CY-10-008, Re-Submittal of Proposed Change to Technical Specifications Haddam Neck Plant Facility Operating License
| ML101100480 | |
| Person / Time | |
|---|---|
| Site: | Haddam Neck File:Connecticut Yankee Atomic Power Co icon.png |
| Issue date: | 04/07/2010 |
| From: | Norton W Connecticut Yankee Atomic Power Co |
| To: | Document Control Desk, NRC/FSME, Office of Nuclear Material Safety and Safeguards |
| References | |
| CY-10-008 | |
| Download: ML101100480 (11) | |
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CONNECTICUT YANKEE ATOMIC POWER COMPANY HADDAM NECK PLANT 362 INJUN HOLLOW ROAD
- EAST HAMPTON, CT 06424-3099 March 30, 2010 CY-1 0-008 Docket No. 50-213 Re: 10 CFR 50.90 U. S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, D. C. 20555-0001 Haddam Neck ISFSI Proposed Change to Technical Specifications Haddam Neck Plant Facility Operating License (DPR-61)
This letter is being re-submitted to clarify Connecticut Yankee's request for the following amendment to the Haddam Neck Plant's Technical Specifications in letter CY-09-006:
Change the title of the Physical Security Plan in the Haddam Neck Facility Operating License, section (5) Physical Protection, from the "Haddam Neck Plant Defueled Physical Security Plan" to the "Haddam Neck Plant ISFSI Physical Security Plan".
In accordance with 10 CFR 50.90, Connecticut Yankee Atomic Power Company (CYAPCO) is submitting Amendment 203 to the Haddam Neck Plant Facility Operating License (DPR-61) for the Haddam Neck Independent Spent Fuel Storage Installation (ISFSI).The proposed change reflects the proper title to Haddam Neck Plant's ISFSI Physical Security Plan.
The proposed change (Amendment 203) of the Haddam Neck Plant Facility Operating License (DPR-61) is provided in Attachment 1.
There are no regulatory commitments contained within this letter.
If you should have any questions regarding this submittal, please contact me at (860) 267-6426 Ext. 301 or Jim Lenois, CY ISFSI Manager at (860) 267-6426 Ext. 303.
Document Control Desk CY-1 0-008/Page 2 Sincerely, Date CE, nd President Connecticut Yankee Subscribed and sworn before me this 7 r, dayof " _4,2010.
- , : -. 47 Notary Public My Commission Expires:
Attachments:
- 1. Proposed Change (Amendment 203) to the HaddamNeck Plant Operating License (DPR-61).
- 2. Description and Justification of the Proposed Change to the Haddam Neck Plant Facility Operating License (DPR-61).
cc: Mr. S. J. Collins, NRC, Region 1 Administrator Mr. Eugene Cobey, Chief, Decommissioning Branch, NRC Region 1 Mr. J. Goshen, NRC, Project Manager
.Dr. E. L. Wilds Jr., CT DEP, Director, Radiation Division
CY-10-008 Docket No. 50-213 Attachment 1 Haddam Neck ISFSI Proposed Chanqe to the Haddam Neck Plant Facility Oreratina License (DPR-61)
March 2010
CONNECTICUT YANKEE ATOMIC POWER COMPANY DOCKET NO. 50-213 HADDAM NECK PLANT -
FACILITY OPERATING LICENSE License No. DPR-61
- 1. The Atomic Energy Commission (the Commission) having found that:
A. The application for license, as amended, filed by Connecticut Yankee Atomic Power Company (the licensee) complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations set forth in 10 CFR Chapter I and all required notifications to other agencies or bodies have been duly made; B. Construction of the Haddam Neck Plant (facility) has been sub-stantially completed in conformity with Construction Permit No. CPPR-14 and the application, as amended, the provisions of the Act, and the rules and regulations of the Commission; C. The facility will operate in conformity with the application, as amended, the provisions of the Act, and the rules and regula-tions of the Commission; D. There is reasonable assurance: (i) that the activities authorized by this operating license can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the rules and regulations of the Commission; E. The licensee is technically and financially qualified to engage in the activities authorized by this operating license in accor-dance with the rules and regulations of the Commission; F. The licensee has satisfied the applicable provisions of 10 CFR Part 140, "Financial Protection Requirements and Indemnity Agreements," of the Commission's regulations; G. The issuance of this operating license will not be'inimical to the common defense and security or to the health and safety of the public; OPLIC .DOC
January 3, 2002 H. After weighing the environmental, economic, technical, and other benefits-of the facility against environmental and other costs and considering available alternatives, the issuance of Facility Operating License No. DPR-61 is in accordance with Appendix D to 10 CFR Part 50 of the Commission's regulations and all applicable requirements have been satisfied; and I. The receipt, possession, and use of byproduct and special nuclear material as authorized by this license will be in accor-dance with the Commission's regulations in 10 CFR Parts 30, 40, and 70.
