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Category:Code Relief or Alternative
MONTHYEARML22123A1922022-05-10010 May 2022
Authorization of Relief Request Nos. 8 and 9 Regarding Extension of Inspection Interval for Reactor Pressure Vessel Welds
ML22069A7112022-03-16016 March 2022
Authorization of Relief Request No. 10 Regarding Use of ASME Code Case N-513-4 for Extended Period for Intake Cooling Water Discharge Piping
ML21302A0902021-10-29029 October 2021
Verbal Authorization by the Office Nuclear Regulation Relief Request No. 10 Use of ASME Code Case N-513-4 for Extended Period Not to Exceed Six Months
L-2021-107, Fifth Ten-Year Inservice Inspection Interval Revised Relief Request Nos. 8 and 9 Proposed Alternative in Accordance with 10 CFR 50.55a(z)(l), Extension of Inspection Interval for Turkey Point Units 3 and 4 Reactor Pressure2021-05-13013 May 2021
Fifth Ten-Year Inservice Inspection Interval Revised Relief Request Nos. 8 and 9 Proposed Alternative in Accordance with 10 CFR 50.55a(z)(l), Extension of Inspection Interval for Turkey Point Units 3 and 4 Reactor Pressure
ML20308A7472020-12-0707 December 2020
Withdrawal of Request for Relief Concerning Train a and B Component Cooling Water Supply and Return Piping
ML20287A5512020-11-0606 November 2020
Approval of Alternative to Use ASME Code Section XI IWA-4340 - for Repairs of Component Cooling Water System Piping
ML18106B1212018-04-25025 April 2018
Proposed Alternative to Use Encoded Phased Array Ultrasonic Examination Techniques
ML17213A8632017-08-29029 August 2017
Safety Evaluation for Relief Request No. PR-03, for the Fifth 10 Year Inservice Testing Interval Regarding Boric Acid Transfer Pump Testing Instrumentation
L-2017-121, Proposed Alternative for the Use of Encoded Phased Array Ultrasonic Examination Techniques in Lieu of Radiography2017-07-24024 July 2017
Proposed Alternative for the Use of Encoded Phased Array Ultrasonic Examination Techniques in Lieu of Radiography
ML17122A1402017-05-10010 May 2017
Safety Evaluation for Relief Request No. 5 for Fifth 10-Year Inservice Inspection Interval
ML17082A5102017-04-0606 April 2017
Verbal Authorization of Relief Request No. 5 for Repair of High Head Safety Injection Recirculation Test Line - Fifth 10-Year Inservice Inspection Interval
L-2017-050, Fifth Ten-Year Lnservice Inspection Interval Relief Request No. 52017-03-22022 March 2017
Fifth Ten-Year Lnservice Inspection Interval Relief Request No. 5
ML16330A1182016-12-15015 December 2016
NextEra Fleet - Safety Evaluation for Proposed Alternative to the American Society of Mechanical Engineers Operation and Maintenance Code by Adoption of Approved Code Case OMN-20, Inservice Test Frequency (CAC Nos. MF8195 Through MF8201)
ML16293A7782016-10-26026 October 2016
Turkey Point Nuclear Generating, Unit Nos. 3 and 4 - Safety Evaluation for Relief Request No. 4 for Fifth 10 Year Inservice Inspection Interval - Risk-Informed Inservice Inspection Program (CAC Nos. MF7277 and MF7278)
ML16047A1182016-03-0909 March 2016
Safety Evaluation for Relief Request No. 3 for Fifth 10-Year Inservice Inspection Interval - Alternative for Examination of Snubbers (CAC Nos. MF6386 and MF6387)
ML15352A1622015-12-23023 December 2015
Safety Evaluation for Relief Request No. 17, for the Fourth 10-Year Inservice Inspection Interval Regarding the Amount of Coverage Obtained During Specific Examinations
ML15328A2402015-12-11011 December 2015
Safety Evaluation for Relief Request No. 15, for the Fourth 10-Year Inservice Inspection Interval Regarding the Amount of Coverage Obtained During Specific Examinations
ML13329A1202014-01-14014 January 2014
SE for RR No. 11 for 4th 10-Year Inservice Inspection Interval - Alternative Through-Wall Sizing Requirements for Implementation of ASME Code, Section XI, Appendix V111, Supplement 10 (TAC Nos. MF1391-92)
L-2012-381, Fourth Ten-Year Interval, Relief Request No. 102012-11-13013 November 2012
Fourth Ten-Year Interval, Relief Request No. 10
L-2012-193, Concrete Containment Inservice Inspection Program, Exempt Tendon Inspection Relief Request No.72012-06-0505 June 2012
