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UNITED STATES
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O auc'caa accu'4Toav corau Jo" W ASHINGTON. D., C.
20555
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Docket No. 50-219 I
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Jersey Central Power 6 Light Company ATTN:' Mr.1. R. Finfrock, Jr.
Vice President - Generation Madison Avenue at Punch Bowl Road Morristown, New Jersey 07960
. Gentlemen:
i Enclosed.for your information~i'wa r'c.
sa opy of the Advisory Committec on Reactor Safeguards' Ictter report entitled " Emergency Core Cooling Systems Evaluation Model (ECCS-EM) for the Nonjet-Pump Boiling Water Reactor".
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Sincerely, l
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George r, Chief I
Operating Reactors Branch #3 Division of Reactor Licensing
Enclosure:
ACRS Letter Report cc: See next page I
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w Nr.I.R.Finfrock,Jr. a MAR 2 6 65 2
ccc: w/ enclosure
- G. F. Trowbridge, Esquire Shaw, Pittman, Potts, Trowbridge and Madden-Barr Building 910.17th Street, N. W.
Washington, D. C.
20006 Jersey Central Power G Light Company ATTN: Mr. Thomas M. Crimmins, Jr.
Safety and Licensing Manager GPU Service Corporation 260 Cherry Hill Road Parsippany, New Jersey 07054 Anthony Z. Roisman, Esquire Berlin,' Roisman 6 Kessler 1712 N Street, N. W.
Washington, D. C.
20036 Paul Rosenberg, Esquire Danici Rappoport, Esquire
'2323 S. Broad Street-Trenton, New Jersey 08610 Honorable Joseph W. Ferraro, Jr.
Deputy Attorney General State of New Jersey 101 Commerce Street - Room 208 Newark, New Jersey 07102 Burtis W. Horner, Esquire Stryker, Tams and Dill 55 Madison Avenue Morristown, New Jersey 07960 George F. Kugler, Jr.
/+.orney General State of New Jersey
-State House Annex Trenton, New Jersey 08625 Ocean County Library 15 Hooper Avenue Toms River, New Jersey 0B753 1
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ADVISORY COMMITTEE ON REACTOR SAFEGUARDS gLEAR REGULATORY COMMISSION
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..******,.~i CASHINGToN, D. C. 20655 i
iS8PD 01875 Ai 9 : U OFROL 7..;.n rhEIlaY
' Hor.orable William A. Anders Chairman U. S. Nuclear Regulatory Cocznission Washington, D. C.
20555
Subject:
EMERGENCY CORE COOLING SYSTEMS EVALUATION MODEL (ECCS-EM) FOR THE NONJET-PUMP BOILING WATER REACTOR
Dear Mr. Anders:
At its 179th meet ng, March 6-8, 1975, the Advisory Cocmittee on Reactor Safeguards completed its review of the Exxon Nuclear Company's ECCS Nonjet-Pump Boiling Water Reactor Fuci Heatup Model. The initial application of this model is for the evaluation of a reload core at the Oyster Creek Nucicar Generating Station and requires the proper coupling with the approved General Elcetric Emergency Core Cooling Syste=s Evaluation hodel (ECCS-EM) for the nonjet-pump boiling water reactor. The Jersey Central Power and Light Company is responsibic for obtaining the overall ECCS-EM l
which meets the requirements of 10 CFR 50.46, Appendix K.
Subcommittee l
meetings were held with the NRC Staff and the representatives of the Exxon Nucicar Company in Washington, D.C., on February 1 and 22,1975, with attendance at the second meeting expanded to include participation by representatives from the Jersey Central Power and Light Company.
The Committee previously reported on Evaluation Models for Commission Criteria i
for Emergency Core Cooling Systems for Light-Water-Cooled Nuclear Power Reactors on November 20, 1974. The Co=mittee also had the benefit of the documents listed below.
4 The ACRS believes that the Exxon Nuclear Company's portion of the ECCS-EM j
with the additional modifications required by the NRC Staff and when properly coupled with the approved General Electric nonjet-pump boiling water reactor j
model will conform to 10 CFR 50.46, Appendix K.
Although the Cocmittee believes that the coupling procedure is acceptable for the present applica-tion, the Committee recommends that future applications be based upon an integrated set of approved models.
Sincerely yours, William Kerr Chairman i
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Honorable William A. Anders
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References:
1.
KN-73-34 (Rev 2), "HUXY:
A Generalized Multirod Heatup Code" 2.
KN-74 25 (Rev 1), "2DQ: ~ A Two Dimensional Quenching Model" 3.
KN-74-27 (Rev 1), "BUIGEX:
A Computer Code to Detemine the Defomation and the Onset of Bulging of Zircaloy Fuel Rod Cladding"
'4.
XN-74-51, "ECCS Analysis for Oyster Creek Fuel Types IIIA, IIIE, and IIIF with the Exxon Nuclear Evaluation Model for BWR Loss of Coolant Accidents" 5.
XN-174 and Suppl 1, "Densification Effects on Exxon Nuclear Boiling Water Reactor Fuel" 6.
XN-235, " Exxon Nuclear Evaluation Model for BWR Loss of Coolant Accidents" 7.
Report Regarding the Exxon Nuclear Company ECCS Non-Jet-Pump-BWR Fuel Heatup Model by the Office of Nuclear Reactor Regulation March 6, 1975 i
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