ML20050B609
| ML20050B609 | |
| Person / Time | |
|---|---|
| Site: | Perry  |
| Issue date: | 03/26/1982 |
| From: | Davidson D CLEVELAND ELECTRIC ILLUMINATING CO. |
| To: | Tedesco R Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 8204060125 | |
| Download: ML20050B609 (6) | |
Text
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' THE CLEVELAND ELECTRIC ILLUMIN ATING COMPANY ILLUMINATING BLDG e PUBLIC SOUARE e CLEVELAND, OHlo 4410 e TELEPHONE (216) 6231360 e MAIL ADDRESS: P.o. BOX 5000 Serving The Best Location in the Nation D:lwyn R. Davidson VICE PRESIDENT SYSTEM ENGINE ERING AND CONSTRUCTlON March 26, 1982 m
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Mr. Robert L. Tedesco ppq D
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f Assistant Director for Licensing T 4 Q...?I>6 W
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Division of Licensing OJ U.S. Nuclear Regulatory Commission
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Washington, DC 20555
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Re: Perry Nuclear Power Plant Docket Nos. 50-440; 50-441 Clarification of Response Submittals - Radiation Protection
Dear Mr. Tedesco:
This letter and its attachment respond to NRC open items identified in an SER of November 1981 from the Radiation Protection Branch.
It is our intention to incorporate these responses in a subsequent amendment to the FSAR.
Very truly yours,
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D. R. Davidson Vice President System Engineering and Construction DRD:mm 13/P/1 fDOl cc: Jay Silberg J
John Stefano Max Gildner
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Mike Lamastra 8204060125 820326 PDR ADOCK 05000440 E
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DSER 12.3-1 In order to complete our review of TMI Item II.F.1(3),
the applicant should provide a plant layout drawing showing the location of the four high-range monitors.
RESPONSE
The locations for the four high-range monitors have been tentatively selected.
Two monitors would be located in the Primary Containment (Drywell) at approxi-mately core midplane spread about 32* apart centered at 225*' azimuth for Unit 1 and 125' for Unit 2.
Two monitors would be located in the Secondary Containment (Reactor Building) at about 689' level.and the same degree spread
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and azimuth as those in the Primary Containment. CEI will submit a drawing showing the monitor locations approximately six months prior to fuel load.
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i DSER 12.3.2
.It is our position that the applicant should, in addition to these post-licensing programs, provide a plan and elevation layout drawing of the areas through which the spent-fuel bundle passes and perform a radiation and shielding design review of all accessible areas around the IFTS.
RESPONSE
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A' radiation and shielding design review for all accessible areas around the IFTS currently is being completed for CEI by Gilbert Commonwealth, our A/E. A plan and elevation layout drawing of the areas vill be submitted approximately
'six months prior to fuel. load.
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6 DSER 12.3-3 The applicant should verify that the key activated system is fail safe.
Response
The key activated system is fail safe when power is lost to the system.
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DSER 12.5-1 In order to complete our review of Item III.D.3.3 of NUREG-0737, the applicant should provide the following information:
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The method of sampling; 2.
The number and type of samplers; 3.
Sample media to be used; 4.
Sample flushing methods; and 5.
Sample analysis equipment, type, and location (must have low background area).
Response
FSAR Section 12.5.3.7 will be revised as follows:
12.5.3.7 Evaluation and Control of Potential Airborns Radioactivity Fixed continuous air monitors and portable air monitors and air samplers are utilized to determine the concentration. of airborne radioactivity throughout the plant.
The fixed air monitors, described in Section 12.3.4 provide continuous data to indicate trends throughout the various plant areas.
Particulate filturs and charcoal cartridges are removed periodically to identify the specific nuclides encountered.
Portable air samplers are used to collect particulate a-d charcoal grab sampics of areas of specific concern, for example, in preparation and conduct of specific work functions, to verify significant indicated changes by one or more fixed air monitors, or periodic air sampling throughout the plant.
In plant iodine analysis under accident conditions is accomplished by collection of iodine samples using silver zeolite cartridges. The cartridges and filters are analyzed by gamma spectroscopy using computer analysis techniques. An Emergency Plan Implementing Procedure will be prepared describing sampling; appropriate personnel will be trained in the procedure.
In the event the counting facilities are lost due to high background counting levels, an alter-nate counting room is established in the Technical Support Center, located in the Service Building.
Flushing of iodine cartridges to reduce nobic gas interference is accomplished with service air available in a hood in the Low Level Laboratory.
Table 12.5-4 lists the quantities of air samplers available. Table 12.3-10 lists the Airborne Radiation Monitors.
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DSER 12.6-1 In order to complete our review of TMI-related items, the
- applicant should provide information clearly indicating that the standby gas treatment system and/or the gaseous radwaste system were designed to' function after an accident or explain why they were excluded.
Response
Information responsive to this question appears in revised Sections 1;.6.4.7 and 12.6.4.8 of the FSAR whi.-h were incorporated by FSAR Amendment 6.
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