Concrete Containment Inservice Inspection Program, Exempt Tendon Inspection Relief Request No.7
ML1030502252010-11-0505 November 2010
Verbal Authorization of Relief Request No. 9, Visual Examination of Containment Liner Repair
ML0533903272005-12-0606 December 2005
Relief Request, Safety Evaluation for Temporary Non-Code Repair of Spent Fuel Pool Cooling Line
ML0520901822005-08-15015 August 2005
Relief, Regarding Mechanical Clamping Device on Pressure Boundary Piping
ML0503503632005-03-0303 March 2005
Relief Request 1, Authorization of ISI Interval
ML0428204702004-10-0606 October 2004
Safety Evaluation for Relief Requests PR-01 and PR-04
L-2004-164, ASME Section Xl Relief Requests Nos. 34 and 35 Alternative Through-Wall Sizing Requirements and Alternative Ultrasonic Examination for Reactor Flange to Upper Shell Welds2004-07-22022 July 2004
ASME Section Xl Relief Requests Nos. 34 and 35 Alternative Through-Wall Sizing Requirements and Alternative Ultrasonic Examination for Reactor Flange to Upper Shell Welds
ML0416100682004-06-0404 June 2004
Correction Ltr, RAI Regarding Fourth Interval Inservice Test Relief Requests
ML0330404922003-10-31031 October 2003
Relaxation of the Requirements of Order (EA-03-009) Regarding Reactor Pressure Vessel Head Inspections
ML0306203852003-04-25025 April 2003
Relief, Associated with Reactor Vessel Closure Head Repair
L-2003-063, ASME Section XI Relief Request No. 33, Alternative Requirements for Implementation of Appendix Viii, Supplement 102003-03-10010 March 2003
ASME Section XI Relief Request No. 33, Alternative Requirements for Implementation of Appendix Viii, Supplement 10
L-2002-085, Alternative Examination for Reactor Pressure Vessel Nozzle Inner Radius Re-submittal of Relief Request No. 252002-05-0606 May 2002
Alternative Examination for Reactor Pressure Vessel Nozzle Inner Radius Re-submittal of Relief Request No. 25
L-2002-044, Resubmittal of Code Relief Requests Nos. 30 & 31, Relief Request No. 30 Revised to Remove Reference to ASME Section IX, Paragraph QW-4242002-03-0101 March 2002
Resubmittal of Code Relief Requests Nos. 30 & 31, Relief Request No. 30 Revised to Remove Reference to ASME Section IX, Paragraph QW-424
2022-05-10
[Table view]
Category:Memoranda
MONTHYEARML23166A0042023-06-15015 June 2023
Summary of Meeting Concerning 2023 Annual Assessment of the Saint Lucie and the Turkey Point Nuclear Plants
ML22276A2302022-10-0606 October 2022
Summary of September 13, 2022, Public Meeting with FPL Concerning Supplemental Information Needed for Acceptance of License Amendment Request to Replace Instrumentation with Digital Systems on Turkey Point, Units 3 and 4
ML22238A3142022-08-0707 August 2022
Documentation of Approval for Longer Review Period for Turkey Point Digital Instrumentation and Control License Amendment Requests Acceptance Review
ML22145A3932022-05-25025 May 2022
Public Meeting Summary 2021 Annual Assessment Meeting 20220434
ML22034A3932022-02-16016 February 2022
Calendar Year 2021 Security Baseline Completion Memo
ML21159A1352021-06-0808 June 2021
Public Meeting Summary Regarding the Saint Lucie Nuclear Plant, Units 1 and 2, Docket No. 50-335 and 389, and the Turkey Point Nuclear Generating Station Units 3 and 4, Docket No. 50-250 and 50-251; Meeting Number 20210505
ML20315A2642020-12-14014 December 2020
November 5, 2020, Summary of Drop-In Meeting with Nextera-Florida Power and Light to Discuss Pending Submittals Related to Digital Instrumentation and Controls and Improved Standard Technical Specifications
ML20150A4732020-05-29029 May 2020
EOC Meeting Summary
ML19330G0542019-11-22022 November 2019
Reconciliation - Analysis of EDO Response to ACRS Ltr - Response to ACRS Report on the Safety Aspects of the SLR Application of the Turkey Point Nuclear Generating Units 3 & 4 - December 2019 Fc Meeting
ML19121A6072019-05-0101 May 2019
Summary of Public Meeting with Turkey Point Nuclear Plant to Discuss Annual Assessment of the Turkey Point Nuclear Plant with Public for Period of January 1, 2018 - December 31, 2018
ML18360A4452018-12-26026 December 2018
