View source for SBK-L-12235, License Amendment Request 12-06, Application for Technical Specification Improvement to Extend the Inspection Interval for Reactor Coolant Pump Flywheels Using the Consolidated Line Item Improvement Process

{{Adams
| number = ML12359A016
| issue date = 12/20/2012
| title = License Amendment Request 12-06, Application for Technical Specification Improvement to Extend the Inspection Interval for Reactor Coolant Pump Flywheels Using the Consolidated Line Item Improvement Process
| author name = Walsh K
| author affiliation = NextEra Energy Seabrook, LLC
| addressee name = 
| addressee affiliation = NRC/Document Control Desk, NRC/NRR
| docket = 05000443
| license number = 
| contact person = 
| case reference number = SBK-L-12235
| document type = Letter type:SBK, License-Application for Facility Operating License (Amend/Renewal) DKT 50, Technical Specifications
| page count = 12
| project = 
| stage = Request
}}

=Text=
{{#Wiki_filter:NEXTera ENERGY December 20, 2012 10 CFR 50.90 SBK-L-12235 Docket No. 50-443 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Seabrook Station License Amendment Request 12-06 Application for Technical Specification Improvement to Extend the Inspection Interval for Reactor Coolant Pump Flywheels Using the Consolidated Line Item Improvement Process Pursuant to 10 CFR 50.90, NextEra Energy Seabrook, LLC (NextEra) hereby requests an amendment to the Technical Specifications (TS) for Seabrook Station. The enclosed license amendment request (LAR) proposes to revise TS 6.7.6.m, "Reactor Coolant Pump Flywheel Inspection Program."
The proposed amendment will extend the reactor coolant pump (RCP) motor flywheel examination frequency from the currently approved 10-year inspection interval, to an interval not to exceed 20 years. 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-15666)." The availability of this TS improvement was announced in the FederalRegister on October 22, 2003 as part of the consolidated line item improvement process (CLIIP).
The Enclosure provides a description and assessment of the proposed change and the requested confirmation of applicability. Attachment 1 to the Enclosure provides the existing TS page marked-up to show the proposed change, and Attachment 2 provides the revised, clean TS page.
NextEra requests approval of the proposed license amendment by December 20, 2013, with the amendment being implemented within 60 days of issuance.
In accordance with 10 CFR 50.91, a copy of this application is being provided to the designated New Hampshire State Official.
oo/.
NextEra Energy Seabrook, LLC, P.O. Box 300, Lafayette Road, Seabrook, NH 03874

United States Nuclear Regulatory Commission SBK-L-12235 / Page 2 No new commitments are made as a result of this change.
In accordance with site administrative procedures, the Station Operation Review Committee has reviewed this LAR.
Should you have any questions regarding this letter, please contact Mr. Michael O'Keefe, Licensing Manager, at (603) 773-7745.
Sincerely, NextEra Energy Seabrook, LLC Kevin T. Walsh Site Vice President Enclosure cc:     NRC Region I Administrator NRC Project Manager NRC Senior Resident Inspector Mr. Christopher M. Pope, Director Homeland Security and Emergency Management New Hampshire Department of Safety Division of Homeland Security and Emergency Management
       .Bureau of Emergency Management 33 Hazen Drive Concord, NH 03305 Mr. John Giarrusso, Jr., Nuclear Preparedness Manager The Commonwealth of Massachusetts Emergency Management Agency 400 Worcester Road Framingham, MA 01702-5399

ENERGY&C                     ,
SEAB ROOK AFFIDAVIT 1, Kevin T. Walsh, Site Vice President of NextEra Energy Seabrook, LLC hereby affirm that the information and statements contained within this license amendment request are based on facts and circumstances which are true and accurate to the best of my knowledge and belief.
Sworn and Subscribed before me this
    .20 day of.Qec_&#xfd;                  '2012
                                                                -A Kevin'ft Wafish Notary                       Site Vice President Public

Enclosure Description and Assessment of the Proposed Change Application for Technical Specification Improvement to Extend the Inspection Interval for Reactor Coolant Pump Flywheels using the Consolidated Line Item Improvement Process 1.0     Introduction 2.0     Description of Proposed Amendment 3.0     Background 4.0     Regulatory Requirements and Guidance 5.0     Technical Analysis 6.0     Regulatory Analysis 7.0     No Significant Hazards Consideration 8.0     Environmental Evaluation 9.0     Precedent 10.0    References Attachments
: 1. Proposed Technical Specifications Changes
: 2. Revised Technical Specification Page I

