ML20210T331

Forwards Questions Re Radiation Protection Design Aspects of Projects,Per Radiological Assessment Branch Review of PSAR Through Amend 0

ML20210T331
Person / Time
Site:	Satsop
Issue date:	09/30/1974
From:	Harold Denton US ATOMIC ENERGY COMMISSION (AEC)
To:	Deyoung R US ATOMIC ENERGY COMMISSION (AEC)
References
CON-WNP-1805 NUDOCS 8605300063
Download: ML20210T331 (3)

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• Requested completion date: Sept. 27, 1974 Description of responses Round 1 Questions I-Review states Con *4nuing The Wa=Mapton Public Fower Supply System's, WPPSS Project No. 3 and 5,

, FEAlt has been reviewed through Amendesat 0 by the Radiological Asseeement.

.u Branch. As a result of this review 4==1mding discuenions with the '

" applicant,em September 16, 1974, questions concerning the Radiation ~#

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.Frotection design aspects of the project have been generated and included

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!  ; This review wee performed by T. D. Murphy, RAB.

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Harold R. Denton, Assistant Director As stated ~

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l 331.0 RADIOLOGICAL ASSESSMENT BRANCH

, 331.1 on a suitable figure in Section 9.1 (or 12.1) detail the I (9.1.1) shielding provided around the fuel transfer tube in the area where the full transfer tube passes from the Reactor Building to the Fuel Handling Building.

l 331.2 With regard to the use of stub walls throughout the auxilliary (12.1.2) building, discuss the review performed of these walls to ' assure

that equipment in cubicles will not be placed within the line

of signt of receptors in corridors.

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331.3 Describe to what extent the applicant will implement the criteria 1 (12.1) ,

of Regulatory Guide 1.69, Concrete Radiation Shields for Nuclear

! Power Plants.

A 331.4 With the fuel pool cleanup system operating as described in (9.1.3) Sections 9.1.3 and 11.2, provide an analysis of the expected

(11.2) radiation levels from the full elements and the radioactivity (12.1) in the fuel pool in working areas around the pool. Provide a i

justification that the capacity of the cleanup system will meet the Zone II criteria in work areas. Show assumptions and

! calculations.

, I 331.5 Discuss plans to provide for temporary ventilation systems for '

(9.4) localized ventilation during maintenance.

331.6 The definition of miscellaneous non-radioactive piping for field (12.1.3) run piping in section 12.1.3.10 is unacceptable for certain applications. Such a "non-radioactive pipe" should not be run through Zone I. This definition should be modified.

331.7 In section 12.1.6.1 second paragraph, you indicate that annual (12.1. 6) doses to plant personnel will be well below the limits of 10 CFR Part 20. Since most exposure is received during maintenance in areas of relatively high radiation, clarify how doses will be maintained well below 10 CFR Part 20.

331.8 Picase supply the referenced material for Table 12.1.17. Is (12.1) data still valid af ter three additional years of operation and

, build up of long lived nuclides.

331.9 To meet the criteria for necessity and location of area monitors (12.1.4) in particular with regard to warning of unauthorized or inadvertent movement of radioactive material in the plant, provide justifi-cation for not locating radiation monitors in areas of the aux 1111ary building and turbine building where radioactive material movement may occur.

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t 331.10 On figure 12.1-10a expected radiation levels from the fuel ll (12.1) pool cooling pump should be reexamined andthe Radiation Zone adjusted as required.

i 331.11 In order to check calculations for the analysis of the airborne (12.2) rsdioactivity monitors, please provide flow rates for various (9.4) cubicles on figures 9.4.1, 9.4.2, and 9.4.3.

I 331.12 The location of the calibration room on the 1st floor of the (12.1) administration building appears to be such that unacceptably high radiation levels will occur on occasion in the counting room and at the frisker locations around the health physics area.

Justify locating the calibration facility adjacent to low level

counting facilities.

331.13 Describe the Radiation Zone Design Criteria for the Administration (12.1) Building.

331.14 With respect to the laundry operation and design in the

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(12.1) Administration Building, describe plans for the following:

a) Storage of used and laundered clothing to reduce radiation

level buildup in this area.

g b) Provisions for filtered ventilation.

• 331.15 In addition to the information in this section including Table (12.1.6) 12.1-17a, provide the expected occupancy in each of the plant radiation areas by job function. For example, tabulate the number of hours maintenance personnel will spend in the solid waste processing area, how many hours operators will spend in that area, how many hours health physics personnel will spend in that area. Continuing for each major area to be occupied by personnel in each job function.

331.16 Provide an esticate of construction worker doses from the (12.1.6) operation of unit 3 during the completion of construction of unit 5.

331.17 Discuss the rationale for providing direct access from the women's (12.1) lounge and health physics areas to the hot laundry facility without going through personnel change facilities.

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