ML19220C186
| ML19220C186 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 08/02/1974 |
| From: | Harold Denton US ATOMIC ENERGY COMMISSION (AEC) |
| To: | Moore V US ATOMIC ENERGY COMMISSION (AEC) |
| References | |
| NUDOCS 7904300034 | |
| Download: ML19220C186 (3) | |
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DISTRIBUTION:
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L-RA3 Voss A. Moore, Assistant Director for Light Water Reactors, Group 2. L FIRST ROTD QUESTIONS IDE "Ntr H1LE ISLAND UNIT 2 Plant us:ne: Three Mile Island, Unit 2 Licensing stage: OL Docket nuzber: 50-320 Responsible branch:
L'aR 2-2 Project Mmmer:
- 5. Washburn Data requast racsived by 2A-L: Blue Book Raquested cc:splatim date: 8/2/74 Dascription of response: Questions fo-Applicant Review status: Q-1 to LEM Cos:plata The ISAR for Thres Mile Isla'2d, Unit 2 has been reviewed by RA3. First round questions are anelased.
Sectica 12.1 is iner-plata. The applicant was notified of this on July 24 during dise n=-W of the Draf e Q-l's.
Since the applicant failed to have availabla the people that worked on Chapter 12, discussions of these questicus did not occur. The applie=e stated that he wculd disensa these questions with the appropriata.pepple at the plant This infornation is requestad to obtain a complate record.
This review was made by R. Iasaler, 213.
Odpal W k7 L L De@:S Harold R. Denton, Assistant Director for Site Safety Directorata of Licensing Enclosura:
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33-1
[403 3g 33.0 RADICLCGICAL ASSESSMI'iT BRANG 33.1 In Sectica 12.1.1 discuss plant design features with regard (12.1.1) to Regulatory Guide 8.8 'Information Relevant to Maintaining Occupational Radiation Exposure As Lcw As Practicable."
In particular show hcw the guidance in paragraph C.3:
Facility and Equipmnt Design have been used in the design.
Section 12.1 of the FSAR states many of the objectives but does not provide specific exa=cles which deconstrate that occupational exposures will be kept as icw as practicable.
The f allcwing questions illustrate censiderations that have not been =entioned or have not been described in sufficient detail.
33.2 What type of surface will be used en walls, floors and ceilings (12.1.1) in areas where equip =ent which may contain radioactive
=aterial is located? Discuss this type of surface with regard to buildup of conen94mtien and with regard to decontasination.
33.3 What types of movable and te=porarf shielding will be available
( 12.1.1) on-site? Discuss provisions that will be =ade to allow the utilization of temporary shielding if necessary.
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33.4 What design features have been incorporated to ensure that (12.1.1) equip =ent which may require servicing will be accessible so that service ti=e and thus potential exposure ti=es will be =ini=1:ed?
33.5 Section 12.1.2 is ince=plete. Provide scalad layout and (12.1. 2) arrangecent drawings of Unit 2 shcwing the location of all radioactive sources of significance. Provide on the layouts the radiation zone designations including zone bcundaries for both nor=nl operational and refueling conditions. The layouts should shev shield wall thicknesses, centrol access areas, personnel and equipeent decent,-4 ation areas, contamination control areas, traffic patterns, location of the health physics facilities, location of airborne radioactivity and area radiation scnitors, location of control panel (s) for radwaste equip =ent and components, location of the ensite laboratory for analysis of chemical and radioactive sanples, and location of the counting room.
33.6 Many =anual valves in Unit 1 have no shielding between them (12.1. 2) and a radioactive scurce. Provide figures in suf ficient detail to shcw whether this occurs in Unit 2.
Give procedures used in operating valves.
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33-2 AUG 2 G74 33.7 Section 12.1.3 is inco=plete as es ti=ates of dose ratas and (12.1. 3) isotopic inventory have not been provided. Describe the sources of radiation that are the basis for the radiation
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protection design in the manner used as input to the shield design calculation. The des cription should tabulate sources by isotopic co= position or ga==a rav energy groups, strength (curie content) and geo=etry a well as provide the basis for the values. Source description should be provided for equip =ent of the radioattive was te =anagement systa=s,
spent fuel s torage pool, various amciliary sys te=s, and the equip =ent contafsing A-41 sources.
33.8 The solid waste storage dru=s have =anual hook-up wires
( 12.1. 5 )
for Unit 1.
If Unit 2 dru=s have =anual hook-up wires, es ti= ate the yearly =an-re= occupational exposure duriag their usage.
Give esti=ated dose level in the area and the a=ount of exposure ti=e.
Co= pare this =an-re= exposure with the =an-re= exposure that would occur if re=ote drum cappers were used instead of =anual hook-up wires.
33.9 The solid waste storage space and facilities appear inadequate, (12.1.5) especially if equip =ent like a de=ineralizer is out of service and =ust be drained. Give procedures to be used if capacity of waste storage spaca is exceeded. Estimate the maxi =us radiation levels cad occupational exposures frc= these vaste storage areas.
33.10 No esti= ate is given of doses to construction workers on Unit (12.1.6) 2 from the operation of Unit 1.
Provide estinated annual d%es to construction workers due to radiation from the ame414 ary building, the reactor building, outside tanks and storage areas which =ay contain radioactivity, and fro = radioactive effluents (direct radiation from the gaseous radioactive ef fluent plu=e) fro: Unit 1, Provide esti=ated =an-re:
doses for the construction period. Incluie =odels,
assu=ptions, cnd input data.
33.11 Se ction 12.1.6.1 is incomplete. Only the total can-re= is (12.1. 6.1) esti=ated.
Provide the esti=ated occupa, of the various plant radiation areas during nor=al operatloa and anticipated operational occurrences. For areas with expected airborne radioactivity concentration provide esti=ated =an-hours of oc cup ancy.
Provide an esti= ate of the annual =an-re= doses associated with =ajor functions such as operation, "intenance, radwaste handling, refueling, and inservice inspection. Provide the basis, models, and assumptions for the above values. For an exa ole of an acceptable approach see Section 12.1.5.2 of the PSA2 for Allens Creek Nuclear Generating S tation.
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