ML081580168
| ML081580168 | |
| Person / Time | |
|---|---|
| Site: | Saint Lucie  |
| Issue date: | 06/06/2008 |
| From: | Mozafari B NRC/NRR/ADRO/DORL/LPLII-2 |
| To: | Stall J Florida Power & Light Co |
| Mozafari B, NRR/ADRO/DORL, 415-2020 | |
| References | |
| TAC MD6202 | |
| Download: ML081580168 (14) | |
Text
June 6, 2008 Mr. J. A. Stall Senior Vice President, Nuclear and Chief Nuclear Officer Florida Power and Light Company P.O. Box 14000 Juno Beach, Florida 33408-0420
SUBJECT:
ST. LUCIE PLANT, UNIT 2 - NOTICE OF CONSIDERATION OF ISSUANCE OF AMENDMENT TO RENEWED FACILITY OPERATING LICENSE, PROPOSED NO SIGNIFICANT HAZARDS CONSIDERATION DETERMINATION, AND OPPORTUNITY FOR A HEARING REGARDING MINOR CHANGES AND CORRECTIONS TO THE TECHNICAL SPECIFICATIONS (TAC NO. MD6202)
Dear Mr. Stall:
Enclosed is a copy of a Notice of Consideration of Issuance of Amendment to Facility Operating License, Proposed No Significant Hazards Consideration Determination, and Opportunity for a Hearing related to the application for an amendment dated July 17, 2007, for the St. Lucie Plant, Unit No. 2. The application proposes to change the Technical Specifications related to adoption of the alternative source term as described in Regulatory Guide 1.183.
The notice has been forwarded to the Office of the Federal Register for publication.
Sincerely,
/RA by EBrown for/
Brenda L. Mozafari, Senior Project Manager Plant Licensing Branch II-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-389
Enclosure:
As stated cc: See next page
Florida Power and Light Company ST. LUCIE PLANT cc:
Mr. Mano Nazar Mr. Christopher R. Costanzo Senior Vice President Plant General Manager and Nuclear Chief Operating Officer St. Lucie Nuclear Plant Florida Power & Light Company 6351 South Ocean Drive P.O. Box 14000 Jensen Beach, Florida 34957 Juno Beach, FL 33408 Mr. Terry Patterson Senior Resident Inspector Licensing Manager St. Lucie Plant St. Lucie Nuclear Plant U.S. Nuclear Regulatory Commission 6351 South Ocean Drive P.O. Box 6090 Jensen Beach, Florida 34957 Jensen Beach, Florida 34957 Don E. Grissette Craig Fugate, Director Vice President, Nuclear Training Division of Emergency Preparedness and Performance Improvement Department of Community Affairs Florida Power & Light Company 2740 Centerview Drive P.O. Box 14000 Tallahassee, Florida 32399-2100 Juno Beach, FL 33408-0420 M. S. Ross, Managing Attorney Mr. Rajiv S. Kundalkar Florida Power & Light Company Vice President - Nuclear Technical P.O. Box 14000 Services Juno Beach, FL 33408-0420 Florida Power & Light Company P.O. Box 14000 Marjan Mashhadi, Senior Attorney Juno Beach, FL 33408-0420 Florida Power & Light Company 801 Pennsylvania Avenue, NW. Mr. J. Kammel Suite 220 Radiological Emergency Washington, DC 20004 Planning Administrator Department of Public Safety Mr. Douglas Anderson 6000 Southeast Tower Drive County Administrator Stuart, Florida 34997 St. Lucie County 2300 Virginia Avenue Mr. Bill Parks Fort Pierce, Florida 34982 Operations Manager St. Lucie Nuclear Plant Mr. William A. Passetti, Chief 6351 South Ocean Drive Department of Health Jensen Beach, Florida 34957-2000 Bureau of Radiation Control 2020 Capital Circle, SE, Bin #C21 Mr. Seth B. Duston Tallahassee, Florida 32399-1741 Training Manager St. Lucie Nuclear Plant Mr. Gordon L. Johnston 6351 South Ocean Drive Site Vice President Jensen Beach, Florida 34957-2000 St. Lucie Nuclear Plant 6351 South Ocean Drive Jensen Beach, Florida 34957-2000
June 6, 2008 Mr. J. A. Stall Senior Vice President, Nuclear and Chief Nuclear Officer Florida Power and Light Company P.O. Box 14000 Juno Beach, Florida 33408-0420
SUBJECT:
ST. LUCIE PLANT, UNIT 2 - NOTICE OF CONSIDERATION OF ISSUANCE OF AMENDMENT TO RENEWED FACILITY OPERATING LICENSE, PROPOSED NO SIGNIFICANT HAZARDS CONSIDERATION DETERMINATION, AND OPPORTUNITY FOR A HEARING REGARDING MINOR CHANGES AND CORRECTIONS TO THE TECHNICAL SPECIFICATIONS (TAC NO. MD6202)
Dear Mr. Stall:
Enclosed is a copy of a Notice of Consideration of Issuance of Amendment to Facility Operating License, Proposed No Significant Hazards Consideration Determination, and Opportunity for a Hearing related to the application for an amendment dated July 17, 2007, for the St. Lucie Plant, Unit No. 2. The application proposes to change the Technical Specifications related to adoption of the alternative source term as described in Regulatory Guide 1.183.
