ML19341A512
| ML19341A512 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 08/30/1979 |
| From: | Major R Advisory Committee on Reactor Safeguards |
| To: | Carbon M, Kerr W, Okrent D Advisory Committee on Reactor Safeguards, NRC OFFICE OF STATE PROGRAMS (OSP) |
| Shared Package | |
| ML19341A503 | List:
|
| References | |
| FOIA-80-516 NUDOCS 8101260099 | |
| Download: ML19341A512 (3) | |
Text
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UNITED STATES y
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,,. ge 'g ADVISORY COMMITTEE ON REACTOR SAFEGUARDS L.g
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August 30, 1979
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I. Catton D. Okrent, Chairman W. Lipinski M. Carbon C. Michelson W. Kerr W. Mathis M. Plesset REVISED TENTATIVE MEETING SCHEDULE FOR THE SEPTEMBER 5, 1979 AD HOC SUBCOMMITTEE MEETING ON THE TMI-2 ACCIDEN
SUBJECT:
Attached for your information is a Revised Tentative Schedule for the
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The meeting will be held in Room 1046 at 1717 H St., NW, subject meeting.
The meeting has been scheduled to run from 8:30 a.m. until Washington, DC.
7:30 p.m.
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Richard Major Reactor Engineer c
Attachment:
As stated.
S. Levine, RES cc: ACRS Members R. Budnitz, RES R. Fraley, ACRS V. Stello, I&E M. Gaske, ACRS H. Wilber, I&E M. Libarkin, ACRS E. Jordan, I&E J. McKinley, ACRS W. Dircks, NMES P. Tam, ACRS D. Ross, DPM H. Voress, ACRS R. Baer, DPM L. Gossick, EDO R. Capra, DPM H. Denton, NRR
- 1. Conran, DPM E. Case, NRR J. Heltemes, DPM D. Eisenhut, NRR D. Basdekas, RSR R. Mattson, DSS R. Tedesco, DSS S. Hanauer, DSS 8101260099
Lt3chq) i TENTATIVE SCHEDULE AD H0C SUBCOMMITTEE MEETING ON THREE MILE' ISLAND 2 ACCIDENT IMPL WASHINGTON, DC SEPTEMBER 5, 1979 APPROXIMATE TIME STATUS REPORT ON SEP (SYSTEMATIC EVALUATION PROGRAM);
8:30 a.m.
where it stands, major areas of concern LONG-TERM LESSONS LEARNED TASK FORCE RECOMMENDATIONS 8:45 a.m.
INCLUDING:
discussion of hydrogen questions in detail future application of Class 9 events to licensing actions - reference, Board Question on Salem Spent Fuel Pool how to address possible improvements involving design changes for future reactors Examples:
a.
more reliable feedwater system b.
more reliable shutdown heat removal system c.
other
- BREAK ********
10 minutes 10:30 a.m.
LONG-TERM LESSONS LEARNED TAST, FORCE RECOMMENDATIONS (CONT'D) 10:40 a.m.
12:30 p.m. -
1:30 p.m.
- LUNCH ********
HOW TO GET SAFETY QUESTIONS ON THE TABLE?
2 1/2 hrs.
1:30 p.m.
1.
B&W actions on internal memoranda on Davis-Besse (September 24,1977) incident (J. MacMillan) 2.
TVA experience in raising questions with B&W (D.Patterson)
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APPR0XIMATE
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NRC experience in their first handling of Michelson's g 3.
l report - Questions and Answers Session (0IA) d te How te cet safety called to the attention of all 4.
parties concerned AIF, r.EI (E. Zebroski, Nuclear Safety Analysis Center - EPRI)
- BREAK ********
10 minutes DISCUSSION OF NUREG-0600, " Investigation into the March 28, 1979 Three Mile Island Accident by the Office of Inspection 45 minutes 4:00 p.m.
and Enforcement 45 minutes 4:45 p.m.
BRIEFING ON BULLETINS79-05C and 79-06C DISCUSSION AND STATUS OF NRC REPORT ON AUXILIARY 45 minutes 5:30 p m.
FEEDWATER 6:15 p.m.
SPECIFIC ISSUES:
a.
Rancho Seco Transient (March 20,1978) b.
Overfilling of Steam Generators c.
Air Systems c
d.
others ADDITIONAL. TIME FOR LESSONS LEARNED (if required) 7:30 p.m.
ADJ0URNMENT er
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August 24, 1979 CFFIC OFTHE COMMIS580NER t
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Memorandum for Lee V. Gossick 6,N Executive Director for Operations h\\
From:
Richard T. Kennedy 7
Subject:
OIA INVESTIGATION REPORT, "MICHELS N REPORT --
EVENTS AND LEVELS OF REVIEW" g
'The subject report provides valuable insight into the following areas of apparent weakness in NRC procedures which contributed to
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the lack of early and adequate staff attention to the Michelson Report:
1.
A lack of a forum, other than the ACRS, within the regulatory system through which safety related concerns expresseo by individuals such as Dr. Michelson can be' addressed and resolved;
.2.
A lack of formal written procedures or guidelines through which the ACRS or its members may request HRC staff review of a particular subject; I
3.
A lack of adequate internal staff procedures to ensure that externally generated reports such as ACRS consultant reports are rigorously distributed, screened for safety concerns, and analyzed by the staff; 4.
A lack of adequate and timely exchange of pertinent safety related information between DSS and 00R.
IIbile I recognize that staff procedures addressing the above-mentioned areas may exist, based on the perceptions of those interviewed during the course of this investigation, it is cicar that, if they do exist, they certainly have not been adequately disseminated or emphasized.
If such procedures do not current.ly exist, they should be developed and implemented without delay.
I would appreciate receiving your* plan to correct this situation by September 7,1979.
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