ML17193B181
| ML17193B181 | |
| Person / Time | |
|---|---|
| Site: | Dresden  |
| Issue date: | 03/13/1981 |
| From: | Marc-Anthony Murray ILLINOIS, STATE OF |
| To: | Goodard R NRC OFFICE OF THE EXECUTIVE LEGAL DIRECTOR (OELD) |
| Shared Package | |
| ML17193A968 | List: |
| References | |
| NUDOCS 8103180967 | |
| Download: ML17193B181 (3) | |
Text
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Richard Goddard Off ice of the General Counsel USN RC Washington, D.C.
20555
Dear Dick:
Here is the list that you requested:
A.
Gene r i c Te ch n i ca 1 I s s u es Li s ti n g mas e d on my review o~ U.S. Nuclear Regulatory Commission,
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5.
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"NRC Program for the Resolution of Issues Related to Nuclear Power Plants,' NUREG-0410 V
(January 1978); U.S. Nuclear Regulaato"o~:::C:Qlfiim=Hrs "Generic Task Problem Description,"
UREG-0471 (June 1978); U.S. Nuclear Regulatory Commis ion, "Identification of Unresolved Safe Re-lating to Nuclear Power Plants,"
UREG-0510 (January 1979); U.S. Nuclear Regula ory Commission, "Task Action Plans for Unresolved ~ety ~es Related to Nuclear Power Plants," ~Ll._REG-OH__0 (February 198~); U.S. NRC letter, Dircks to Chilk, dated December 25, 1980 entitled usECY-80-325, Specia-1 Report to Congress Identifying Unresolved Safety Issues.:'.)
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Task A-17, systems interaction in nuclear power plants.
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Task A-24, qualification of Class IE safety-re 1 ate d equipment.
Task A-28, increase in spent fuel pool storage capacity.
Task A-29, design features to control sabotage.
Task A-30, DC power supplies.
Task A-34, instruments for monitoring radiation and process variables during accidents.
Task A-36t control of heavy loads near spent fuel.
Task A-40, seismic design criteria.
Task A-42, pipe cracks in boiling water reactors.
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Task A-44, station blackout.
Task A-46, seismic qualification of equipment in operating plants.
Task A-47, safety implication of control systems.
Task A-48, hydrogen control measures and effects of hydrogen burns on safety equipment.
14.
Ta s k B - 3 4, o cc up at i on a 1 rad i at i on expos u re reduction.
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Task B-67, effluent and process monitoring instru-ment a ti on.
B.
TMI Generic Issues
[]ased_on my review of U.S. NRC "NRC Action o
d as a Result of the TMI-2 Accident," NUREG-0660 Vol. 1 and Vol. 2 (May, 1980);
i on of TM I Ac U. on Pl an Re qui re -
November, 1980)J
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Item I.0.1, control-room design reviews.
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Item III.0.3.4, control-room habitability.
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Item II.B.1, reactor-coolant-system vent.
4.
I te m I I. B. 2, p 1 an t s hi e 1 di n g.
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Item II.B.3, post-accident sampling.
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Item II.B. 7, analysis of hydrogen control.
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Item II.E.4.4, containment design-purging~
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Item II.F.l, additional accident-monitoring instrumentation.
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Item II.C.3, systems interaction.
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Item II.F.5, class1fication of instrumentation, control, and electrical equipment.
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Item II.F.l, expand quality assurance list.
C.
ACRS Generic Items
~ased on my view of the then ACRS Chairman Carbon's letter to the then NRC Chairman Hendrie on March 21, 1979; and ACRS Chairman Plesset's letter to NRC Chairman Ahearne on August 12, 198if}
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Item 58, non-random multiple failures.
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Item 65, periodic review of all power reactors.
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Item 68, stress corrosion cracking in BWR piping.
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Item 70, design features to control sabotage.
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Item 77, soil-structure interaction.
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New Item 1, DC power supply reliability.
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New Item 2, single failure criterion.
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New Item 3, control system reliability.
I will try and provide the bases for t ese h
USis to you next week.
Sincerely, General