NRC-2009-0451, FRN: General Notice. Nine Mile Point Nuclear Station, Unit No. 1 - Removal of Pressure Isolation Valve Requirements Consistent with Improved TS
| ML092740798 | |
| Person / Time | |
|---|---|
| Site: | Nine Mile Point  |
| Issue date: | 10/06/2009 |
| From: | Guzman R V Plant Licensing Branch 1 |
| To: | |
| Guzman R V, NRR/DORL, 415-1030 | |
| References | |
| NRC-2009-0451, TAC ME2253 | |
| Download: ML092740798 (10) | |
Text
7590-01-P NUCLEAR REGULATORY COMMISSION NRC-2009-0451 NINE MILE POINT NUCLEAR STATION, UNIT NO. 1 DOCKET NO. 50-220 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 Operat ing License No. DPR-63 issued to Nine Mile Point Nuclear Station, LLC (the licensee) for operation of Nine Mile Point, Unit No. 1 (NMP1) located in Oswego, NY. The proposed amendment would modify Technical Specification (TS) Sections 3.2.7.1 and 4.2.7.1, "Primary Coolant System Pressure Isolation Valves," to incorporate requirements that are consistent with Section 3.4.5 of the Improved Standard TSs, NUREG-1433, Revision 3.
The proposed TS changes include the addition of applicable reactor operating conditions, addition of actions to be taken when pressure isolation valve (PIV) leakage is not within limit, relocation of the PIV leakage limit criterion from TS Table 3.2.7.1 to Specification 4.2.7.1.a, replacement of the existing PIV leakage test frequencies with a reference to the Inservice Testing Program, and deletion of TS Table 3.2.7.1, "Primary Coolant System Pressure Isolation Valves." The list of PIVs would be relocated from TS Table 3.2.7.1 to the NMP1 Updated Final Safety Analysis Report, consistent with the guidance in Generic Letter (GL) 91-08, "Removal of Component Lists from Technical Specifications." 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 ev aluated; 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. Does the proposed amendment involve a significant increase in the probability or consequences of an accident previously evaluated?
Response: No.
The proposed amendment involves changes to the TS requirements that apply to reactor coolant system (RCS) PIVs. No physical plant changes are involved.
PIVs isolate the boundary between the high pressure RCS and connected low pressure piping systems. The TS requirements are intended to detect PIV degradation that has the potential to cause a loss of coolant accident (LOCA) outside of containment due to the failure of low pressure portions of systems connected to the RCS.
The proposed changes to the TS requirements are consistent with NUREG-1433, "Standard Technical Specific ations, General Electric Plants, BWR/4," and will continue to ensure that excessive leakage through these valves is properly identified and resolved. Testing in accordance with the IST [Inservice Testing]
Program will continue to detect PIV leakage in excess of the established limits, which are not being changed. When these limits are exceeded, required actions will initiate appropriate activities to minimize the impact of the leakage. These actions will not adversely impact nuclear safety because the flow paths will be sufficiently isolated, the period of time without redundant isolation capability will be appropriately limited, and the probability of a second valve failing during this time period is low. Thus, the proposed amendment does not result in operation that would make an accident more likely to occur, and does not alter assumptions relative to mitigation of a previously evaluated accident.
Relocation of the list of PIVs from the TS to a licensee-controlled document (the UFSAR) in accordance with the guidance in GL 91-08 is an administrative change that does not alter the TS requirements that are applicable to the PIVs.
Based on the above discussion, it is concluded that the proposed amendment does not involve a signific ant increase in the probability or consequences of an accident previously evaluated.
- 2. Does the proposed amendm ent create the possibility of a new or different kind of accident from any accident previously evaluated?
Response: No.
The proposed amendment involves changes to the TS requirements that apply to RCS PIVs. These changes to the TS requirements are consistent with NUREG-1433. The proposed changes do not involve a physical alteration of the plant (no new or different type of equipment will be installed) or changes in the methods governing normal plant operation. The changes also do not alter the design function of the PIVs and do not adversely affect the ability of the PIVs to perform their design function.
