ML14218A180
| ML14218A180 | |
| Person / Time | |
|---|---|
| Site: | Saint Lucie  |
| Issue date: | 09/16/2014 |
| From: | Farideh Saba Plant Licensing Branch II |
| To: | Nazar M Florida Power & Light Co |
| Saba F DORL/LPL2-2 301-415-1447 | |
| References | |
| TAC MF1888, TAC MF1889 | |
| Download: ML14218A180 (18) | |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 Mr. Mane Nazar President and Chief Nuclear Officer Nuclear Division NextEra Energy P.O. Box 14000 700 Universe Boulevard Juno Beach, Florida 33408-0420 September 16, 2014
SUBJECT:
ST. LUCIE PLANT, UNIT NOS. 1 AND 2-ISSUANCE OF AMENDMENTS REGARDING MODERATOR TEMPERATURE COEFFICIENT SURVEILLANCE REQUIREMENTS (TAC NOS. MF1888 AND MF1889)
Dear Mr. Nazar:
The U.S. Nuclear Regulatory Commission (NRC or the Commission) has issued the enclosed Amendment Nos. 219 and 168 to Renewed Facility Operating License Nos. DPR-67 and NPF-16 for the St. Lucie Plant, Unit Nos. 1 and 2, respectively. These amendments consist of changes to the Technical Specifications (TSs) in response to your application dated May 21, 2013, as supplemented by letter dated October 4, 2013.
These amendments modify the St. Lucie Plant Units 1 and 2 TSs for moderator temperature coefficient surveillance requirements associated with implementation of Westinghouse Commercial Atomic Power (WCAP)-16011-P-A, "Startup Test Activity Reduction (STAR)
Program."
The NRC staff's related safety evaluation of the amendments is enclosed. The Notice of Issuance will be included in the Commission's biweekly Federal Register notice.
Docket Nos. 50-335 and 50-389
Enclosures:
- 1. Amendment Nos. 219 and 168
- 2. Safety Evaluation cc w/encls: Distribution via Listserv Sincerely,
- -/,. 'Je-i v-s-~~
Farideh E. Saba, Senior Project Manager Plant Licensing Branch 11-2 Division of Operator Reactor Licensing Office of Nuclear Reactor Regulation
- 2.
Accordingly, Renewed Facility Operating License No. DPR-67 is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and by amending paragraph 3.B to read as follows:
B.
Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No./219, are hereby incorporated in the renewed license.
FPL shall operate the facility in accordance with the Technical Specifications.
- 3.
This license amendment is effective as of its date of issuance and shall be implemented within 90 days.
Attachment:
Changes to the Renewed Facility Operating License and Technical Specifications NUCLEAR REGULATORY COMMISSION Lisa M. Regner, Acting Chief Plant Licensing Branch 11-2 Division of Operator Reactor Licensing Office of Nuclear Reactor Regulation Date of Issuance: September 16, 2014
ATTACHMENT TO LICENSE AMENDMENT N0.219 TO RENEWED FACILITY OPERATING LICENSE NO. DPR-67 DOCKET NO. 50-335 Replace Page 3 of Renewed Operating License DPR-67 with the attached Page 3.
Replace the following pages of the Appendix A Technical Specifications with the attached pages. The revised pages are identified by amendment number and contain vertical lines indicating the area of change.
Remove Pages 3/4.1-5 3/4.1-6 Insert Pages 3/4.1-5 3/4.1-6
3-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:
A.
Maximum Power Level FPL is authorized to operate the facility at steady state reactor core power levels not in excess of 3020 megawatts {thermal).
B.
Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 219 are hereby incorporated in the renewed license.
FPL shall operate the facility in accordance with the Technical Specifications.
Appendix B, the Environmental Protection Plan (Non-Radiological), contains environmental conditions of the renewed license. If significant detrimental effects or evidence of irreversible damage are detected by the monitoring programs required by Appendix B of this license, FPL will provide the Commission with an analysis of the problem and plan of action to be taken subject to Commission approval to eliminate or significantly reduce the detrimental effects or damage.
C.
Updated Final Safety Analysis Report The Updated Final Safety Analysis Report supplement submitted pursuant to 10 CFR 54.21 (d), as revised on March 28, 2003, describes certain future activities to be completed before the period of extended operation. FPL shall complete these activities no later than March 1, 2016, and shall notify the NRC in writing when implementation of these activities is complete and can be verified by NRC inspection.