==1.0   INTRODUCTION==

The proposed license amendment changes Technical Specification (TS) 6.7.6.m, "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-15666)." The availability of this TS improvement was announced in the FederalRegister on 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 6.7.6.m:
The examination interval for the RCP flywheels is changed from 10 year intervals coinciding with the Inservice Inspection schedule as required by ASME Section XI to 20 year intervals.
The TS change provided in TSTF-421 was based on the premise that the licensee's TS would be consistent with the Standard TS (STS) for Westinghouse Plants (NUREG-1431) as follows:
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.
Current Seabrook TS 6.7.6.m, Reactor Coolant PumpFlywheel Inspection Program, neither includes the first STS paragraph above nor does it state that the test methods are in lieu of Positions C.4.b.(1) and C.4.b.(2) in Regulatory Guide (RG) 1.14. Therefore, the proposed amendment also revises Seabrook TS 6.7.6.m to reference RG 1.14 for consistency with the STS as shown below.
: m. Reactor Coolant Pump Flywheel Inspection Program In addition to the requirements of Specification 4.0.5, each reactor coolant pump flywheel shall be inspected per the recommendationsof Regulatory Position C.4.b of Regulatory Guide 1.14, Revision 1, August 1975 at least once every 1-0 20 years. In lieu of Position C.4.b(1) and C.4.b(2), this inspection shall be by either of the following examinations:
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: a. An in-place examination, utilizing ultrasonic testing, over the volume from the inner bore of the flywheel to the circle of one-half the outer radius; or
: b. A surface examination, utilizing magnetic particle testing and/or penetrant testing, of the exposed surfaces of the disassembled flywheel.
Although not specifically addressed in TSTF-421, this change is administrative in nature.
Including a reference to RG 1.14 in TS 6.7.6.m does not change the technical requirements of the Reactor Coolant Pump Flywheel Inspection Program; rather, it establishes consistency with STS 5.5.7 on which TSTF-421 was based. This change does not alter the conclusion in the significant hazards consideration determination published on June 24, 2003 as part of the CLIIP.

==3.0    BACKGROUND==

The background for this application is 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-1 5666, "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-15666, and the related NRC SE.

==5.0    TECHNICAL ANALYSIS==

NextEra 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 staffs model SE, as well as the information provided to support TSTF-421 (including WCAP-1 5666 and the related SE dated May 5, 2003). NextEra has concluded that the justifications presented in the TSTF proposal and the model SE prepared by the NRC staff are applicable to Seabrook Station and justify this amendment for incorporation of the changes to the Seabrook TS.

==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 5666, and the associated SE.
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7.0    NO SIGNIFICANT HAZARDS CONSIDERATION NextEra has reviewed the proposed no significant hazards consideration determination published on June 24, 2003 (68 FR 37590) as part of the CLIIP. NextEra has concluded that the proposed determination presented in the notice is applicable to Seabrook and the determination is hereby incorporated by reference to satisfy the requirements of 10 CFR 50.91(a).
8.0    ENVIRONMENTAL EVALUATION NextEra has reviewed the environmental evaluation included in the model SE published on June 24, 2003 (68 FR 37590) as part of the CLIIP. NextEra has concluded that the staff's findings presented in that evaluation are applicable to Seabrook Station and the evaluation is hereby incorporated by reference for this application.
9.0    PRECEDENT This application is being made in accordance with the CLIIP. Byron and Braidwood stations received similar amendments to extend the reactor coolant pump flywheel inspections in accordance with TSTF-421 in September 2010. NextEra has proposed a minor change in addition to the TS changes described in TSTF-421. The change is administrative in nature and is included to establish consistency with the STS on which TSTF-421 was based.

==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-15666)," Revision 0, November 2001.
: 4. WCAP-15666, "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-15666.
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Attachment I Proposed Technical Specifications Changes

Proposed Technical Specifications Changes The attached markups reflect the currently issued version of the TS and Facility Operating License. At the time of submittal, the Facility Operating License was revised through Amendment No. 131.
Listed below are the license amendment requests that are awaiting NRC approval :and may impact the currently issued version of the Facility Operating License affected by this LAR.
LAR,     Title                                                 NextEra Energy     Date Seabrook Letter >Submitted 10-02    Application for Change to the Technical               SBK-L-10074        05/14/2010 Specifications for the Containment Enclosure Emergency Air Cleanup System Changes to the Technical Specifications for New 11-04    and Spent Fuel Storage                               SBK-L-11245         01/30/2012 Application to Revise the Applicability of the 11-06    Reactor Coolant System Pressure - Temperature        SBK-L-1 1186        11/17/2011 Limits and the Cold Overpressure Protection Setpoints The following TS pages are included in the attached markup:
Technical                               Title                                Page Specification         :
TS 6.7.6.m               Reactor Coolant Pump Flywheel                     6-14a Inspection Program

