ML13114A928
| ML13114A928 | |
| Person / Time | |
|---|---|
| Site: | Oconee  |
| Issue date: | 07/01/2013 |
| From: | Zimmerman R NRC/OE |
| To: | Batson S Duke Energy Carolinas |
| Boska J NRR/DORL/LPL2-1 301-415-2901 | |
| Shared Package | |
| ML13114A919 | List: |
| References | |
| EA-13-010 | |
| Download: ML13114A928 (19) | |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555..0001 EA-13-010 Mr. Scott Batson Site Vice President Oconee Nuclear Station Duke Energy Carolinas, LLC 7800 Rochester Highway Seneca, SC 29672-0752 July 1, 2013
SUBJECT:
NOTICE OF VIOLATION AND CONFIRMATORY ORDER RELATED TO A FIRE PROTECTION PROGRAM LICENSE CONDITION (OCONEE NUCLEAR STATION, UNITS 1, 2, AND 3)
Dear Mr. Batson:
The purpose of this letter is to provide you with the results of the apparent violation of Amendment Nos. 371, 373, and 372 to Renewed Facility Operating License DPR-38, DPR-47, and DPR-55 provided to you by the Nuclear Regulatory Commission (NRC) staff in a letter dated January 31,2013 (ML13017A456').
On December 29, 2010, the NRC issued Amendment Nos. 371, 373, and 372 to Renewed Facility Operating Licenses DPR-38, DPR-47, and DPR-55, for the Oconee Nuclear Station, Units 1, 2, and 3, respectively (ML103630612). The amendments consisted of changes to the licenses and Technical Specifications (TSs) to allow you to maintain a fire protection program (FPP) in accordance with 10 CFR 50.48(c). Condition 3.0, Fire Protection, Transition License Condition 1 required you to complete the items described in Section 2.9, Table 2.9*1, "Implementation Items," in the NRC safety evaluation dated December 29, 2010, prior to January 1, 2013. Table 2.9-1, item 23 required completion of the analysis of non*power operation (NPO) fire impacts for fire zones following installation of the NFPA-805 committed modifications, including the Protected Service Water (PSW) modifications. Item 32 required incorporation of the PSW modification into the FPP site documents after the modification was implemented. Item 43 required confirmation that the risk decrease from the as-built PSW system continued to bound the cumulative variances from deterministic requirements (VFDR) transition risk once the PSW modifications were installed.
On July 31,2012, Duke Energy Carolinas, LLC (Duke or the licensee) submitted a license amendment request (LAR) to extend full PSW implementation by two years, but stated that the power supply from the PSW building to the Standby Shutdown Facility would be completed by December 31, 2012 (ML12216A317). In a clarification call on November 27, 2012 (ML 1301 OA439), Duke discussed draft milestones which would extend some items, such as installation of the PSW pumps, by at least three years. As of January 1, 2013, and continuing through the date of this letter, the PSW modification has not been completed. As a result, Duke 1 Designation in parentheses refers to an Agencywide Documents Access and Management system (ADAMS} accession number. Documents referenced in this letter are publicly available using the accession number in ADAMS.
is in violation of License Condition 3.D. After considering the information provided by Duke, the NRC denied the July 31, 2012, LAR application in a letter dated January 15, 2013 (ML12345A204).
A Predecisional Enforcement Conference was held on March 5, 2013, (ML13072A426) at NRC headquarters in Rockville, Maryland with members of your staff to discuss the apparent violation, its significance, root causes, and your corrective actions. Based on the information that you provided during this conference and the information in the staff's letter of January 31, 2013, the NRC staff has determined that a violation of NRC requirements occurred.
The violation is cited in the enclosed Notice of Violation (Notice) and the circumstances surrounding it are described in the January 31, 20131etter.
In assessing the significance of the violation, the NRC concluded that Duke's failure to comply with the terms of the Oconee Nuclear Station Licenses impacts the NRC's ability to perform its regulatory oversight function, as the NRC would not have issued the license amendments to implement a revised fire protection program at Oconee without the expectation that Duke would comply with the conditions of the Oconee Nuclear Station Licenses regarding that fire protection program. For that reason, the NRC is handling this issue under its traditional enforcement process. Your failure to implement the PSW system modification is of significant regulatory concern. In addition, the staff concluded that the factors and difficulties encountered in meeting the January 1, 2013, implementation date were reasonably within Duke's control. Therefore, in accordance with the Enforcement Policy, the NRC has decided that a Severity Levell II is the appropriate level to reflect the significance of this particular violation.
