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ML103220312 +

10 CFR 20 +, 10 CFR 20 Appendix B +, 10 CFR 50.59 +, 10 CFR 61 +, 10 CFR 20.1301 +, 10 CFR 50 Appendix I +, 10 CFR 50.36a + and 10 CFR 5036 +

CR

LO-CAR-2007-00053 +, LO-CAR-2004-06851 +, LO-CAR-2005-00891 + and LO-CAR-2007-01309 +

Correspondence

ULNRC-05743, Offsite Dose Calculation Manual Revision 17 + and ULNRC-05508, Transmittal of 2007 Annual Radioactive Effluent Release Report +

Cross cutting aspect

H.3(o) +

Docket

05000483 + and 00483 +

From

Union Electric Co +, AmerenUE + and Maglio S +

Generic letter

NRC Generic Letter 89-01, Implementation of Programmatic and Procedural Controls for Radiological Effluent Technical Specifications +

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Hours

2.777778e-4 d (0.00667 hours, 3.968254e-5 weeks, 9.132e-6 months) +, 0.0127 d (0.306 hours, 0.00182 weeks, 4.1855e-4 months) +, 0.00579 d (0.139 hours, 8.267196e-4 weeks, 1.9025e-4 months) +, 0.00174 d (0.0417 hours, 2.480159e-4 weeks, 5.7075e-5 months) + and 0.101 d (2.433 hours, 0.0145 weeks, 0.00333 months) +

Isotope

Tritium +, Co-60 +, Cs-137 +, Sr-90 +, Fe-55 +, Y-90 +, Co-57 +, Ni-63 +, Kr-85 +, Cu-64 +, N-16 +, Iodine-131 +, H-3 +, Cd-109 +, Mo-99 + and Mn-54 +

Issue date

November 18, 2010 +

Modification date"Modification date" is a predefined property that corresponds to the date of the last modification of a subject and is provided by <a rel="nofollow" class="external text" href="https://www.semantic-mediawiki.org/wiki/Help:Special_properties">Semantic MediaWiki</a>.

06:17:34, 14 January 2025 +

NUREG

NUREG/CR-2919 +, NUREG-0543 +, NUREG-0133, Safety Evaluation Accepting Licensee Rev 3 to ODCM for Plant Through Temporary Change 4.Rev Meets Criteria of NUREG-0133 & Other Guidance. Guidance +, NUREG-1058, Forwards Rev 1 to NUREG-1058,presenting Tech Specs for Plant at Time Util Received Full Power License,Per T Lang Request. W/O Encl + and NUREG-0324, Forwards Crac Code Input for 790328-0402 at Site.Wind Speeds Corrected to 10 Meter Level Using Procedures Outlined in NUREG-0324 +

Page count

80 +

Project stage

Request +

Regulatory Guide

Regulatory Guide 1.109 +, Regulatory Guide 4.15 +, Regulatory Guide 1.23 +, Regulatory Guide 1.111 + and Regulatory Guide 4.13 +

SR

SR-9.10.2.1 +

SSC

6E-9 +, 7E-7 +, 4E-7 +, 9E-6 +, 9E-3 +, 3E-9 +, 7E-2 +, 92E-04 +, 22E-04 +, 16E-05 +, 15E-02 +, 19E-04 +, 85E-02 +, 17E-04 +, 11E-04 +, 18E-06 +, 15E-08 +, 3I-day +, 87E-0 +, 13E-10 +, 2xlO-4 +, 84E-0 +, 07-95-004 +, 6lE-OI +, S89E-t06 +, L95E-Ol +, 9IE-08 + and 13E-tO +

NPF-30 +

November 18, 2010 +

Missouri + and Washington +

System

Steam Generator + and Reactor Coolant System +

TS

TS-3.0.1 +, TS-3.9.9 +, TS-5.4.1 +, TS-5.5.4 +, TS-6.14 +, TS-5.6.3 +, TS-6.9.1.7 +, TS-5.6.2 +, TS-6.8.4.F +, TS-4.9.4.2 +, TS-6.8.4.E + and TS-6.8.1.F +

Title

Offsite Dose Calculation Manual Revision 17 +

To

Office of Nuclear Reactor Regulation + and Document Control Desk +

Topic

Grab sample +, Offsite Dose Calculation Manual +, Annual Radioactive Effluent Release Report +, Annual Radiological Environmental Operating Report +, Process Control Program + and Annual Radiological Effluent Release Report +

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http://pbadupws.nrc.gov/docs/ML1032/ML103220312.pdf +

Ultimate Heat Sink

Cooling Tower +

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