ML12335A492

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Official Exhibit - NYS000352-00-BD01 - Entergys Submission to the ASLB Conveying Entergys NL-10-082 Communication to NRC Staff (Aug. 9, 2010) Re Indian Point License Renewal Application Commitment 33, Fatigue Monitoring Program (Aug. 10, 20
ML12335A492
Person / Time
Site: Indian Point  Entergy icon.png
Issue date: 08/10/2010
From: Sutton K
Morgan, Morgan, Lewis & Bockius, LLP
To: Lathrop K, Lawrence Mcdade, Richard Wardwell
Atomic Safety and Licensing Board Panel
SECY RAS
References
RAS 21620, 50-247-LR, 50-286-LR, ASLBP 07-858-03-LR-BD01
Download: ML12335A492 (31)
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Text

United States Nuclear Regulatory Commission Official Hearing Exhibit In the Matter of:

Entergy Nuclear Operations, Inc.

(Indian Point Nuclear Generating Units 2 and 3)

ASLBP #: 07-858-03-LR-BD01 Docket #: 05000247 l 05000286 Exhibit #:

Identified:

Admitted:

Withdrawn:

Rejected:

Stricken:

Other:

NYS000352-00-BD01 10/15/2012 10/15/2012 NYS000352 Submitted: December 22, 2011 c.\\.t.p.R REGU{.q""

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0-Morgan, Lewis & Bockius LLP 1111' Pennsylvania Avenue, NW Washington, DC 20004 Tel: 202.739.3000 Fax: 202.739.3001 www.morganlewis.com Kathryn M. Sutton Partner 202.739.5738

.. ksutton@morganlewis.com

. PaulM. Bessette

. Partner 202.739.5796 pbessette@morganlewis.com August 10;2010

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Lawrence G.*McDade, Chairman Dr. Richard E. Wardwell Dr. Kaye D.Lathrop Atomic Safety.and Licensing Board U.S. Nuclear Regulatory Commission Washington, DC 20555-0001 Morgan Lewis C 0 U N S E LOR S. A T L A* W DOCKETED USNRC.

August 11, 2010 (8:30a.m.)

OFFICE OF SECRETARY RUlEMAKINGS AND ADJUDICATIONS STAFF Docket:

Entergy Nuclear Operations, Inc. (Indian Point Nuclear Generating Units 2 and 3), Docket Nos. 50-247-LR and 50-286-LR RE:

Notification of Entergy's Submittal Regarding Completion of Commitment 33 for Indian Point Units 2 and 3

Dear Administrative Judges:

Entergy Nuclear Operations, Inc. ("Entergy") is providing this notice to the Atomic Safety and Licensing Board and the parties regarding Entergy' s August 9, 2010 submittal of a.

notice)o the U.S. Nuclear Regulatory Commission ("NRC") regarding completion of Commitment 33 to the Indian Point Units 2 and 3 License Renewal Application associated with the Fatigue Monitoring Program. See NL-1 0-082, Letter from Fred Dacimo, Entergy, to NRC Document Control Desk, "License Renewal Application - Completion of Commitment #33 Regarding the Fatigue Monitoring Program" (August 9, 2010). A copy ofNL-10-082 is attached for your reference. Counsel is providing this notification insofar as the completion of Commitment 33 may be relevant and material to admitted contentions NYS-26/26A and Riverkeeper TC-111A.

OAGI0001230_00001

Lawrence G. McDade, Chairman Dr. Richard E. Wardwell Dr. Kaye D. Lathrop August 10, 2010 Page 2 CBM/als Attachment cc:Service List Respectfully submitted, "JuJk<f!-:tr Kathryn M. Sutton, Esq.

Paul M. Bessette, Esq.

Morgan Lewis COUNSELORS AT LAW Counsel for EntergyNuclear Operations, Inc.

OAGI0001230 00002

'r UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION

. BEFORE THE ATOMIC SAFETY AND LICENSING BOARD In the Matter of.

)

Docket Nos.

50-247-LR and 286-LR

)

ENTERGY NUCLEAR OPERATIONS, INC.

