ML20094A097
| ML20094A097 | |
| Person / Time | |
|---|---|
| Site: | Peach Bottom  |
| Issue date: | 11/01/1984 |
| From: | Daltroff S PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC |
| To: | Stolz J Office of Nuclear Reactor Regulation |
| References | |
| RTR-NUREG-0737, RTR-NUREG-737, TASK-2.E.4.2, TASK-TM NUDOCS 8411060247 | |
| Download: ML20094A097 (2) | |
Text
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w PHILADELPHIA ELECTRIC COMPANY 2301 M ARKET STREET P.O'. BOX 8699 PHILADELPHIA. PA.19101 SHIELDS L. D ALTROFF su'c'W"?EU.o=
November 1, 1984 Docket Nos. 50-277 50-278 Mr. John F. Stolz, Chief Operating Reactors Branch #4 Division of Licensing U.S. Nuclear Regulatory Commission Washington, D.C.
20555
SUBJECT:
Peach Bottom Atomic Power Station NUREG-0737, Item II.E.4.2(7)
Radiation Signal On Purge Valves
REFERENCE:
a)
Correspondence dated December 12, 1983, J. F. Stolz, NRC, to E.
G. Bauer, Jr., PECo b)
Correspondence dated January 25, 1984, S. L.
Daltroff, PECo, to J.
F.
Stolz, NRC c)
Correspondence dated September 28, 1984 J. F. Stolz, NRC, to E. G. Bauer, Jr., PECo
Dear Mr. Stolz:
This letter identifies our plans for responding to reference (c) titled, " Updated Safety Evaluation for NUREG-0737, Item II.E. 4. 2 (7) ", and reviews the past licensing activities associated with this issue.
Reference (c) provided clarification relative to which containment purge and vent line sizes need high radiation isolation trips, and concluded that the Peach Bottom design was not in conformance with the design criteria presented in the Updated Safety Evaluation.
NUREG-0737, Item II.E.4.2, requires that " Containment purge and vent isolation valves must close on a high radiation signal".
However, NUREG-0737 did not specify any design criteria for the trip feature.
In reference (a), the staff provided The guidance regarding the design criteria for Item II.E.4.2.
guidance required a high radiation trip initiated by gaseous effluent radiation monitors.
In reference (b), we proposed high radiation trips for valves greater than 3 inches in diameter.
8411060247 841191 Ah PDR ADOCK 05000277 D
PDR i
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s Mr. John F. Stolz November 1, 1984 Page 2 This proposed Peach Bottom design is in full accordance with the NRC evaluations of this topic provided to the BWR Owners' Group via letters dated October 14, 1981, and May 31, 1983.
Our proposed design is also consistent with the design at our Limerick Generating Station which was specifically reviewed and approved by the NRC staff in the Safety Evaluation Report (reference: NUREG-0991, Section 6.2.4.3).
. Consequently, we were surprised to find that the Containment Systems Branch in reference (c) requested the high radiation isolation trip feature for all valves regardless of size.
Since the proposed Peach Bottom design is in compliance with previous NRC evaluations, is consistent with designs recently approved for another plant, and since the updated evaluation substantially alters your generic position on this issue, we have referred this subject to the BWR Owners' Group for
-resolution.
The BWR Owners' Group will consider further generic efforts for resolution of this issue at its November 7, 1984, general meeting.
If this topic is not pursued generically by the BWROG, we will re-evaluate our position and advise you of our intended course of action by November 30, 1984.
Should you have any questions regarding this matter, please do not hesitate to contact us.
Very truly yours, i' ?
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G cc:
A.
R. Blough, Site Inspector
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