ML032540532

Federal Register Notice, Revise the Updated Final Safety Analysis Report to Use the Reactor Building Crane for Heavy Loads Up to a Total of 117 Tons for Removal and Reinstallation Activities for the Reactor Shield Blocks

ML032540532
Person / Time
Site:	Dresden
Issue date:	09/12/2003
From:	Banerjee M NRC/NRR/DLPM/LPD3
To:	Skolds J Exelon Generation Co, Exelon Nuclear
Banerjee M, NRR/ADPT, 415-2277
References
TAC MC0596, TAC MC0597
Download: ML032540532 (9)

Text

September 12, 2003 Mr. John L. Skolds, President Exelon Nuclear Exelon Generation Company, LLC 4300 Winfield Road Warrenville, IL 60555

SUBJECT:

DRESDEN NUCLEAR POWER STATION, UNITS 2 AND 3 - NOTICE OF APPLICATION FOR AMENDMENT TO FACILITY OPERATING LICENSES (TAC NOS. MC0596 AND MC0597)

Dear Mr. Skolds:

Enclosed is a copy of a "Notice of Consideration of Issuance of Amendments to Facility Operating Licenses, Proposed No Significant Hazards Consideration Determination and Opportunity for a Hearing," related to your application dated August 29, 2003 for amendments to Facility Operating License Nos. DPR-19 and DPR-25 for the Dresden Nuclear Power Station, Units 2 and 3. The proposed amendment would revise the Updated Final Safety Analysis Report to use the reactor building crane for heavy loads up to a total of 117 tons for removal and reinstallation activities for the reactor shield blocks prior to and during the Units 2 outage D2R18.

This notice was forwarded to the Office of the Federal Register for publication, and has been published in the Federal Register on September 10, 2003 (68 FR 53401).

Sincerely,

/RA/

Maitri Banerjee, Project Manager, Section 2 Project Directorate III Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket Nos.: 50-237 and 50-249

Enclosure:

Notice cc w/encl: See next page

September 12, 2003 Mr. John L. Skolds, President Exelon Nuclear Exelon Generation Company, LLC 4300 Winfield Road Warrenville, IL 60555

SUBJECT:

DRESDEN NUCLEAR POWER STATION, UNITS 2 AND 3 - NOTICE OF APPLICATION FOR AMENDMENT TO FACILITY OPERATING LICENSES (TAC NOS. MC0596 AND MC0597)

Dear Mr. Skolds:

Enclosed is a copy of a "Notice of Consideration of Issuance of Amendments to Facility Operating Licenses, Proposed No Significant Hazards Consideration Determination and Opportunity for a Hearing," related to your application dated August 29, 2003 for amendments to Facility Operating License Nos. DPR-19 and DPR-25 for the Dresden Nuclear Power Station, Units 2 and 3. The proposed amendment would revise the Updated Final Safety Analysis Report to use the reactor building crane for heavy loads up to a total of 117 tons for removal and reinstallation activities for the reactor shield blocks prior to and during the Units 2 outage D2R18.

This notice was forwarded to the Office of the Federal Register for publication, and has been published in the Federal Register on September 10, 2003 (68 FR 53401).

Sincerely,

/RA/

Maitri Banerjee, Project Manager, Section 2 Project Directorate III Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket Nos.: 50-237 and 50-249

Enclosure:

Notice cc w/encl: See next page DISTRIBUTION:

PUBLIC PDIII-2 R/F PCoates MRing, RIII TMarsh/ELeeds AMendiola OGC WRuland ACRS MBanerjee ADAMS Accession Number: ML032540532 OFFICE PDIII-2/PM PDIII-2/LA PDIII-2/SC NAME MBanerjee THarris for PCoates AMendiola DATE 09/11/03 09/12/03 09/12/03 OFFICIAL RECORD COPY

Dresden Nuclear Power Units 2 and 3 cc:

Site Vice President - Dresden Nuclear Senior Vice President, Nuclear Services Power Station Exelon Generation Company, LLC Exelon Generation Company, LLC 4300 Winfield Road 6500 N. Dresden Road Warrenville, IL 60555 Morris, IL 60450-9765 Vice President - Operations Support Dresden Nuclear Power Station Plant Exelon Generation Company, LLC Manager 4300 Winfield Road Exelon Generation Company, LLC Warrenville, IL 60555 6500 N. Dresden Road Morris, IL 60450-9765 Chief Operating Officer Exelon Generation Company, LLC Regulatory Assurance Manager - Dresden 4300 Winfield Road Exelon Generation Company, LLC Warrenville, IL 60555 6500 N. Dresden Road Morris, IL 60450-9765 Vice President - Licensing and Regulatory Affairs U.S. Nuclear Regulatory Commission Exelon Generation Company, LLC Dresden Resident Inspectors Office 4300 Winfield Road 6500 N. Dresden Road Warrenville, IL 60555 Morris, IL 60450-9766 Director - Licensing Chairman Exelon Generation Company, LLC Grundy County Board 4300 Winfield Road Administration Building Warrenville, IL 60555 1320 Union Street Morris, IL 60450 Senior Counsel, Nuclear Exelon Generation Company, LLC Regional Administrator 4300 Winfield Road U.S. NRC, Region III Warrenville, IL 60555 801 Warrenville Road Lisle, IL 60532-4351 Manager Licensing - Dresden and Quad Cities Illinois Emergency Management Exelon Generation Company, LLC Agency 4300 Winfield Road Division of Disaster Assistance & Warrenville, IL 60555 Preparedness 110 East Adams Street Springfield, IL 62701-1109 Document Control Desk - Licensing Exelon Generation Company, LLC 4300 Winfield Road Warrenville, IL 60555

7590-01-P UNITED STATES NUCLEAR REGULATORY COMMISSION EXELON GENERATION COMPANY, LLC DOCKET NO. 50-237 and 50-249 NOTICE OF CONSIDERATION OF ISSUANCE OF AMENDMENT TO FACILITY OPERATING LICENSES, 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. DPR-19 and DPR-25 issued to Exelon Generation Company, LLC (EGC, the licensee) for operation of the Dresden Nuclear Power Station (DNPS), Units 2 and 3, located in Grundy County, Illinois.

The proposed amendment would allow the licensee to revise the Updated Final Safety Analysis Report to use the reactor building crane for heavy loads up to a total of 117 tons for removal and reinstallation activities for the reactor shield blocks prior to and during the Units 2 outage D2R18.

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 changes do not involve a significant increase in the probability or consequences of an accident previously evaluated.

The current DNPS licensing basis does not consider a load drop accident involving the reactor building crane as a credible event for loads up to and including 110 tons. The proposed changes will allow use of the reactor building crane at DNPS during power operations to lift heavy loads up to 117 tons for removal and installation activities for the reactor shield blocks prior to and during the Unit 2 refueling outage (i.e., D2R18). The reactor building crane has additional margin for a total lifted load of 117 tons with single failure proof features if a Design Basis Earthquake (DBE) is not assumed. The licensee has qualitatively demonstrated that the probability of a DBE occurring during the limited 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> duration of the request is very small. The probability of load drop accidents is not increased since the single-failure proof capacity of the reactor building crane exceeds the weight of the reactor shield blocks, assuming that no DBE occurs. Since no load drop is assumed to occur, the consequences of a load drop accident are not affected.

Therefore, the proposed changes do not involve a significant increase in the probability or consequences of an accident previously evaluated.

2. The proposed changes do not create the possibility of a new or different kind of accident from any accident previously evaluated.

The proposed changes allow use of the DNPS reactor building crane for a limited duration to lift heavy loads up to a total of 117 tons during removal and installation activities for the reactor shield blocks. The reactor building crane has additional margin for a lifted load of 117 tons with single failure-proof features if a DBE is not assumed. The probability of a DBE during the limited duration of the request is very small. Therefore, the single failure-proof features ensure that the proposed changes provide an equivalent level of safety and will not create the possibility of a new or different kind of accident from any accident previously evaluated.

3. The proposed changes do not involve a significant reduction in a margin of safety.

The reactor building crane is rated for lifting loads up to 125 tons. The NRC has approved qualification of the DNPS reactor building crane as single failure-proof for loads of up to 110 tons. The proposed change allows use of the crane for a limited duration to lift loads up to 117 tons. Existing safety margins are enhanced when lifting loads up to 117 tons if a DBE is not assumed, and EGC has demonstrated that the probability of a DBE during the limited duration of the request is very small. Therefore, it is concluded that the proposed changes do 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 the 30-day notice period. However, should circumstances change during the notice period such that failure to act in a timely way would result, for example, in derating or shutdown of the facility, the Commission may issue the license amendment before the expiration of the 30-day notice period, provided that its final determination is that the amendment involves no significant hazards consideration. The final determination will consider all public and State comments received. Should the Commission take this action, it will publish in the FEDERAL REGISTER a notice of issuance and provide for opportunity for a hearing 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, Rules and Directives 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, 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.