06/18/18 Summary of Interagency Meeting Related to Subsequent License Renewal for Turkey Point Nuclear Generating Unit Nos. 3 and 4
ML18221A2652018-08-0909 August 2018
Referral Memorandum from the Secretary to the Atomic Safety and Licensing Board Panel
ML18144A1242018-05-24024 May 2018
Summary of Public Meeting Concerning Annual Assessment of Turkey Point Nuclear Generating Station Unit 3 and Unit 4, for Period of January 1, 2017 December 31, 2017
ML18074A2522018-04-12012 April 2018
Status of Subsequent License Renewal Application
ML17082A5102017-04-0606 April 2017
Verbal Authorization of Relief Request No. 5 for Repair of High Head Safety Injection Recirculation Test Line - Fifth 10-Year Inservice Inspection Interval
ML18187A0332016-07-19019 July 2016
County Resolution to Seek a Commitment from FPL to Discontinue Use of the Cooling Canal System at the Turkey Point Power Plant
ML16097A1402016-04-0404 April 2016
March 30, 2016, Summary of Public Meeting Turkey Point Nuclear Plant
ML23333A0162016-03-0707 March 2016
Att H - MDC Report on Biscayne Bay Wq at Turkey Point CCS (March 4, 2016)-1
ML15222A5332015-08-10010 August 2015
Regulatory Audit in Support of Relief Request 1, Revised, for Fifth Ten-Year Inservice Inspection Interval
ML14156A2212014-06-0404 June 2014
Public Meeting Summary - Turkey Point Nuclear Generating Station Docket Nos. 50-250 and 50-251
ML12222A0392012-08-0909 August 2012
8/16/2012 Cancellation Notice of Forthcoming Conference Call with NextEra Energy and Florida Power and Light Concerning Generic Letter 2004-02 and Request for NRC Staff Review of Draft Proposed Guideline for Strainer Fiber Bypass Test Proto
ML12213A0612012-08-0101 August 2012
8/16/12 Forthcoming Conference Call with NextEra Energy and Florida Power & Light Concerning Generic Letter 2004-02 and Request for NRC Staff Review of Draft Proposed Guideline for Strainer Fiber Bypass Test Protocol
ML1117101092011-06-22022 June 2011
Independent Spent Fuel Storage Installation Physical Security Plan and Verification of ASM Incorporation
ML11160A0482011-06-10010 June 2011
Notice of Forthcoming Meeting with Florida Power & Light, to Discuss Turkey Point Extended Power Uprate License Amendment Request Currently Under Review
ML1107405982011-03-16016 March 2011
Notice of Forthcoming Meeting with Florida Power & Light, Turkey Point, Units 3 & 4, to Discuss Extended Power Uprate License Amendment Request That Is Currently Under Review
ML1106104272011-03-0707 March 2011
Notice of Forthcoming Pre-Application Meeting with Florida Power & Light Company and NextEra Energy Regarding Turkey Point, Units 3 and 4, St. Lucie, Units 1 and 2, Point Beach, Units 1, and 2, and Duane Arnold
ML1100704852011-02-0404 February 2011
Close-out of National Fire Protection Association Frequently Asked 07-0030 on Establishing Recovery Actions
ML1031205002010-11-10010 November 2010
Notice of Forthcoming Teleconference with Florida Power & Light to Discuss Differences Between the Turkey Point Spent Fuel Pool Criticality Analysis License Amendment Request Currently Under Review & Draft Division of Safety Systems Interim
ML1030502252010-11-0505 November 2010
Verbal Authorization of Relief Request No. 9, Visual Examination of Containment Liner Repair
ML1030100892010-11-0505 November 2010
Verbal Authorization of Relief Request No. 8, Transfer Canal Drain Line Piping Repairs
ML1025601362010-09-0707 September 2010
Notice of Meeting with Florida Power & Light Company to Discuss the Florida Power & Light Company'S Forthcoming Applications for the Extended Power Uprates of St. Lucie Units 1 & 2 and Turkey Point Units 3 & 4, Focusing on the Topic of Spen
ML1019405202010-07-14014 July 2010
Notice of Conference Call with Florida Power and Light Company to Discuss Draft Responses to NRC Requests for Additional Information for Generic Letter 2004-02
ML1018806202010-07-0808 July 2010
Notice of Forthcoming Meeting with Florida Power & Light, to Discuss with Representatives of Florida Power & Light Company (FPL) the Turkey Point, Units 3 and 4 Proposed Extended Power Uprate License Amendment Request
ML1016704282010-06-17017 June 2010
Meeting Summary Notice
