ML19290C304
| ML19290C304 | |
| Person / Time | |
|---|---|
| Issue date: | 07/20/1979 |
| From: | NRC - NRC THREE MILE ISLAND TASK FORCE |
| To: | |
| References | |
| REF-GTECI-A-36, REF-GTECI-SF, TASK-A-36, TASK-OR NUDOCS 8001100509 | |
| Download: ML19290C304 (9) | |
Text
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July 20,1979 I.
Plan - Task A-36 Completion MILESTONE TARGET DATE bMP(g (a) Prepare Table of Contents For NUREG Report July 20, 1979 Ce U b W h*
August 3,1979 - W.nl P (b) C mpletion of Survey Of Operating Plants.
usc-cw (c) Completion of Task Group discussions on various scenarios.
August 15,1979 -fo& Led acIr Ald#
-Io I (d) First draft of NUREG distributed to task group members.
September 15, 1979
/g//Q d-Q (e) Second draft of NUREG distributed to Section Leaders and Branch
"# 4 Nj' Chiefs.
September 28, 1979 (f) Third draft of NUREG distributed to A/D's and Division Director's.
October 15, 1979 (g) NUREG issued.
November 16, 1979 (h) Memo issued with recommended changes to SRP's and R.G.'s.
December 14, 1979 1728 298 80011 0 0 5C f,
r//7y OUTLINE FOR NUREG REPORT TASK A-36 CONTROL OF HEAVY LOADS NEAR SPENT FUEL 1.
INTRODUCTION
1.1 BACKGROUND
(Def. of Heavy Load, potential consequences of accidental load drop [ release of radioactive material, criticality, damage to systems required for safe shutdown or continued decay heat removal], extent considered in previous licensing actions, and purpose for task).
1.2 DEFINITIONS 1.3 A-36 REVIEW PROCESS (Brief dc;criptic.. of review process including: initial a
review, generic letter to licensees, information submitted, survey of information, group discussion of various scenarios, development of fault trees, analysis of available data, develop-ment of guidelines, NUREG report).
1.4
SUMMARY
OF RECOMMENDATIONS (An executive type sumary of guidelines and recommendations).
2.
SURVEY OF LICENSEE INFORMATION 2.1 HEAVY LOADS (A discussion of the various heavy loads, and their frequency of movement, that may be moved over or near spent fuel in the reactor vessel or spent fuel pool).
2.2 PRESENT PROTECTION (A description of the present protection provided that prevents, or mitigates the consequences of, accidental load drops in-cluding discussions of the following:)
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, s 2.2.1 Technical Specifications 2.2.2 Procedures 2.2.3 Crane Designs 2.2.4 Other Design Features 2.2.5 Crane Operator Training 2.3 PREVIOUS ANALYSES
( A discussion of various analyses performed previously by licensees or their consultants related to heavy load drop accidents).
3.
REVIEW 0F HISTORICAL DATA (A discussion of the available historical data related to heavy load handling at nuclear facilities and crane operations at non-nuclear facilities. Will include a discussion of the conclusions that may be drawn from this data. Provide summary of data in Appendix A).
4.
GUIDELINES GUIDELINES FOR CONTROL 0F HEAVY LOADS 4.1 _
(Lead-in should provide background, such as: the objectives of the guidelines, that various alternatives are provided to meet the objectives, and that fault trees were developed and used as discussed in Section 4.3 to evaluate the adequacy of the guidelines).
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. 4."1.1 General 4.1.2 Spent Fuel Pool Area - PWP,'s 4.1.3 Containment Building - PUR's 4.1.4 Reactor Building - BUR 4.1.5 Other Areas 4.1.6 Single Failure Proof Cranes and Lifting Devices 4.2 BASES FOR GUIDELINES (A discussion which provides the staff basis for the guidelines including use of fault trees, historical data, and information from licensees.
Should sumarize conclusions that may be drawn from the fault trees).
5.
RECOMMENDATIONS 5.1 IMPLEMENTATION OF GUIDELINES - OPERATING PLANTS (Recommend a program for implementing guidelines at operating plants, reference draft generic letter, discuss impact of implementation on operating plants, and discuss manpower, technical assistance, and schedule for NRC to carry out a pro-gram to implement the guidelines).
5.2 INTERIM ACTIONS
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hadww (Discuss imediate actions required until guidelines are implemented and basis for operation with only these actions and existing measures).
5.3 CHANGES TO S.R.P's and R.G. 's (Generalize recommended changes to SRP's and RG's to incorporate guidelines not almady included).
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. 5.4 ISSUES REQUIRING FURTHER STAFF ATTENTION (Issues identified during task review but not within scope oftask).
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APPENDICES Appendix A - Crane Historical Data 1.
Navy 2.
OSHA 3.
NASA 4.
LER Will provide a data summary for each of these data sources.
Appendix B - Fault Trees Will provide the fault trees developed related to handling of heavy loads, development of probabilities for various events and sumary of probability estimates for various cut-sets.
Appendix C - Modification of Existing Cranes
(
A discussion of the typical modifications that may have to be made if upgrading to intent of NUREG - 0554, feasibility of making such modifications, and availability of equipment for these modifications. Will also include, if possible, an implementation section identifying elements of NUREG 0554 that must be met in upgrading, and those elements where alternative compensating actions may be taken in lieu of specific compliance.
May also indicate typical alternative actions that may be acceptable.
Appendix 0 - Draft Generic Letter To Licensees 1728 303
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