The NRC considered whether credit was warranted for Corrective Action in accordance with the civil penalty assessment process in Section 2.3.4 of the Enforcement Policy. Although the final completion date for the PSW plant modifications is in 2016, the staff concluded that the corrective actions you described at the enforcement conference were reasonably comprehensive and the completion of intermediate milestones will provide significant risk reduction prior to 2016. The NRC staff also took into consideration the additional compensatory measures implemented at the Oconee Nuclear Station, beyond those already in place as part of the NFPA-805 transition, including implementing a method to use a pre-staged diesel-driven pump to add water to the steam generators in the event a fire renders the installed feedwater systems inoperable; providing guidance to use a separate pre-staged diesel-driven pump to supply the fire system header if the normal supplies are affected by a fire; and maintaining a continuous ten person staff for the plant fire brigade. As a result, the NRC staff gave credit for corrective action.
Due to your particularly poor performance associated with the planning and execution of this modification, the NRC staff also considered the use of enforcement discretion to impose a civil penalty in accordance with Section 3.6 of the NRC's Enforcement Policy. However, the staff concluded that the issuance of a Confirmatory Order containing specific milestones and dates for achieving compliance is a more appropriate means of enforcement to assure timely completion of the PSW project. There are six milestones, with final completion due by
November 15, 2016. Each of the intermediate milestones provide risk reduction, and the first milestone is due by October 1, 2013. Additional staff considerations regarding the appropriate enforcement posture included recognition of the unusually large project scope and complexity of the PSW modification; the fact that approximately 80 percent of the modification has structurally been completed; and recognition of the unforeseen engineering challenges that arose during the project implementation.
The NRC staff is hereby issuing a Confirmatory Order (CO) which specifies the milestones which must be met as you work to complete the terms of the license condition. As evidenced by the signed uconsent and Hearing Waiver Form (copy enclosed) dated June 18, 2013, you agreed to the issuance of the enclosed CO. Pursuant to Section 223 of the Atomic Entergy Act of 1954, as amended, any person who willfully violates, or attempts to violate, any provision of the enclosed CO shall be subject to criminal prosecution as set forth in that section. Failure to comply with the terms of the CO will result in additional enforcement action up to, and including, daily civil penalties.
You are not required to respond to this letter. However, if you choose to provide a response, please provide it to the U.S. Nuclear Regulatory Commission, ATTN: Document Control Desk, Washington, DC 20555-0001, with a copy to Director, Office of Enforcement, U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001, within 30 days.
In accordance with 10 CFR 2.390 of the NRC's "Rules of practice," a copy of this letter and its enclosures will also be made available electronically for public inspection in the NRC Public Document Room or from the NRC's document system (ADAMS). ADAMS is accessible from the NRC Website at http://www.nrc.gov/readinq-rm/adams.html. The NRC will also include this letter, and the attached CO on its Website at www.nrc.gov; the letter can be found on this website by selecting the "Public Meetings and lnvolvemene link and then the "Enforcement" link.
Your response, if you choose to provide one, will also be made available electronically for public inspection in the NRC Public Document Room or from the NRC's document system. To the extent possible, your response should not include any personal privacy, proprietary, or safeguards information so that it can be made available to the public without redaction. The NRC also includes significant enforcement actions on its Website at http:l/www.nrc.gov/reading-rm/doc-collections/enforcement/actions/.
If you have any questions concerning this matter, please contact John Boska of the Office of Nuclear Reactor Regulation at 301-415-2901.
Docket Nos. 50-269, 50-270, and 50-287 License Nos. DPR-38, DPR-47, DPR-55
Enclosure:
- 2. Consent and Hearing Waiver Form
- 3. Confirmatory Order Sincerely, T ?
