ML20138N196
| ML20138N196 | |
| Person / Time | |
|---|---|
| Site: | Oyster Creek |
| Issue date: | 10/31/1985 |
| From: | Wilson R GENERAL PUBLIC UTILITIES CORP. |
| To: | Zwolinski J Office of Nuclear Reactor Regulation |
| References | |
| RFW-0670, RFW-670, NUDOCS 8511050104 | |
| Download: ML20138N196 (2) | |
Text
o OPU Nuclear Q
Qf 100 Interpace Parkway Parsippany, New Jersey 07054 201 263-6500 TELEX 136-482 Writer's Direct Dial Number:
October 31 1905 RFU - 06 0 Mr. John A. Zwolinski, Chief Operating Reactors Branch No. 5 Division of Licensing U.S. Nuclear Regulatory Commission Washington, D. C. 20555
Dear Mr. Zwolinski:
Subject:
Oyster Creek Nuclear Generating Station Docket No. 50-219 Suppression Pool Local Temperature Limit
References:
- 1) NRC Order dated January 19, 1982
- 2) Letter, D. M. Crutchfield to P. B. Fiedler,
" Mark I Containment Long Term Program - Structural Review", January 13, 1984
- 3) Letter, J. M. Fulton to C. O. Thomas,
" Request for Review of NED0 30832", March 21, 1985 In our letter dated July 26, 1985, concerning the work scope for our next (Cycle 11) refueling outage, we listed eight items in Attachment 2 for which we proposed a scope change or cancellation. Based upon the technical bases presented in NED0 30832 and our previous analysis of Electr matic Relief Valve discharges at Oyster Creek, we conclude that it is not necessary to provide suppression pool temperature monitoring local to the quenchers (Item 7) or the thermal mixing modification for the suppression pool (Item 6). Our previously proposed modifications for suppression pool local temperature monitoring and thermal mixing had been in response to NUREGs 0661 and 0783.
GPU Nuclear endorses the BWR Owner's Group position contained in the General Electric (GE) report NED0 30832, " Elimination of Limit on BWR Suppression Pool Temperature for SRV Discharge with Quenchers", December 1984. The GE report concluded that unstable steam condensation is not a concern when quencher devices are utilized on SRV discharge piping.
Quenchers have been installed at Oyster Creek.
NRC review of the NEDO report was requested by Reference 3.
Our review of the report concluded that it is applicable to the Oyster Creek Nuclear Generating Station.
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GPU Nuclear is a part of the General Public Utilities System t
. The issue of suppression p'ool temperature limits was addressed at a September, 1983 meeting with Brookhaven National Laboratory (BNL).
Based
- upon BNL's review of GPU Nuclear Technical Data Report No. 187, Revision 1, " Report on the Effects of Electromatic Relief Valve Discharge on Torus Water Temperature", coupled with the Monticello suppression pool temperature data base, General Electric Report No. NDE-24542-P, April 1979, BNL concluded that "... local pool temperature will not exceed the limits dictated by the acceptance criteria during the most severe SRV transients of interest". BNL Report No. 04243, " Technical Evaluation of the Oyster Creek Plant Unique Analysis Reports", was forwarded to us by Reference 2.
We request NRC concurrence with our cancellation of the nmdifications discussed above with the understanding that they will no longer be considered as part of the scope of work required by the Order (Reference 1) relating to the Mark I Containment Long Term Program.
If you should have any questions concerning the above matter, please contact Mr. Michael W. Laggart, Manager BWR Licensing, at (201) 299-2341.
ry t ly yours, O$Mh
. F. Wil on Vice President and Director Technical Functions RFW:gpa 2417f/001 cc: Dr. Thomas E. Murley, Administrator Region I U.S. Nuclear Regulatory Commission 631 Park Avenue King of Prussia, PA 19406 NRC Resident Inspector Oyster Creek Nuclear Generating Station Forked River, New Jersey Mr. Jack N. Donohew, Jr.
U.S. Nuclear Regulatory Commission 7920 Norfolk Avenue Phillips Building, Mail Stop 314 Bethesda, Maryland 20014
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