ML061140442

License Amendment 350 Replacement of Reactor Building Emergency Sump Suction Inlet Trash Racks and Screens with Strainers

ML061140442
Person / Time
Site:	Oconee
Issue date:	05/04/2006
From:	Olshan L Plant Licensing Branch III-2
To:	Brandi Hamilton Duke Power Co
Olshan L N, NRR/DLPM, 415-1419
Shared Package
ML061150507	List: ML061140442 ML061160014
References
TAC MC8127
Download: ML061140442 (9)

Text

May 4, 2006 Mr. Bruce H. Hamilton Vice President, Oconee Site Duke Power Company LLC 7800 Rochester Highway Seneca, SC 29672

SUBJECT:

OCONEE NUCLEAR STATION, UNIT 3, ISSUANCE OF AMENDMENTS RE:

REPLACEMENT OF REACTOR BUILDING EMERGENCY SUMP SUCTION INLET TRASH RACKS AND SCREENS WITH STRAINERS (TAC NO. MC8127)

Dear Mr. Hamilton:

The Nuclear Regulatory Commission has issued the enclosed Amendment No. 350 to Renewed Facility Operating License DPR-55 for the Oconee Nuclear Station, Unit 3. The amendment consists of changes to the Technical Specifications (TS) in response to your application dated August 18, 2005, as supplemented by letters dated September 15, 2005, and January 5 and April 6, 2006.

The amendment revises TS 3.5.2.6 and 3.5.3.6 to accommodate the replacement of the reactor building emergency sump suction inlet trash racks and screens with strainers. Similar amendments were issued for Units 1 and 2 on November 1, 2005; however, the amendment for Unit 3 was not issued at that time since the licensee had not completed its evaluation of the impact of pipe whip, jet impingement and internally-generated missiles for Unit 3.

A copy of the related Safety Evaluation is also enclosed. A Notice of Issuance will be included in the Commission's biweekly Federal Register notice.

Sincerely,

/RA/

Leonard N. Olshan, Sr. Project Manager Plant Licensing Branch II-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-287

Enclosures:

1. Amendment No. 350 to DPR-55

2. Safety Evaluation cc w/encls: See next page

May 4, 2006 Mr. Bruce H. Hamilton Vice President, Oconee Site Duke Power Company LLC 7800 Rochester Highway Seneca, SC 29672

SUBJECT:

OCONEE NUCLEAR STATION, UNIT 3, ISSUANCE OF AMENDMENTS RE:

REPLACEMENT OF REACTOR BUILDING EMERGENCY SUMP SUCTION INLET TRASH RACKS AND SCREENS WITH STRAINERS (TAC NO. MC8127)

Dear Mr. Hamilton:

The Nuclear Regulatory Commission has issued the enclosed Amendment No. to Renewed Facility Operating License DPR-55 for the Oconee Nuclear Station, Unit 3. The amendment consists of changes to the Technical Specifications (TS) in response to your application dated August 18, 2005, as supplemented by letters dated September 15, 2005, and January 5 and April 6, 2006.

The amendment revises TS 3.5.2.6 and 3.5.3.6 to accommodate the replacement of the reactor building emergency sump suction inlet trash racks and screens with strainers. Similar amendments were issued for Units 1 and 2 on November 1, 2005; however, the amendment for Unit 3 was not issued at that time since the licensee had not completed its evaluation of the impact of pipe whip, jet impingement and internally-generated missiles for Unit 3.

A copy of the related Safety Evaluation is also enclosed. A Notice of Issuance will be included in the Commission's biweekly Federal Register notice.

Sincerely,

/RA/

Leonard N. Olshan, Sr. Project Manager Plant Licensing Branch II-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-287

Enclosures:

1. Amendment No. 350 to DPR-55

2. Safety Evaluation cc w/encls: See next page DISTRIBUTION: Public RidsAcrsAcnwMailCenter LPL2-1 R/F GHill(6 hard copies)

RidsNrrDorlLplc(EMarinos) RidsNrrDirsItsb(TBoyce)

RidsNrrPMLOlshan(hard copy) Princ Contr of SE/Tech Br RidsNrrLAMOBrien(hard copy) RidsRgn2MailCenter(MErnstes)

RidsOgcRp BSingal (DORL DPR)

Package No.: ML061150507 License Amendment No. ML061140442 Tech Spec No.: ML061160014 NRR-058 OFFICE NRR/LPL2-1/PM NRR/LPL2-1/LA OGC BGCB/BD NRR/LPL2-1/BC NAME LOlshan MOBrien SHamrick RKaras CM for EMarinos DATE 4/13/06 5/4/06 4/25/06 4/17/06 5/4/06

OFFICIAL RECORD COPY DUKE POWER COMPANY LLC DOCKET NO. 50-287 OCONEE NUCLEAR STATION, UNIT 3 AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment No. 350 Renewed License No. DPR-55

1. The Nuclear Regulatory Commission (the Commission) has found that:

A. The application for amendment to the Oconee Nuclear Station, Unit 3 (the facility) Renewed Facility Operating License No. DPR-55 filed by the Duke Power Company LLC, (the licensee) dated August 18, 2005, supplemented September 15, 2005, and January 5 and April 6, 2006, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations as set forth in 10 CFR Chapter I; B. The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C. There is reasonable assurance (I) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations set forth in 10 CFR Chapter I; D. The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E. The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.