The notice has been forwarded to the Office of the Federal Register for publication.
Sincerely,
/RA by EBrown for/
Brenda L. Mozafari, Senior Project Manager Plant Licensing Branch II-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-389
Enclosure:
As stated cc: See next page DISTRIBUTION:
PUBLIC LPL2-2 R/F RidsNrrPMBMozafari RidsNrrLABClayton RidsNrrDorlLpl2-2 RidsOgcRp RidsAcrsAcnw&mMailCenter RidsNrrDorlDpr RidsRgn2MailCenter (MSykes)
ADAMS Accession Number: ML081580168 ADM-012 OFFICE LPL2-2/SPM LPL2-2/LA LPL2-2/BC NAME EBrown for BClayton TBoyce BMozafari DATE 06/06/08 06/06/08 06/06/08 OFFICIAL RECORD COPY
7590-01-P UNITED STATES NUCLEAR REGULATORY COMMISSION FLORIDA POWER & LIGHT COMPANY DOCKET NO. 50-389 NOTICE OF CONSIDERATION OF ISSUANCE OF AMENDMENT TO FACILITY OPERATING LICENSE, PROPOSED NO SIGNIFICANT HAZARDS CONSIDERATION DETERMINATION, AND OPPORTUNITY FOR A HEARING The U.S. Nuclear Regulatory Commission (the Commission) is considering issuance of an amendment to Facility Operating License No. NPF-16 issued to the Florida Power and Light Company (the licensee) for operation of the St. Lucie Plant, Unit 2, located in St. Lucie County, Florida. The proposed amendment would change the Technical Specifications to modify the facilities operating licensing bases to adopt the alternative source term as allowed in 10 CFR 50.67 and described in Regulatory Guide 1.183. Through reanalysis of the following radiological consequences of the Updated Final Safety Analysis Report Chapter 15 accidents:
Loss-of-Coolant Accident, Fuel Handling Accident, Main Steam Line Break, Steam Generator Tube Rupture, Reactor Coolant Pump Shaft Seizure, Control Element Assembly Ejection, Letdown Line Break, and Feedwater Line Break.
Before issuance of the proposed license amendment, the Commission will have made findings required by the Atomic Energy Act of 1954, as amended (the Act), and the Commission's regulations.
The Commission has made a proposed determination that the amendment request involves no significant hazards consideration. Under the Commission's regulations in Title 10 of the CODE OF FEDERAL REGULATIONS (10 CFR), Section 50.92, this means that operation of the facility in accordance with the proposed amendment would not (1) involve a significant
increase in the probability or consequences of an accident previously evaluated; or (2) create the possibility of a new or different kind of accident from any accident previously evaluated; or (3) involve a significant reduction in a margin of safety. As required by 10 CFR 50.91(a), the licensee has provided its analysis of the issue of no significant hazards consideration, which is presented below:
- 1. The proposed amendment does not involve a significant increase in the probability or consequences of an accident previously evaluated.
Alternative source term calculations have been performed for St. Lucie Unit 2 which demonstrate that the dose consequences remain below limits specified in NRC Regulatory Guide 1.183 and 10 CFR 50.67. The proposed changes modify the setpoint for Control Room Isolation radiation monitoring instrumentation and add a new surveillance requirement. Control Room Isolation radiation monitoring instrumentation does not adversely affect accident initiators or precursors or prevent the ability of structures, systems, and components to perform their intended function to mitigate the consequences of an initiating event within the assumed acceptance limits. The modified setpoint and new surveillance requirement will ensure that the Control Room is isolated within the limits assumed in the AST analysis. The use of the AST only changes the regulatory assumptions regarding the analytical treatment of the design basis accidents and has no direct effect on the probability of any accident. The AST has been utilized in the analysis of the limiting design basis accidents listed above. The results of the analyses, which include the proposed changes to the Technical Specifications, demonstrate that the dose consequences of these limiting events are all within the regulatory limits.
