ML20150D439
| ML20150D439 | |
| Person / Time | |
|---|---|
| Issue date: | 11/21/1978 |
| From: | Roberts J NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| To: | Rouse L NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| Shared Package | |
| ML20150D442 | List: |
| References | |
| REF-PROJ-M-1 M-1, NUDOCS 7812060107 | |
| Download: ML20150D439 (3) | |
Text
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UNITED STiTES 4
NUCLEAR REGULATORY COMMISSION g
C.
978 Project M-1 MEMORANDUM FOR:
Leland C. Rouse, Acting Chief Fuel Reprocessing and Recycle Branch Division of Fuel Cycle and Material Safety FROM:
John P. Roberts, Group Leader for Spent Fuel Storage Ins tallations Fuel Reprocessing and Recycle Branch (FCRR)
Division of Fuel Cycle and Material Safety
SUBJECT:
NOVEMBER 16, 1978 MEETING OF STONE AND WEBSTER ENGINEERING CORPORATION (S&W) PERSONNEL AND NRC STAFF TO DISCUSS CONTINUED REVIEW 0F TOPICAL REPORT SWECO-7601
Participants:
Stan Jacobs, S&W Craig Grochmal, S&W Leland C. Rouse, NRC-FCRR John Roberts, NRC-FCRR
Purpose:
Stone and Webster personnel and NRC staff met to discuss commitments made to continue review of SWEC0-7601 by Richard Starostecki, former Chief of the Fuel Reprocessing and Recycle Branch.
Discussion:
Le Rouse, Acting Chief, FCRR, reaffirmed that the first step of the review approach agreed to in an August 22, 1978 meeting between Richard Starostecki and Stan Jacobs of S&W would be executed by the end of 1978.(See enclosure 1, Meeting Notes of August 22, 1978 Meeti ng. )
A schedule for the remaining steps has not been determined and will depend on staff availability.
Stan Jacobs indicated that S&W desires swift completion of the first step and would provide the S&W effort needed to forward the remaining review steps. He also agreed to insert a revision of Chapter 8 of SWECO-7601 after the first paragraph of Section 8.1.1.
(See enclosure 2.)
This had previously been received by NRC but not incorporated in the text of SWECO-7601 by S&W.
John P. Roberts, Group Leader for q g 12 0 6 01p Spent Fuel Storage Installations Fuel Reprocessing and Recycle Branch C
Division of Fuel Cycle and Material Safety C
Enclosures:
As stated
f snara e c
PMIATION PRCrrrcrTCH
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l 8.1 RADIATION EXPOSIIRES -
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3.1.1 Po1 icv conaiderations protection, including radiation shielding, is designeq to ensure that the criteria specified in 10crR20 are met and that Radiation the guidelines specified in 10CFR100 are met during accident, conditions.
Design basis doses for accident conditions are presented in Section 2 3.4..
'the design reflects the policy g(
as low as gensanably 2
Xeeping occupats.onal radiation===ures
- 3 achievable (AIARA).
8.1.2 Desian considerations Table 8.1.2-1 gives the design dose rates for radiation zoning.
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Fig. 8.1.2-1 gives the design base radiation zones throughout thf f
A discussion of design f eatureg controlled area of the facility.
~ 1 to meet the AIARA objectives is presented in Section 8.3.1.
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access to the facility is throwith the security checkpoing l
area ig l
Normal Access to the potentially contaminated (Fig. 8.1.2-1).
through the health physica checkpoint where the radiation contron l
to al Nor %}
Some I or II access is provided station is located.within the potentially contaminated area.
l station areas way of the Radiation Control Station wherq egress is byclothing and egaipment are deposited in appropriatg contaminated containers for disposal.
These access and egress routes ensure prevent th*e spread of the control of operating personnel to t
radioactive materials.
Emergency egress is provided at variouq locations in the facility.
All outside doors are locked fog "g
access and alarmed upon egress.
m methods are employed with respect to buiiding arrangementa]
'three to protect operators free radiations 1
She primary means of minimizing exposure to radiation iq sources of radiatiog}
1.
to provide shielding between the and personnel.
The thickness of the shielding
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l estab11shed by radiation protection specialists to mecy design radiation dose rates outside the shield walla, I
The design radiation dose rates are listed
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Table 8.1.2-1 and schematically represented by radiation l8 zone maps (Fig. 8.1.2-1).
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i The separation of radioactive and waradioactivq i
2.
equipment is required to prevent unnecessary exposure to while malataining or operating naaradioactlyg radiaH an 4
components.
I Revision 1~,
8 1-1 6/15/77 d4 w.ny,
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0 Inmart A Personnel I
h individuale responsible for the S&W Radiation Protection Design Revie
[
Lead Radiation Protection Engineer and the Led Nuolear Engineer,
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i The qualifications of the personnel who are participating in radiation pri D
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design review, meet or exceed the qualification requirements in that 'they i
experienced in radiation protection and vill haves
@9 A Bachelor's Degree in the physical sciences or engineering.
a.
W Attended courses in radiation protection and be familiar with
})q radiation control instrunentation, exposure limits, shielding, b.
dosimetry, air sampling (courses take in (a) above may be used A,
to meet this requirement).
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At least three years of engineering experience, requiring the h
implementation of radiation protection principles.
This experience c.
j should be on power plant cystems similar or assocalted to the g
. systema being reviewed.
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