ML25196A171
| ML25196A171 | |
| Person / Time | |
|---|---|
| Issue date: | 02/16/1977 |
| From: | Bender M Advisory Committee on Reactor Safeguards |
| To: | Rowden M NRC/Chairman |
| References | |
| Download: ML25196A171 (1) | |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION ADVISORY COMMITTEE ON REACTOR SAFEGUARDS WASHINGTON. D. C. 20555 February 16, 1977 Honorable Marcus A. Rowden Olairman
- u. s. Nuclear Regulatory Comnission Washington, D.C. 20555
SUBJECT:
REPORT ON EXXON NUCLEAR COMPANY WREM-BASED NON-JET PUMP BOILING WATER REACTOR ECCS EVALUATION MODEL
Dear Mr. Rowoen:
At its 202nd meeting, February 10-12, 1977, the Advisory Committee on Reactor Safeguards completed its review of the Exxon Nuclear Company's ECCS Evaluation Model for non-jet pump boiling water reactors. Sub-cormnittee meetings were held on July 21-22, 1976, in Richland, Washing-ton, and on December 21, 1976, and January 29, 1977, in Washington, D.C.
During its review, the Cormnittee had the benefit of discussions with representatives of the Exxon Nuclear Company and the NRC Staff. 'lbe Cormnittee also had the benefit of the documents listed.
The ACRS previously reported on an evaluation model developed by Exxon for non-jet pump boiling water reactors in the Committee's letter of March 10, 1975. 'lbat model required the coupling of the General Elec-tric non-jet pump boiling water reactor model for blowdown with the Exxon model for the fuel heatup. The Committee recommended that future applications be based upon an integrated set of approved models.
'Ihe first Exxon integrated model reviewed by the Committee was approved in a September 15, 1975 report on an evaluation model for a PWR.
'!be present non-jet pump BWR integrated evaluation model uses several portions of the Exxon WREM-Based Generic PWR Evaluation Mod<?l, and the Conmittee concurs with the NRC Staff that the blowdown portions are treated in an acceptable manner.
The NRC Staff has not accepted the proposed transient critical heat flux correlation, and Exxon has agreed to use a conservative pro-cedure proposed by the Staff. '!he Comnittee concurs with the Staff in imposing this requirement.
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Honorable Marcus
- February 16, 1977 Use of the Evaluation Model will require review by the NRC Staff of plant-specific items for case-by--case applications. The Corrmittee believes that, with the requirements set forth by the NRC Staff, the Exxon Nuclear: Company WREM-Based Non-Jet Pump Boiling Water Reactor ECCS Evaluation Model will conform to Appendix K to IO CFR 50.
D:r:s. s. H. Bush and M. w. Carbon did not participate in this review.
REFERENCES:
M., Bender Chairman
- 1. Exxon Nuclear Company, "GAPEX:
A Computer Program for Predicting Pellet-to-Cladding Heat Transfer Coefficients," XN-73-25, August 13, 1973, as found in XN-174 "Densification Effects on Exxon Nuclear:
Boiling Water Reactor Fuel," November 1973, and Supplement 1, November 29, 1973.
- 2. Exxon Nuclear Company, "2DQ: A Two-Dimensional Quenching Model,"
XN-74-25, Revision 1, October 30, 1974.
- 3. Exxon Nuclear Company, "BULGEX:
A Computer Code to Determine the Deformation and the Onset of Bulging of Zircaloy Fuel Rod Cladding,"
XN-74-27, Revision2, December 1974.
- 4. U.S. Nuclear Regulatory Corrmission, "WREM:
Water Reactor Evalua-tion Model," Revision 1, May 1975.
- 5. Exxon Nuclear Company, "Exxon Nuclear Company WREM-Based Generic PWR ECCS Evaluation Model," XN-75-41, Vol. I, Vol. II, and Appen-dices A, B, C, and D, Vol. III (Revision 2), and Supplements 1-7, July-November 1975.
- 6. Exxon Nuclear: Company, "HUXY:
A Generalized Multirod Heatup Code with 10 CFR 50 Appendix K Heatup Option - User's Manual," XN-CC-33 (A), July 28, 1975.
- 7. Exxon Nuclear Company, "Core Physics Methods and Data Used as Input to LOCA Analysis," XN-75-43, August 1975.
- 8. Exxon Nuclear Company, "The Exxon Nuclear Company WREM-Based NJP-BW'R ECCS Evaluation Model and Application to the Oyster Creek Plant,"
XN-75-55, Revision 2, August 1976, Supplement 1, September 1976, and Supplement 2, December 1976.
- 9. Intermountain Technologies, Inc., "Comparh:ons of the RELAP-4 Computer Code with Experimental Data," December 1976_.
- 10. U.S. Nuclear Regulatory Commission, "Revision 1 to Safety Evaluation Report Regarding Review of the Exxon Nuclear Company Non-Jet Pump Boiling Water Reactor ECCS Evaluation Model for Conformance to Appendix K to 10 CFR 50 by the Office of Nuclear Reactor Regulation,"
January 14, 1977.
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