The proposed Technical Specification [TS] changes are consistent with, or more restrictive than, the current TS requirements, with the possible exception of the alarm/trip setpoint for Control Room Isolation radiation monitoring instrumentation. The current alarm/trip setpoint of 2 times background is variable. A background reading of approximately 40 cpm is typical for the Control Room Isolation radiation monitors. It is possible that the background reading could increase to above 160 cpm. Revising the Control Room Isolation alarm/trip setpoint from 2 times background to 320 cpm will establish a maximum setpoint value and ensure automatic actuation of the control room emergency ventilation system for the limiting case event with adequate margin for the bounding total loop uncertainty of 200%. None of the affected systems, components or programs are related to accident initiators. As such, the revised TS requirements can not affect the probability of an accident and can only reduce the consequences of analyzed accidents.
Therefore, the proposed change does not involve a significant increase in the probability or consequences of an accident previously evaluated.
- 2. The proposed amendment does not create the possibility of a new or different kind of accident from any accident previously evaluated.
Other than discussed below, the proposed change does not affect any plant structures, systems, or components. The operation of plant systems and equipment will not be affected by this proposed change. Neither implementation of the alternative source term methodology nor establishing more restrictive TS requirements have the capability to introduce any new failure mechanisms or cause any analyzed accident to progress in a different manner.
The proposed changes associated with the Control Room Isolation radiation monitoring instrumentation setpoint and new surveillance requirement are not accident initiators.
These proposed changes do not involve a physical alteration of the plant (i.e., no new or different type of equipment will be installed) or a significant change in the methods governing normal plant operation. These changes do not alter any safety analysis assumptions and will not affect or degrade the ability of structures, systems, and components to perform their specified safety function.
Therefore, the proposed change does not create the possibility of a new or different kind of accident from any accident previously evaluated.
- 3. The proposed amendment does not involve a significant reduction in the margin of safety.
The proposed implementation of the alternative source term methodology is consistent with NRC Regulatory Guide 1.183. The proposed Technical Specification changes are consistent with, or more restrictive than, the current TS requirements with the possible exception of the alarm/trip setpoint for Control Room Isolation radiation monitoring instrumentation. The current alarm/trip setpoint of 2 times background is variable. A background reading of approximately 40 cpm is typical for the Control Room Isolation radiation monitors. It is possible that the background reading could increase to above 160 cpm. Revising the Control Room Isolation radiation monitoring instrumentation alarm/trip setpoint from 2 times background to 320 cpm will establish a maximum setpoint value and ensure automatic actuation of control room emergency ventilation system for the limiting case event with adequate margin for the bounding total loop uncertainty of 200%. These TS requirements support the AST revisions to the limiting design basis accidents. As such, the current plant margin of safety is preserved.
Conservative methodologies, per the guidance of RG 1.183, have been used in performing the accident analyses. The radiological consequences of these accidents are all within the regulatory acceptance criteria associated with use of the alternative source term methodology.
The proposed changes continue to ensure that the doses at the exclusion area and low population zone boundaries and in the Control Room are within the corresponding regulatory limits of RG 1.183 and 10 CFR 50.67. The margin of safety for the radiological consequences of these accidents is considered to be that provided by meeting the applicable regulatory limits, which are set at or below the 10 CFR 50.67 limits. An acceptable margin of safety is inherent in these limits.
Therefore, the proposed change does not involve a significant reduction in the margin of safety.
The NRC staff has reviewed the licensee's analysis and, based on this review, it appears that the three standards of 10 CFR 50.92(c) are satisfied. Therefore, the NRC staff proposes to determine that the amendment request involves no significant hazards consideration.
The Commission is seeking public comments on this proposed determination. Any comments received within 30 days after the date of publication of this notice will be considered in making any final determination.
Normally, the Commission will not issue the amendment until the expiration of 60 days after the date of publication of this notice. The Commission may issue the license amendment before expiration of the 60-day period provided that its final determination is that the amendment involves no significant hazards consideration. In addition, the Commission may issue the amendment prior to the expiration of the 30-day comment period should circumstances change during the 30-day comment period such that failure to act in a timely way would result, for example, in derating or shutdown of the facility. Should the Commission take action prior to the expiration of either the comment period or the notice period, it will publish in the Federal Register a notice of issuance. Should the Commission make a final No Significant Hazards Consideration Determination, any hearing will take place after issuance. The Commission expects that the need to take this action will occur very infrequently.
