ML20037B875
| ML20037B875 | |
| Person / Time | |
|---|---|
| Issue date: | 10/30/1980 |
| From: | Kreger W Office of Nuclear Reactor Regulation |
| To: | Ross D Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML19295F938 | List: |
| References | |
| FOIA-81-381 NUDOCS 8101070258 | |
| Download: ML20037B875 (3) | |
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OCT 3 01930 NOTE TO: Denwood F. Ross, Jr., Director, DSI FROM:
William E. Y,reger, Assistant Director for Radiation Protection, DSI
SUBJECT:
DEGRADED COOLING STEERING GROUP In accordance with your request of October 27, 1980, I've reviewed our work that may be related to Degraded Cooling Rulemaking.
1.
Accident Impact Analyses - In AEB there is the current activity in doing site specific accident impact analyses for plants for which a final environmental statement has not been issued. Although these analyses consider accident release information,and generate subsequent radiological impact results, they are not modifying source terms or looking at accidents other than those described by proposed Annex to Appendix D to 10 CFR Part 50 and the RSS.
I would expect this project to use the results of the degraded cooling rulemaking, but not to gen-erate input, to that effort.
2.
TMI Action Plan items - As is mentioned in 45 FR 65466 of October 2, 1980, there are a number of TMI items that relate to degraded core and cooling.
Those in my area are as follows:
a.
Protection of Safety Equipment and Areas which may be used during and following an accident (555.44a(b)(1)).
Task action plan II.B.2. Plant Shielding, concerns itself with post ac;cident procedural controls and increased permanent or '
temporary shielding to protect people and equipment after an accident.
RAB has the action.
Operating reactors are to have i
available final design details for review by January 1,1981 and have plant modifications completed by January 1,1982 or the first outage thereafter.
Operating license applicants are to submit a sumary of the shielding design review, etc. Source terms for now are specified in NUREG-737 to be equivalent to those in Reg. Guide
- 1. 3, 1. 4, 1. 7 and SRP 15.6.5 with appropriate decay terms based on plant design.
This activity may receive useful input from licen-sees and applicants regarding most appropriate source terms, although it is likely they will just use the guidance mentioned tbove.
b.
In Plant Iodine Instrumentation (555.44a(b)(2)).
Task Action Plan II.F.1. At.tachment 2, Sampling and Analysis of Plant Effluents," concerns post accident iodine sampling and 10b-oratory analysis.
ETSB has the lead on this item. The requirement
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- Denwood F. Ross, Jr. i applies to all operating reactors and applicants for operating license.
It is to be implemented by January 1,1982, with post implementation review.
Licensees and applicants are to submit final design description of as built systems for those needing to meet that date.
By January 1,1981 OR's are to have available for review the final design details. OL applicants submit details more than four months prior to OL issuance or by above date.
This activity may receive useful input regarding iodine in effluents following an accident, although guidance is given in NUREG-737.
c.
Sampling During and Following an Accident (550.44a(c)).
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Task Action Plan II.B.3, Post Accident Sampling Capability, concerns t
m its' elf with reactor coolant and containment atmosphere sampling line systems and ability to sample without overexposing personnel, and to quantify radionuclides in samples.
ETSB has the lead.
Actual imple-mentation date is now January 1,1982 and,0R's are to have available for review final design details by January 1,1981.
OL applicants are to provide a description of the implementation, in accordance with the proposed review schedule, but in no case less than 4 months prior to OL issuance. Again, there will need to be determination of source strengths and nuclide composition, although R.G.1.3 and 1.4 releases are cited as guidance on coolant spectrum.
d.
Accident Monitoring Instrumentation (550.44a(e)).
Task Action Plan II.F.1, Additional Accident-Monitoring Instrumenta-tion includes noble gas effluent radiological monitor (ETSB), and containment high-range radiation monitor (RAB), in addition to the item discussed in b. above.
Both items have implementation required for operating reactors by January 1,1982 with post implementatior review.
Design details are to be available for review by Januhry 1, 1981.
Source conditions on upper limit dose rates are specified but as above*, there are possibilities that licensees or applicants udll have useful input.
e.
Leakage Integrity Outside Containment (550.44a(d)).
Task Action Plan III.D.l.1, Integrity of Systems Outside Containment Likely to Contain Radioactive Material for PWRs and BWRs may well necessitate evaluation of primary coolant activity in such systems and the possibility that there will be. other source terms.
ETSB will be reviewing for this item.
Implementation in terms of tech spec commitments to check leakage at regular intervals and correct deficiencies were required by December 15, 1980.
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, Denwood F. Ross, Jr.
Task Action Plan III.D.3.3. Improved Inplant Iodine Instrumentation Under Accident Conditions, which is the responsibility of RAB will f.
require the evaluation of increased iodine levels in plant buildings outside containment and proposals for equipment and training for determining iodine concentrations, a
Task Action Plan III.D.3.4, Control Room Habitability Requirements, under AEB cognizance, requires that control room operators be ade-g.
quately protected against effects of accidental releases to be the loss of coolant accident contair.nent leakage and ESF leak-active gases.
age contribution outside containment, there may be fu provided.
Licensee responses to more severe control room hazard than a LOCA.
NRC review this requirement have to be submitted by January 1,1981.
is by July 1981.
Selective Absorption Systent - ETSB is reviewin'g for the Commission, the Oak Ridge method for selective absorption of noble gases from containme 3.
This two month activity by ORNL on a 189 to be negotiated with ETSB, will have to relook at noble gas source terms in containment.
atmospheres.
I believe this covers the appropriate activities in RP that relate to degraded core and cooling rulemaking.
William E. Kreger, Assistant Director for Radiation Protection Division of Systems Integration, cc: TMurphy WHouston WGammill PCheck LRubenstein JMeyer
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