' )

)

(Indian Point Nuclear Generating Units 2 and 3)

)

)

August 10,2010 CERTIFICATE OF SERVICE I hereby certify that copies of the letter entitled "Notification of Entergy's Submittal Regarding Completion of Commitment 33 for Indian Point Units 2 and 3," dated August 10,

. 2010, were served this 10th day of August, 2010 upon the persons listed below, by first class mail and e-mail as shown below.

Administrative Judge Lawrence G: McDade, Chair Atomic Safety and Licensing Board Panel Mail Stop: T-3 F23 '

U.S. Nuciear Regulatory Commission Washington, DC 20555-0001 (E-mail: 19m1@nrc.gov)

Administrative Judge Richard E. Wardwell Atomic Safety and Licensing Board Panel Mail Stop: T-3 F23 U.S. Nuclear Regulatory Commission Washington, DC 20555-0001 (E-mail: rew@nrc.gov)

Office of Commission Appellate Adjudication U.S. Nuclear Regulatory Commission Mail Stop: 0-16G4 Washington, DC 20555-0001 (E-mail: ocaamail@nrc.gov)

Administrative Judge Kaye D. Lathrop Atomic Safety and Licensing Board Panel 190 Cedar Lane E.

Ridgway, CO 81432 (E-mail: kdI2@nrc.gov)

Office of the Secretary*

Attn: Rulemaking and Adjudications Staff u.s. Nuclear Regulatory Commission Washington, D.C. 20555-0001 (E-mail: hearingd6cket@nrc.gov)

Josh Kirstein, Law Clerk Atomic Safety and Licensing Board Panel Mail Stop: T-3 F23 U.S. Nuclear Regulatory Commission Washington, DC 20555-0001 (E-mail: losh.Kirstein@nrc.gov)

OAGI0001230 00003

Page 2 Sherwin E. Turk, Esq.

Beth N. Mizuno, Esq.

David E. Roth, Esq.

Brian G. Harris, Esq.

Andrea Z. Jones, Esq.

Office of the General Counsel Mail Stop: 0-15 D21 U.S. Nuclear Regulatory Commission Washington, DC 20555-0001 (E-mail: set@nrc.gov)

(E-mail: bnml@nrc.gov)

(E-mail: david.roth@nrc.gov)

(E-mail: brian.harris@,nrc.gov)

(E-mail: andrea.jones@nrc.gov)

Manna J 0 Greene Enviromnental Director Hudson River Sloop Clearwater, Inc.

724 Wolcott Avenue Beacon, NY 12508 (E-mail: manna j o@,clearwater.org)

Stephen C. Filler, Board Member Hudson River Sloop Clearwater, Inc.

303 South Broadway, Suite 222 Tarrytown, NY 10591 (E-mail: sfil1er@nylawline.com)

Ross Gould, Member Hudson River Sloop Clearwater, Inc.

10 Park Avenue, #5L New York, NY 10016 (E-mail: rgouldesq@gmai1.com)

Greg Spicer, Esq.

Office of the Westchester County Attorney 148 Martine Avenue, 6th Floor White Plains, NY 10601 (E-mail: gssl@westchestergov.com )

Thomas F. Wood, Esq.

Daniel Riesel, Esq.

Ms. Jessica Steinberg, J.D.

Sive, Paget & Riesel, P.C.

460 Park Avenue New York, NY 10022 (E-mail: driesel@sprlaw.com)

(E-mail: jsteinberg@sprlaw.com)

John Louis Parker, Esq.

Regional Attorney Office of General Counsel, Region 3 NYS Dept. of Enviromnental Conservation 21 S. Putt Comers Road New Paltz, New York 12561-1620 (E-mail: jlparker@.gw.dec.state.ny.us)

Michael J. Delaney, V.P. - Energy New York City Economic Development Corp.

110 William Street New York, NY 10038 (E-mail: mdelaney@nycedc.com)

OAGI0001230 00004

Page 3 Phillip Musegaas, Esq.

Deborah Brancato, Esq.

Riverkeeper, Inc.

828 South Broadway Tarrytown, NY 10591 (E-mail: phillip@riverkeeper.org)

(E-mail: dbrancato@riverkeeper.org)

Robert D. Snook, Esq.