ML1014501902010-05-26026 May 2010
Notice of Meeting with Florida Power & Light to Discuss the Turkey Point Alternative Source Term License Amendment Request That Is Currently Under Review
ML1009105332010-04-0505 April 2010
U.S. Nuclear Regulatory Commission Staff Review of the Department of Homeland Security Consultation Reports
ML1001900112010-01-19019 January 2010
Notice of Conference Call with Florida Power & Light Concerning Turkey Point Generic Letter 2004-02 Response
ML1000800922010-01-0808 January 2010
Notice of Meeting with Florida Power & Light - Turkey Point Units 3 and 4, to Discuss Proposed License Amendment Request to Update Turkey Point Unit 3 Spent Fuel Pool Licensing Basis
ML0934911442009-12-16016 December 2009
Summary of Category 2 Public Meeting with Nuclear Energy Institute to Discuss Health Physics Issues for New Reactors
ML0925404602009-09-10010 September 2009
Summary of Phone Call with Industry to Issues Related to Eccentricity of the Steam Generator Tube-to-Tubesheet Joints in the Finite Element Model Used for the Technical Basis of the Permanent Alternate Repair Criteria License Amendment Requ
ML0921805182009-08-0606 August 2009
Notice of Public Meeting with Florida Power & Light Energy
IR 05000250/20090032009-07-30030 July 2009
IR 05000250-09-003, 05000251-09-003, on 04/01/2009 - 06/30/2009; Turkey Point Nuclear Power Plant, Units 3 and 4; Equipment Alignment, Fire Protection, Maintenance Effectiveness, Plant Modifications, Refueling and Other Outage Activities
ML0910302212009-04-13013 April 2009
Meeting Notice, Meeting with Florida Power & Light Company Turkey Point Nuclear Plant, Units 3 and 4
ML0832502332008-12-0202 December 2008
Summary of Public Meeting with Operators of Vogtle Units 1 & 2, San Onofre Units 2 & 3, St. Lucie Unit 1, Turkey Point Unit 3, Indian Point Units 2 & 3, Nuclear Energy Institute, and Alion Science and Technology
ML0807400842008-03-14014 March 2008
Draft Regulatory Guide for Comment
ML0706400412007-03-0606 March 2007
Commitment Lists for Renewed Operating License (ROL) Plants with No Commitment Appendix Attached to Its ROL Sers/Nuregs for Use with IP-71003
ML0617805592006-07-10010 July 2006
Revised Closeout Letter for Bulletin 2003-01, Potential Impact of Debris Blockage on Emergency Sump Recirculation at Pressurized-Water Reactors.
ML0614505922006-05-26026 May 2006
Wits 200600198 - Actions to Be Taken in Response to Hurricane Lessons Learned Task Report
ML0518904892005-07-14014 July 2005
Unit 2 - Closeout Letter for Bulletin 2003-01, Potential Impact of Debris Blockage on Emergency Sump Recirculation at Pressurized-Water Reactors.
ML0506300702005-03-0202 March 2005
January Monthly Report on the Status of Open TIAs Assigned to NRR
2023-06-15
[Table view] |
Text
MEMORANDUM TO: Benjamin G. Beasley, Chief Plant Licensing Branch 11-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation FROM: Audrey L. Klett, Project Manager Plant Licensing Branch 11-2 a--------
Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
SUBJECT:
TURKEY POINT NUCLEAR GENERATING UNIT NO. 4 - VERBAL AUTHORIZATION OF RELIEF REQUEST NO. 5 FOR REPAIR OF HIGH HEAD SAFETY INJECTION RECIRCULATION TEST LINE -
FIFTH 10-YEAR INSERVICE INSPECTION INTERVAL (CAC NO. MF9459)
By letter L-2017-050 dated March 22, 2017 (Agencywide Documents Access and Management System Accession No. ML17093A457), Florida Power & Light Company (the licensee) submitted Relief Request No. 5 for the fifth 10-year inservice inspection interval at Turkey Point Nuclear Generating Unit No. 4 (Turkey Point 4). Pursuant to Title 10 of the Code of Federal Regulations (10 CFR), Paragraph 50.55a(z)(2), the licensee requested the U.S. Nuclear Regulatory Commission (NRC) to authorize an alternative to the requirements of American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code (Code),Section XI, 2007 Edition with Addenda through 2008, Subsection IWC-3130, subparagraph IWC-3132.2, because compliance with the specified requirements would result in hardship or unusual difficulty, without a compensating increase in the level of quality and safety.