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i -lr;Zimme an, D~rector
~df Enforcement
NOTICE OF VIOLATION Duke Energy Carolinas, LLC Oconee Nuclear Station, Units 1, 2, and 3 Docket Nos. 05000269,05000270,05000287 License Nos. DPR-38, DPR-47, DPR-55 EA-13-010 On January 1, 2013, and continuing through the date of this Notice of Violation (Notice), a violation of Nuclear Regulatory Commission {NRC) requirements occurred. In accordance with the NRC Enforcement Policy, the violation is listed below:
Renewed Facility Operating Licenses DPR-38, DPR-47, and DPR-55, as modified by License Amendment Nos. 371,373, and 372, License Condition 3.0, Fire Protection, Transition License Condition 1 required completion of the items described in Section 2.9, Table 2.9-1, "Implementation Items," in the NRC safety evaluation dated December 29, 2010, prior to January 1, 2013. Table 2.9-1, item 23 required completion of the analysis of non-power operation (NPO) fire impacts for fire zones following installation of the NFPA-805 committed modifications, including the Protected Service Water (PSW) modifications. Item 32 required incorporation of the PSW modification into the fire protection program (FPP) site documents after the modification was implemented. Item 43 required confirmation that the risk decrease from the as-built PSW system continued to bound the cumulative variances from deterministic requirements (VFDR) transition risk once the PSW modifications were installed.
Contrary to the above, from January 1, 2013, and continuing through the date of this Notice, items 23, 32, and 43 were not completed as required by Transition License Condition 1 for Units 1, 2, and 3. Specifically, the PSW modification was not completed by the January 1, 2013 date, which prevented the analysis of NPO fire impacts, the incorporation of the PSW modification into the FPP site documents, and confirmation that the risk decrease from the as-built PSW system continued to bound the cumulative VFDR transition risk.
This is a Severity Levell II violation.
The NRC has concluded that information regarding: (1) the reason for the violation; (2) the actions planned or already taken to correct the violation and prevent recurrence; and, (3) the date when full compliance was achieved, is already adequately addressed on the docket, and in the Confirmatory Order enclosed with the letter transmitting this Notice. However, you are required to submit a written statement or explanation pursuant to 10 CFR 2.201, if the description therein does not accurately reflect your corrective actions or your position. In that case, or if you choose to respond, clearly mark your response as a "Reply to a Notice of Violation," include the EA number, and send it to the U.S. Nuclear Regulatory Commission, ATTN: Document Control Desk, Washington, DC 20555-0001 with a copy to Director, Office of Enforcement, U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001, within 30 days of the date of the letter transmitting this Notice.
If you choose to respond, your response will be made available electronically for public inspection in the NRC Public Document Room or from the NRC's document system (ADAMS),
accessible from the NRC Website at http://www.nrc.gov/reading-rm/adams.html. Therefore, to the extent possible, the response should not include any personal privacy, proprietary, or safeguards information so that it can be made available to the Public without redaction.
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Dated this i-day au ()~2013.
CONSENT AND HEARING WAIVER FORM Duke Energy Carolinas, LLC (Duke Energy), hereby agrees to comply with the terms and conditions of the attached Confirmatory Order and to those commitments described therein.
Duke understands that the Confirmatory Order will be effective upon its issuance. Duke Energy recognizes that by signing below, it consents to the issuance of the Confirmatory Order effective upon its issuance, and by doing so, pursuant to 10 CFR 2.202(a)(3} and (d), waives the right to request a hearing on all or any part of the Confirmatory Order.
~y:J6:£ Scott L. Batson Site Vice President Oconee Nuclear Station Duke Energy Carolinas, LLC 0~- /$- Z.0/.:5 Date
In the Matter of UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION
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[7590-01-P]
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Docket Nos. 50-269, 50-270, and 50-287 DUKE ENERGY CAROLINAS, LLC (Oconee Nuclear Station, Units 1, 2, and 3)
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License Nos. DPR-38, DPR-47, and DPR-55
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EA-13-010 CONFIRMATORY ORDER MODIFYING LICENSE Duke Energy Carolinas, LLC (Duke, Licensee) is the holder of Renewed Facility Operating License Nos. DPR-38, DPR-47, and DPR-55 issued by the Nuclear Regulatory Commission (NRC or Commission) pursuant to Title 10 of the Code of Federal Regulations (1 0 CFR), Part 50, "Domestic Licensing of Production and Utilization Facilities," on May 23, 2000.
The licenses authorize the operation of Oconee Nuclear Station, Units 1, 2, and 3, in accordance with the conditions specified therein. The facilities are located on the Licensee's site in Seneca, South Carolina.