2. Accordingly, the license is hereby amended by page changes to the Technical Specifications as indicated in the attachment to this license amendment, and Paragraph 3.B of Renewed Facility Operating License No. DPR-55 is hereby amended to read as follows:

B. Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 350, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.

3. This license amendment is effective as of its date of issuance and shall be implemented within 60 days of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION

/RA/

Evangelos C. Marinos, Chief Plant Licensing Branch II-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation

Attachment:

Technical Specification Changes Date of Issuance: May 4, 2006

ATTACHMENT TO LICENSE AMENDMENT NO. 350 RENEWED FACILITY OPERATING LICENSE NO. DPR-55 DOCKET NO. 50-287 Replace the following pages of the Appendix A Technical Specifications with the attached revised pages. The revised pages are identified by amendment number and contain marginal lines indicating the areas of change.

Remove Insert 3.5.2-5a 3.5.2-5 3.5.2-5b 3.5.3-3 3.5.3-3a 3.5.3-3b

SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 350 TO RENEWED FACILITY OPERATING LICENSE DPR-55 DUKE POWER COMPANY LLC OCONEE NUCLEAR STATION, UNIT 3 DOCKET NO. 50-287

1.0 INTRODUCTION

By letter dated August 18, 2005, as supplemented September 15, 2005, and January 5 and April 6, 2006, Duke Power Company LLC (the licensee), submitted a request for changes to the Oconee Nuclear Station, Unit 3, Technical Specifications (TSs). The requested changes would revise TSs 3.5.2.6 and 3.5.3.6 to accommodate the replacement of the reactor building emergency sump (RBES) suction inlet trash racks and screens with strainers. Similar amendments were issued for Units 1 and 2 on November 1, 2005; however, the amendment for Unit 3 was not issued at that time since the licensee had not completed its evaluation of the impact of pipe whip, jet impingement and internally generated missiles for Unit 3.

The supplements dated September 15, 2005, and January 5 and April 6, 2006, provided clarifying information that did not change the scope of the original application and the initial proposed no significant hazards consideration determination.

2.0 REGULATORY EVALUATION

Nuclear Regulatory Commission (NRC) Generic Letter (GL) 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents and Pressurized Water Reactors, is part of the regulatory framework the NRC staff is using to address issues associated with Generic Safety Issue (GSI)-191, Assessment of Debris Accumulation on PWR Sump Performance, for requirements to improve evaluation of plant capability to meet Title 10 of the Code of Federal Regulations (10 CFR), Part 50, Section 50.46(b)(5).

The new strainers are functionally equivalent to the existing trash racks and screens for meeting requirements of 10 CFR 50.46(b)(5) for long-term cooling and 10 CFR Part 50, Appendix A, Criterion 35 for emergency core cooling.

3.0 TECHNICAL EVALUATION

The proposed change involves revising TS Surveillance Requirements 3.5.2.6 and 3.5.3.6 to use the term "strainers" to replace the terms "trash racks and screens. This change is needed to reflect the replacement of RBES suction inlet trash racks and screens with strainer

assemblies in response to NRC Generic Letter 2004-02. The new strainers are functionally equivalent to the existing trash racks and screens for meeting the requirements of 10 CFR 50.46(b)(5) for long-term cooling and 10 CFR Part 50, Appendix A, Criterion 35 for emergency core cooling. The use of the generic term "strainers" can be used for both the existing and new designs, will not affect implementation of Surveillance Requirements 3.5.2.6 and 3.5.3.6, and can be used for implementation of corrective actions to address GSI-191.

GSI-191 was established by the NRC to determine whether transport and accumulation of debris in pressurized-water reactor (PWR) containments following a loss-of-coolant accident (LOCA) would impede the long-term operation of the emergency core cooling system or containment spray system. The NRC is currently implementing its plan to have all PWR licensees evaluate the potential for excessive head loss across the containment sump screen and implement necessary actions to resolve concerns associated with GSI-191. This action plan includes review of all licensee responses to GL 2004-02 and plant audits as needed to confirm proper evaluation and corrective actions to address all technical issues associated with proper sump performance. The information that was provided by the licensee regarding jet impingement and pipe whip effects, and missile protection, will be reviewed as part of this action plan.

