ML081090473
| ML081090473 | |
| Person / Time | |
|---|---|
| Site: | Pilgrim |
| Issue date: | 04/15/2008 |
| From: | Entergy Nuclear Operations |
| To: | NRC/SECY/RAS |
| SECY RAS | |
| References | |
| 50-293-LR, ASLBP 06-848-02-LR, Pilgrim-Exhibit-9, RAS J-39 | |
| Download: ML081090473 (4) | |
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April 15, 2008 (10:00am) OFFEREDby:i "-t/ ""-- Inte rvenor" .. *---- '" ' C, NRC r OFFICE OF SECRETARY IDENTIFIED on_ '09 .<....anel Pilgrim Nuclear Power Station RULEMAKINGS AND License Renewal Application ADJUDICATIONS STAFF AltoioTa*len: q _ý.5p REJECTED Wf Licen Technical Information F.-di~i Thd~x'lui APPENDIX A UPDATED FINAL SAFETY ANALYSIS REPORT SUPPLEMENT TABLE OF CONTENTS A.0 INTRODUCTION ....................................... A-1 A.1 CHANGES TO EXISTING UFSAR INFORMATION ........................ A-2 A.1.1 UFSAR Chapter 3 Changes ..................................... A-2 A. 1.2 UFSAR Chapter 4 Changes ..................................... A-3 A.1.3 UFSAR Chapter 6 Changes ..................................... A-7 A.1.4 UFSAR Chapter 7 Changes ..................................... A-7 A.1.5 UFSAR Appendix C Changes ................................... A-8 A.1.6 UFSAR Appendix M Changes ................................... A-12 A.2 NEW UFSAR SECTION .............................................. A-13 A.2.0 Supplement for Renewed Operating License ........................ A-13 A.2.1 Aging Management Programs and Activities ........................ A-13 A.2.1.1 Boraflex Monitoring Program ......................... .. A-13 A.2.1.2 Buried Piping and Tanks Inspection Program ............... A-14 A.2.1.3 BWR CRD Return Line Nozzle Program ................... A-14 A.2.1.4 BWR Feedwater Nozzle Program ........................ A-14 A.2.1.5 BW R Penetrations Program ............................ A-14 A.2.1.6 BWR Stress Corrosion Cracking Program .................. A-15 A.2.1.7 BWR Vessel ID Attachment Welds Program ................ A-15 A.2.1.8 BWR Vessel Internals Program .......................... A-15 A.2.1.9 Containment Leak Rate Program ........................ A-15 A.2.1.10 Diesel Fuel Monitoring Program ......................... A-16 A.2.1.11 Environmental Qualification (EQ) of Electric Components Program A-16 A.2.1.12 Fatigue Monitoring Program ............................ A-16 A.2.1.13 Fire Protection Program ................................ A-16 A.2.1.14 Fire W ater System Program ............................ A-17 Appendix A Updated Final Safety Analysis Report Supplement Page A-1
Pilgrim Nuclear Power Station License Renewal Application Technical Information A.0 INTRODUCTION This appendix provides the information to be submitted in an Updated Final Safety Analysis Report Supplement as required by 10 CFR 54.21(d) for the Pilgrim Nuclear Power Station (PNPS) License Renewal Application (LRA). The LRA contains the technical information required by 10 CFR 54.21(a) and (c). Appendix B of the PNPS LRA provides descriptions of the programs and activities that manage the effects of aging for the period of extended operation.
Section 4 of the LRA documents the evaluations of time-limited aging analyses for the period of extended operation. Appendix B and Section 4 have been used to prepare the program and activity descriptions for the PNPS Updated Final Safety Analysis Report (UFSAR) Supplement information in this appendix.
This appendix is divided into two parts. The first part identifies changes to the existing sections of the UFSAR related to license renewal. The second part provides new information to be incorporated into the UFSAR. The information presented in both parts will be incorporated into the UFSAR following issuance of the renewed operating license. Upon inclusion of the UFSAR Supplement in the PNPS UFSAR, future changes to the descriptions of the programs and activities will be made in accordance with 10 CFR 50.59.
Pilgrim Nuclear Power Station License Renewal Application Technical Information A.2 NEW UFSAR SECTION The following information will be integrated into the UFSAR to document aging management programs and activities credited in the PNPS license renewal review and time-limited aging analyses evaluated for the period of extended operation. References to other sections are to UFSAR sections, not to sections in the LRA.
A.2.0 Supplement for Renewed Operating License The Pilgrim Nuclear Power Station license renewal application (Reference A.2-1) and information in subsequent related correspondence provided sufficient basis for the NRC to make the findings required by 10 CFR 54.29 (Final Safety Evaluation Report) (Reference A.2-2). As required by 10 CFR 54.21(d), this UFSAR supplement contains a summary description of the programs and activities for managing the effects of aging (Section A.2.1) and a description of the evaluation of time-limited aging analyses for the period of extended operation (Section A.2.2). The period of extended operation is the 20 years after the expiration date of the original operating license.
A.2.1 Aging Management Programs and Activities The integrated plant assessment for license renewal identified aging management programs necessary to provide reasonable assurance that components within the scope of license renewal will continue to perform their intended functions consistent with the current licensing basis (CLB) for the period of extended operation. This section describes the aging management programs and activities required during the period of extended operation. All aging management programs will be implemented prior to entering the period of extended operation.
PNPS quality assurance (QA) procedures, review and approval processes, and administrative controls are implemented in accordance with the requirements of 10 CFR 50, Appendix B. The Entergy Quality Assurance Program applies to safety-related structures and components.
Corrective actions and administrative (document) control for both safety-related and nonsafety-related structures and components are accomplished per the existing PNPS corrective action program and document control program and are applicable to all aging management programs and activities that will be required during the period of extended operation. The confirmation process is part of the corrective action program and includes reviews to assure that proposed actions are adequate, tracking and reporting of open corrective actions, and review of corrective action effectiveness. Any follow-up inspection required by the confirmation process is documented in accordance with the corrective action program.
A.2.1.1 Boraflex Monitoring Program The Boraflex Monitoring Program assures that degradation of the Boraflex panels in the spent fuel racks does not compromise the criticality analysis in support of the design of the spent fuel storage racks. The program relies on (1) neutron attenuation testing, (2) determination of boron loss through correlation of silica levels in spent fuel pool Appendix A Updated Final Safety Analysis Report Supplement Page A-13
Pilgrim Nuclear Power Station License Renewal Application Technical Information water samples and periodic areal density measurements, and (3) analysis of criticality to assure that the required 5% subcriticality margin is maintained.
A.2.1.2 Buried Piping and Tanks Inspection Program The Buried Piping and Tanks Inspection Program includes (a) preventive measures to mitigate corrosion and (b) inspections to manage the effects of corrosion on the pressure-retaining capability of buried carbon steel, stainless steel, and titanium components. Preventive measures are in accordance with standard industry practice for maintaining external coatings and wrappings. Buried components are inspected when excavated during maintenance. If trending within the corrective action program identifies susceptible locations, the areas with a history of corrosion problems are evaluated for the need for additional inspection, alternate coating, or replacement.
A focused inspection will be performed within the first 10 years of the period of extended operation, unless an opportunistic inspection (or an inspection via a method that allows assessment of pipe condition without excavation) occurs within this ten-year period.
A.2.1.3 BWR CRD Return Line Nozzle Program Under the BWR CRD Return Line Nozzle Program, PNPS has cut and capped the CRD return line nozzle to mitigate cracking and continues inservice inspection (ISf) examinations to monitor the effects of crack initiation and growth on the intended function of the control rod drive return line nozzle and cap, ISI examinations include ultrasonic inspection of the nozzle-to-vessel weld and ultrasonic inspection of the dissimilar metal weld overlay at the nozzle.
A.2.1.4 BWR Feedwater Nozzle Program Under the BWR Feedwater Nozzle Program, PNPS has removed feedwater blend radii flaws, removed feedwater nozzle cladding, and installed a triple-sleeve-double-piston sparger to mitigate cracking. This program continues enhanced inservice inspection (ISI) of the feedwater nozzles in accordance with the requirements of ASME Section XI, Subsection IWB and the recommendation of General Electric (GE) NE-523-A71-0594 to monitor the effects of cracking on the intended function of the feedwater nozzles.
A.2.1.5 BWR Penetrations Program The BWR Penetrations Program includes (a) inspection and flaw evaluation in conformance with the guidelines of staff-approved boiling water reactor vessel and internals project (BWRVIP) documents BWRVIP-27 and BWRVIP-49 and (b) monitoring and control of reactor coolant water chemistry in accordance with the guidelines of BWRVIP-130 to ensure the long-term integrity of vessel penetrations and nozzles.
Appendix A Updated Final Safety Analysis Report Supplement Page A-14