ML19297C011
| ML19297C011 | |
| Person / Time | |
|---|---|
| Issue date: | 11/04/1980 |
| From: | Check P Office of Nuclear Reactor Regulation |
| To: | Ross D Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML19295F938 | List: |
| References | |
| FOIA-81-381 NUDOCS 8012230088 | |
| Download: ML19297C011 (3) | |
Text
u G;j '; j Noventer 4,1980 NOTE T0:
D. F. Ross, Jr., Director, Division of Systems Integration CROM:
Paul S. Check, Assistant Director for Plant Systems, Division of Systems Integration
SUBJECT:
DEGRADED COOLING STEERING GROUP.
In accordanu with your request of October 27, 1980, I've sunnarized our work that is related to degraded cooling rulemaking.
1.
Zion / Indian Point action in the area of witigation features for degraded core / molten core accidents. This activity is a ma,jor one of which you are well aware. Three points should be made concerning it that have direct impact on the work of the Steering Group, a) This action covers 'some of the most important technical areas that will have to be addressed in a broader context by the Steering Group.
These areas include:
1)
Selection of ' risk-dominant accident sequences, ii)
Analysis of the loading histories in containment (pressure, temperature, radiological source tenn) resulting from various key accident sequences together with analysis of the impli-cation of these histories in terms of containment failure and subsequent radiological consequences.
iii) Analysis and a'ssessment of the appropriateness of mitigation features in terms of risk-reduction potential and in terms of practical engineering application to existing nuclear power plants (backfit). Features being considered include filtered, vented containment system, core retention devices, and hydrogen control measures.
b) This action considers some of the most important policy areas that will have to be addressed in a broader context by the Steering Group.
These areas include:
1) the role of probabilistic risk assessment in Class-9 licensing decision making.
ii) mitigation vs. prevention of :: ore melt accidents.
,S
.' b fA Lv
Contact:
J. Meyer y 77Qd3 I
OFFICE h.
..L SURNAMEk.
. c.g..
DATEk.
.g.
.p
'N18 (9-76) NRCM 0240 DU.S. GOVERNMENT PRINTING OFFtC' : ])F7
-?69 d
D. F. Ross, Jr.. 111) some clarification of current thinking on an unofficial safety goal.
iv) the role of the licensees in the degraded core accident licensing effort.
v) the place and empnasis of research in particular the RES efforts, in the licensing program.
c) From a view of the Z/IP schedule, the decisions that will be made, and the content of the program, the action will set an important precedent for Class 9 licensing activities.
The Z/IP action is centered in the RSB and has an extensive T.A.
program associated with it. If necessary, further details on Z/IP could be provided to the Steering Group by handing out Jim Meyer's 9/29/80 Z/IP update.
2.
There have been a nur.te'r of other related activities that should also be listed.
a) Siting: participation on " source terms for siting analysis
- working group.
b)
Input to Sequoyah Hydrogen Ignitors Study.
c)
Input to hearings on Class-9.
- 1) Rancho Seco ti)TMI-l 3.
Reactor coolant systems vents. TAP Section II.9.1, is an activity to implement requirements.for the installation of high-point RCS and reactor vessel head vents,, that are remotely operable from the control room.
I believe this covers the app'ropriate activities.
Paul S. Check Assistant Director Distribution for Plant Systems Central File Division of Systems Integration RSB Reading J. Meyer T. Speis P. Check
. VI 0 _1
' kh,.
W.
RSB;DSI,,/b 4,
0,,,cc suR~.McM.o
/.
TPSpeis C.k
. l, 11/
'80
. f,...r/ /80 11
/80
,. q...
NRC FORM J18 (9-76) NRCM 0240 U U.S. GO% CRNMENT PuiNTING Cri
,g: 3-2.e. w g
November 4, 1980 CNGOING WORK IN DSI THAT RELATES TO DEGRADED COOLING RULEMAKING (Detailed Comments on these activities are attached)
TAC Section 1.
Zicn/ Indian Point action in the area of mitigation II.S.6 features for degraded core / molten core accidents.
I1.3.1 2.
Reactor Coolant System Vents.
3.
Protection of Safety Ecuicment and Areas which may be II.B.2 used during and folicwing an accident.
4.
Post Accident Iodine Sampling and Laboratory Analysis.
II.F.1 (Attach. 2)
II.B.3 5.
Post Accident Sampling Capability.
II.F.1 6.
Accident Monitoring Instrumentation.
III.D.l.1 7.
Leakage Integrity Outside Containment.
8.
Imoroved Inplant Iodine Instrumentation under Accident III.D.3.3 Ccnditions.
III.D.3.4 9.
Control Room Habitability Requirements.
- 10. Accident Impact Analysis.
- 11. Selective Absorption System for Noble Gases.
- 12. Sequoyah Core Degradation Program: Hydrogen Study.
II.A
- 13. Reactivity Siting Program Activities.
- 14. Specific Licensing Actions, Hearings (e.g., TMI-1, Rancho Seco).
Contact:
J. F. Meyer x-27943 f