On March 17, 2017, during a boric acid walkdown, the licensee observed evidence of leakage from an ASME Class 2, 3/4-inch pipe located on the Turkey Point 4 high head safety injection pump recirculation test line. The licensee observed a through-wall 3/4-inch flaw in the piping that was leaking one to two drops per minute. The licensee requested NRC authorization of a proposed alternative to the ASME Code,Section XI, 2007 Edition with Addenda through 2008, subparagraph IWC-3132.2, "Acceptance by Corrective Measures or Repair Replacement Activity," which states that a component containing relevant conditions is acceptable for continued service if the relevant conditions are corrected by a repair/replacement activity or by corrective measures to the extent necessary to meet the acceptance standards of Table IWC-3410-1. The licensee's proposed alternative is to temporarily delay ASME Code repair/replacement activities and apply the evaluation methods of ASME Code Case N-513-3, "Evaluation Criteria for Temporary Acceptance of Flaws in Moderate Energy Class 2 or 3 Piping,Section XI, Division 1," to a Class 2 safety injection system recirculation test line, with exceptions. The licensee requested to use the proposed alternative until as soon as practical after the Turkey Point 3 refueling outage, up to 90 days from the date of the request.
The licensee requested the NRC to authorize the proposed alternative to prevent a shutdown of Turkey Point 4 while a Turkey Point 3 high head safety injection pump is unavailable.
Therefore, the licensee requested verbal approval of Relief Request No. 5 for Turkey Point 4.
The NRC reviewed the licensee's submittal and determined that complying with the requirements of subparagraph IWC-3132.2 would result in hardship or unusual difficulty, without a compensating increase in the level of quality and safety and that the licensee met the regulatory requirements in 10 CFR 50.55a(z)(2). Therefore, during a conference call with the licensee on March 22, 2017, the NRC verbally authorized the licensee's use of Relief Request No. 5 for Turkey Point 4 for up to 90 days from the date of the verbal authorization. The script for the verbal authorization is enclosed. The participants on the telephone call consisted of the following:
NRC Participants Licensee Participants Benjamin Beasley Mitch Guth David Alley Stavroula Mihalakea Audrey Klett Steve Catron John Tsao Edward Neville LaDonna Suggs Sergio Chaviano Lundy Pressley This verbal authorization does not preclude the NRC staff from asking additional clarification questions regarding Relief Request No. 5 while preparing the subsequent written safety evaluation. The NRC staff's goal is to issue the written safety evaluation within 150 days from the date of the verbal authorization.
Docket No. 50-251
Enclosure:
Verbal Authorization Script
VERBAL AUTHORIZATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION FOR RELIEF REQUEST NO. 5 ALTERNATE REPAIR OF HIGH HEAD SAFETY INJECTION RECIRCULATION TEST LINE FIFTH 10-YEAR INSERVICE INSPECTION INTERVAL FLORIDA POWER & LIGHT COMPANY TURKEY POINT NUCLEAR GENERATING UNIT NO. 4 DOCKET NO. 50-251 1.0 Script read by David Alley, Chief of the Office of Nuclear Reactor Regulation's Component Performance, Non-Destructive Examination, and Testing Branch, on March 22, 2017, to the staff of Florida Power & Light Company (FPL, the licensee),
with attendance coordinated by Audrey Klett from the U.S. Nuclear Regulatory Commission (NRC)
By letter dated March 22, 2017, Florida Power & Light Company (the licensee) requested relief from certain requirements of the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code (Code),Section XI, 2007 Edition through 2008 Addenda, IWC-3132.2 at Turkey Point Nuclear Generating Unit No. 4 (Turkey Point 4).