The Updated Final Safety Analysis Report supplement as revised on March 28, 2003, described above, shall be included in the next scheduled update to the Updated Final Safety Analysis Report required by 10 CFR 50.71 (e)(4), following issuance of this renewed license. Until that update is complete, FPL may make changes to the programs described in such supplement without prior Commission approval, provided that FPL evaluates each such change pursuant to the criteria set forth in 10 CFR 50.59 and otherwise complies with the requirements in that section.
D.
Sustained Core Uncoverv Actions Procedural guidance shall be in place to instruct operators to implement actions that are designed to mitigate a small-break loss-of-coolant accident prior to a calculated time of sustained core uncovery.
Renewed License No. DPR-67 Amendment No. 219
REACTIVITY CONTROL SYSTEMS MODERATOR TEMPERATURE COEFFICIENT LIMITING CONDITION FOR OPERATION 3.1.1.4 The moderator temperature coefficient (MTC) shall be maintained within the limits specified in the COLR. The maximum positive limit shall be:
- a.
Less positive than + 7 pcm/°F whenever THERMAL POWER is,:: 70% of RATED THERMAL POWER, and
- b.
Less positive than +2 pcm/°F whenever THERMAL POWER is > 70% of RATED THERMAL POWER.
APPLICABILITY: MODES 1 AND 2*#.
ACTION:
With the moderator temperature coefficient outside any one of the above limits, be in HOT STANDBY within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
SURVEILLANCE REQUIREMENTS 4.1.1.4.1 Verify MTC is within the upper limit specified in LCO 3.1.1.4.
- a.
Prior to entering MODE 1 after each fuel loading, and
- b.
Each fuel cycle within 7 effective full power days (EFPD) of reaching 40 EFPD core burnup.**
With Kett ~ 1.0.
Only required to be performed when MTC determined prior to entering MODE 1 is verified using adjusted predicted MTC.
See Special Test Exception 3.1 0.2.
ST. LUCIE-UNIT 1 3/4 1-5 Amendment No.2+-, EM, 8e, 4-W 219
REACTIVITY CONTROL SYSTEMS SURVEILLANCE REQUIREMENTS (continued) 4.1.1.4.2***
Verify MTC is within the lower limit specified in the COLR.
Each fuel cycle within 7 EFPD of reaching 2/3 of expected core burnup.
If MTC is more negative than the lower limit specified in the COLR when extrapolated to the end of cycle, 4.1.1.4.2 may be repeated. Shutdown must occur prior to exceeding the minimum allowable boron concentration at which MTC is projected to exceed the lower limit.
ST. LUCIE - UNIT 1 3/4 1-6 Amendment No.2+ 219
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 FLORIDA POWER & LIGHT COMPANY DOCKET NO. 50-389 ST. LUCIE PLANT UNIT NO.2 AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment No. 168 Renewed License No. NPF-16
- 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Florida Power & Light Company (FPL, the licensee), dated May 21, 2013, as supplemented by letter dated October 4, 2013, 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; B.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C.
There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D.
The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
- 2.
Accordingly, Renewed Facility Operating License No. NPF-16 is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and by amending paragraph 3.B to read as follows:
B.
Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.168, are hereby incorporated in the renewed license.
FPL shall operate the facility in accordance with the Technical Specifications.
- 3.
This license amendment is effective as of its date of issuance and shall be implemented within 90 days.
Attachment:
Changes to the Renewed Facility Operating License and Technical Specifications FOR TH,~UCLEAR REGULATORY COMMISSION film---"
Lisa M. Regner, Acting Chief Plant Licensing Branch 11-2 Division of Operator Reactor Licensing Office of Nuclear Reactor Regulation Date of Issuance: September 16, 2014
ATTACHMENT TO LICENSE AMENDMENT NO. 168 TO RENEWED FACILITY OPERATING LICENSE NO. NPF-16 DOCKET NO. 50-389 Replace Page 3 of Renewed Operating License NPF-16 with the attached Page 3.
Replace the following page of the Appendix A Technical Specifications with the attached page.
The revised pages are identified by amendment number and contain vertical lines indicating the area of change.
Remove Page 3/4.1-5 Insert Page 3/4.1-5 neutron sources for reactor startup, sealed sources for reactor instrumentation and radiation monitoring equipment calibration, and as fission detectors in amounts as required.
