ML20234F382
| ML20234F382 | |
| Person / Time | |
|---|---|
| Site: | 05000000, 05000531 |
| Issue date: | 09/25/1974 |
| From: | Kreger W US ATOMIC ENERGY COMMISSION (AEC) |
| To: | Crutchfield D US ATOMIC ENERGY COMMISSION (AEC) |
| Shared Package | |
| ML20234C970 | List:
|
| References | |
| FOIA-87-40 NUDOCS 8707080204 | |
| Download: ML20234F382 (2) | |
Text
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1 M-Dennis Crutchfield, Project Manager, Light Water Reactors Group 2-1, L l
Lil dj; ACCEPTANCE REVIEW DN 251 GESSAR NSSS h^
Plant name: GESSAR-251 I
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Licensing stage: Acdeptance Review i
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Docket number: Project Number: 538 l
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. Responsible branch: LWR 2-1 Jr Date request received by RA-L:, /3/74 9
Requested completion date: 9/25/74 I
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Description of response: Acceptance review questions kn
' Review status: Complete ul.
Radiation Protection Section, RAB, has reviewed the subject report.
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The attached questions describe the additional information that will j
be needed in order for us to continue our review.
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This review was performed by W. Kreger, kPS/RAB.
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T Willia'm E. Kreger, Leader, d
Radiation Protection Section j
Enclosure:
Radiological Assessment Branch, SS/L W
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W. Mcdonald 3
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9/2 6/ 74 4/ /7F DATE F form AEC.)l8 (Rev. 9 53) ARCM 0240 ero ces se e s ses.: eso.a na 8707000204 070527 PDR FDIA PDR P;-
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331.0 RADIOLOGICAL ASSESSMENT BRANCH q
?j 331.1 Provide the 'Ju~stification for the use of 100,000 p Ci/sec for (12.1. 3. 5.1 )
the radioactive sources in the gas treatment system.
It is
]q not clear in section 11.1.1.1, exactly what operating experience was used to select this value.
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j 331.2 Is any calibration capability proposed for the range from 3
(12.1.4.2) 125 mr/hr to 1000 R/hr (containment building operating floor
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monitor)?
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331.3 This section mentions discussion in Sections 15.1 and 12.1 of
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~(12.2.3) the modes of relief valve discharge, the frequency of occurrence, d
and containment occupancy. There is no discussion of these in N
Section 12.1.
S 331.4 The applicant has provided answers to some of the pertinent
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9 (Supplementary questions from the review of 238 Reactor Island GESSAR.
%s information) However, several additional questions from that review should be addressed in Chapter 12 of 251 GESSAR.
These are 12.17, 12.31 y
and 12.48.
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331.5 In the radiation protection design of a nuclear steam supply d
(Chapter 12) system, there are several considerations that the applicant can implement for the equipment and comp 7;nents of that system that ij are important for assuring that occu will be as low as practicable (ALAP)pational radiation exposures a
These include design and i
d choice of equipment for low maintenance, design for quick removal (from high radiation areas), design for maintenance in low Q
radiation fields, design for quick access and entry, design for y
adequate working space, design for remote handling or tool use, y;
and others.
d These and any other design considerations relative
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to the ALAP requirement should be discussed in Chapter 12.
Illustrative examples of such design features should be provided.
h These should include the reactor and reactor systems during 4
nonnal operation and anticipated operational occurrences g
(including refueling, purging, maintenance, routine operational 1gj surveillanceandinserviceinspection).
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Have any design considerations been given to radiation exposure problems that will occur during decommissioning?
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