ML19249E530
| ML19249E530 | |
| Person / Time | |
|---|---|
| Site: | Grand Gulf  |
| Issue date: | 05/19/1978 |
| From: | Kreger W Office of Nuclear Reactor Regulation |
| To: | Stolz J Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 7910010637 | |
| Download: ML19249E530 (4) | |
Text
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l Pfi1RA.1DUM FOR:
J. F. Stolz, Chief, Light Water Reactors Cranch 1, DPH FRO'i:
V. E. Krecer, Chief, Radiological Assesst.ent Crcnch, DSE SUDJECT:
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DESCf11H IC1 0F E TG3E: Rccc>cmandation far acceptcoce with requests for infcrcation PEVIO: LT/,TUS: Acc.pta.nce ru lew cccplete i
The Radiation Prot.ctica Section of the Rnliological Assessr. eat ra anch ics p:rfer. ed el acceptance review of Sectica 12 and icatorial ref.'r. ced in Sactica 12 of the arand Culf FSt.R.
TI.e FSAR contains x!cw ate infer..itfoa to allow es to begin car full revic.4; therefore, we recc:.:nd th:t. t!.c FSAR to accepted for decketing. Attac!ad are a ccpy of segulatcry Guide 3.19 c,nd rer.uests for auitional ir.far:n-tica thich ve *,.ill read to car.;plete cur revic.1 Fa request the opportunity to discuss cur reTjests v.ith the cpplicaat, p g,....., _,
Ori;b al cip c i sy T. D. ". p 'iy F
Willian E. Kreger, Chief
!!adiological Assessaent Cranch y,.,.j)
Division of Site Safety and
' TM b \\ l_uq Environnantal Ar.alysis
Enclosure:
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331-1 12.0
_ RADIOLOGICAL ASSESSMENT 331.1 Describe the applicable activities performed by the (12.1.1) individual (s) in your utility management having responsibility for radiation protection.
Describe the individual (s) with specific responsibility for design review to assure that occupational dose will be main-tained As Low As is Reasonably Achievable (ALARA) by title aiid general qualifications.
331.2 Your description of your comsliance with the guidance (12.1.1) of Regulatory Guide 8.8, (Revision 2), states that these considerations were not implemented:
- 1) C.2.e(3), use of bright hydrogen-annealed tubing and piping in pr N ry coolant and feedwater systems, 2)
C.2.e(6), provision of laminar flow in the primary i
- system, 1
- 3) C.2.i(7), use of canned pumps to reduce leakage,
- 4) C.2.i(9), use of spare connections on tanks and other components located in higher radiation zones.
Exp. lain why these considerations were not implemented in light of your commitment to maintain doses ALARA.
331.3 Describe how you have used your dose assessment and (12.1.2) the resultant man-rem doses to evaluate the facility design to assure that occupational doses will be ALARA. Also describe how you have factored experience from nperating power reactors into your radiation protection design and procedures.
Provide examples of improvements you have made in your design and procedures as a result of your use of l) dose assessment,
- 2) operational experience, and 3) ALARA design review.
331.4 It is our position that the in-plant accident radiation (12.3.4) monitoring systems should provide personnel with the (RSP) capability to assess the radiation hazard in areas which may be accessed during the course of an accident.
The accident monitoring systems may include the normal area radiation monitors, airborne radioactivity monitors, and portable radiation monitoring equipment I
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331-2 (item 331.8 deals with the portable equipment).
Emergency power should be provided for installed accident monitoring systems. The accident monitoring systems should have usable ranges which include the maximum calculated accident levels, and they should be designed to operate properly in the environment caused by the accident.
Describe your accident monitoring systems, and describe how your systems will meet this position.
331.5 Provide the frequency for calibration of the area (12.3.4) radiation monitors.
331.6 Describe how your continuous airborne radioactivity (12.3.4) systems will provide adequate coverage of general areas, rooms, and corridors which have a possibility I
of containing airborne radioactivity and whicn may be occupied by personnel.
In order to provide adequate k
coverage, the systems must be capable of detecting ten MPCa-hours of airborne particulate and iodine radioactivity.
331.7
. 'Your dose assessment requires two additional elements (12.4) in order to be complete.
First, provide sufficient illustrative detail to explain how the radiation dose assessment process was performed.
Table 12.4-3 provides adequate summary information for all categories except special maintenance; however, you should provide table (s) showing the activity or job, average dose rate, exposure time, number of workers, frequency, and dose for several jobs to demonstrate the detailed method v.hich is summarized in Table 12.4-3.
The details for every activity are not necessary, only several illustrative examples.
Second, provide a break-down of the activities which are included in the total of 150 man-rems / unit for special maintenance.
Regulatory Guide 8.19, " Occupational Radiation Dose Assessment in Light-Water Reactor Power Plants Design Stage Man-rem Estimates", (attached) which has been publ bhed for comment will provide further guidance.
331.8 Describe what radiation protection equipment, including (12.5.2) portable monitoring devices and respiratory protection devices, will be available to personnel responding to an accident.
Describe where this equipment will be stored.
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231-3 331.9 Provide the minimum frequency of whole body counting (12.5.3) for personnel who enter radiation areas.
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