D.
Pursuant to the Act and 10 CFR Parts 30, 40, and 70, FPL 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 E.
Pursuant to the Act and 10 CFR Parts 30, 40, and 70, FPL to possess, but not separate, such byproduct and special nuclear materials as may be produced by the operation of the facility.
- 3.
This renewed license shall be deemed to contain and is subject to the conditions specified in the following Commission's regulations: 10 CFR Part 20, Section 30.34 of 10 CFR Part 30, Section 40.41 of 10 CFR Part 40, Section 50.54 and 50.59 of 10 CFR Part 50, and Section 70.32 of 10 CFR Part 70; and 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 below:
A.
Maximum Power Level FPL is authorized to operate the facility at steady state reactor core power levels not in excess of 3020 megawatts (thermal).
B.
Technical Specifications The Technical Specifications contained in Appendices A and 8, as revised through Amendment No. 168 are hereby incorporated in the renewed license.
FPL shall operate the facility in accordance with the Technical Specifications.
Renewed License No. NPF-16 Amendment No. 168
REACTIVITY CONTROL SYSTEMS MODERATOR TEMPERATURE COEFFICIENT LIMITING CONDITION FOR OPERATION 3.1.1.4 The moderator temperature coefficient (MTC} shall be maintained within the limits specified in the COLR. The maximum upper limit shall be +5 pcm/°F at :<::; 70% of RATED THERMAL POWER, with a linear ramp from +5 pcm/°F at 70% of RATED THERMAL POWER to 0 pcm/°F at 100% RATED THERMAL POWER.
APPLICABILITY: MODES 1 AND 2*#.
ACTION:
With the moderator temperature coefficient outside any one of the above limits, be in at least HOT STANDBY within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
SURVEILLANCE REQUIREMENTS 4.1.1.4.1 Verify MTC is within the upper limit specified in LCO 3.1.1.4.
- a.
Prior to entering MODE 1 after each fuel loading, and
- b.
Each fuel cycle within 7 effective full power days (EFPD) of reaching 40 EFPD core burnup. **
4.1.1.4.2***
Verify MTC is within the lower limit specified in the COLR.
Each fuel cycle within 7 EFPD of reaching 2/3 of expected core burnup.
See Special Test Exception 3.1 0.2 and 3.1 0.5.
With Ketr greater than or equal to 1.0.
Only required to be performed when MTC determined prior to entering MODE 1 is verified using adjusted predicted MTC.
ST. LUCIE-UNIT 2 3/4 1-5 Amendment No. 44, 2-5, W, ~. ~
168
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 RELATED TO AMENDMENT NOS. 219 AND 168 TO RENEWED FACILITY OPERATING LICENSE NOS. DPR-67 AND NPF-16 FLORIDA POWER & LIGHT COMPANY. ET AL.
1.0 INTRODUCTION
ST. LUCIE PLANT. UNIT NOS. 1 AND 2 DOCKET NOS. 50-335 AND 50-389 By letter to the U.S. Nuclear Regulatory Commission (NRC or the Commission) dated May 21, 2013 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML13144A166), as supplemented by letter dated October 4, 2013 (ADAMS Accession No. ML13289A179), Florida Power & Light Company (FPL or the licensee) requested to amend Renewed Operating Licenses DPR-67 and NPF-16 for St. Lucie Plant, Unit Nos. 1 and 2 (St. Lucie).
The proposed change would modify the Technical Specifications (TSs) moderator temperature coefficient (MTC) surveillance requirements (SRs) associated with the implementation of Westinghouse Commercial Atomic Power (WCAP)-16011-P-A, "Startup Test Activity Reduction (STAR) Program" (ADAMS Accession No. ML050660118 for the non-proprietary version) for St. Lucie. The WCAP-16011-P-A is a topical report providing the technical justification to support licensees making changes to post-refueling startup physics test programs that are performed following a core reload.
By letter dated March 31, 2003, the Combustion Engineering (CE) Owners Group submitted to the NRC a proposed topical report WCAP-16011-P (proprietary version) and WCAP-16011-NP (nonproprietary version found at ADAMS Package Accession No. ML030980342). By letter dated January 14, 2005 (ADAMS Accession No. ML050180327), the NRC-approved WCAP-16011-P-A for referencing in licensing applications forCE-designed pressurized-water reactors (PWRs).
