LD-83-024, Provides Ref Info in Order to Close Out NUREG-0737,Items II.K.2.13, Thermal-Mechanical Rept, II.K.2.17, Potential Voiding in RCS & II.K.3.30, 10CFR50 App K Small Break LOCA Methods
| ML20072F503 | |
| Person / Time | |
|---|---|
| Site: | 05000470 |
| Issue date: | 03/22/1983 |
| From: | Scherer A ABB COMBUSTION ENGINEERING NUCLEAR FUEL (FORMERLY |
| To: | Eisenhut D Office of Nuclear Reactor Regulation |
| References | |
| RTR-NUREG-0737, RTR-NUREG-737, TASK-2.K.2.13, TASK-2.K.2.17, TASK-2.K.3.30, TASK-TM LD-83-024, LD-83-24, NUDOCS 8303240261 | |
| Download: ML20072F503 (2) | |
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C-E Power Oystems Tel. 203/688-1911 Combusbon Engineenng. Inc.
Telex 99297 1000 Prospect Hill Road Windsor, Connecticut 06095 H POWER SYSTEMS Docket No.:
STN 50-470F March 22, 1983 LD-83-024 Mr. Darrell G. Eisenhut, Director Division of Licensing U.S. Nuclear Regulatory Commission Washington, D.C.
20555
Subject:
Appendix B to CESSAR-F
References:
(A) C-E Owners Group Letter, K. P. Baskin to D. G. Eisenhut, dated December 31, 1981 (B)
Southern California Edison Letter, K. P. Baskin to F.
Miraglia, dated April 28, 1982 (C) Letter LD-82-044, A. E. Scherer to J. R. Miller, dated April 15, 1982
Dear Mr. Eisenhut:
Appendix B to CESSAR-F, " Address of TMI Action Plan Requirements", addresses matters derived from the NRC's THI Action Plan as provided in NUREG-0737,
" Clarification of TMI Action Plan Requirements".
Three of the items identified as within CESSAR-F scope and documented in Appendix B cite future Combustion Engineering (C-E) Owners' Group efforts to prepare generic responses.
Specifically, these are sections II.K.2.13, " Thermal Mechanical Report",
II.K.2.17, " Voiding in RCS", and II.K.3.30, "Small Break LOCA Methods".
These reports have been prepared by C-E and submitted to the NRC on other dockets.
In order to close out items II.K.2.13, II.K.2.17, and II.K.3.30 on the CESSAR-F docket, we are incorporating, by reference, the responses prepared.
In addition, we are referencing the appropriate transmittal letters to verify that the information has in fact been submitted for NRC staff review.
In response to II.K.2.13, C-E prepared CEN-189, " Evaluation of Pressurized Thermal Shock Effects Due to Small Break LOCAs with Loss of Feedwater for the Combustion Engineering NSSS", December 1981. The report was transmitted to the staff via Reference (A).
In addition to the generic report, plant specific aspects of the issue were addressed in a series of plant specific appendices to CEN-189. These appendices must be provided on the referencing applicant's docket.
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8303240261 830322 FDR ADOCK 05000 l
Mr. Darrell G. Eisenhut Page 2 s
In response to II.K.2.17, C-E prepared CEN-199, " Effects of Vessel Head Voiding During Transients and Accidents in C-E NSSS's", March 1982. The report has been transmitted to the staff by Southern California Edison via Reference (B).
In response to II.K.3.30, C-E prepared CEN-203, Revision 1, " Response to NRC Action Plan Item II.K.3.30 - Justification of Small Break LOCA Methods", March 1982. The report was submitted to the staff via Reference (C).
The references cited above indicate that the reports committed to by C-E in CESSAR-F have, in fact, been submitted to the NRC. Appendix B shall be revised to reference the appropriate reports in the next amendment.
If you have any questions on the above, please contact me or Mr. G. A. Davis of my staff at (203) 688-1911, extension 2803.
Very truly yours, COMBUSTION ENGINEERING, INC.
yfe A. E cherer Director Nuclear Licensing xc: G. Meyer (Project Manager /USNRC) l l
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