Assistant Attorney General Office of the Attorney General State of Connecticut 55 Elm Street P.O. Box 120 Hartford, CT 06141-0120 (E-mail: Robert.Snook@po.state.ct.us)

Andrew M.Cuomo, Esq.

Attorney General of the State of New York John J. Sipos, Esq.

Charlie Donaldson Esq.

Assistants Attorney General The Capitol Albany, NY 12224-0341 (E-mail: john.sipos@oag.state.ny.us)

Joan Leary Matthews, Esq.

Senior Attorney for Special Projects Office of the General Counsel New York State Department of Environmental Conservation 625 Broadway, 14th Floor Albany, NY 12207 (E-mail: jlmatthe@gw.dec.state.ny.us )

Daniel E. O'Neill, Mayor James Siermarco, M.S.

Liaison to Indian Point Village of Buchanan MUnicipal Building 236 Tate Avenue Buchanan, NY 10511-1298 (E-mail: vob@bestweb.net)

Mylan L. Denerstein, Esq.

Executive Deputy Attorney General, Social Justice Office of the Attorney General of the State of New York 120 Broadway, 25th Floor New York, New York 10271 (E-mail: Mylan.Denerstein@oag.state.ny.us).

Janice A. Dean Office of the Attorney General of the State of New York Assistant Attorney General 120 Broadway, 26th Floor New York; New York 10271 (E-mail: Janice.Dean@oag.state.ny.us)*

OAGI0001230 00005

Page 4

  • Original and 2 copies provided to the Office Oft/secretary.

!~

. Paul M. Bessette, Esq.

Counsel for Entergy Nuclear Operations, Inc.

DB 1/65420875. 1 OAGI0001230 00006

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Entergy Nuclear Northeast Iridian Point Energy Center 450 Broadway, GSB P.O. Box 249 Buchanan, N.Y. 10511-0249 Tel (914) 788-2055-Fred Dacimo Vice President License Renewal NL-10-082 August 9, 2010 ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555-0001

SUBJECT:

License Renewal Application - Completion of Commitment#33 Regarding the Fatigue Monitoring Program Indian Point Nuclear Generating Unit Nos. 2 and 3 Docket Nos. 50-247 and 50-286 License Nos. DPR-26 and DPR-64 REFERENCE

1. Entergy Letter dated April 23, 2007, F. R. Dacimo to Document Control Desk, "License Renewal Application" (NL-07 -039)
2. Entergy Letter dated April 23, 2007, F. R. Dacimo to Document Control Desk, "License Renewal Application Boundary Drawings (NL-07-040)
3. Entergy Letter dated April 23,2007, F. R. Dacimo to Document Control Desk, "License Renewal Application Environmental Report

. References (Nt-07 -041)

4. Entergy Letter dated October 11,2007, F. R, Dacimo to Document Control Desk, "License Renewal Application (LRA)" (NL-07-124)
5. Entergy Letter November 14, 2007, F. R, Dacimo to Document Control Desk, "Supplement to License Renewa'l Application (LRA)

Environmental Report References" (NL-07-133)

Dear Sir or Madam:

In the referenced letters, Entergy Nuclear Operations, Inc. applied for renewal of the Indian Point Energy Center operating license. This letter contains information supporting the completion of commitment 33 to the License Renewal Application regarding the Fatigue Monitoring Program.

OAGI0001230 00007

Nl-10-082 Docket Nos. 50-247 and 50-286 Page 2 of 2 There are no new commitments identified in this submittal. If you have any questions, or require additional information, please contact Mr. Robert Walpole at 914-734-6710.

Sincerely,

!3J~

FD/mb Attachments:

1.
2.