The supplement dated October 4, 2013, provided additional information that clarified the application, did not expand the scope of the application as originally noticed, and did not change the staffs original proposed no significant hazards consideration determination as published in the Federal Register on July 23, 2013 (78 FR 44173).
Enclosure
2.0 REGULATORY EVALUATION
In Title 10 of the Code of Federal Regulations (1 0 CFR) Section 50.36, the Commission established its regulatory requirements related to the content of TSs. Pursuant to 1 0 CFR 50.36, the TSs must include items in five specific categories related to station operation: (1) safety limits, limiting safety system settings, and limiting control settings; (2) limiting conditions for operations (LCOs); (3) SRs; (4) design features; and (5) administrative controls.
The regulations do not specify the particular-requirements to be included in a plant's TSs and do not explicitly prescribe specific post-refueling startup testing. However, the post-refueling startup testing can be traced to the pre-operational testing required to be specified in the Final Safety Analysis Report required by 10 CFR 50.34.
Section 50.36 of 10 CFR specifies SRs relating to test, calibration, or inspection to assure that the necessary quality of systems and components is maintained, that facility operation will be within safety limits, and that the limiting conditions for operation will be met.
Appendix A, "General Design Criteria" (GDC), of 10 CFR Part 50 apply, in that the GDC establish the necessary design, fabrication, construction, testing, and performance requirements for structures, systems, and component important to safety. Part 50 of 10 CFR, Appendix B, "Quality Assurance Criteria for Nuclear Power Plants and Fuel Reprocessing Plants," applies, in that Criterion III"Design Control" requires that "measures shall provide for verifying or checking the adequacy of design, such as by the performance of design reviews, by the use of alternate or simplified calculational methods, or by the performance of a suitable testing program."
Specifically, the MTC is a parameter controlled in the licensees' TSs, including the SRs. As a value in the TSs, the MTC and the applicable SRs are subject to regulatory oversight.
Technical Specifications Task Force (TSTF}-486 changes NUREG-1432, "Standard Technical Specifications [STSs] Combustion Engineering Plants," to generically implement MTC SR changes associated with implementation of WCAP-16011-P-A, "Startup Test Activity Reduction (STAR) Program." WCAP-16011-P-A describes methods to reduce the time required for startup testing. WCAP-16011-P-A proposes methods to eliminate the control element assembly (CEA) worth and isothermal temperature coefficient (lTC) measurements at hot zero power (HZP).
The measured lTC is used to calculate the HZP MTC. WCAP-16011-P-A includes a method to substitute the measured verification of MTC at HZP with an alternate MTC verification consisting of the predicted (calculated) MTC and measured critical boron concentration at HZP. When this alternate MTC verification is utilized, WCAP-16011-P-A adds the requirement for the early in-cycle MTC measurement to verify MTC is not more negative or positive than allowed.
WCAP-16011-P-A adds an lTC measurement at intermediate to hot full power and applicability requirements for core design, fabrication, refueling, startup testing, and CEA lifetime viability requirements. WCAP-16011-P-A methods can only be applied to cores that are well characterized by an existing database. WCAP-16011-P-A is only applicable to the particular plants that participated in its development, as indicated in the document. TSTF-486 provides standardized wording in the CE STSs for plants implementing the WCAP-16011-P-A alternate MTC verification at startup.
3.0 TECHNICAL EVALUATION
3.1 Proposed Changes The licensee's proposed license amendment request (LAR) dated May 21, 2013, would modify MTC SRs associated with the implementation of WCAP-16011-P-A. The licensee proposed to make the following changes to the TSs for St. Lucie:
The proposed change revises the MTC SR 4.1.1.4.1, to indicate the MTC upper limit is specified in LCO 3.1.1.4.
The proposed change revises the MTC SR 4.1.1.4.1, Frequency, to add a requirement to verify MTC is within the upper limit within 7 effective full power days (EFPDs) of reaching 40 EFPDs of core burn up for each fuel cycle and prior to entering Mode 1 after each fuel loading. This verification would only be required if the MTC determined prior to entering Mode 1 is determined using an adjusted, predicted MTC.
The proposed change revises MTC SR 4.1.1.4.2 to indicate the MTC lower limit is specified in the core operating limits report (COLR).
