ML020380684
| ML020380684 | |
| Person / Time | |
|---|---|
| Site: | Oyster Creek |
| Issue date: | 02/14/2002 |
| From: | Tam P NRC/NRR/DLPM/LPD1 |
| To: | Kingsley O Exelon Generation Co |
| Tam P | |
| References | |
| TAC MB1747 | |
| Download: ML020380684 (6) | |
Text
February 14, 2002 Mr. Oliver D. Kingsley, President and Chief Nuclear Officer Exelon Nuclear Exelon Generation Company, LLC 4300 Winfield Road Warrenville, IL 60555
SUBJECT:
OYSTER CREEK NUCLEAR GENERATING STATION - CORRECTION OF SAFETY EVALUATION ASSOCIATED WITH AMENDMENT NO. 223 (TAC NO. MB1747)
Dear Mr. Kingsley:
On January 23, 2002, the Nuclear Regulatory Commission (NRC) staff issued Amendment No. 223 to Facility Operating License No. DPR-16 for Oyster Creek Nuclear Generating Station.
The amendment revised requirements associated with Section 5.3.1, Fuel Storage.
Section 2.2 of the safety evaluation (SE) associated with Amendment No. 223 contains an inadvertent error. Specifically, the words inspection or should not be present in the last sentence on page 3 of the SE. Accordingly, the NRC staff is reissuing page 3 (enclosed) of the SE to correct this error in Section 2.2. We apologize for any inconvenience this inadvertent error may have caused you.
Sincerely,
/RA/
Peter S. Tam, Senior Project Manager, Section 1 Project Directorate I Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket No. 50-219
Enclosure:
Revised page 3 of SE cc w/encl: See next page
February 14, 2002 Mr. Oliver D. Kingsley, President and Chief Nuclear Officer Exelon Nuclear Exelon Generation Company, LLC 4300 Winfield Road Warrenville, IL 60555
SUBJECT:
OYSTER CREEK NUCLEAR GENERATING STATION - CORRECTION OF SAFETY EVALUATION ASSOCIATED WITH AMENDMENT NO. 223 (TAC NO. MB1747)
Dear Mr. Kingsley:
On January 23, 2002, the Nuclear Regulatory Commission (NRC) staff issued Amendment No. 223 to Facility Operating License No. DPR-16 for Oyster Creek Nuclear Generating Station.
The amendment revised requirements associated with Section 5.3.1, Fuel Storage.
Section 2.2 of the safety evaluation (SE) associated with Amendment No. 223 contains an inadvertent error. Specifically, the words inspection or should not be present in the last sentence on page 3 of the SE. Accordingly, the NRC staff is reissuing page 3 (enclosed) of the SE to correct this error in Section 2.2. We apologize for any inconvenience this inadvertent error may have caused you.
Sincerely,
/RA/
Peter S. Tam, Senior Project Manager, Section 1 Project Directorate I Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket No. 50-219
Enclosure:
Revised page 3 of SE cc w/encl: See next page DISTRIBUTION:
PUBLIC SLittle JMunday PD1-1 R/F GHill (2)
GHatchett OGC EAdensam BThomas ACRS JRogge, RI Accession Number: ML020380684 OFFICE PDI-1/PM PDI-1/LA PDI-1/ASC SPLB/SC NAME PTam SLittle JMunday BThomas DATE 2/12/02 2/11/02 2/14/02 2/13/02 OFFICIAL RECORD COPY
Oyster Creek Nuclear Generating Station cc:
John Skolds Chief Operating Officer Exelon Generation Company, LLC 4300 Winfield Road Warrenville, IL 60555 William Bohkle Senior Vice President Nuclear Services Exelon Generation Company, LLC 4300 Winfield Road Warrenville, IL 60555 John B. Cotton Senior Vice President - Operations Support Exelon Generation Company, LLC 4300 Winfield Road Warrenville, IL 60555 Joseph J. Hagan Senior Vice President -
Mid Atlantic Regional Operating Group Exelon Generation Company, LLC 200 Exelon Way, Suite 305 Kennett Square, PA 19348 Kevin P. Gallen, Esquire Morgan, Lewis, & Bockius LLP 1800 M Street, NW Washington, DC 20036-5869 Kent Tosch, Chief New Jersey Department of Environmental Protection Bureau of Nuclear Engineering CN 415 Trenton, NJ 08625 Mr. Jeffrey A. Benjamin Vice President -