The NRC staff has reviewed the licensees regulatory and technical analyses in support of its proposed license amendment, which are described in Attachments 3, 4, and 5 of the licensees August 18, 2005, submittal and finds these justifications acceptable.

On November 1, 2005, similar amendments were issued for Units 1 and 2; however, the amendment for Unit 3 was not issued at that time since the licensee had not completed its evaluation of the impact of pipe whip, jet impingement, and internally-generated missiles for Unit 3. By letter dated April 6, 2006, the licensee provided the results of these evaluations.

The NRC staff has reviewed Dukes evaluation of pipe whip, jet impingement and internally generated missile impact on the emergency sump strainer. The sources and targets were identified by a walkdown of Unit 1 and applied to Unit 3 on the basis of similarity. Duke Calculations S-005 "Missile Evaluation for the Emergency Sump Strainer," and S-006, "Jet Impingement and Pipe Whip Evaluation for the Emergency Sump Strainer," document the walkdown results and perform the analysis of the findings. The calculations document that Unit 3 piping arrangement in the area of the RBES is similar to that of Unit 1 & Unit 2. The NRC staff concurs with the conclusions of these calculations. Based on this evaluation, the licensee concludes that the emergency strainer operability will not be compromised during a LOCA by missiles, jet impingement or pipe whip. The NRC staff concludes that there are no credible missiles nor credible high-energy line break jets or pipe whips that could damage the strainer when needed during a LOCA.

Based on the review of the calculations provided by the licensee, the NRC staff grants approval of the proposed TS changes with regard to the evaluation for jet impingement, pipe whip and internally-generated missile impact of the RBES for Unit 3.

4.0 STATE CONSULTATION

In accordance with the Commission's regulations, the South Carolina State official was notified of the proposed issuance of the amendments. The State official had no comments.

5.0 ENVIRONMENTAL CONSIDERATION

The amendment changes requirements with respect to installation or use of a facility component located within the restricted area as defined in 10 CFR Part 20 and changes surveillance requirements. The NRC staff has determined that the amendment involves no significant increase in the amounts and no significant change in the types of any effluents that may be released offsite and that there is no significant increase in individual or cumulative occupational radiation exposure. The Commission has previously issued a proposed finding that the amendment involves no significant hazards consideration, and there has been no public comment on such finding (70 FR 51852). Accordingly, the amendment meets the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(9). Pursuant to 10 CFR 51.22(b), no environmental impact statement or environmental assessment need be prepared in connection with the issuance of the amendment.

6.0 CONCLUSION

The Commission has concluded, based on the considerations discussed above, that: (1) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner, (2) such activities will be conducted in compliance with the Commission's regulations, and (3) the issuance of the amendment will not be inimical to the common defense and security or to the health and safety of the public.

Principal Contributors: T. Hafera S. Samaddar Date: May 4, 2006 Oconee Nuclear Station, Units 1, 2, and 3

cc:

Ms. Lisa F. Vaughn Manager - Nuclear Regulatory Duke Power Company, LLC Issues and Industry Affairs 526 South Church Street Duke Power Company, LLC P. O. Box 1006 526 S. Church St.

Mail Code = EC07H Mail Stop EC05P Charlotte, North Carolina 28201-1006 Charlotte, NC 28202 Manager, LIS Division of Radiation Protection NUS Corporation NC Dept of Environment, Health, & Natural 2650 McCormick Dr., 3rd Floor Resources Clearwater, FL 34619-1035 3825 Barrett Dr.

Raleigh, NC 27609-7721 Senior Resident Inspector U.S. Nuclear Regulatory Commission Mr. Peter R. Harden, IV 7812B Rochester Highway VP-Customer Relations and Sales Seneca, SC 29672 Westinghouse Electric Company 6000 Fairview Road Mr. Henry Porter, Director 12th Floor Division of Radioactive Waste Management Charlotte, NC 28210 Bureau of Land and Waste Management Dept. of Health and Env. Control Mr. Henry Barron 2600 Bull St. Group Vice President, Nuclear Generation Columbia, SC 29201-1708 and Chief Nuclear Officer P.O. Box 1006-EC07H Mr. Michael A. Schoppman Charlotte, NC 28201-1006 Framatome ANP 1911 North Ft. Myer Dr.

Suite 705 Rosslyn, VA 22209 Mr. B. G. Davenport Regulatory Compliance Manager Oconee Nuclear Site Duke Power Company, LLC ON03RC 7800 Rochester Highway Seneca, SC 29672 Ms. Karen E. Long Assistant Attorney General NC Department of Justice P.O. Box 629 Raleigh, NC 27602 Mr. R. L. Gill, Jr.