ML15170A378

PWROG-15039-NP, Revision 0, Waterford Unit 3 Summary Report for the Fuel Design / Fuel Management Assessments to Demonstrate MRP-227-A Applicability.

ML15170A378
Person / Time
Site:	Waterford
Issue date:	06/18/2015
From:	Bevington K, Hayes E Westinghouse
To:	Document Control Desk, Office of Nuclear Reactor Regulation
Shared Package
ML15170A406	List: ML15170A378 ML15170A379 W3F1-2015-0038, Response to Request for Additional Information Regarding Reactor Vessel Internals Aging Management Program
References
TAC MF3247, W3F1-2015-0038 PA-MSC-0983, Rev. 1, Task 7, PWROG-15039-NP, Rev. 0
Download: ML15170A378 (9)

Text

Attachment 4 to W3F1 -2015-0038 PWROG-15039-NP

WESTINGHOUSE NON-PROPRIETARY CLASS 3 PWROG-15039-NP Revision 0 Waterford Unit 3 Summary Report for the Fuel Design / Fuel Management Assessments to Demonstrate MRP-227-A Applicability PA-MSC-0983, Revision 1, Task 7 Kurt D. Bevington*

Containment and Radiological Analysis Eugene T. Hayes*

Radiation Engineering and Analysis June 3, 2015 Reviewer: Arzu Alpan*

Radiation Engineering and Analysis Approved: Laurent P. Houssay*, Manager Radiation Engineering and Analysis Approved: James P. Molkenthin*, Program Director PWR Owners Group PMO

• Electronically approved records are authenticated in the electronic document management system.

Westinghouse Electric Company LLC 1000 Westinghouse Drive Cranberry Township, PA 16066, USA

© 2015 Westinghouse Electric Company LLC All Rights Reserved

WESTINGHOUSE NON-PROPRIETARY CLASS 3 iii ACKNOWLEDGEMENTS This report was developed and funded by the PWR Owners Group under the leadership of the participating utility representatives of the Materials Committee.

June 3, 2015 PWROG-1 5039-NP PWROG-15039-NP June 3, 2015 Revision 0

WESTINGHOUSE NON-PROPRIETARY CLASS 3 iv LEGAL NOTICE This report was prepared as an account of work performed by Westinghouse Electric Company LLC. Neither Westinghouse Electric Company LLC, nor any person acting on its behalf:

1. Makes any warranty or representation, express or implied including the warranties of fitness for a particular purpose or merchantability, with respect to the accuracy, completeness, or usefulness of the information contained in this report, or that the use of any information, apparatus, method, or process disclosed in this report may not infringe privately owned rights; or

2. Assumes any liabilities with respect to the use of, or for damages resulting from the use of, any information, apparatus, method, or process disclosed in this report.

COPYRIGHT NOTICE This report has been prepared by Westinghouse Electric Company LLC and bears a Westinghouse Electric Company copyright notice. As a member of the PWR Owners Group, you are permitted to copy and redistribute all or portions of the report within your organization; however all copies made by you must include the copyright notice in all instances.

DISTRIBUTION NOTICE This report was prepared for the PWR Owners Group. This Distribution Notice is intended to establish guidance for access to this information. This report (including proprietary and non-proprietary versions) is not to be provided to any individual or organization outside of the PWR Owners Group program participants without prior written approval of the PWR Owners Group Program Management Office. However, prior written approval is not required for program participants to provide copies of Class 3 Non-Proprietary reports to third parties that are supporting implementation at their plant, and for submittals to the NRC.

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WESTINGHOUSE NON-PROPRIETARY CLASS 3 V TABLE OF CONTENTS MRP 2013-025 GUIDELINES TO DEMONSTRATE MRP-227-A APPLICABILITY FOR WATERFORD UNIT 3 REACTOR INTERNALS AGING MANAGEMENT FUEL DESIGN / FUEL MANAGEMENT ASSESSMENTS ............................................ 1-1 1.1 WATERFORD UNIT 3 EVALUATION FOR QUESTION 2 ................................. 1-1 1.1.1 Components Located Beyond the Outer Radius of the Reactor C o re ................................................................................................... 1-2 1.1.2 Components Located Above the Reactor Core ................................... 1-2 1.1.3 Components Located Below the Reactor Core ................................... 1-3 2 R E F E R E NC E S ............................................................................................................. 2-1 PWROG-15039-NP JRne 3, 2015 Revision 0

WESTINGHOUSE NON-PROPRIETARY CLASS 3 1-1 MRP 2013-025 GUIDELINES TO DEMONSTRATE MRP-227-A APPLICABILITY FOR WATERFORD UNIT 3 REACTOR INTERNALS AGING MANAGEMENT FUEL DESIGN / FUEL MANAGEMENT ASSESSMENTS Applicant/Licensee Action Item 1 from the U.S. Nuclear Regulatory Commission (NRC) staff's final safety evaluation of MRP-227-A, "Materials Reliability Program: Pressurized Water Reactor Internals Inspection and Evaluation Guidelines (MRP-227-A)," [1] states that:

"The MaterialsReliability Program indicated that each applicant/licenseewas responsible for assessingits plant's operatinghistory and demonstratingthat the approved version of MRP-227 is applicable to the facility. Each applicant/licensee shall refer, in particular,to the assumptionsregardingplant design and operating history made in the FMECA and functionality analyses for reactorsof their design (i.e., Westinghouse, CE, or B&W) which support MRP-227, and each applicant/licenseeshall describe the process used for determiningplant-specific differences in the design of their reactorvessel integrity components or plant operatingconditions, which result in different component inspection categories."

In the Reference 2 Request for Additional Information (RAI) 2, the NRC provided the following question to Entergy Operations, Inc. regarding the reactor vessel internals aging management program submitted for Waterford Unit 3 (WF3).

RAI-2-B:

"Pleaseexplain if WF3 has ever utilized atypical design or fuel management that could make the assumptions of MRP-227-A regarding core loading/core design non-representativefor thatplant, including power changes/upratessuch as the extended power uprate implemented in 2005. ... "

1.1 WATERFORD UNIT 3 EVALUATION FOR QUESTION 2 Westinghouse has evaluated the Waterford Unit 3 reactor internals components with regard to fuel designs and fuel management according to industry guideline MRP 2013-025 [3].

Waterford Unit 3 has not utilized atypical fuel designs or fuel management that could make the assumptions of MRP-227-A regarding core loading/core design non-representative, including power changes/uprates that have occurred over the operating lifetime of the unit. This conclusion is based on comparisons of the Waterford Unit 3 core geometry and operating characteristics with the MRP-227-A applicability guidelines for CE-designed reactors specified in MRP 2013-025 [3].

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WESTINGHOUSE NON-PROPRIETARY CLASS 3 1-2 Performing the MRP 2013-025 [3] guideline assessment using a calendar years basis is not required but would provide bounding results. Demonstrating that the fluence guideline compliance requirement is met based on effective full-power years, as was done in this evaluation, is acceptable and provides a technically robust and accurate assessment of plant-specific historical operating conditions.

Specifically, the following comparisons with the MRP-227-A applicability guidelines in MRP 2013-025 [3] were established for the key reactor internals components at Waterford Unit 3.

1.1.1 Components Located Beyond the Outer Radius of the Reactor Core Guideline 1 - The reactor has been operated with out-in fuel management for 30 effective full-power years or less and all future operation will use low-leakage fuel management.

Comparison -Waterford Unit 3 initiated low-leakage fuel management strategy in the third fuel cycle following 2.0 effective full-power years of operation and has been implementing low-leakage core designs since that time.

Guideline 2 - For operation going forward, the average power density of the reactor core (as defined in MRP 2013-025 [3]) shall be less than 110 W/cm 3 .

Comparison - For the last five operating fuel cycles (Cycles 15 through 19), Waterford Unit 3 has been operating at a rated power level of 3716 MWt. For the 217 fuel assembly Waterford Unit 3 core geometry, the 3716 MWt power level corresponds to a core power density of 104.1 W/cm 3. This level of power generation is also representative of anticipated future operation.

Guideline 3 - For operation going forward, the nuclear heat generation rate figure of merit (HGR-FOM) (as defined in MRP 2013-025 [3]) shall not exceed 68 W/cm 3.

Comparison -For the last five operating fuel cycles at Waterford Unit 3, the HGR-FOM at key baffle locations has ranged between [ ]a~c. This range of HGR-FOM is representative of anticipated future operation.

1.1.2 Components Located Above the Reactor Core Guideline 1 - Considering the entire operating lifetime of the reactor, the average power density of the core (as defined in MRP 2013-025 [3]) shall be less than 110 W/cm 3 for a period of more than two effective full-power years.

Comparison -Over the operating lifetime of the Waterford Unit 3 reactor, the rated core power level, including power uprates, has varied between 3390 MWt and 3716 MWt. This variation of rated power level corresponds to a power density range of 95.0 W/cm 3 to 104.1 W/cm 3.

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WESTINGHOUSE NON-PROPRIETARY CLASS 3 1-3 WESTINGHOUSE NON-PROPRIETARY CLASS 3 1-3 Guideline 2 - Considering the entire operating lifetime of the reactor, the distance between the top of the active fuel stack and the bottom of the fuel alignment plate (FAP) shall be greater than 12.4 inches for a period of more than two effective full-power years.

Comparison - For the Waterford Unit 3 reactor internals and fuel assembly geometry, the nominal distance between the top of the active fuel stack and the bottom of the FAP averaged over the first 19 fuel cycles of operation was I ]a~c. During that period of time, the nominal distance between the FAP and the top of the active fuel was greater than 12.4 inches.

1.1.3 Components Located Below the Reactor Core Based on the discussion provided in MRP 2013-025 [3], plant-specific applicability of MRP-227-A for components located below the reactor core with no further evaluation required is demonstrated by meeting the MRP-227-A, Section 2.4 criteria.

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WESTINGHOUSE NON-PROPRIETARY CLASS 3 2-1 2 REFERENCES

1. Materials Reliability Program:PressurizedWater Reactor Internals Inspection and Evaluation Guidelines (MRP-227-A). EPRI, Palo Alto, CA: 2011. 1022863.

2. U.S. NRC Letter, "Waterford Steam Electric Station, Unit 3 - Request for Additional Information Regarding the Reactor Vessel Internals Aging Management Program (TAC No. MF3247)," October 21, 2014. (NRC ADAMS Accession No. ML14232A023)

3. EPRI Letter MRP 2013-025, "MRP-227-A Applicability Template Guideline,"

October 14, 2013. (NRC ADAMS Accession No. ML13322A454)

June 3, 2015 PWROG-1 5039-NP PWROG-15039-NP June 3, 2015 Revision 0