ML19317E866
| ML19317E866 | |
| Person / Time | |
|---|---|
| Site: | Oconee  |
| Issue date: | 04/05/1973 |
| From: | Peltier I US ATOMIC ENERGY COMMISSION (AEC) |
| To: | Deyoung R US ATOMIC ENERGY COMMISSION (AEC) |
| References | |
| NUDOCS 8001070664 | |
| Download: ML19317E866 (4) | |
Text
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APR 5 5 73 Docket No. 50-269 1
- 1. C. DeYoung, Assistant Director for Pressurized Water Reactors, L
\\
A. Schwencer, Chief, Pressurized Water Reactors Branch No. 4. L
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THRU:
1 NEETINC WITH B&W AND DUKE APRIL 3, 1973 - TECHNICAL DISCUSSIONS ON ECCS I attended another technical meeting which B&W requested with the l
The primary purpose of the meeting was to staff on ECCS matters.
i inform the staff of the results of analysis using the data Duke has acquired from the Westinghouse test facility. Most of the discussion was technical but the following other matters were discussed.
B&W (through Duke) will submit its report on the results of analysis 1.
using Westinghouse and CE data which applies to Oconee Unit 1 by April 27, 1973.
In order to speed up the staff's review the important data will 2.
be transmitted informally byt April 11, 1973.
3.
The bulk of the "estinghouse test data will be submitted to the AEC in three copies.
4.
Duke was inforned that we intend to complete our supplemental safety review on Oconee Unit 1 in early May. This review consists of ECCS, Vessel Internals, High Energy Line Ruptures and Fuel Densification and with the exception of Fuel Densification and vessel Internals the results of this review will be applicable to the Units 2/3 review. Puel Densification and Vessel Internals for Units 2/3 will require additional information from Duke (which is scheduled to be submitted for Unit 2 prior to May 1, 1973.)
Whether or not the review is complete in time for power escalation in Unit 1 (estimated to be May 4,1973 by Duka) thus permitting the lifting of cil power restrictions (except the 95% full power for 30 days) depends upon Duke's timely response in supplying the results of the Westinghouse ECCS data and timely resolution of key problems with the fuel densification analysis.
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6 APR 5 1973 -
R. C. DeYoung The alternative to a clean bill on these matters would be another interim position on power to meet the May 4, 1973 deadlina which would be undesirable from everyone's point of view.
Duke was alerted also to the need for the staff to cociplete its Unit 2/3 5.
review earlier than originally scheduled because of the new ACRS requirements for lead time resulting from ACRS meetings being opened to the public.
An attendance list for the meeting is enclosed.
Original Signof iey Irving A.Peltier I. A. Peltier, Project Manager Pressurized Water Reactors Branch No. 4 Directorate of Licensing
Enclosure:
Attendance List DISTRIBUTION Docket File PWR-4 Rdg RP rdg RCDeYoung RWKlecker MRosen R0 (3)
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ATOMIC ENERGY COMMISSION l *l WASHINGTON. D.C. 20545
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<<,,,, e ant 5 3 73 Docket No. 50-269 R. C. DeYoung, Assistant Director for Pressurized Water Reactors, L THRU:
A. Schwencer, Chief, Pressurized Water Reactors Branch No. 4, L g
MEETING WITH B&W AND DUKE APRIL 3, 1973 - TECHNICAL DISCUSSIONS ON ECCS I attended another technical meeting which B&W requested with the staff on ECCS matters. The primary purpose of the meeting was to inform the staff of the results of analysis using the data Duke has acquired from the Westinghouse test facility. Most of the discussion was technical but the following other matters were discussed.
l.
B&W (through Duke) will submit its report on the results of analysis using Westinghouse and GE data which applies to Oconee Unit 1 by April 27, 1973.
2.
In order to speed up the staff's review the important data will be transmitted informally by April 11, 1973.
3.
The bulk of the Westinghouse test data will be submitted to the AEC in three copies.
4.
Duke was informed that we intend to complete our supplemental safety review on Oconee Unit 1 in early May. This review consists of ECCS, Vessel Internals, High Energy Line Ruptures and Fuel
/
Densification and with the exception of Fuel Densification and f
Vessel Internals the results of this review will be applicable a
I to the Units 2/3 review. Fuel Densification and Vessel Internals for Units 2/3 will require additional information from Duke (which is scheduled to be submitted for Unit 2 prior to May 1, 1973.)
Whether or not the review is complete in time for power escalation in Unit 1 (estimated to be May 4,1973 by Duke) thus permitting the lifting of all power restrictions (except the 95% full power for 30 days) depends upon Duke's timely response in supplying the results of the Westinghouse ECCS data and timely resolution of key problems with the fuel densification analysis.
e-R. C. DeYoung APR 5 5 73 The alternative to a clean bill on these matters would be another interim position on power to meet the May 4,1973 deadline which would be undesirable from everyone's point of view.
5.
Duke was alerted also to the.need for the staff to complete its Unit 2/3 review earlier than originally scheduled because of the new ACRS requirements for lead time resulting from ACRS meetings being opened to the public.
An attendance list for the meeting is enclosed..
0 11 ~
I. A. Peltier, Project Manager Pressurized Water Reactors Branch No. 4 Directorate of Licensing
Enclosure:
Attendance List i
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L
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MEETING WITH DUKE AND B&W ECCS DISCUSSIONS ATTENDANCE LIST APRIL 3, 1973 Atomic Energy Commission IAPeltier DKDavis HSullivan Dross I
Duke Power Company TLCotton KScanady Babcock & Wilcox Company CACreacy RVStraub j
RRSteinke
.CDMorgan CEParks i
BMDunn 1
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