Written comments may be submitted by mail to the Chief, Rulemaking, Directives and Editing Branch, Division of Administrative Services, Office of Administration, U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001, and should cite the publication date and page number of this Federal Register notice. Written comments may also be delivered to Room 6D59, Two White Flint North, 11545 Rockville Pike, Rockville, Maryland, from 7:30 a.m.
to 4:15 p.m. Federal workdays. Documents may be examined, and/or copied for a fee, at the NRCs Public Document Room (PDR), located at One White Flint North, Public File Area O1 F21, 11555 Rockville Pike (first floor), Rockville, Maryland.
The filing of requests for hearing and petitions for leave to intervene is discussed below.
Within 60 days after the date of publication of this notice, the licensee may file a request for a hearing with respect to issuance of the amendment to the subject facility operating license and any person whose interest may be affected by this proceeding and who wishes to participate as a party in the proceeding must file a written request for a hearing and a petition for leave to intervene. Requests for a hearing and a petition for leave to intervene shall be filed in accordance with the Commissions Rules of Practice for Domestic Licensing Proceedings in 10 CFR Part 2. Interested persons should consult a current copy of 10 CFR 2.309, which is available at the Commissions PDR, located at One White Flint North, Public File Area O1 F21, 11555 Rockville Pike (first floor), Rockville, Maryland. Publicly available records will be accessible from the Agencywide Documents Access and Management Systems (ADAMS)
Public Electronic Reading Room on the Internet at the NRC Web site, http://www.nrc.gov/reading-rm/doc-collections/cfr/. If a request for a hearing or petition for leave to intervene is filed by the above date, the Commission or a presiding officer designated by the Commission or by the Chief Administrative Judge of the Atomic Safety and Licensing Board Panel, will rule on the request and/or petition; and the Secretary or the Chief Administrative Judge of the Atomic Safety and Licensing Board will issue a notice of a hearing or an appropriate order.
As required by 10 CFR 2.309, a petition for leave to intervene shall set forth with particularity the interest of the petitioner in the proceeding, and how that interest may be affected by the results of the proceeding. The petition should specifically explain the reasons
why intervention should be permitted with particular reference to the following general requirements: 1) the name, address and telephone number of the requestor or petitioner; 2) the nature of the requestors/petitioners right under the Act to be made a party to the proceeding; 3) the nature and extent of the requestors/petitioners property, financial, or other interest in the proceeding; and 4) the possible effect of any decision or order which may be entered in the proceeding on the requestors/petitioners interest. The petition must also identify the specific contentions which the petitioner/requestor seeks to have litigated at the proceeding.
Each contention must consist of a specific statement of the issue of law or fact to be raised or controverted. In addition, the petitioner/requestor shall provide a brief explanation of the bases for the contention and a concise statement of the alleged facts or expert opinion which support the contention and on which the petitioner intends to rely in proving the contention at the hearing. The petitioner/requestor must also provide references to those specific sources and documents of which the petitioner is aware and on which the petitioner intends to rely to establish those facts or expert opinion. The petition must include sufficient information to show that a genuine dispute exists with the applicant on a material issue of law or fact. Contentions shall be limited to matters within the scope of the amendment under consideration. The contention must be one which, if proven, would entitle the petitioner to relief.
A petitioner/requestor who fails to satisfy these requirements with respect to at least one contention will not be permitted to participate as a party.
Those permitted to intervene become parties to the proceeding, subject to any limitations in the order granting leave to intervene, and have the opportunity to participate fully in the conduct of the hearing.
If a hearing is requested, the Commission will make a final determination on the issue of no significant hazards consideration. The final determination will serve to decide when the
hearing is held. If the final determination is that the amendment request involves no significant hazards consideration, the Commission may issue the amendment and make it immediately effective, notwithstanding the request for a hearing. Any hearing held would take place after issuance of the amendment. If the final determination is that the amendment request involves a significant hazards consideration, any hearing held would take place before the issuance of any amendment.
A request for hearing or a petition for leave to intervene must be filed in accordance with the NRC E-Filing rule, which the NRC promulgated on August 28, 2007 (72 FR 49139). The E-Filing process requires participants to submit and serve documents over the internet or in some cases to mail copies on electronic storage media. Participants may not submit paper copies of their filings unless they seek a waiver in accordance with the procedures described below.