II On December 29, 2010, the NRC issued Amendment Nos. 371, 373, and 372 to Renewed Facility Operating Licenses DPR-38, DPR-47, and DPR-55, for the Oconee Nuclear Station, Units 1, 2, and 3, respectively (Agencywide Documents Access and Management System (ADAMS) Accession No. ML103630612). The amendments consisted of changes to the licenses and Technical Specifications to allow Duke to maintain a fire protection program (FPP) in accordance with 10 CFR 50.48(c). Condition 3.0, Fire Protection, Transition License Condition 1 required Duke to complete the items described in Section 2.9, Table 2.9-1, "Implementation Items," in the NRC safety evaluation dated December 29, 2010, prior to January 1, 2013. Table 2.9-1, item 23 required completion of the analysis of non-power operation (NPO) fire impacts for fire zones following installation of the NFPA-805 committed modif(cations, including the Protected Service Water (PSW) modifications. Item 32 required incorporation of the PSW modification into the FPP site documents after the modification was implemented. Item 43 required confirmation that the risk decrease from the as-built PSW system continued to bound the cumulative variances from deterministic requirements (VFDR) transition risk once the PSW modifications were installed. Transition License Condition 2 required Duke to complete the items described in Section 2.8, Table 2.8.1-1, "Committed Plant Modifications," in the NRC safety evaluation dated December 29,2010. Item 1 of the table included implementation of the PSW modifications.
On July 31, 2012, Duke submitted a license amendment request (LAR) to extend full PSW implementation by two years, but stated that the modification to supply power from the PSW building to the Standby Shutdown Facility (SSF) would be operational by December 31, 2012. In a clarification call on November 27, 2012, Duke discussed draft milestones which would extend some items, such as installation of the PSW pumps, by at least three years. As of January 1, 2013, the full PSW modification had not been completed, which put Duke in violation of License Condition 3. D in all three licenses. After considering the information provided by Duke, the NRC staff denied the July 31, 2012, LAR application in a letter dated January 15, 2013. Subsequently, the NRC staff described an apparent violation to Duke by letter dated January 31, 2013. This apparent violation has been considered for escalated enforcement action in accordance with the NRC Enforcement Policy.
Ill On March 5, 2013, a predecisional enforcement conference (ADAMS Accession No. ML13072A426) was conducted at NRC headquarters in Rockville, Maryland with members of Duke's staff to discuss the apparent violation, its significance, root causes, and Duke's corrective actions. By letter dated March 11, 2013 (ADAMS Accession No. ML13079A321), and in a public meeting on April10, 2013, Duke provided additional information on milestones Duke plans to meet while completing the installation of the PSW system. The NRC staff is issuing this Confirmatory Order to provide regulatory oversight of these milestones. The requirements needed to effectuate the foregoing are set forth in Section IV below. On June 18, 2013, the Licensee consented to the license modifications set forth in Section IV below. The Licensee further agreed that it has waived its right to a hearing on this order, and, therefore, that the terms of the Order are effective upon issuance.
I find that the license modifications set forth in Section IV are acceptable and necessary because they reduce the risk of significant damage from fire, as determined by the NRC staff in the safety evaluation for Amendment Nos. 371, 373, and 372 to Renewed Facility Operating Licenses OPR-38, OPR-47, and OPR-55. Thus I find this order acceptable in order to ensure public health and safety. Based on the above and the Licensee's consent, this Order is effective upon issuance.
IV In view of the foregoing and pursuant to Sections 1 04b, 161 b, 161 i, 161 o, 182, and 186 of the Atomic Energy Act of 1954, as amended, and the Commission's regulations in 10 CFR 2.202 and 10 CFR Part 50, IT IS HEREBY ORDERED, THAT LICENSE NOS. DPR-38, DPR-47, AND DPR-55 ARE MODIFIED AS FOLLOWS:
- 1.
The licensee shall provide the capability to supply off-site electrical power to the PSW building switchgear and from there to the SSF switchgear, with sufficient capacity to operate all credited SSF equipment in the event of a failure of the SSF diesel generator during a fire for which the SSF is credited. This modification along with approved plant procedures and the completion of operator training necessary to accomplish this lineup, and a combination of testing and engineering evaluation in accordance with station procedures which verifies this capability, will be completed and operational no later than October 1, 2013.
- 2.
The licensee shall provide the capability to supply electrical power from each of the Keowee Hydro Units to the PSW building switchgear and from there to the SSF switchgear, with sufficient capacity to operate all credited SSF equipment in the event of a failure of the SSF diesel generator during a fire for which the SSF is credited. This modification along with approved plant procedures and the completion of operator training necessary to accomplish this lineup, and a combination of testing and engineering evaluation in accordance with station procedures which verifies this capability, will be completed and operational no later than July 18, 2014.
- 3.
The licensee shall provide the capability to supply electrical power from the PSW building switchgear to simultaneously operate at least one high-pressure injection pump per unit, and to operate the associated valves needed to align water flow to the reactor coolant pump seals and to inject water into the reactor coolant system, as an alternate path within the emergency operating procedures. This modification along with approved plant procedures and the completion of operator training necessary to accomplish this lineup, and a combination of testing and engineering evaluation in accordance with station procedures which verifies this capability, will be completed and operational no later than October 1, 2014.
- 4.
The licensee shall have the PSW pump installed and provide the capability to supply electrical power from the PSW building switchgear to operate the PSW pump and the associated valves to provide water to the steam generators of all three units sufficient to remove decay heat following simultaneous reactor trips from 100% power, with the steam generators at the pressure corresponding to the lowest safety valve setting, as an alternate path within the emergency operating procedures. This modification along with approved plant procedures and the completion of operator training necessary to accomplish this lineup, and a combination of testing and engineering evaluation in accordance with station procedures which verifies this capability, will be completed and operational no later than June 3, 2015.
- 5.
The licensee shall provide the capability to supply electrical power from the PSW building switchgear to those DC battery chargers that provide power to controls and instrumentation that allow PSW system control and monitoring from the control room for an extended period of time as prescribed by the NFPA-805 fire protection program approved for Oconee. The licensee shall provide electrical power from the PSW building switchgear to at least 400 kW (nameplate rating) of pressurizer heaters for each unit, and provide the ability to select the PSW power source to those pressurizer heaters from the Auxiliary Building. The licensee shall provide Auxiliary Building and Reactor Building environments suitable for equipment operation. The licensee shall provide the ability to control and monitor the high-pressure injection equipment, the PSW equipment, and the steam generator heat removal equipment from the associated Oconee control rooms.
This modification along with approved plant procedures and the completion of operator training necessary to accomplish this lineup, and a combination of testing and engineering evaluation in accordance with station procedures which verifies this capability, will be completed and operational no later than February 4, 2016.
- 6.
The licensee shall complete all items in Table 2.9-1, "Implementation Items," of the December 29, 2010, Oconee NFPA 805 safety evaluation report no later than November 15, 2016.
- 7.
The licensee shall provide a letter to the NRC under oath or affirmation, and in accordance with 10 CFR 50.4, "Written communications," reporting the completion of each milestone described above, and a final letter reporting when it has achieved full compliance with the requirements contained in this Order, within 30 days of completion.
The Director, Office of Enforcement, may, in writing, relax or rescind any of the above conditions upon demonstration by the Licensee of good cause.
v In accordance with 1 0 CFR 2.202, "Orders," the licensee, under oath or affirmation, may submit a written answer to this Order within 30 days from the date of this Order. Additionally, any person adversely affected by this Order, other than Duke, may submit a written answer and/or request a hearing on this Order within 30 days from the date of this Order. Where good cause is shown, consideration will be given to extending the time to answer or request a hearing. A request for extension of time must be directed to the U.S. Nuclear Regulatory Commission, AITN: Document Control Desk, Washington, DC 20555-0001, with a copy to Director, Office of Enforcement, U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001, and include a statement of good cause for the extension.
If a hearing is requested by a person whose interest is adversely affected, the Commission will issue an Order designating the time and place of any hearings. If a hearing is held, the issue to be considered at such hearing shall be whether this Order should be sustained.
All documents filed in the NRC adjudicatory proceedings, including a request for a 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 (72 FR 49139, August 28, 2007). 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 optical 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 associated withE-Filing, at least 10 days prior to the filing deadline the participant should contact the Office of the Secretary by e-mail at hearing.docket@nrc.gov, or by telephone at (301) 415-1677, to request (1) a digital identification (10) 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 (2) advise the Secretary that the participant will be submitting a request or petition for hearing (even in instances in which the participant, or its counsel or representative, already holds an NRC-issued digital certificate). Based on this information, the Secretary will establish an electronic docket for the hearing in this proceeding if the Secretary has not already established an electronic docket.