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 involves changes to the TS requirements that apply to RCS PIVs. No physical plant changes are involved. PIVs isolate the boundary between the high pressure RCS and connected low pressure piping systems.
The revised TS PIV requirements will c ontinue to ensure that excessive leakage through these valves is properly identified and resolved, such that a LOCA outside of containment due to the failure of low pressure portions of systems connected to the RCS will be no more likely to occur. Thus, the proposed amendment will not result in a design basis or safety limit being exceeded or altered.
Based on the above discussion, it is concluded that the proposed amendment does not involve a significant reduction in a 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 t he 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 acti on prior to the expiration of either the comment peri od 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 and Directives Branch (RDB), TWB-05-B01M, 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 faxed to the RDB at 301-492-3446. Documents may be examined, and/or copied for a fee, at the NRC
=s Public Document Room (PDR), located at One White Flint North, Public File Area O1 F21, 11555 Rockville Pike (first floor), Rockville, Maryland. Within 60 days after the date of publication of this notice, any person(s) whose interest may be affected by this action may file a request for a hearing and a petition to intervene with respect to issuance of the amendment to the subject facility operating license. Requests for a hearing and a petition for leave to intervene shall be filed in accordance with the Commission
=s ARules of Practice for Domestic Licensing Proceedings
@ in 10 CFR Part 2. Interested person(s) should consult a current copy of 10 CFR 2.309, which is available at the Commission
=s PDR, located at One White Flint Nort h, Public File Area O1F21, 11555 Rockville Pike (first floor),
Rockville, Maryland. Publicly available records will be accessible 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/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 pet ition; 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 requestor=s/petitioner
=s right under the Act to be made a party to the proceeding; 3) the nature and extent of the requestor
=s/petitioner
=s 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 requestor's/petitioner
=s 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 hazar ds 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. All documents filed in NRC adjudicatory proceedings, including a request for hearing, a petition for leave to intervene, any motion or other document filed in the proceeding prior to the submission of a request for hearing or petition to intervene, and documents filed by interested governmental entities participating under 10 CFR 2.315(c), must be filed in accordance with the NRC E-Filing rule, which the NRC promulgated in Augus t 28, 2007 (72 FR 49139). The E-Filing process requires participants to submit and serve all adjudicatory 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 an exemption in accordance with the procedures described below.
To comply with the procedural requirements of E-Fili ng, at least ten (10) days prior to the filing deadline, the petitioner/requestor should must contact the Office of the Secretary by e-mail at hearing.docket@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 Viewer J to access the Electronic Information Exchange (EIE), a component of the E-Filing system. The Workplace Forms Viewer J 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 Web site 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 Web site 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 using the agency's adjudicatory e-filing system may seek assistance through the "Contact Us" link located on the NRC website at http://www.nrc.gov/site-help/e-submittals.html or by calling the NRC Meta-System Help Desk, which is available between 8:00 a.m. and 8:00 p.m., Eastern Time, Monday through Friday, excluding government holidays. The Meta-System Help Desk can be contacted by telephone at 1-866-672-7640 or by e-mail at MSHD.Resource@nrc.gov. Participants who believe that they have a good cause for not submitting documents electronically must file an exemption request, 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, A ttention: Rulema king 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 entertai ned absent a determination by the Commission, the presiding officer, or the Atomic Safety and Licensing Board that the request and/or petition should be granted and/or the contentions should be
admitted, based on a balancing of the factors specified in 10 CFR 2.309(c)(1)(i)-(viii).
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, unless an NRC regulation or other law requires submission of such information. 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 September 18, 2009 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML092640681), which is available for public inspection at the Commission's PDR, located at One White Flin t North, File Public Area O1 F21, 11555 Rockville Pike (first floor), Rockville, Maryland. Publicly available records will be accessible electronically from the 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.resource@nrc.gov.
Attorney for licensee: Mark J. Wetterhahn, Esquire, Winston & Strawn, 1700 K Street, NW., Washington, DC 20006. Dated at Rockville, Maryland, this 6 th day of October 2009.
FOR THE NUCLEAR REGULATORY COMMISSION
/RA/
Richard V. Guzman, Senior Project Manager Plant Licensing Branch 1-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation