ML20039E758
| ML20039E758 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 10/01/1979 |
| From: | Voglewede J Office of Nuclear Reactor Regulation |
| To: | Silver H Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML111090060 | List:
|
| References | |
| FOIA-80-515, FOIA-80-555 NUDOCS 8201110356 | |
| Download: ML20039E758 (3) | |
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[%pc* utogf,j UNITED STATES NUCLEAR REGULATORY COMMISSION 5
p WASHINGTON, D. C. 20555 OCT.0 11979 MEMORANDUM FOR: Harley Silver, DPM FROM:
John Voglewede, DSS
SUBJECT:
ACCEPTANCE OF TMI-l RESTART SAFETY ANALYSIS REPORT Per your request, I have performed a preliminary acceptance review of the short-term Lessons Learned items contained in the submittal for restart of Three Mile Island Nuclear Station Unit 1.
The results are attached in tabular form.
The acceptance criterion used was whether or not the item of interest was addressed in the TMI-l submittal. No attempt was made to judge the adequacy of the response, if present. You will note from the attached tables that the majority of the items required were not yet submitted or not addressed at all. Of those items which were addressed, the material is often limited (for example, see " Shift Technical Advisor" which is item 5.2.8 in the submittal).
John C. Voglewede Core Performance Branch Div'ision of Systems Safety 8201110356 810403 PDR FOIA MADDEN 80-515 PDR
TMI-l RESiART SAFETY ANALYSIS REPORT n
Item Description NUREG-0578 Number Met-Ed SAR Remarks l.
Emergency Power Supply Requirements 2.1.1 2.1.1. 3 Addressed in SAR 2.
Relief and Safety Valve Testing 2.1. 2 None Met-Ed will participate in industry program.
3.
Direct Indication of Valve Position 2.1.3.a 2.1.1.2 Addressed in SAR 4.
Instrumentation for Inadequate Core 2.1.3.b 2.1.1. 6 Addressed in SAR Cooling 5'.
Diverse Containment Isolation 2.1.4 2.1.1. 5 Addressed in SAR 6.
Dedicated H2 Control Penetrations 2.1.5.a 2.1.1.4 Addressed in SAR 7.
Inerting BWR, Containments 2.1.5.b None Not Applicable 8.
Combustible Gas Control Recombiner 2.1. 5.c 2.1.1.4 Rulemaking 9.
' System Integrity for High Radioactivity 2.1.6.a None To be submitted 10.
Plant Shielding Review 2.1.6.b None To be submitted 11.
Auto Initiation of Auxiliary feedwater 2.1.7.a None To be submitted 12.
Auxiliary feedwater Flow Indication 2.1.7.b None To be submitted 13.
Post Accident Sampling 2.1.8.a None To be submitted 14.
High Range Radiation Monitors 2.1.8.b None To be submitted 15.
Improved Iodine Instrumentation 2.1.8.c None To be submitted 16.
Transient and Accident Analysis 2.1. 9 8.1 Incomplete
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THI-2 RESTART SAFETY ANALYSIS REPORT T'
Item Description NUREG-0578 Number Met-Ed SAR Remarks 17.
Shift Supervisor Responsibilities 2.2.1.a None To be submitted 18.
Shift Technical Advisor 2.2.1.b 5.2.8 Addressed in SAR 19.
Shift Turnover Procedures 2.2.1.c None To be submitted 20.
Control Room Access Control 2.2.2.a None To be submitted 21.
Onsite Technical Support Center 2.2.2.b None To be submitted 22.
Onsite Operational Support Center 2.2.2.c None To be submitted 23.
Revised Limiting Condition for Operation 2.2.3 None Rulemaking 24.
Containment Pressure Instrumentation ACRS #1 None Not addressed 25.
Containment Water Level Instrumentation ACRS #2 None Not addressed 26.
Containment Hydrogen Concentration ACRS #3 None Not addressed Instrumentation 27.
Remote High Point Venting Denton #1 None Not addressed 28.
Emergency Preparedness Eisenhut #1 4.0 To be submitted i
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