Information about applying for a digitaiiD certificate is available on the NRC's public Website at http://www.nrc.gov/site-help/e-submittals/apply-certificates.html. System requirements for accessing the E-Submittal server are detailed in the NRC's "Guidance for Electronic Submission," which is available on the NRC's public Website at http://www.nrc.gov/site-help/e-submittals.html. Participants may attempt to use other software not listed on the Website, but should note that the NRC's E-Filing system does not support unlisted software, and the NRC Meta System Help Desk will not be able to offer assistance in using unlisted software.
If a participant is electronically submitting a document to the NRC in accordance with the E-Filing rule, the participant must file the document using the NRC's online, Web-based submission form. In order to serve documents through the Electronic Information Exchange System, users will be required to install a Web browser plug-in from the NRC's Website.
Further information on the Web-based submission form, including the installation of the Web browser plug-in, is available on the NRC's public Website at http:llwww.nrc.qovlsite-he/ple-submittals. html.
Once a participant has obtained a digitaiiD certificate and a docket has been created, the participant can then submit a request for a 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:llwww.nrc.qovlsite-helple-submittals.html. A filing is considered complete at the time the documents are submitted through the NRC's E-filing system. To be timely, an electronic filing must be submitted to theE-Filing system no later than 11:59 p.m. Eastern Time on the due date. Upon receipt of a transmission, theE-Filing system time-stamps the document and sends the submitter an e-mail notice confirming receipt of the document. The E-Filing 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 document on those participants separately. Therefore, applicants and other participants (or their counsel or representative) must apply for and receive a digitaiiD certificate before a hearing requesUpetition to intervene is filed so that they may obtain access to the document via the E-Filing system.
A person filing electronically using the NRC's adjudicatory E-Filing system may seek assistance by contacting the NRC Meta System Help Desk through the ucontact Us" link located on the NRC Web site at http:l!www.nrc.gov/site-hefple-submittals.html, by e-mail to MSHD.Resource@nrc.gov, or by a toll-free call to 1-866-672-7640. The NRC Meta System Help Desk is available between 9 a.m. and 7 p.m., Eastern Time, Monday through Friday, excluding government holidays.
Participants who believe that they have good cause for not submitting documents electronically must file an extension 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, MD 20852, Attention: Rulemaking and Adjudications Staff. Participants filing a document in this manner are responsible for serving the document on all other participants.
Copies shall be sent to the Director, Office of Enforcement and the Assistant General Counsel for Materials Litigation and Enforcement at the same address, the Regional Administrator, NRC Region II, Marquis One Tower, Suite 1200, 245 Peachtree Center Avenue, NE, Atlanta, GA 30303, and to the Licensee, Duke Energy Carolinas, LLC, Oconee Nuclear Station, 7800 Rochester Highway, Seneca, SC 29672. 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. A presiding officer, having granted an exemption request from using E-Filing, may require a participant or party useE-Filing if the presiding officer subsequently determines that the reason for granting the exemption from use of E-Filing no longer exists.
Documents submitted in adjudicatory proceedings will appear in NRC's electronic hearing docket, which is available to the public at http://ehd1.nrc.gov/ehd, unless excluded pursuant to an Order of the Commission, an Atomic Safety and Licensing Board, or the 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.
If a person other than the licensee requests a hearing, that person shall set forth with particularity the manner in which his or her interest is adversely affected by this Order and shall address the criteria set forth in 10 CFR 2.309(d) and (f).
In the absence of any request for hearing or written approval of an extension of time in which to request a hearing, the provisions specified in Section IV above shall be final 30 days from the date of this Order without further order or proceedings. If an extension of time for requesting a hearing has been approved, the provisions specified in Section IV shall be final when the extension expires if a hearing request has not been received.
. S) otfh Dated this / -
day (;
/
FOR THE NUCLEAR REGULATORY COMMISSION man, Director Office of Enforcement 2013
PKG ML13114A919; Letter ML13114A928; Order ML13114A941
- Via email OFFICE NRR/DORUPM NRRJDORULA NRR/DORUBC NRR/DRAIBC NRRJDRAID NAME JBoska SFigueroa RPascarelli AKiein JGiitter Non-concur DATE 4/26/13 4/25/13 4/26/13 5/6/13 5/7/13 OFFICE RII/D*
NRR/DORUD OGC OE NAME RCroteau MEvans Mlemoncelli RZimmerman DATE 5/2/13 5/16/13 6/4/13 7/1/2013