ADMINISTRATIVE CONTROLS PROCEDURES AND PROGRAMS 6.7.6 (Continued)
: d.       Measurement, at designated locations, of the CRE pressure relative to all external areas adjacent to the CRE boundary during the pressurization mode of operation by~onetrain of the!CREMAFS,'
operating at a flow rate of less than or equal to 600 CFM at a Frequency of 18 months on a STAGGERED TEST BASIS. The results shall be trended and used as part of the 18 month assessment of the CRE boundary.
: e.      The quantitative limits on unfiltered air in-leakage into the CRE. These limits shall be stated in a manner to allow direct comparison to the unfiltered air in-leakage measured by the testing described in paragraph c. The unfiltered air in-leakage limit for radiological challenges is the in-leakage flow rate assumed in the licensing basis analyses of DBA consequences. Unfiltered air inleakage limits for hazardous chemicals must ensure that exposure of CRE occupants to these hazards will be within the assumptions in the licensing basis.
: f.      The provisions of SR 4.0.2 are applicable to the Frequencies for assessing CRE habitability, determining CRE unfiltered in-leakage, and measuring CRE pressure and assessing the CRE boundary as required by paragraphs c and d, respectively.                      //,- W ,,0 f,
: m. Reactor Coolant Pump Flywheel Inspection Progqram In addition to the requirements of Specification 4.0.5, ea h reactor coolant pump flywheel shall be inspected at least once everyoyears. his inspection shall be by either of the following      aminations:       &
: a.      An in-place examination, utilizing ultrasonic testing, over the volume from the inner bore of the flywheel to the circle of one-half the outer radius-, or
: b.      A surface examination, utilizing magnetic particle testing and/or penetrant testing, of the exposed surfaces of the disassembled flywheel.
           ,k4     ~         4     3    o0/i4       1441 la/
leo                                7 SEABROOK - UNIT 1                               6-14a                  Amendment No. 441-94_26-

Attachment 2 Revised Technical Specification Pages I

ADMINISTRATIVE CONTROLS PROCEDURES AND PROGRAMS 6.7.6 (Continued)
: d.       Measurement, at designated locations, of the CRE pressure relative to all external areas adjacent to the CRE boundary during the pressurization mode of operation by one train of the CREMAFS, operating at a flow rate of less-than or equal to 600-CFM at a Frequency of 18 months on a STAGGERED TEST BASIS. The results shall be trended and used as part of the 18 month assessment of the CRE boundary.
: e.       The quantitative limits on unfiltered air in-leakage into the CRE. These limits shall be stated in a manner to allow direct comparison to the unfiltered air in-leakage measured by the testing described in paragraph c. The unfiltered air in-leakage limit for radiological challenges is the in-leakage flow rate assumed in the licensing basis analyses of DBA consequences. Unfiltered air inleakage limits for hazardous chemicals must ensure that exposure of CRE occupants to these hazards will be within the assumptions in the licensing basis.
: f.      The provisions of SR 4.0.2 are applicable to the Frequencies for assessing CRE habitability, determining CRE unfiltered in-leakage, and measuring CRE pressure and assessing the CRE boundary as required by paragraphs c and d, respectively.
: m. Reactor Coolant Pump Flywheel Inspection Program In addition to the requirements of Specification 4.0.5, each reactor coolant pump flywheel shall be inspected per the recommendations of Regulatory Position C.4.b of Regulatory Guide 1.14, Revision 1, August 1975 at least once every 20 years. In lieu of Position C.4.b(1) and C.4.b(2), this inspection shall be by either of the following examinations:
: a.      An in-place examination, utilizing ultrasonic testing, over the volume from the inner bore of the flywheel to the circle of one-half the outer radius; or
: b.      A surface examination, utilizing magnetic particle testing and/or penetrant testing, of the exposed surfaces of the disassembled flywheel.
SEABROOK - UNIT 1                               6-14a                   Amendment No. 44-g 426ra}}