- 2. Facility Operating License No. DPR-61 is hereby issued to the Connecticut Yankee Atomic Power Company to read as follows:
A. This license applies to the Haddam Neck Plant, a pressurized lightwater reactor and associated equipment (the facility) owned by the Connecticut Yankee Atomic Power Company. The facility is located on Connecticut Yankee's Haddam Neck site on the east bank of the Connecticut River, approximately 21 miles south-southeast of Hartford, in the Town of Haddam, Middlesex County, Connecticut, and is described in the "Facility Description and Safety Analysis Report" as supplemented and amended (Amend-ment 10 through Amendment 25 to the License Application) and the "Environmental Report" (as supplemented by Amendment 1).
B. Subject to the conditions and requirements incorporated herein, the Commission hereby licenses Connecticut Yankee Atomic Power Company:
(1) Pursuant to Section 104b of the Act and 10 CFR Part 50, "Licensing of Production and Utilization Facilities," to possess, use, and operate the facility at the designated location in the Town of Haddam, Middlesex County, Connecticut, in accordance with the procedures and limita-tions set forth in this license; (2) Pursuant to the Act and 10 CFR Part 70, to receive, possess, and use at any time special nuclear material as reactor fuel in accordance with the limitations for storage and amounts required for reactor operation, as described in the Facility Description and Safety analysis as supplemented and amended; or as described in any amendment to this license; (3) CYAPCO, pursuant to the Act and 10 CFR Parts 30, 40, and 70, to receive, possess, and use at any time any byproduct, source and special nuclear material as sealed neutron sources for reactor startup (possession only), sealed sources for reactor instrumentation (possession only), and radiation monitoring equipment calibration, and as fission detectors in amounts as required; Amendment No. 196 OPLIC. DOC
December 20, 2004 (4) CYAPCO, pursuant to the Act and 10 CFR Parts 30, 40, and 70,to receive, possess, and use in amounts as required any byproduct, source or special nuclear material, without restriction to chemical or physical form, for sample analysis or instrument calibration or associated with radioactive apparatus or components; and (5) CYAPCO, pursuant to the Act and 10 CFR Parts 30 and 70, to possess, but not separate, such byproduct and special nuclear material as may be produced by the operations of the facility.
C. This license shall be deemed to contain and is subject to the conditions specified in the following Commission regulations in 10 CFR Chapter I: Part 20, Section 30.34 of Part 30, Section 40.41 of Part 40, Sections 50.54 and 50.59 of Part 50, and Section 70.32 of Part 70; is subject to all applicable provisions of the Act and to the rules, regulations, and orders of the Commission now or hereafter in effect; and is subject to the additional conditions specified or incorporated below:
(1) Maximum Power Level The licensee is not authorized to operate the reactor. Fuel may not be placed in the reactor vessel.
(2) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 201, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
(3) Deleted by Amendment No. 29.
(4) Fire Protection The licensee shall implement and maintain in effect all provisions of the approved fire protection program as described in the Updated Final Safety Analysis Report and as approved in the SER, dated October 3, 1978, and Supplements dated February 6, 1981, November 11, 1981, November 14, 1984, November 27, 1987, January 20, 1990, April 10, 1990, August 14, 1990, June 27, 1991, October 16, 1991, November 21, 1991, and February 1, 1995, subject to the following provisions.
The licensee may make changes to the fire protection program without NRC approval if these changes do not reduce the effectiveness of fire protection for facilities, systems, and equipment which could result in a radiological hazard, taking into account the decommissioning plant conditions and activities.
Amendment No. 201 OPLIC. DOC
March 2010 (5) Physical Protection The licensee shall fully implement and maintain in effect all provisions of the Commission-approved physical security, guard training and qualification, and safeguards contingency plans including amendments made pursuant to provisions of the Miscellaneous Amendments and Search Requirements revisions to 10 CFR 73.55 (51 FR 27817 and 27822) and to the authority of 10 CFR 50.90 and 10 CFR 50.54(p). The plans, which contain Safeguards Information protected under 10 CFR 73.21, is entitled:
"Haddam Neck Plant ISFSI Physical Security Plan," with revisions submitted through May 2006.
(6) Fuel Movement The movement of special nuclear material used as reactor fuel into the containment is prohibited.
(7) License Termination Plan The License TERMINATION Plan dated August 2004, as revised in December 2004 and May 2005 (Revision 3), is approved by NRC License Amendment No. 202.
In addition to those criteria specified in 10 CFR 50.59, 10 CFR 50.82(a)(6), and 10 CFR 50.82(a)(7), changes to the approved License Termination Plan shall require NRC approval prior to being implemented, if the change:
(a) Increases the radionuclide-specific derived concentration guideline levels (as discussed in Section 6 of the LTP) or area factors (as discussed in Section5.5.1.1 of the LTP)i (b) Increases the probability of making a Type 1 decision error above the level stated in the LTP (discussed in Section5.5.1.1 of the LTP);
(c) Increases the investigation level thresholds for a given survey unit classification (as given in Table 5-8 of the LTP);
(d) Changes the classification of a survey unit from the more restrictive classification to a less restrictive classification (e.g., Class 1 to 2, or Class A to Class B). Definitions of the different classifications for structures and surface solids are provided in Section 2.3.3.2 of the LTP, and definitions for different classifications for subsurface soils are provided in Section 2.3.3.1.5 of the LTP; (e) Reduces the coverage requirements for scan measurements (Table 5-9 of the LTP); or (f) Involves reliance upon statistical tests other than the WRS or Sign Test (as discussed in Section 5.8 of the LTP) for data evaluation.
