ML17037C347
| ML17037C347 | |
| Person / Time | |
|---|---|
| Site: | Nine Mile Point  |
| Issue date: | 07/22/1971 |
| From: | Morris P US Atomic Energy Commission (AEC) |
| To: | Brosnan T Niagara Mohawk Power Corp |
| References | |
| Download: ML17037C347 (4) | |
Text
Docket No. 50-220 JUL'2 2 ]97]
Niagara Ihhawk Power Corp.
ATM: Nr. Thomas J. Brosnam Vice President and Chief B~eer 300 Erie Boulevard, M.
- Syracuse, New*York 13202 Gentlemen:
On June 19, 1971, the ABC adopted interim acceptance criteria for the performance of energency core cooling syste11$
(ECCS) in light-water nuclear power plants.
A copy of'he CommissianIs interim policy state-ment on th1s matter is enclosed for your information.
In accordance with Section IV C.l(a) of the policy statement, you are requested to dubmLC an analysis of the performance of the ECCS presents installed in Nine i%le Point using methods equivalent to the evaluation model 1n Appendix A, Part 2 of the policy statement as soon as practicable, but not later than October 1, 3973., to canQ.nn that the performance of the ECCS is in, compliance with the criteria of Sect1on IV.A and 3 of the statement.
Ne have discussed this request with representatives of the General Electr1c Company and, we understand that ana3yses using this mode3. have been or are being performed for your plant.
9he information Chat we need regarding these ana3jrses is outlined below.
1.
Provide curves of peak clad tenyerature and percent clad natal-water reaction as a function of'reak size for the various conhinations of ECC subsystems evaluated by using single failure criteria equivalent to those incU.cated in Table 2-1 of the topical report; "Loss-of-Coolant Accident and Brergency Core Cooling Nadels for General Electric Boi31ng Mater Reactors",
A cKscussion should be included shmdng the Justification for the ECC subsystem conhinations used in Che evaluatian.
2.
For several brealcs that typi@ small, intermediate and large breaks, provide curves of (a) peak fuel clad temperature for various rod
- gmups, (b) core flow, (c) fuel channel inlet and outlet quality, (d) heat transfer coefficients, (e) reactor vessel water level, and (f) minhmun critical heat flux ratio (lIEHFR), a31 as functions of time.
Inculcate Che time Chat rated core cooling flow is initiated, the time the fuel channel becomes wetted based upon item 4 of Appendix A, Part 2, and the time Chat the temperature transient is terTIrinated.
OFFICE P SURNAME 19 DATE>
Form hEC-318 (Rcv. 9-33) AKCM 0240
- (I.S. GOVERNMENT PRINTING OFFICE> 1970~7 758
0 A'
0 Niagara Mohawk Power Corp.
JUL 82 ~gt 3.
For the uses performed in l and 2 above, discuss the range of peaking factors studied and the basis for selecting the com-bination that resulted in the nnst severe thermal transient.
Curves of peak clad temperature vs time for the range of pealdng
'actors studied should be &eluded.
4.
Discuss in detail any deviations in the evaluation Dndel used in the foregoing studies from that described in Appendix A, Part 2 of the Cmnd.ssion's interim policy statenent.
When this information has been prepared. please send us 60 copies.
When we have completed our review of the Nine Nile Point ECCS we willcontact you regarding the results of our evaluation.
Sincerely, Originel Signed by Peter A. Merris Peter A. Norris, Director Division of Reactor Licensing Enclosure
'EC Interim Policy Statement cc:
Arvin E. Upton, Esp.
LeBmuf, Lanb, Ieiby & 1'CacRae l82l Jefferson Place, N.W.
Washington, D. C.
20036 DISTHIBtJi'ION
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0I U. S, GovSRNMENT PRINTINO OFFICE 3970 407 798
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