ML022950107
| ML022950107 | |
| Person / Time | |
|---|---|
| Site: | Duane Arnold |
| Issue date: | 10/28/2002 |
| From: | Hood D NRC/NRR/DLPM/LPD3 |
| To: | Peifer M Nuclear Management Co |
| References | |
| TAC MB4269 | |
| Download: ML022950107 (6) | |
Text
October 28, 2002 Mark A. Peifer Site Vice President Duane Arnold Energy Center Nuclear Management Company, LLC 3277 DAEC Road Palo, IA 52324-0351
SUBJECT:
DUANE ARNOLD ENERGY CENTER - CORRECTION TO ISSUANCE OF AMENDMENT (TAC NO. MB4269)
Dear Mr. Peifer:
On October 2, 2002, the U. S. Nuclear Regulatory Commission issued Amendment No. 248 to Facility Operating License No. DPR-49 for the Duane Arnold Energy Center. The amendment changed Technical Specification (TS) Section 5.0 to be consistent with TS Task Force Change No. 258, Revision 4.
We are reissuing a corrected copy of TS Pages 5.0-10 and 5.0-24. A revision bar is missing from 5.5.4.j on Page 5.0-10 where the words beyond the site boundary were added, and on Page 5.0-24 Section 5.7.d.1 the word should be reached versus reach.
Sincerely,
/RA/
Darl S. Hood, Senior Project Manager Project Directorate III Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket No. 50-331
Enclosures:
As stated cc w/encls: see next page
ML022950107 OFFICE PM:PD3-1 LA:PD3-1 SC:PD3-1 NAME DHood THarris LRaghavan DATE 10/28/02 10/28/02 10/28/02
Duane Arnold Energy Center cc:
Mr. Al Gutterman Morgan, Lewis & Bockius LLP 111 Pennsylvania Avenue NW Washington, DC 20004 Chairman, Linn County Board of Supervisors Cedar Rapids, IA 52406 Plant Manager, Nuclear Duane Arnold Energy Center Nuclear Management Company, LLC 3277 DAEC Road Palo, IA 52324 U.S. Nuclear Regulatory Commission Resident Inspectors Office Rural Route #1 Palo, IA 52324 Regional Administrator U.S. NRC, Region III 801 Warrenville Road Lisle, IL 60532-4351 Daniel McGhee Utilities Division Iowa Department of Commerce Lucas Office Building, 5th floor Des Moines, IA 50319 Mr. Roy A. Anderson Executive Vice President and Chief Nuclear Officer Nuclear Management Company, LLC 700 First Street Hudson, WI 54016 Nuclear Asset Manager Alliant Energy/IES Utilities, Inc.
Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.4 Radioactive Effluent Controls Program (continued) g.
Limitations on the dose rate resulting from radioactive material released in gaseous effluents from the site to areas at or beyond the site boundary l
shall be limited to the following:
1.
For noble gases: less than or equal to a dose rate of 500 mrem/yr to the whole body and less than or equal to a dose rate l
of 3000 mrem/yr to the skin, and 2.
For Iodine-131, iodine-133, tritium, and for all radionuclides in particulate form with half lives > 8 days: less than or equal to a dose rate of 1500 mrem/yr to any organ; h.
Limitations on the annual and quarterly air doses resulting from noble gases released in gaseous effluents to areas beyond the site boundary, conforming to 10 CFR 50, Appendix I; i.
Limitations on the annual and quarterly doses to a member of the public from iodine-131, iodine-133, tritium, and all radionuclides in particulate form with half lives > 8 days in gaseous effluents released to areas beyond the site boundary, conforming to 10 CFR 50, Appendix I; and l
j.
Limitations on the annual dose or dose commitment to any member of the public, beyond the site boundary, due to releases of radioactivity and l
to radiation from uranium fuel cycle sources, conforming to 40 CFR 190.
The provisions of SR 3.0.2 and SR 3.0.3 are applicable to the Radioactive l
Effluent Controls Program surveillance frequency.
l l
5.5.5 Component Cyclic or Transient Limit This program provides controls to track the UFSAR Section 5.3.3, cyclic and transient occurrences to ensure that components are maintained within the design limits.
DAEC 5.0-10 (continued)
Corrected by NRC Letter dated October 28, 2002 Amendment No. 248
High Radiation Area 5.7 5.7 High Radiation Area (continued) b.
Access to, and activities in, each area shall be controlled by means of an l
RWP or equivalent that includes specification of radiation dose rates in l
the immediate work area(s) and other appropriate radiation protection l
equipment and measures.
l l
c.
Individuals qualified in radiation protection procedures may be exempted l
from the requirement for an RWP or equivalent while performing radiation l
surveys in such areas provided that they are otherwise following plant l
radiation protection procedures for entry to, exit from, and work in such l
areas.
l l
d.
Each individual or group entering such an area shall possess:
l l
1.
A radiation monitoring device that continuously integrates the l
radiation rates in the area and alarms when the devices dose l
alarm setpoint is reached with an appropriate alarm setpoint, or l
l 2.
A radiation monitoring device that continuously transmits dose l
rate and cumulative dose information to a remote receiver l
monitored by radiation protection personnel responsible for l
controlling personnel radiation exposure within the area with the l
means to communicate with and control every individual in the l
area, or l
l 3.
A self-reading dosimeter (e.g., pocket ionization chamber or l
electronic dosimeter) and, l
l (i)
Be under the surveillance, as specified in the RWP or l
equivalent, while in the area, of an individual qualified in l
radiation protection procedures, equipped with a radiation l
monitoring device that continuously displays radiation dose l
rates in the area; who is responsible for controlling l
personnel exposure within the area, or l
l (ii)
Be under the surveillance as specified in the RWP or l
equivalent, while in the area, by means of closed circuit l
television, of personnel qualified in radiation protection l
procedures, responsible for controlling personnel radiation l
exposure in the area, and with the means to communicate l
with and control every individual in the area.
l l
(continued) l l
DAEC 5.0-24 Amendment No. 248 l
Corrected by NRC Letter dated October 28, 2002