To comply with the procedural requirements of E-Filing, at least ten (10) days prior to the filing deadline, the petitioner/ requestor must contact the Office of the Secretary by e-mail at HEARINGDOCKET@NRC.GOV, or by calling (301) 415-1677, to request (1) a digital ID certificate, which allows the participant (or its counsel or representative) to digitally sign documents and access the E-Submittal server for any proceeding in which it is participating; and/or (2) creation of an electronic docket for the proceeding (even in instances in which the petitioner/requestor (or its counsel or representative) already holds an NRC-issued digital ID certificate). Each petitioner/ requestor will need to download the Workplace Forms ViewerJ to access the Electronic Information Exchange (EIE), a component of the E-Filing system. The Workplace Forms ViewerJ is free and is available at http://www.nrc.gov/site-help/e-submittals/install-viewer.html. Information about applying for a digital ID certificate is available on NRC=s public website at http://www.nrc.gov/site-help/e-submittals/apply-certificates.html.
Once a petitioner/requestor has obtained a digital ID certificate, had a docket created, and downloaded the EIE viewer, it can then submit a request for hearing or petition for leave to intervene. Submissions should be in Portable Document Format (PDF) in accordance with NRC guidance available on the NRC public website at http://www.nrc.gov/site-help/e-submittals.html.
A filing is considered complete at the time the filer submits its documents through EIE. To be timely, an electronic filing must be submitted to the EIE system no later than 11:59 p.m. Eastern Time on the due date. Upon receipt of a transmission, the E-Filing system time-stamps the document and sends the submitter an e-mail notice confirming receipt of the document. The EIE system also distributes an e-mail notice that provides access to the document to the NRC Office of the General Counsel and any others who have advised the Office of the Secretary that they wish to participate in the proceeding, so that the filer need not serve the documents on those participants separately. Therefore, applicants and other participants (or their counsel or representative) must apply for and receive a digital ID certificate before a hearing request/petition to intervene is filed so that they can obtain access to the document via the E-Filing system.
A person filing electronically may seek assistance through the AContact Us@ link located on the NRC website at http://www.nrc.gov/site-help/e-submittals.html or by calling the NRC technical help line, which is available between 8:30 a.m. and 4:15 p.m., Eastern Time, Monday through Friday. The help line number is (800) 397-4209 or locally, (301) 415-4737.
Participants who believe that they have a good cause for not submitting documents electronically must file a motion, in accordance with 10 CFR 2.302(g), with their initial paper filing requesting authorization to continue to submit documents in paper format. Such filings must be submitted by: (1) first class mail addressed to the Office of the Secretary of the Commission, U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001, Attention:
Rulemaking and Adjudications Staff; or (2) courier, express mail, or expedited delivery service to the Office of the Secretary, Sixteenth Floor, One White Flint North, 11555 Rockville, Pike, Rockville, Maryland, 20852, Attention: Rulemaking and Adjudications Staff. Participants filing a document in this manner are responsible for serving the document on all other participants.
Filing is considered complete by first-class mail as of the time of deposit in the mail, or by courier, express mail, or expedited delivery service upon depositing the document with the provider of the service.
Non-timely requests and/or petitions and contentions will not be entertained absent a determination by the Commission, the presiding officer, or the Atomic Safety and Licensing Board that the petition and/or request should be granted and/or the contentions should be admitted, based on a balancing of the factors specified in 10 C.F.R. ' 2.309(c)(1)(i)-(viii). To be timely, filings must be submitted no later than 11:59 p.m. Eastern Time on the due date.
Documents submitted in adjudicatory proceedings will appear in NRC's electronic hearing docket which is available to the public at http://ehd.nrc.gov/EHD_Proceeding/home.asp, unless excluded pursuant to an order of the Commission, an Atomic Safety and Licensing Board, or a Presiding Officer. Participants are requested not to include personal privacy information, such as social security numbers, home addresses, or home phone numbers in their filings. With respect to copyrighted works, except for limited excerpts that serve the purpose of the adjudicatory filings and would constitute a Fair Use application, Participants are requested not to include copyrighted materials in their submissions.
For further details with respect to this license amendment application, see the application for amendment dated July 16, 2007, as supplemented June 2, 2008, which is available for public inspection at the Commission's PDR, located at One White Flint North, File Public Area O1 F21, 11555 Rockville Pike (first floor), Rockville, Maryland. Publicly available
records will be accessible electronically from the Agencywide Documents Access and Management System's (ADAMS) Public Electronic Reading Room on the Internet at the NRC Web site, http://www.nrc.gov/reading-rm/adams.html. Persons who do not have access to ADAMS or who encounter problems in accessing the documents located in ADAMS, should contact the NRC PDR Reference staff by telephone at 1-800-397-4209, 301-415-4737, or by e-mail to pdr@nrc.gov.
Dated at Rockville, Maryland, this 6th day of June 2008.
FOR THE NUCLEAR REGULATORY COMMISSION
/RA/
Lois M. James, Chief Plant Licensing Branch III-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation