ML040910123
| ML040910123 | |
| Person / Time | |
|---|---|
| Site: | Mcguire, Catawba, McGuire  |
| Issue date: | 03/23/2004 |
| From: | Mccollum W Duke Energy Corp |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| Download: ML040910123 (16) | |
Text
. hDuke WILLIAM R MCCOLLUM, JR.
4 Powere VP, Nuclear Support A
Due EergyComanyDuke Energy Corporation A Duke Energy Company Duke Power EC07H / 526 South Church Street Charlotte, NC 28202-1802 Mailing Address:
P. 0. Box 1006 - EC07H Charlotte, NC 28201-1006 March 23, 2004 704 382 8983 704 382 6056 fax U. S. Nuclear Regulatory Commission wrmccoll~duke-energy.com Washington, DC 20555-0001 ATTENTION:
Document Control Desk
SUBJECT:
Duke Energy Corporation McGuire Nuclear Station Units 1 and 2 Docket Nos. 50-369 and 50-370 Catawba Nuclear Station Units 1 and 2 Docket Nos. 50-413 and 50-414 License Amendment Request Applicable to Technical Specifications 5.5.7, Reactor Coolant Pump Flywheel Inspection Program, Using the Consolidated Line Item Improvement Process (CLIIP)
Pursuant to 10 CFR 50.90, Duke Energy Corporation (Duke) is submitting a license amendment request (LAR) for the Facility Operating Licenses and Technical Specifications (TS) for McGuire Nuclear Station Units 1 and 2, and Catawba Nuclear Station Units 1 and 2. The changes are consistent with Industry/Technical Specification Task Force (TSTF) Standard Technical Specification Change Traveler, TSTF-421, "Revision to RCP Flywheel Inspection Program (WCAP-15666A)."
The availability of this TS improvement was announced in the Federal Register on October 22, 2003 as part of the Consolidated Line Item Improvement Process (CLIIP). provides a description of the proposed change and the requested confirmation of applicability.
Attachments 2a and 2b provide the existing TS pages marked up to show the proposed change for McGuire and Catawba, respectively.
Attachments 3a and 3b provide revised (clean) TS pages for McGuire and Catawba, respectively.
Implementation of this proposed change to TS 5.5.7 will impact both the McGuire and Catawba Updated Final Safety Analysis Reports (UFSAR).
Section 5.2.6.3 of the McGuire UFSAR and Section 5.4.1.5 of the Catawba UFSAR will require revision in www. dukepower. corn
U. S. Nuclear Regulatory Commission March 23, 2004 Page 2 order to update the referenced Topical Report (WCAP-15666A, Extension of Reactor Coolant Pump Motor Flywheel Examination) and to be consistent with the new 20-year examination interval contained in this LAR.
The necessary permanent revisions to the UFSARs will be made in accordance with 10 CFR 50.71(e).
Since this is a CLIIP item, Duke is requesting NRC review and approval of this submittal by July 1, 2004, and it has been determined that the NRC's standard 30-day implementation grace period is sufficient for this LAR. There are no additional regulatory commitments contained in this submittal package.
In accordance with Duke administrative procedures and the Quality Assurance Program Topical Report, the site-specific changes contained in this proposed amendment have been reviewed and approved by the applicable McGuire or Catawba Plant Operations Review Committee.
This proposed amendment has also been reviewed and approved by the Duke Nuclear Safety Review Board.
Pursuant to 10 CFR 50.91, a copy of this amendment request is being sent to the designated official of the State of North Carolina and to the designated official of the State of South Carolina.
Inquiries on this matter should be directed to J. S. Warren at 704-875-5171.
Very truly yours, W. R. McCollum/
Attachments
U. S. Nuclear Regulatory Commission March 23, 2004 Page 3 Attachments: -
Description and Assessment Attachments 2a and 2b -
Proposed Technical Specifications Changes (Mark-up)
Attachments 3a and 3b -
Revised (Clean) Technical Specifications Pages xc w/Attachments:
L. A. Reyes U. S. Nuclear Regulatory Commission Regional Administrator, Region II Atlanta Federal Center 61 Forsyth St., SW, Suite 23T85 Atlanta, GA 30303 L. N. Olshan (Addressee Only)
NRC Senior Project Manager (MNS)
U. S. Nuclear Regulatory Commission Mail Stop 0-8 H12 Washington, DC 20555-0001 S. E. Peters (Addressee Only)
NRC Project Manager (CNS)
U. S. Nuclear Regulatory Commission Mail Stop 0-8 H12 Washington, DC 20555-0001 J. B. Brady Senior Resident Inspector (MNS)
U. S. Nuclear Regulatory Commission McGuire Nuclear Site E. F. Guthrie Senior Resident Inspector (CNS)
U. S. Nuclear Regulatory Commission Catawba Nuclear Site
U. S. Nuclear Regulatory Commission March 23, 2004 Page 4 xc w/Attachments:
Beverly 0. Hall, Section Chief Radiation Protection Section 1645 Mail Service Center Raleigh, NC 27699-1645 H. J. Porter, Director Division of Radioactive Waste Management South Carolina Bureau of Land and Waste Management 2600 Bull Street Columbia, SC 29201
U. S. Nuclear Regulatory Commission March 23, 2004 Page 5 W. R. McCollum, Jr., affirms that he is the person who subscribed his name to the foregoing statement, and that all the matters and facts set forth herein are true and correct to the best of his knowledge.
