ML17254A916
| ML17254A916 | |
| Person / Time | |
|---|---|
| Site: | Kewaunee, Point Beach, Prairie Island, Ginna, 05000000 |
| Issue date: | 08/09/1984 |
| From: | Diianni D Office of Nuclear Reactor Regulation |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| TAC-08350, TAC-8350, NUDOCS 8408160482 | |
| Download: ML17254A916 (8) | |
Text
Docket Nos.
50-282 50-306
~0-244
~ 50-266 50-301 and 50-305
@!cog gg Facilities:
Prairie Island Unit Nos. I and 2, Ginna, Point Beach Unit Nos. I and 2, and Kewaunee Licensees:
Northern States Power Company, Rochester Gas and Electric
SUBJECT:
SUMMARY
OF JULY 24, 1984 MEETING WITH THE WESTINGHOUSE OWNERS GROUP OF TWO-LOOP PLANTS REGARDING UPPER PLENUM INJECTION (UPI)
On July 24, 1984, the NRC staff met with Westinghouse and the Owners Group of the two-loop plants to review and establish mutually agreed upon direction for resolving the Upper Plenum Injection (UPI) for two loop plants.
The pre-sentation given at the meeting involved Westinghouse UPI model, test data and analyses as related to UPI, Sandia TRAC calculation, and the NRC staff's position on this issue as it relates to meeting the requirements of Appendix K
of 10 CFR Part 50.
Copies of the viewgraphs and handouts are not included with this summary because of the proprietary nature of the material.
A list of attendees is attached (Enclosure I).
The meeting opened with a presentation of the Agenda (Enclosure 2).
The following areas were discussed.
1.
Introduction The Westinghouse Owners Group presented the history of the UPI issue consisting of the W ECCS evaluation model for two-loop plants dating back to 1971.
The objectives of the meeting from the Owners Group point of view covered the appropriateness of the Westinghouse
- model,
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the Sandia UPI calculation and the test data from the simulated UPI tests conducted by the Japanese.
The objective was also to cover the NRC staff's specific concerns with the Westinghouse UPI Model and establish the basis for any revisions to the model so that it would more adequately describe core cooling during accident conditions.
2.
Westin house UPI ECCS Model Westinghouse described their reflood model that applies to a two-loop system during a hot and cold leg break.
The presentation covered the conservative features of the UPI model.
3.
Test Data and Anal ses The Sandia TRSC Calculations were reviewed and comments by the Westing-house Owners Group related to the applicability and level of conserva-tism that exist for the two-loop plants were made.
The Japan Atomic Energy Research Institute (JAERI) was requested by the NRC to run UPI tests in Cylindrical Core Test Facility (CCTF).
During this meeting, UPI data from test Runs 57, 59 and 72 were evaluated for simulated hot and cold leg breaks.
4.
Conclusion The objective of this meeting was to define an NRC acceptable standard as described in item 5 of Paragraph II of Appendix K of 10 CFR Part 50.
The Westinghouse Owners Group has submitted an analysis which they believe is adequate to show that an acceptable margin exists and a penalty on the peak clad temperature is not necessary to meet the requirements of Appendix K of 10 CFR Part 50.
The staff agrees with the Owners Group that based on available information, a margin does
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In order to resolve this issue, the staff will provide for the Westinghouse two-loop Owners i
Group a list of those items needed to make a finding that the Westinghouse two-loop ECCS model as currently proposed is sufficiently conservative and meets the requirements of Appendix K of 10 CFR Part 50.
The staff will provide the listing of these items in draft form within two weeks from the meeting date to allow comments from the Owners Group before a formal issue is made.'he Owners Group requested that a similar list of items be provided for the Exxon two loop ECCS model.
The staff agreed that a mechanism will be established for handling the UPI analyses for other fuel vendors (i.e.,
Exxon 8 Combustion Engineering) after the needed specific items are determined for the Westinghouse Owners Group. This matter must be Fl I
resolved before establishing an implementation schedule for resolving this issue and preparing the final SE.
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Enclosure:
1.
List of attendees 2.
Agenda Dominic C. DiIanni, Project Manager Operating Reactors Branch t3 Division of Licensing ORB 3:DL PK tzer 8/g) /84 ORB83:DL DDiIanni: dd 8/GF /84
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MEETING
SUMMARY
DISTRIBUTION Licensee:
Northern States Power Co., Rochester Gas and Elec.
Co., Wisconsin Electric Power Co.,
and Wisconsin Public Service Corp.
- Copies also sent to those people on service (cc) list for subject plant(s).
Docket File
'ORB83 Rdg ORB03 Summary File JRMiller PMKreutzer Project Manager OELD ELJordan JMTaylor ACRS-10 NRC Participants