The proposed change revises MTC 4.1.1.4.2, Frequency, to add a requirement to verify MTC is within the lower limit within 7 EFPDs of reaching 2/3 of expected core burnup for each fuel cycle. This SR requires that shutdown must occur prior to exceeding the minimum allowable boron concentration at which MTC is projected to exceed the lower limit and allows repeating SR 4.1.1.4.2 if the MTC is more negative than the lower limit specified in the COLR when extrapolated to the end of cycle.
This LAR revises St. Lucie Units 1 and 2 SRs 4.1.1.4.1 and 4.1.1.4.2, associated with TS 3.1.1.4, "Moderator Temperature Coefficient."
Currently, St. Lucie Units 1 and 2 SR 4.1.1.4.1 states:
The MTC shall be determined to be within its limits by confirmatory measurements.
MTC measured values shall be extrapolated and/or compensated to permit direct comparison with the above 1 limits.
The proposed SR 4.1.1.4.1 states; Verify MTC is within the upper limit specified in LCO 3.1.1.4.
- a. Prior to entering MODE 1 after each fuel loading, and
- 1. The 'above' limits are specified in LCO 3.1.1.4.
- Only required to be performed when MTC determined prior to entering MODE 1 is verified using adjusted predicted MTC.
Currently, St. Lucie Unit 1 SR 4.1.1.4.2 states:
The MTC shall be determined at the following frequencies and THERMAL POWER conditions during each fuel cycle:
- a. Prior to initial operation above 5% of RATED THERMAL POWER, after each refueling.
- b. At any THERMAL POWER, within 7 EFPD after initially reaching a RATED THERMAL POWER equilibrium boron concentration.
- c. At any THERMAL POWER, within 7 EFPD after reaching a RATED THERMAL POWER equilibrium boron concentration of 300 ppm.
Currently, St. Lucie Unit 2 SR 4.1.1.4.2 states:
The MTC shall be determined at the following frequencies and THERMAL POWER conditions during each fuel cycle:
- a. Prior to initial operation above 5% of RATED THERMAL POWER, after each fuel loading.
- b. At any THERMAL POWER, within 7 EFPD after reaching a RATED THERMAL POWER equilibrium boron concentration of 800 ppm.
- c.
At any THERMAL POWER, within 7 EFPD after reaching a RATED THERMAL POWER equilibrium boron concentration of 300 ppm.
The proposed St. Lucie Units 1 and 2 SR 4.1.1.4.2 states:
4.1.1.4. 2*** Verify MTC is within the lower limit specified in the COLR.
Each fuel cycle within 7 EFPD of reaching 2/3 of expected core burnup.
3.2 The NRC Staff Technical Evaluation The NRC approved WCAP-16011-P-A on January 14, 2005, for referencing in LARs for participating CE-designed PWRs to the extent specified and under the limitations delineated in the topical report and the NRC staff's safety evaluation. The safety evaluation defines the conditions and limitations for applicability of the STAR program to a plant-specific application.
The proposed amendment would modify the TS MTC SRs associated with the implementation of WCAP-16011-P-A. The WCAP-16011-P-A describes the technical justification to support licensees making changes to post-refueling startup physics test programs that are performed following a core reload.
The NRC staff reviewed the licensee's proposed LAR dated May 21, 2013, and the licensee's response, dated October 4, 2013, to the staff's request for additional information in conjunction with WCAP-16011-P-A, and TSTF-486, Revision 2, as included in NUREG-1432, Revision 4.0.
The NRC staff determined that an NRC-approved methodology, WCAP-16011-P-A, is applied in the LAR to the extent specified and under the limitations and conditions stated in the topical report and the NRC safety evaluation for WCAP-16011-P-A. The St. Lucie cycle specific MTC values are calculated using approved methodologies specified in TS 6.9.1.11.b. "Core Operating Limits Report (COLR)." The staff concluded that the proposed TS changes regarding MTC surveillance for implementing the STAR program is applicable to St. Lucie.
SR 4.1.1.4.1 is being revised to state the upper MTC limit is specified in LCO 3.1.1.4. Currently, the location of the upper limit is stated in TS LCO 3.1.1.4, and SR 4.1.1.4.1 references this limit by stating the above limits." FPL is replacing this wording with, "specified in LCO 3.1.1.4." This change provides a more accurate representation of where the limits are stated and does not change any technical requirements in the TSs. Therefore, this change is acceptable.
