ML20043G452
| ML20043G452 | |
| Person / Time | |
|---|---|
| Site: | Perry  |
| Issue date: | 06/11/1990 |
| From: | Colburn T Office of Nuclear Reactor Regulation |
| To: | Hiatt S OHIO CITIZENS FOR RESPONSIBLE ENERGY |
| References | |
| RTR-REGGD-01.097, RTR-REGGD-1.097 GL-89-06, GL-89-6, TAC-74844, NUDOCS 9006200313 | |
| Download: ML20043G452 (3) | |
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UNITED STATES NUCLEAR REGULATORY COMMISSION W ASHINGTON, D. C, 20555 3
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June 11, 1990 j
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Ms. Susan L. Hiatt Ohio Citizens for Responsible Energy, Inc.
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8275 Munson Road Mentor, Ohio 44060
Dear Ms. Hiatt:
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SUBJECT:
PERRY NUCLEAR POWER PLANT, UNIT NO. 1 RESPONSE TO' GENERIC LETTER 89-06, REGARDING THE SAFETY PARAMETER DISPLAY SYSTEM (SPDS) (TAC NO. 74844)
We received your August 29, 1989, letter commenting on the Cleveland Electric Illuminating Company's (licensee) July 12, 1989, response to Generic Letter (GL) 89-06 for the Perry Nuclear Power Plant, Unit No. 1.
We appreciate your concern in this area and thank you for your comments.
You took an exception'to the licensee's position that the SPDS will not inc'ude a display for drywell oxygen concentration because the Perry l;
Mrk III' containment is not inerted.
en and oxygen concentra-The NRC requirements for containment /drywell hydrofRG) 1.97, Revision 2.
tion monitoring are contained in Regulatory Guide That document prescribes the class and category of monitored parameters, the-prescribed range over which monitoring should take place and the reasons for monitoring the parameter. The range of monitoring for oxygen concentra-tion is 0 to 10% by volume and is primarily intended to detect a breach in containmert (or drywell) integrity for those plants not normally subjected to normal oxygen concentration (i.e., inerted). Thus, an oxygen monitor for a non-inerted containment /drywell would not serve a similar safety function and'is not needed. As such, RG 1.97, Revision 2, prescribes containment /drywell oxygen concentration monitoring for inerted plants only.
We aapreciate ycur concern for post-accident oxygen monitoring in the unlitely event of a blowdown of the reactor coolant piping within the drywell. For Mark'III containments,10 CFR 50.44 provides an acceptable post-accident strategy to maintain hydrogen concentration low using a combustible gas' control system in combination with the licensee's emergency procedares for' post-accident recovery. The licensee's position that containment /drywell oxygen concentration monitoring is not required for non-inerted Mark III containments has been found acceptable on this basis.
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,.F, Ms. Susan t.. Hiatt 2
June 11, 1990 If you have any questions or if I can be of any furthar assistance to you, please call me at (301) 492-1369.
Sincerely, h
Timothy G. Colburn, Sr. Project Manager Project Directorate 111-3 Division of Reactor Projects Ill, IV, Y and Special Projects Office of Nucisar Reactor Regulation o,
, - g-Ms. Susan L. Hiatt 2'
June 11, 1990
'If'you have any questions or if I can be of any further assistance to you, please call me at (301) 492-1369.
-l Sincerely,
/S/
l Timothy G. Colburn,.Sr. Project Manager Project Directorate III-3 Division of Reactor Projects III, IV, V and Special Projects Office of Nuclear Reactor Regulation DISTRIBUTION 1CentraLE11ess NRC & Local PDRs PD33 Rdg File JZwolinski GHolahan PKreutzer TColburn SNewberry JHannon-OGC
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