Amendment No. ", 14T, 9, 24a, 203 OPLIC.DOC
11/25/02 Prior to a request to release a survey area from the license, the licensee shall have performed a Capture Zone Analysis and have assured that the ground water dose contribution is included for all applicable survey areas per the process described in Section 5.4.7.1 of Revision 1 of the LTP.
D. This license is effective as of the date of issuance and authorizes ownership and possession of this facility until the Commission notifies the licensee in writing that the license is terminated. The licensee shall:
- 1. Take actions necessary to decommission and decontaminate this facility and continue to maintain this facility, including, where applicable, the storage, control and maintenance of the spent fuel, in a safe condition; and
- 2. Conduct activities in accordance with all other restrictions applicable to this facility in accordance with NRC regulations and the specific provisions of this 10CFR50 facility license.
FOR THE ATOMIC ENERGY COMMISSION A. Giambusso, Deputy Director for Reactor Projects Directorate of Licensing Original Signed by A. Giambusso
Enclosure:
Appendices A and B - Technical Specifications Date of Issuance: December 27, 1974 Amendment No. 197 OPLIC. DOC
CY-1 0-008 Docket No. 50-213 Attachment 2 Haddam Neck ISFSI Description and Justification of Proposed Changqes to the Haddam Neck Plant Facility Operatingq License (DPR-61)
March 2010
Document Control Desk CY-1 0-008/Attachment 2/Page 1 Haddam Neck Plant Technical Specifications Amendment Request Change to Title of Haddam Neck Plant Physical Security Plan Facility Operating License (DPR-61)
Description of the Change:
Pursuant, to 10 CFR 50.90, Connecticut Yankee Atomic Power Company (CYAPCO) proposes to amend its Operating License, DPR-61, by revising the Haddam Neck Plant Technical Specifications. This change of the Haddam Neck Plant Facility Operating License (DPR-61) would update the title of the Physical Security Plan, from the 'Haddam Neck Plant Defueled Physical Security Plan' to the 'Haddam Neck Plant ISFSI Physical Security Plan', which is the current NRC approved Physical Security Plan.
Evaluation The proposed changes are administrative in nature and reflect current conditions at the Haddam Neck site. These proposed changes do not reduce the commitments in the Physical Security Plan or adversely affect the operation of the ISFSI.
Determination of Impact Amendment 203 of the Haddam Neck Plant Facility Operating License (DPR-61) is a title change only.
This change does not constitute a reduction in commitments in the Physical Security Plan.
Technical Analysis Significant Hazarda Consideration Connecticut Yankee Atomic Power Company has evaluated whether or not a significant hazards consideration is involved with the proposed amendment by focusing on the three standards set forth in 10 CFR 50.92, "Issuance of Amendment," as discussed below:
- 1. Does the Proposed amendment involve a significant increase to the probability or consequences of an accident previously evaluated?
Response: No.
Document Control Desk CY-1 0-008/Attachment 2/Page 2 The proposed amendment is a title change only. Therefore, the proposed amendment does not involve a significant increase in the probability or consequences of an accident previously evaluated.
- 2. Does the proposed amendment create the possibility of a new or different kind of accident from any accident previously evaluated?
Response: No.
The proposed amendment is a title change only. Therefore, the proposed amendment does not create the possibility of a new or different kind of accident from any accident previously evaluated.
- 3. Does the proposed amendment involve a significant reduction in a margin of safety?
Response: No.
The proposed amendment is a title change only. Therefore, the proposed amendment does not involve a significant reduction in a margin of safety.
Based on the above, Connecticut Yankee Atomic Power Company concludes that the proposed amendment presents no significant hazards consideration under the standards set forth in 10 CFR 50.92 (c), and accordingly, a finding of "no significant hazards consideration%is justified.
Environmental Consideration Connecticut Yankee Atomic Power Company has determined that the proposed amendment does not involve: (i) a significant hazards consideration; (ii) a significant change in the types or significant increases in the amounts of any effluent that may be released offsite; or (iii) a significant increase in individual or cumulative occupational radiation exposure. Accordingly, the proposed amendment meets the the eligibility criterion for categorical exclusion set forth in 10 CFR 51.22 (c)(9). Therefore, pursuant to 10 CFR 51.22 (c)(9), no environmental impact statement or environmental assessment need be prepared in connection with the proposed amendment.
Conclusion Based on the results of this evaluation, the changes proposed do not reduce the level of commitment in the Security Plan and may be implemented without detriment.