with severe core damage; consequences of transferring small quantities of liquid outside containment; importance of using leak tight systems.
2.
Expected isotopic breakdown for core damage; for clad damage.
3.
Corrosion effects of extended immersion in primary water; time to failure.
E.
Radiation Monitoring (2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />) 1.
Response of Process and Area Monitors to severe damages; behavior of detectors when saturated; method for detecting radiation readings by direct measurenent at detector output (overranged detector); expected accuracy of detectors at different locations; use of detectors to detennine extent of core damage.
2.
Methods of determining dose rate inside containment from measurements taken outside containment.
F.
Gas Generation (1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />) 1.
Methods of H2 generation during an accident; other sources of gas (Xe, Ke); techniques for venting or disposal of non-condensibles.
2.
H flammability and explosive limit; sources of 02 in containment p
or Reactor Coolant System. -
.