Pursuant to Title 1O of the Code of Federal Regulations (10 CFR), Part 50, Paragraph 50.55a(z)(2), the licensee submitted Relief Request No. 5 to utilize ASME Code Case N-513-3 to demonstrate structural integrity and accept a flaw by analysis in a nonmoderate energy system on the basis that compliance with the specified ASME requirements would result in hardship or unusual difficulty, without a compensating increase in the level of quality and safety.
On March 17, 2017, the licensee observed leakage from the 3/4-inch diameter, stainless steel high head safety injection recirculation test line. The licensee proposed to use ASME Code Case N-513-3 to disposition the circumferential through wall flaw in the subject pipe. The licensee's proposed alternative is to leave the flaw that caused the leakage in place having demonstrated the structural integrity of the piping and proposing periodic monitoring in accordance with Code Case N-513-3.
To demonstrate the structural integrity of the subject pipe, the licensee performed a flaw evaluation using the method in the ASME Code,Section XI, Appendix C, as specified in Code Case N-513-3. The licensee calculated an allowable flaw length of approximately 1.4 inches.
The current through wall flaw length is 3/4 inches. The licensee will perform daily visual walkdowns and penetrant tests every 30 days to monitor the crack growth in accordance with Code Case N-513-3. The licensee stated that if the monthly measurement increases from the present by 1/16-inch in either direction (allowing 1/16-inch for measurement uncertainty), then the growth rate will be reexamined to verify the structural analysis conclusions.
The NRC staff finds that the licensee has used the appropriate loading, considering various pressure and temperature conditions in its flaw evaluation. The NRC staff determines that the Enclosure
current flaw length has sufficient margin before reaching the allowable flaw length. The NRC staff notes that the licensee will perform required periodic monitoring of the flaw and has implemented a threshold of 1/16-inch to initiate corrective actions.
The NRC staff finds that the licensee's proposed flaw evaluation and periodic monitoring provide reasonable assurance of the structural integrity of the subject pipe for the duration of the request.
2.0 Script read by Benjamin G. Beasley, Chief of the Office of Nuclear Reactor Regulation's Plant Licensing Branch 11-2 As Chief of the Plant Licensing Branch 11-2 in the Office of Nuclear Reactor Regulation, I concur with the Component Performance, Non-Destructive Examination, and Testing Branch's conclusions.
The NRC staff has determined that complying with the ASME Code requirement would result in a hardship or unusual difficulty, without a compensating increase in the level of quality and safety. Furthermore, the NRC staff has determined that the proposed Relief Request No. 5 provides reasonable assurance of structural integrity of the subject piping. Accordingly, the NRC staff concludes that the licensee has adequately addressed all of the regulatory requirements set forth in 10 CFR 50.55a(z)(2). Effective March 22, 2017, the NRC staff authorizes the use of Relief Request No. 5 at Turkey Point Unit 4 for up to 90 days from the date of this authorization.
All other requirements of ASME Code,Section XI for which relief or a proposed alternative was not specifically requested and authorized by the NRC remain applicable, including the third party review by the Authorized Nuclear lnservice Inspector.
This verbal authorization does not preclude the NRC staff from asking additional clarification questions regarding Relief Request No. 5 while preparing the subsequent written safety evaluation. The NRC staff's goal is to issue the written safety evaluation within 150 days from the date of this verbal authorization.
SUBJECT:
TURKEY POINT NUCLEAR GENERATING UNIT NO. 4 - VERBAL AUTHORIZATION OF RELIEF REQUEST NO. 5 FOR REPAIR OF HIGH HEAD SAFETY INJECTION RECIRCULATION TEST LINE- FIFTH 10-YEAR INSERVICE INSPECTION INTERVAL (CAC NO. MF9459)
DATED APRIL 3, 2017 DISTRIBUTION:
Public LPL2-2 R/F RidsNrrPMTurkeyPoint RidsNrrLABClayton RidsNrrDorlLpl2-2 RidsNrrDeEpnb RidsRgn2MailCenter JTsao, NRR LPressley, R-11 LSuggs, R-11 ADAMS A ccess1on No.: ML17082A510 *b1yema1*1 OFFICE NRR/DORL/LPL2-2/PM NRR/DORL/LPL2-2/LA NRR/DE/EPNB/BC* NRR/DORL/LPL2-2/BC NAME AKlett BClayton DAiiey BBeasley (LRonewicz for)
DATE 04/3/2017 03/31/2017 03/23/2017 04/5/2017 OFFICE NRR/DORL/LPL2-2/PM NAME A Klett DATE 04/6/2017 OFFICIAL RECORD COPY