By October 10, 2003, 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 Commission's "Rules of Practice for Domestic Licensing Proceedings" in 10 CFR Part 2.

Interested persons should consult a current copy of 10 CFR 2.714, which is available at the Commission's Public Document Room, located at One White Flint North, 11555 Rockville Pike (first floor), Rockville, Maryland, or electronically on the Internet at the NRC Web site http://www.nrc.gov/reading-rm/doc-collections/cfr/. If there are problems in accessing the document, contact the Public Document Room Reference staff at 1-800-397-4209, 301-415-4737, or by e-mail to pdr@nrc.gov. If a request for a hearing or petition for leave to intervene is filed by the above date, the Commission or an Atomic Safety and Licensing Board, designated by the Commission or by the Chairman of the Atomic Safety and Licensing Board Panel, will rule on the request and/or petition; and the Secretary or the designated Atomic Safety and Licensing Board will issue a notice of hearing or an appropriate order.

As required by 10 CFR 2.714, 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 factors: (1) the nature of the petitioner's right under the Act to be made party to the proceeding; (2) the nature and extent of the petitioner's property, financial, or other interest in the proceeding; and (3) the possible effect of any order which may be entered in the proceeding on the petitioner's interest.

The petition should also identify the specific aspect(s) of the subject matter of the proceeding as to which petitioner wishes to intervene. Any person who has filed a petition for leave to intervene or who has been admitted as a party may amend the petition without requesting leave of the Board up to 15 days prior to the first prehearing conference scheduled in the proceeding, but such an amended petition must satisfy the specificity requirements described above.

Not later than 15 days prior to the first prehearing conference scheduled in the proceeding, a petitioner shall file a supplement to the petition to intervene which must include a list of the contentions which are sought to be litigated in the matter. Each contention must consist of a specific statement of the issue of law or fact to be raised or controverted. In addition, the petitioner shall provide a brief explanation of the bases of 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 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.

Petitioner must provide 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 who fails to file such a supplement which satisfies 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, including the opportunity to present evidence and cross-examine witnesses.

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 a hearing or a petition for leave to intervene must be filed with the Secretary of the Commission, U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001, Attention: Rulemakings and Adjudications Staff, or may be delivered to the Commission's Public Document Room (PDR), located at One White Flint North, Public File Area O1 F21, 11555 Rockville Pike (first floor), Rockville, Maryland, by the above date.

Because of the continuing disruptions in delivery of mail to United States Government offices, it is requested that petitions for leave to intervene and requests for hearing be transmitted to the Secretary of the Commission either by means of facsimile transmission to 301-415-1101 or by e-mail to hearingdocket@nrc.gov. A copy of the petition for leave to intervene and request for hearing should also be sent to the Office of the General Counsel, U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001, and because of continuing disruptions in delivery of mail to United States Government offices, it is requested that copies be transmitted either by means of facsimile transmission to 301-415-3725 or by e-mail to OGCMailCenter@nrc.gov. A copy of the request for hearing and petition for leave to intervene should also be sent to Senior

Counsel, Nuclear; Exelon Generation Company, LLC; 4300 Winfield Road; Warrenville, IL 60555; attorney for the licensee.

Nontimely filings of petitions for leave to intervene, amended petitions, supplemental petitions and/or requests for hearing will not be entertained absent a determination by the Commission, the presiding officer or the presiding Atomic Safety and Licensing Board that the petition and/or request should be granted based upon a balancing of the factors specified in 10 CFR 2.714(a)(1)(i)-(v) and 2.714(d).

For further details with respect to this action, see the application for amendment dated August 29, 2003, 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 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 4th day of September, 2003.

FOR THE NUCLEAR REGULATORY COMMISSION

/RA/

Maitri Banerjee, Project Manager, Section 2 Project Directorate III Division of Licensing Project Management Office of Nuclear Reactor Regulation