W. R. McCollum, Jr jor Vice President Subscribed and sworn to me:
3 2 3-V Date
/
, Notary Public oc/' '-Lce
My commission expires:
Date SEAL _
U. S. Nuclear Regulatory Commission March 23, 2004 Page 6 bxc w/Attachments:
R. L. Gill (ECQ50)
L. A. Keller (CN0lRC)
B. G. Davenport (ON03RC)
A. J. Hogge (ECO50)
K. L. Crane (MGOIRC)
K. E. Nicholson (CNOIRC)
J. M. Ferguson (Date File) -
CNOlSA NRIA File/ELL McGuire Master File -
MG01DM Catawba Master File 801.01 -
CN04DM Catawba Owners:
Saluda River Electric Corporation P. 0. Box 929 Laurens, SC 29360-0929 NC Municipal Power Agency No. 1 P. 0. Box 29513 Raleigh, NC 27626-0513 T. R. Puryear NC Electric Membership Corporation CN03G Piedmont Municipal Power Agency 121 Village Drive Greer, SC 29651
ATTACHMENT 1 Description and Assessment
1.0 INTRODUCTION
The proposed License amendment changes Technical Specification (TS) 5.5.7, "Reactor Coolant Pump Flywheel Inspection Program." The changes are consistent with Industry/Technical Specification Task Force (TSTF) Standard Technical Specification Change Traveler, TSTF-421, "Revision to RCP Flywheel Inspection Program (WCAP-1 5666A)." The availability of this TS improvement was announced in the Federal Registeron October 22, 2003 as part of the consolidated line item improvement process (CLIIP).
2.0 DESCRIPTION
OF PROPOSED AMENDMENT Consistent with the NRC-approved TSTF-421, the proposed TS change includes the following revision to TS 5.5.7:
The examination interval for the RCP flywheels is changed from approximately 10 year intervals coinciding with the Inservice Inspection schedule as required by ASME Section Xi to 20 year intervals.
3.0 BACKGROUND
The background for this application is adequately addressed by the NRC Notice of Availability published on Ocotber 22, 2003 (68 FR 60422), NRC Notice for Comment published on June 24, 2003 (68 FR 37590), TSTF-421, WCAP-1 5666A, "Extension of Reactor Coolant Pump Motor Flywheel Examination," and the related NRC safety evaluation (SE) dated May 5, 2003.
4.0 REGULATORY REQUIREMENTS AND GUIDANCE The applicable regulatory requirements and guidance associated with this application are adequately addressed by the NRC Notice of Availability published on October 22, 2003 (68 FR 60422), NRC Notice for Comment published on June 24, 2003 (68 FR 37590), TSTF-421, WCAP-15666A, and the related NRC SE.
5.0 TECHNICAL ANALYSIS
Duke Energy Corporation (Duke) has reviewed the model SE published on June 24, 2003 (68 FR 37590), and verified its applicability as part of the CLIIP. This verification included a review of the NRC staff's model SE, as well as the information provided to support TSTF-421 (including WCAP-1 5666A and the related SE dated May 5, 2003). Duke has concluded that the justifications presented in the TSTF proposal and the model SE prepared by the NRC staff are applicable to McGuire Nuclear Station, Units 1 and 2 and Catawba Nuclear Station, Units 1 and 2, and justify this amendment for the incorporation of the changes to the McGuire and Catawba TS.
2
6.0 REGULATORY ANALYSIS
A description of this proposed change and its relationship to applicable regulatory requirements and guidance was provided in the NRC notices related to the CLIIP, TSTF-421, Topical Report WCAP-1 5666A, and the associated SE.
7.0 NO SIGNIFICANT HAZARDS CONSIDERATION Duke has reviewed the proposed no significant hazards consideration determination published on June 24, 2003 (68 FR 37590) as part of the CLIIP. Duke has concluded that the proposed determination presented in the notice is applicable to McGuire and Catawba and the determination is hereby incorporated by reference to satisfy the requirements of 10 CFR 50.91 (a).