SR 4.1.1.4.1 is also being revised to add a frequency that is required by WCAP-16011-P-A when the alternate MTC verification method is used to verify MTC is within the upper limit during startup testing. This frequency is consistent with WCAP-16011-P-A and NUREG-1432, "Combustion Engineering Standard Technical Specifications." Therefore, this change is acceptable.
SR 4.1.1.4.2 is being revised to state the lower MTC limit is in the COLR. Currently, the location of the lower limit is specified in LCO 3.1.1.4 to be, "in the COLR." This change makes SR 4.1.1.4.2 consistent with the LCO 3.1.1.4. The specific wording is also consistent with current wording in the NUREG-1432. Therefore, this change is acceptable.
The NRC staff also determined that an acceptable justification was provided by the licensee for the deviation of SR 4.1.1.4.2 for the MTC lower limit verification between each fuel cycle within 7 EFPDs of reaching 40 EFPDs core burnup and each fuel cycle within 7 EFPDs of reaching 2/3 of expected core burnup. Within 7 EFPDs of reaching 40 EFPDs of each fuel cycle is early in the cycle and adds less technical value for verification of the MTC lower limit. However, within 7 EFPDs of reaching 2/3 of expected core burnup of each fuel cycle verifies the lower limit well in advance of reaching the expected end of-life core burnup and well in advance of approaching the MTC lower limit. Therefore, the proposed deviation is acceptable.
In summary, the NRC staff concludes that the proposed changes are consistent with TSTF-486, Revision 2, NUREG-1432, Revision 4.0 and WCAP-16011-P-A, therefore the proposed TS changes to St. Lucie Units 1 and 2 SR 4.1.1.4.1 and SR 4.1.1.4.2 are acceptable.
3.3 Technical Evaluation Conclusion
The Commission has concluded, on the basis of the considerations discussed above, that: (1) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner, {2) such activities will be conducted in compliance with the Commission's regulations, and (3) the issuance of the amendments will not be inimical to the common defense and security or to the health and safety of the public.
4.0 STATE CONSULTATION
Based upon a letter dated May 2, 2003, from Michael N. Stephens of the Florida Department of Health, Bureau of Radiation Control, to Ms. Brenda L. Mozafari, Senior Project Manager, U.S. Nuclear Regulatory Commission, the State of Florida does not desire notification of issuance of license amendments. In an email dated July 25, 2012 (ADAMS Accession No. ML12208A014), from Cynthia Becker, Florida State Bureau of Radiation Control, to Farideh Saba, Senior Project Manager, U.S. Nuclear Regulatory Commission, the State of Florida confirmed that the May 2003 letter continues to reflect the State's position on notification of issuance of license amendments.
5.0 ENVIRONMENTAL CONSIDERATION
These amendments change a requirement with respect to installation or use of a facility component located within the restricted area as defined in 1 0 CFR Part 20 and changes surveillance requirements. The NRC staff has determined that the amendment involves no significant increase in the amounts, and no significant change in the types, of any effluents that may be released offsite, and that there is no significant increase in individual or cumulative occupational radiation exposure. The Commission has previously issued a proposed finding that the amendment involves no significant hazards consideration and there has been no public comment on such finding (78 FR 44173, dated July 23, 2013). Accordingly, these amendments meet the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22{c)(9). Pursuant to 10 CFR 51.22{b) no environmental impact statement or environmental assessment need be prepared in connection with the issuance of these amendments.
6.0 CONCLUSION
The Commission has concluded, based on the considerations discussed above, that: (1) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner, (2) there is reasonable assurance that such activities will be conducted in compliance with the Commission's regulations, and (3) the issuance of the amendment will not be inimical to the common defense and security or to the health and safety of the public.
Principal Contributors: Tai Huang Kristy Bucholtz Date: September 16, 2014
- ML14218A180 OFFICE LPLII-2/PM LPLII-2/LA DSS/SRXB*
NAME FSaba BCiayton CJackson DATE 09/02/14 08/28/14 04/10/14 OFFICE LPLII-2/BC(A)
LPLII-2/PM NAME LRegner FSaba DATE 09/15/14 09/16/14 RidsNrrLABCiayton Resource RidsRgn2MaiiCenter Resource THuang, NRR KBucholtz, NRR By a memorandum DSS/STSB OGC REIIiott STurk (with comments) 09/03/14 09/04/14