Licensing and Regulatory Affairs Exelon Generation Company, LLC 4300 Winfield Road Warrenville, IL 60555 Mr. Ronald J. DeGregorio Vice President Oyster Creek Nuclear Generating Station AmerGen Energy Company, LLC PO Box 388 Forked River, NJ 08731 H. J. Miller Regional Administrator, Region I U.S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406-1415 Mayor of Lacey Township 818 West Lacey Road Forked River, NJ 08731 Senior Resident Inspector U.S. Nuclear Regulatory Commission P.O. Box 445 Forked River, NJ 08731 Michael P. Gallagher Director - Licensing Exelon Generation Company, LLC Correspondence Control Desk P.O. Box 160 Kennett Square, PA 19348 Ernest J. Harkness Plant Manager Oyster Creek Nuclear Generating Station AmerGen Energy Company, LLC P.O. Box 388 Forked River, NJ 08731 Manager Regulatory Assurance Oyster Creek Nuclear Generating Station AmerGen Energy Company, LLC P.O. Box 388 Forked River, NJ 08731
Oyster Creek Nuclear Generating Station cc:
Edward J. Cullen, Jr., Esquire Vice President, General Counsel and Secretary Exelon Generation Company, LLC 300 Exelon Way Kennett Square, PA 19348 J. Rogge, Region I U.S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406-1415 pool (SFSP). It also removes requirements relating to the design function of the CDPS for cask moves into the SFSP. To effect this, the reactor building crane has been upgraded to single-failure-proof as defined by NUREG-0612.
These sections of the TSs provide restrictions applicable to the safe handling of heavy loads at Oyster Creek using the non-single-failure-proof 100-ton main and 10-ton auxiliary (100/10) hoists and trolley to the reactor building crane. By upgrading the handling system to include single-failure-proof features consistent with NUREG-0612, Appendix C, and NUREG-0554, restrictions applicable to the previous reactor building crane will no longer be needed.
The new 105/10 ton single-failure-proof heavy load handling system, which is fully compliant with NUREG-0554 (see Section 3.2 of this safety evaluation (SE)) reduces the probability of a handling accident. Moreover, the licensee, in its October 12, 2001, response to the NRC staffs request for additional information (RAI), stated that its heavy load handling program would continue to meet NUREG-0612 Phase I guidelines as approved by the NRC staff in an SE dated June 21, 1983. The combination of the crane upgrade to single-failure-proof and meeting NUREG-0612 Phase I guidelines satisfies the defense-in-depth philosophy of NUREG-0612 and assures a consistent level of protection in handling heavy loads at Oyster Creek.
In addition, to satisfy the defense-in-depth methodology described in NUREG-0612, the licensee made the following commitments in its letters:
In accordance with NUREG-0612, Section 5.1.1(1), Safe Load Paths, procedures governing heavy load paths will be revised to require authorization from the Plant Manager and Engineering Director, or their designee, to use load paths over the reactor cavity with the shield blocks removed, or over the spent fuel storage pool that have not been previously analyzed; Plant procedures will be revised to prevent heavy load travel over HOT irradiated fuel; Plant procedures will be revised to minimize the length of travel of heavy loads over spent fuel; and All new lifting devices and interfacing lift points, associated with heavy loads handled by the reactor building crane, will meet the guidelines in NUREG-0612, Section 5.1.6 (5.1.6(1) and 5.1.6(3)).
The NRC staff finds that reasonable controls for the implementation and for subsequent evaluation of proposed changes pertaining to the above regulatory commitments are provided by the licensee's administrative processes, including its commitment management program.
The NRC staff has determined that the commitments do not warrant the creation of regulatory requirements which would require prior NRC approval of subsequent changes. The NRC staff has agreed that NEI 99-04, Revision 0, "Guidelines for Managing NRC Commitment Changes,"
provides reasonable guidance for the control of regulatory commitments made to the NRC staff.
(See Regulatory Issue Summary 2000-17, Managing Regulatory Commitments Made by Power Reactor Licensees to the NRC Staff, dated September 21, 2000.) The commitments should be controlled in accordance with the industry guidance or comparable criteria employed by a specific licensee. The NRC staff may choose to verify the implementation and maintenance of these commitments in a future audit. l Corrected by letter of 2/14/02