8.0 ENVIRONMENTAL EVALUATION Duke has reviewed the environmental evaluation included in the model SE published on June 24, 2003 (68 FR 37590) as part of the CLIIP. Duke has concluded that the staff's findings presented in that evaluation are applicable to McGuire and Catawba and the evaluation is hereby incorporated by reference for this application.
9.0 PRECEDENT This application is being made in accordance with the CLIIP. Duke is not proposing variations or deviations from the TS changes described in TSTF-421 or the NRC staff's model SE published on June 24, 2003 (68 FR 37590).
10.0 REFERENCES
- 1.
Federal Register Notice: Notice of Availability of Model Application Concerning Technical Specification Improvement Regarding Extension of Reactor Coolant Pump Motor Flywheel Examination for Westinghouse Plants Using the Consolidated Line Item Improvement Process, published October 22,2003, (68 FR 60422).
- 2.
Federal Register Notice: Notice of Opportunity to Comment on Model Safety Evaluation on Technical Specification Improvement Regarding Extension of Reactor Coolant Pump Motor Flywheel Examination for Westinghouse Plants Using the Consolidated Line Item Improvement Process, published June 24, 2003 (68 FR 37590).
- 3.
Industry/Technical Specification Task Force (TSTF) Standard Technical Specification Change Traveler, TSTF-421, "Revision to RCP Flywheel Inspection Program (WCAP-15666A)," Revision 0, November 2001.
- 4.
WCAP-1 5666A, "Extension of Reactor Coolant Pump Motor Flywheel Examination," July 2001.
- 5.
NRC letter dated May 5, 2003, from H. Berkow to R. Bryan (WOG) transmitting Safety Evaluation of WCAP-15666A.
a McGuire Units 1 and 2 Proposed Technical Specifications Changes (Mark-up)
Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.5 Radioactive Effluent Controls Program (continued) ii.
A determination that the change(s) maintain the overall conformance of the solidified waste product to existing requirements of Federal, State, or other applicable regulations or a determination that the change will maintain the level of radioactive effluent control required by 10 CFR 20.1302, 40 CFR Part 190, 10 CFR 50.36a, and Appendix I to 10 CFR Part 50 and not adversely impact the accuracy or reliability of effluent, dose, or setpoint calculations;
- 2.
Shall become effective after approval of the station manager.
- 3.
Shall be submitted to the Commission in the form of a complete, legible copy of the entire Section 16.11 of the UFSAR as a part of or concurrent with the Radioactive Effluent Release Report for the period of the report in which any changes to Section 16.11 of the UFSAR was made. Each change shall be identified by markings in the margin of the affected pages, clearly indicating the area of the page that was changed, and shall indicate the date (i.e.,
month/year) the change was implemented.
5.5.6 Component Cyclic or Transient Limit This program provides controls to track the UFSAR, Section 5.2.1.5, cyclic and transient occurrences to ensure that components are maintained within the design limits.
5.5.7 Reactor Coolant Pumnp Flywheel InsDection Program This program shall provide for the inspection of each reactor coolant pump flywheel per the recommendations of Regulatory Position C.4.b of Regulatory Guide 1.14, Revision 1, August 1975.
In lieu of Position C.4.b(1) and C.4.b(2), a qualified in-place UT xamination over the volume from the inner bore of the flywheel to the circle on half of the outer radius or a surface examination (MT and/or PT) of expose rfaces of the removed flywheels may be conducted at m tely ear intervals icidin;witt sies is esqid (continued)
McGuire Units 1 and 2 5.5-5 Amendment Nos.en b
Catawba Units 1 and 2 Proposed Technical Specifications Changes (Mark-up)
Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.5 Radioactive Effluent Controls Program (continued)
- 1.
Shall be documented and records of reviews performed shall be retained. This documentation shall contain:
- i.
Sufficient information to support the change(s) together with the appropriate analyses or evaluations justifying the change(s), and ii.
A determination that the change(s) maintain the overall conformance of the solidified waste product to existing requirements of Federal, State, or other applicable regulations or a determination that the change will maintain the level of radioactive effluent control required by 10 CFR 20.1302, 40 CFR Part 190, 10 CFR 50.36a, and Appendix I to 10 CFR Part 50 and not adversely impact the accuracy or reliability of effluent, dose, or setpoint calculations;
- 2.
Shall become effective after approval of the station manager.
- 3.
Shall be submitted to the Commission in the form of a complete, legible copy of the entire Section 16.11 of the UFSAR as a part of or concurrent with the Radioactive Effluent Release Report for the period of the report in which any changes to Section 16.11 of the UFSAR was made. Each change shall be identified by markings in the margin of the affected pages, clearly indicating the area of the page that was changed, and shall indicate the date (i.e.,
month/year) the change was implemented.
