ML20041A974

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Comments on DES,NUREG-0854,Sections 1.2 & 5 Re Permits & Licenses, & Environ Consequences & Mitigating Actions
ML20041A974
Person / Time
Site: Clinton Constellation icon.png
Issue date: 02/18/1982
From: Gustafson P
ILLINOIS, STATE OF
To:
Office of Nuclear Reactor Regulation
References
RTR-NUREG-0854, RTR-NUREG-854 NUDOCS 8202230106
Download: ML20041A974 (2)


Text

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g.~ Illinois Department of %uclear Safety b 1035 Outer Park Drive Springfield, Illinois 62704 (217)546-8100 Philip f. Gustafson Jane A. Bolin Dirnfor Deputy Director c) b#

February 18, 1982 <9 /

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( RECEIVED b(.,

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Director, Division of Licensing "$m u Office of Nuclear Reactor Regulations g /'

U.S. Nuclear Regulatory Commission A v>

Washington, D.C. 20555 RE: Draft Environmental Statement Related to the Operation of Clinton Power Station, Unit #1 (NUREG-0854), Operating License Stage. (Docket No. 50-461)

Dear Sir:

After review of the subject document, the following comments and questions are directed to your attention:

A. Permits and Licenses - Section 1.2 This section addresses environmentally related permits, approvals and licenses required from federal and state agencies in connection with the project. For all other nuclear plants in the State of Illinois, ASME reglstration, stamp requirements, and inspection certification with the state jurisdictional authority have been addressed in the draft environmental statements. The " constructor" presently maintains the required registration and inspection certification for this applicant. The procurement from the appro-priate state jurisdiction of the necessary ASME Stamps, (NA, NPT) required to conduct maintenance on items officially turned over from the constructor to the applicant prior to operation of the plant and during the plant lifetime also needs to be addressed. What commit-ments or contractural agreements have been made by t'- applicant in this area?

c3N B. Environmental Consequences and Mitigating Actions - Section 5 b)

$N I oo 1. Section 5.3.2 " Quality" discusses the effect of the project

$0 on Jae area's water quality, and indicates that under certain /D 4

meteorological conditions, Unit 1 may have to be operated at o:f reduced power levels to prevent severe thermal pollution to the

~

oo Salt Creek. What operating restrictions, technical specification

@ requirements, etc. will be placed on the plant, as well as the g meteorological monitoring instrumentation, to restrict these nio thermal releases?

a)o o

i Page 2

2. Section 5.9, " Radiological Impacts" discusses the radiological impacts of routine and postulated accident conditions, and the applicants proposals for its ALARA programs. The staff indicates that its occupational dose estimates are based on annual average occupational doses for other BWR's to date. The staff also indicates that actual values could be two to'three times higher, which are still within the limits of the current 10CFR Part 20.

What considerations or assessments have been made for these evaluations in light of the proposed revisions to 10CFR 20?

Since the containment design has several different design features compared to other operating BWRs, (e.g. suppression pool indirectly open to refueling floor area) what ALARA approaches will be taken by the applicant during events like relief valve releases and other small break incidents within containment?

3. Section 5.94, " Environmental Impact of Postulated Accidents",

specifically addresses plant accidents and their impacts. In light of the guidance from NRC Regulatory Guides and NRC NUREGs on Post IMI-2 requirements, which source terms and related assumptions have been used for this plant design in considering Design Basis Accidents and small break loss of coolant accidents?

Thank you for the opportunity to review the Clinton Draft Environmental Statement - Operating License Stage. Your consideration of the above comments is appreciated.

Sincerely, ,-

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PhilipF.Gustafson,Qirector Department of Nuclear Safety PFG:RWD:jt cc: Gary N. Wright Roger Dettenmeier