ML20213C967
| ML20213C967 | |
| Person / Time | |
|---|---|
| Site: | Columbia  |
| Issue date: | 05/10/1979 |
| From: | Congel F Office of Nuclear Reactor Regulation |
| To: | Varga S Office of Nuclear Reactor Regulation |
| References | |
| CON-WNP-0272, CON-WNP-272 NUDOCS 7906110251 | |
| Download: ML20213C967 (2) | |
Text
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-3 W M i 0 ti79
' MEMDRANDUM FOR:
Steven A. Varga. Chief Light Water Reactors Branch 4. DPM FROM:
Frank J. Congel, Acting Chief Radiological Assessment Branch, DSE
SUBJECT:
WPPSS 2--ROUND TWO QUESTIONS PLANT NAME:
WPPSS Nuclear Project No. 2 LICENSING STAGE:
OL DOCKET NUMBER:
50-397 MILEST0f!E NUMBER /BRANCil CODE:
12/33 PROJECT MANAGER:
M. Lynch RESPONSIBLE BRANCH:
LWR-4 REQUESTED COMPLETION DATE:
May 11, 1979 DESCRIPTION OF. ESPONSE: Round Two Questions REVIEW STATUS:
Continuing The Radiation Protection Section of the Radiological Assessment Branch has completed its round two review of Section 12 and related sections of the WPPSS #2 FSAR. As a result of this review and a review of the applicant's responses to the round one questions, we have attached five round two questions. The applicant should be aware that we may ask additional questions concerning radiation j
protection at WPPSS #2 based on experience gained from the Three i
Mile Island incident.
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This review was performed by C. S. Hinson, RPS/RAB.
Ort 4nal Arvalb; F.J.congel Frank J. Congel, Acting Chief Radiological Assessment Branch Division of $1;e Safety and Envimnnental Analysis
Enclosure:
as stated 10M5/X ~
cc:
R.Hartfield(w/oencl.)
J. Collins DISTRIButLuci R. DeYoung R. Boyd Central File D. Muller M. Lynch NRR Reading L. Crocker T. Murphy pAB Readino F Concel
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c 331-1 12.0 RADIOLOGICAL MSESS:'EMi 331.25 It is our position that you base your radiation protection (12.0) practices on the latest revisions of Regulatory Guides 8.3 (Rev. 3, June 1973) and 8.10 (Rev.1-R, itay 1977).
Provide your plans to comply with these latest revisions.
331.26 Indicate whether, and if so, how, the guidance provided (12.0) by the following Regulatory Guides has been followed; if not followed, describe the specific alternative nethods used:
R.G. 8.7, " Occupational Radiation Exoosure Records Systcin" R.G. 3.12. " Criticality Accident Alarm Systems" 331.27 Describe the circunstances which would necessitate personnel (12.1.2.1) entry into the puns corridor C-125 while systens are opera ti ng.
331.28 fising the appropriate layout drawings as referances, indicate (12.3) the path to be travellad by the uaste container fre.n the time it is renoved from the e.,pty drun cask storage area to the time it is Icaded onto the waste leiding trailer. Justi fy your reasoning for not providing any area nonitors in this area of the rad laste cuilding on ela.<ation 437' where the uaste containars ara fill 3d and stored (area vetwe3n grids
?!-1 and S, and 13.2 and 17).
331.29 Describe cerir.anent shielding provided t.) assure acceptable (12.3) radiation levels in potentially occupied areas in the vicinity of the spent fuel transfer process.
If very high radiation areas are projacted, describe precautions taken to prevant inadvertent parsonnel access during fuel transfer.
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