5.5.6 Component Cyclic or Transient Limit This program provides controls to track the UFSAR, Section 3.9.1.1, cyclic and transient occurrences to ensure that components are maintained within the design limits.
5.5.7 Reactbr Coolant PumD Flywheel Inspection Program This program shall provide for the inspection of each reactor coolant pump flywheel per the recommendations of Regulatory Position C.4.b of Regulatory Guide 1.14, Revision 1, August 1975.
In lieu of Position C.4.b(1) and C.4.b(2), a qualifi in-place UT examination over the volume from the inner bore of the flywheel t the circle one-half of the outer radius or a surface examination (MT and/rP f exposed surfaces of the removed flywheels may be conduce yti 1
1 ear intervals 4tle ln che ul s
irejb (continued)
Catawba Units 1 and 2 5.5-5 Amendment Nos.
a McGuire Units 1 and 2 Revised (Clean) Technical Specifications Pages Remove Insert 5.5-5 5.5-5 1
Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.5 Radioactive Effluent Controls Program (continued) ii.
A determination that the change(s) maintain the overall conformance of the solidified waste product to existing requirements of Federal, State, or other applicable regulations or a determination that the change will maintain the level of radioactive effluent control required by 10 CFR 20.1302, 40 CFR Part 190, 10 CFR 50.36a, and Appendix I to 10 CFR Part 50 and not adversely impact the accuracy or reliability of effluent, dose, or setpoint calculations;
- 2.
Shall become effective after approval of the station manager.
- 3.
Shall be submitted to the Commission in the form of a complete, legible copy of the entire Section 16.11 of the UFSAR as a part of or concurrent with the Radioactive Effluent Release Report for the period of the report in which any changes to Section 16.11 of the UFSAR was made. Each change shall be identified by markings in the margin of the affected pages, clearly indicating the area of the page that was changed, and shall indicate the date (i.e.,
month/year) the change was implemented.
5.5.6 Component Cyclic or Transient Limit This program provides controls to track the UFSAR, Section 5.2.1.5, cyclic and transient occurrences to ensure that components are maintained within the design limits.
5.5.7 Reactor Coolant Pump Flywheel Inspection Pro-gram This program shall provide for the inspection of each reactor coolant pump flywheel per the recommendations of Regulatory Position C.4.b of Regulatory Guide 1.14, Revision 1, August 1975.
In lieu of Position C.4.b(1) and C.4.b(2), a qualified in-place UT examination over the volume from the inner bore of the flywheel to the circle one-half of the outer radius or a surface examination (MT and/or PT) of exposed surfaces of the removed flywheels may be conducted at 20 year intervals.
(continued)
McGuire Units 1 and 2 5.5-5 Amendment Nos.
b Catawba Units 1 and 2 Revised (Clean) Technical Specifications and Bases Pages Remove Insert 5.5-5 5.5-5 1
Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.5 Radioactive Effluent Controls Program (continued)
- 1.
Shall be documented and records of reviews performed shall be retained. This documentation shall contain:
- i.
Sufficient information to support the change(s) together with the appropriate analyses or evaluations justifying the change(s), and ii.
A determination that the change(s) maintain the overall conformance of the solidified waste product to existing requirements of Federal, State, or other applicable regulations or a determination that the change will maintain the level of radioactive effluent control required by 10 CFR 20.1302, 40 CFR Part 190, 10 CFR 50.36a, and Appendix I to 10 CFR Part 50 and not adversely impact the accuracy or reliability of effluent, dose, or setpoint calculations;
- 2.
Shall become effective after approval of the station manager.
- 3.
Shall be submitted to the Commission in the form of a complete, legible copy of the entire Section 16.11 of the UFSAR as a part of or concurrent with the Radioactive Effluent Release Report for the period of the report in which any changes to Section 16.11 of the UFSAR was made. Each change shall be identified by markings in the margin of the affected pages, clearly indicating the area of the page that was changed, and shall indicate the date (i.e.,
month/year) the change was implemented.
5.5.6 Component Cyclic or Transient Limit This program provides controls to track the UFSAR, Section 3.9.1.1, cyclic and transient occurrences to ensure that components are maintained within the design limits.
5.5.7 Reactor Coolant Pump Flywheel Inspection Program This program shall provide for the inspection of each reactor coolant pump flywheel per the recommendations of Regulatory. Position C.4.b of Regulatory Guide 1.14, Revision 1, August 1975.
In lieu of Position C.4.b(1) and C.4.b(2), a qualified in-place UT examination over the volume from the inner bore of the flywheel to the circle one-half of the outer radius or a surface examination (MT and/or PT) of exposed surfaces of the removed flywheels may be conducted at 20 year intervals.
(continued)
Catawba Units 1 and 2 5.5-5 Amendment Nos.