ML20041E169
| ML20041E169 | |
| Person / Time | |
|---|---|
| Site: | Perry  |
| Issue date: | 03/02/1982 |
| From: | Coffey R CLEVELAND ELECTRIC ILLUMINATING CO. |
| To: | Lamastra M Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 8203100211 | |
| Download: ML20041E169 (7) | |
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s P.o. box 97 E PERRY, oHlo 44081 m TEL EPHoN E (216) 259-37 37 m ADD RESS.10 CENTER Ro AD Serving The Best Location in the Nation s d ' plO 40 s
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March 2, 1982 9
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P Mike Lamastra E,'fip q Jo3% 7 Radiological Assessment Branch
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Dear Mike:
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hV In response to your request, I am forwarding to you our proposed responses to all of the radiological assessment branch open items, except for OI 471.29 calling for a plan and elevation layout drawing for the areas through which the spent fuel bundle passes and a radiation shielding of accessible areas analysis. Gilbert Commonwealth continues to pursue completion of this task for CEI. We hope the attached responses will close the four open items to which we are responding.
If the answers are sufficient, we will submit them to you in a formal response on the docket. Call me at (216) 259-3737, ext. 506, if you have any comments.
Very Truly Yours, Mk k
Rebecca Coffey Licensing Specialist cc:
S. F. Kensicki/J. Bontempo W. E. Coleman RBC: mlb
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8203100211 820302 PDR ADOCK 05000440 A
PDR i
DSER 12 3-1 In order to complete our review of Item II. F.l(3) cf UUREG - 0737, the applicant should provide a plant
- .ayout drawing showing the location of the four nigh-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 approximately core midplane spread about 32o apart centered at 2250 azimuth for Unit 1 and 125o for Unit 2.
Two monitors would be located in the Secondary Containment (Reactor Building) at about the 689' level and the same degree spread and azimuth as those in the Primary Containment. A drawing will be prepared when these sites become firm,
DSER 12.3-2 It is our position that the applic. ant 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
A radie. tion and shielding design review for all accessible areas around the IFTS currently is being completed for CEI by Gilbert Commonwealth,ourA/E. A plan and elevation layout drawing of the areas will be prepared upon completion of the design review.
l 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.
1 DSER 12 5-1 In orier to complete our review of Item II.D.3.3 of NUREG-0737, the applicant ('should provide the following information:
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1.
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).
4
Response
FSAR Section 12.5.3.7 will be revised as follows:
12.5.3.7 Evaluation and Control of Potential Airborne Radioactivity Fixed continuous air monitors and portable air monitors and air samplers are utilized to determine the concentrations of airborne radioactivity throughout the plant.
The fixed air monitors, described in Section 12.3.4 provide cont-inuous data to indicate trends throughout the various phnt areas.
Particulate filters and charcoal cartridges are removed periodically to identify the specific nuclides encountered.
Portable air samplers are used to collect particulate and charcoal grab samples 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 is accomplished by collection of iodine samples utilizing charcoal cartridges with particulate pre-filters and low volume air samplers.
The cartridges and filters are analyzed by gamma spectroscopy and gross beta methods.
t In the event the counting facilities are lont due to high back-ground counting levels, an alternate counting room is established in the Technical Support Center, located in the Service Building.
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Flushing of iodine cartridges to reduce noble gas interference is accomplished with service air available in a hood in the Low Level Laboratory.
Table 12.5 14 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 IMI-related items, the applicant should provide information clearly indicating that the standby gas treatment systemand/orthegaseousradwastesystemwere designed to function after an accident or explain why they were excluded.
Response
Information responsive to this question appears in revised Sections 12.6.4.7 and 12.6.4.8 of the FSAR which were incorporated by FSAR Amendment 6.