ML20198F238
| ML20198F238 | |
| Person / Time | |
|---|---|
| Site: | Washington Public Power Supply System |
| Issue date: | 12/27/1973 |
| From: | Harold Denton US ATOMIC ENERGY COMMISSION (AEC) |
| To: | Moore V US ATOMIC ENERGY COMMISSION (AEC) |
| References | |
| CON-WNP-0936, CON-WNP-936 NUDOCS 8605280446 | |
| Download: ML20198F238 (3) | |
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DISTRIBUTION Docket File AD/SS-L-Rdg q* 2 7 yy3 L-Rdg L.RAB Voss A. Moore, Assistant Director for Liqht Water Reactors, Group 2, L ROU:iD O';E QUESTI0flS - WPPSS !!UCLEAR 1 PSAR REVIEW Plant name: WPPSS Nuclear Project No. 1 Licensing stage: CP Docket nunber: 50 460 Responsible branch: LWR Project Oranch 2-3 Project Manager: T. Cox Data request received by RA.L: Bluebook Requested comletion dato: Dece%er 28. 1973 Description of response: Transmittal of 01 questions on UPPSS ?!u:lcar 1 Review status: titlestone 05-33 Completed Enclosed are round one questions which were prepared as a result of our review of Section 12.1,12.2, and 12.3 of the WPPSS Muclear 1 PSAR.
The enclosed questions are, with the exception of question 12.12, the s e as those transnitted in early December.
This review was conducted by T. Essig, RA.L.
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Harold R. Denton, Assistant Director for Site Safety Directorate of Licensing As stated cc: w/o encl.
A. Giambusso W. Mcdonald cc: w/ encl.
S. Hanauer J. Hendrfe A. Schwencer J. Kastner T. Cox T. Essia 0605200446 b OOO460 12a7 S. Block PDR ADUCK R. Klecker A
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- 12-1 12.0 RADIATION PROTECTION l
12.8 Provide more detail with respect to laycut and function of rooms within the health physics area (PSAR Figure 1.2-5).
Indicate access points and traffic flow to and from this area (PSAR Figura 1.2-5).
12.9 Provide a clearer distinction between the various radiation zones shown in the figures in Section 1.2 (e.g., see Figures 12.1-3 through 12.1-14 of the Perry Nuclear Plant PSAR, docket nos.
50-440 and 50-441).
12.10 Provide additional information on considerations followed in 8
design and to be followed in operation to minimize radiation exposures to plant personnel as discussed in Regulatory Guide 8.8.
In particular, the following items warrant further discussions i
The expected procedure for the review of detailed shielding l
a.
design (during preliminary and periodic design reviewers) by competent radiation protection engineers (with the support of other specialists as necessary).
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b.
Description of how caposura from routina in-plant inspections j
is considered in shielding and piping design and layouts.
l Manage =ent policy, organi=ational structure, and program for c.
maintaining radiation exposures as low as practicable (ALAP).
d.
Ambient radiation levels at instrument locations for calibration.
e.
Design features for contamination control considerations.
I f.
Provision for localized ventilation during maintenance operations.
g.
Provision for easy and rapid filter changes in the ventilation system.
i 12.11 Provide illustrative examples of the design considerations for cach of the following items fficers, dominera11:arn, tanks, j
evaporators, pumps, and sampling stations.
12.12 Provide the radiation protection critoria for process piping which l
nay be detailed and fabricated in the field. Ihn response should include a listing of critoria similar to those provided in the Creenwood PSAR (p.12.1-8, items a-f, dockot non. 50-452, 453).
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12-2 12.13 Provide the failed fuel design basis for the personnel doses presented in Table 12.1-4 (i.e.,1% or 0.1%).
12.14 Show the locations of all area monitors on the figures in I
Section 1.2.-
12.15 In Section 12.1.6.1, it is stated that " consideration will be given...to a level as low as practical in accordance with 10 CFR 20 guidelines".
The applicant should also reference Regulatory Guide 8.8, since it contains guidance for implementing the ALAP provisions of 10 CFR 20 (PSAR p. 12.1-11).
j 12.16 a.
Explain the relationship between the radiation monitors shown in Figures 9.4-1 through 9.4-13 and the airborne radioactivity monitors listed in Table 12.2-7.
The locations of all airborne radioactivity monitoring sample b.
l heads listed in Table 12.2-7 should be indicated on Figures I
9.4-1 through 9.4-13 or indicated on a figure such as Figure l
9.4-2 of the Seabrook PSAR, docket nos. 50-443 and 50-444.
Also, show the locations of these sample heads in the figures in Section 1.2.
i 12.17 Demonstrate that the airborne radioactivity monitoring system which monitors many compartments via a plant vent (e.g., Figure I
9.4-2) can adequately measure the concentrations of airborne i
l radioactivity to which plant personnel are exposed while occupying j
individual compartments.
12.18 The statement on p. 12.2-6 that "The iodine filter...is placed in i
parallel with the particulate filter." appears incorrect (it should l
be in series rather than in parallel). Also, justify the use of an activated charcoal type filter for lodine removal since an impregnated (EI) charcos1 type is more suitable for collecting l
organic iodide.
12.19 Describe the internal dosimetry program (e.g., whole body counting and bicansay) which will be conducted for plant personnel, f
12.20 Show the locations of isokinetic probes in the ceneral Services Building on the building layout drawings and ventilation systems drawings. Explain the relationship between the isokinetic probes and the airborne radioactivity monitoring system discussed in Section 12.2.
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