ML20207K091
| ML20207K091 | |
| Person / Time | |
|---|---|
| Site: | FitzPatrick  |
| Issue date: | 07/22/1986 |
| From: | Brons J POWER AUTHORITY OF THE STATE OF NEW YORK (NEW YORK |
| To: | Muller D Office of Nuclear Reactor Regulation |
| References | |
| JPN-86-33, NUDOCS 8607290334 | |
| Download: ML20207K091 (2) | |
Text
a 123 Main Street White Plains, New Wrk 10601 914 681.6240
- > NewYorkPbwer te""A"eT met 4# Authority
"-e'o-e-July 22, 1986 J m-86-33 Director of Nuclear Reactor Regulation U.S.
Nuclear Regulatory Commission Washington, D.C.
20555 Attention:
Mr. Daniel R. Muller, Director BWR Project Directorate No. 2 Division of BWR Licensing
Subject:
James A.
FitzPatrick Nuclear Power Plant Docket No. 50-333 Mark I Containment Lona Term Procram
References:
NRC letter, D.
B. Vassallo to C.
A.
- McNeill, Jr.,
dated December 12, 1984, transmitted TER.
Dear Mr. Muller:
The New York Power Authority submitted a Plant Unique Analysis of suppression pool dynamic loads for the FitzPatrick Mark I containment.
This analysis described the application to the FitzPatrick plant of the generic Mark I poo.1 dynamic loads and evaluation methods.
It also described plant unique loads used in assessing the capability of the containment and certain components to accommodate pool dynamic loading phenomena.
The referenced letter transmitted the NRC Technical Evaluation Report (TER) on the FitzPatrick analysis.
This report concluded i
that the pool dynamic loads utilized by the New York Power Authority are conservative and acceptable.
The purpose of this letter is to address an item in the TER which states:
"Because the fatigue analysis of the torus depended upon the operator initiating a procedure to end chugging within 15 minutes of a small break accident (SBA), the Licensee was asked to provide precautionary measures in case the operator failed to act.
The Licensee responded that the NRC and the Boiling Water Reactors Owners Group were reviewing the plant emergency procedure guides and that the FitzPatrick plant would implement the emergency procedure guides as necessary.
This response is satisfactory."
k P
P l l>
The FitzPatrick Mark I analysis assumes that the duration of chugging will not exceed 15 minutes.
By requiring the operator to activate the drywell sprays or Automatic Depressurization System based on the appropriate suppression pool and drywell temperature and pressure, Emergency Operating Procedures ensure that this design criterion is met.
Should you or your staff have any questions regarding this matter, please contact Mr.
J.
A.
Gray, Jr. of my staff.
Very truly yours,
) GL Jchn C.
Brons Senior Vice President Nuclear Generation cc:
Office of the Resident Inspector U.S.
Nuclear Regulatory Commission P.
O.
Box 136
- Lycoming, N.Y.
13093
_ _., _.., _ _.,