ML20037A371
| ML20037A371 | |
| Person / Time | |
|---|---|
| Site: | Oconee, Crane  |
| Issue date: | 09/25/1972 |
| From: | Schwencer A US ATOMIC ENERGY COMMISSION (AEC) |
| To: | Knuth D, Maccary R US ATOMIC ENERGY COMMISSION (AEC) |
| Shared Package | |
| ML20037A372 | List: |
| References | |
| NUDOCS 8001100652 | |
| Download: ML20037A371 (2) | |
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l-D. F. Knuth, Assistant Director for Reactor Safety, L R. R. Maccary, Assistant Director for Engineering, L THRU:
R. C. DeYoung, Assistant-Director for Pressurized Vater Reactors, L OUTSTANDING ISSUES FOR THREE MILE ISLA'iD U'ilT-1 (DOC AND OCONEE UNITS 2 AND 3 (DOCKET NOS.50-270, 50-287)
The applications for operating licenses for Three Mile Island 1 and Oconee 2 and 3 are scheduled to be reviewed with the ACRS in Novecher.
Certain issues generic to B&W vent valve reactors.
still remain outstanding.
The purpose of. this memorandum is to bring these outstanding items to ' your attention.
Reactor Core Internals With respect to the redesign of reactor internals following the Oconee 1 incident the following three topical B&W reports were submitted September 15, 1972.
These-reports are:.BAW-10051,
" Design of Reactor Internals and Incore Instrument Nozzles for-Flow Induced Vibrations," BAW-10037, '! Reactor Vessel Model Flow Tests," and BAW-10038, " Prototype Vibration Measurement Program for Reactor Internals. "
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' At an earlier meeting, D. Lange stated that these topical reports could be reviewed and a Safety Evaluation Report section could he pr: pared within 1
one month of receipt of formal documentation on the condition that B&W would provide a rapid response to any additional information requests which we might deen necessary.
our understanding that this schedule remains valid and that
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Y contributions to the Safety Evaluation Reports for ihree Mile
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Island 1 and Oconee 2 and 3 can be available by October 15 i
subject to the above conditicn.
.s Fuel System Integrity Both TMI-l and Oconee 2 and 3 use pressurized fuel.
J. Hendrie, in his memo of August 2,1972 to R. C. DeYoung, stated that Technical Review would not be able to complete their generic review of B&W fuel in time for a September ACRS meeting.
However, the ' first stage of this generic fuel review was expected to be completed in late September. Since TMI-l and Oconee 2 and 3 are now both scheduled for November ACRS review, please provide a fuel performance contribution for the fe:ty o m
Evaluation Reports for these units.
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ECCS The proposed ECCS section for the TMI-3 Safety Evaluation Report is enclosed for your review and concurrence.. his material is modeled from that published for the Oconee 1 Safety Evaluation Report, Supplement 1 dated March 24, 1972.
D. Knuth, in his memo of July 3,1972 to R. C. DeYoung.. stated that the rupture of a core flood line and a small break analysis cust be considered.
Appropriate remerks on these subjects are included in sections 6.3.3.5 and 6.3.3.6 of the proposed catorial, Since the above memo stated that the core flood tank issue must be analyzed to permit the recor:mondation for.
licensing action, please scrutinize and correct that portion -
i of the write-up as necessary.
l Re ECCS performance as described in. the attachment uses a reflood rate that is presented in'B&W topical report 10034-Revision 3.
It is our present understanding that there may be questions as to the precise validity of this reflooding Please make appropriate changes and/or additions to.
rate.
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the attached material to. reflect your present position with
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respect to this issue.
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i The Oconee 2-3 Safety Evaluation supplemental material on these recent ECCS concerns will be adapted from your approved descrip-(
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tion for TMI-1.
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If, for any reason, there are que'stions as to the availability of the above information consistent with the publication of
- ' a Safety Evaluation Reports for the scheduled Nove=ber ACRS-meeting, please notify H. Schierling, (TMI-1),1. Peltier (Oconee 2-3), or myself as appropriate, and as soon as possible.
A. Schwencer, Chief PWR Project Branch No. 4 Directorate of Licensing -
Enclosure:
DISTRIBUTION:
Docket file.
As stated I'UR-2 Reading cc:
R. C. DeYoung D. Lange H. Faulkner V. Stello
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