Environmental Fatigue Evaluations List of Regulatory Commitments cc:

Mr. S. J. Collins, Regional Administrator, NRC Region I Mr. J. Boska, Senior Project Manager, NRC, NRR, DORl Mr. SherWin E. Turk, NRC Office of General Counsel, Special Counsel Ms. Kimberly Green, NRC Safety Project Manager*

NRC Resident Inspectors Office, Indian Point Mr. Paul Eddy, NYS Dept. of Public Service Mr. Francis J. Murray, Jr., President and CEO, NYSERDA OAGI0001230 00008

ATTACHMENT 1 TO NL-10-082 Environmental Fatigue Evaluations ENTERGY NUCLEAR OPERATIONS, INC INDIAN POINT NUCLEAR GENERATING UNITS 2 AND 3 DOCKET NOS. 50-247 & 50-286 OAGI0001230 00009

. NL-10-082 Docket Nos. 50-247 and 50-286 Page 1 of 4 INDIAN POINT NUCLEAR GENERATING UNIT NOS. 2 AND 3 LICENSE RENEWAL APPLICATION ENVIRONMENTAL FATIGUE EVALUATIONS Environmental Fatigue Evaluation for Indian Point Unit 2 and Unit 3 Entergy has applied*for renewed operating licenses for Indian Point Nuclear Generating Unit 2 and Unit 3 (IP2 and IP3). In the license renewal application, Entergy committed to address environmentally assisted fatigue. Entergy's commitment, amended by letter, NL-08-021, dated January 22, 2008, reads as follows.

At least 2 years prior to entering the period of extended operation, for the locations identified in LRA Table 4.3-13 (IP2) and LRA Table 4.3-14 (IP3), under the Fatigue Monitoring Program, IP2 and IP3 will implement one or more of the following:

(1) Consistent with the Fatigue Monitoring Program, Detection of Aging Effects, update the fatigue usage calculations using refined fatigue analyses to determine valid CUFs less than 1.0 when accounting for the effects of reactor water environment. This includes applying the appropriate Fen factors to valid CUFs determined in accordance with one of the following:

I. For locations in LRA Table 4.3-13 (IP2) and LRA Table 4.3-14 (IP3), with existing fatigue analysis valid for the period of extended operation, use the existing CUF.

2. Additional plant-specific locations with a valid CUF may be evaluated~ In particular, the pressurizer lower shell will be reviewed to ensure the surge nozzle remains the limiting component.
3. Representative CUF values from other plants, adjusted to or enveloping the IPEC plant specific exte rnC). I loads may be used if demonstrated applicable to IPEC.
4. An analysis using an NRC-approved version of the ASME code or NRC-approved alternative (e.g., NRC-approved code case) may be performed to determine a valid CUF.

(2) Consistent with the Fatigue Monitoring Program, Corrective Actions, repair or replace the affected locations before exceeding a CUF of 1.0.

Entergy has updated the fatigue usage calculations using refined fatigue analyses to determine CUFs when accounting for the effects of reactor water environment. This includes applying the appropriate Fen factors to valid CUFs for the locations shown in LRA Table 4.3-13 and LRA Table 4.3-14.

The tables from the LRA are repeated as follows with the updated CUF values inserted.

The results of the refined analyses are shown in the tables as underlined values.

OAGI0001230 00010

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Table 4.3-13, NL-l0-082 Docket Nos. 50-247 and 50-286 Page 2 of 4, IP2Cumuiative Usage Factors for NUREG/CR-6260 Limiting Locations Per NUREGlCR*6583 or NUREG-6260 Generic IP2 Plant*

Material

. CUF of NUREGlCR-5704 location Specific Type..

Record location Fen Envlronmentall y Adjusted CUF

.1 Vessel shell and Bottom head to lower head shell LAS 0.004 2.45 0.01 2

Vessel inlet and Reactor vessel outlet nozzles inlet nozzle LAS 0.05 2.45.

0.12 2

Vessel inlet and Reactor vessel LAS outlet nozzles outlet nozzle 0.281 2.45 0.69 3

Pressurizer surge Pressurizer.

(},2e4 2A6 M46 line nozzles surge line LAS*

0.109 noZzle 1.74 0.188 3

Pressurizer surge Surge line piping g,.e

~

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lilie piping to safe end weld SS 0.062 13.26 0.822 4

RCS piping Charging system Q...99

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charging system nozzle SS nozzle 0.0323 8.7 0.2809 5

RCS piping safety NA NA:i

~

NA2 injection nozzle SS 0.1083 7.8975 0.8553 6

RHR Class 1 piping NA NA:i

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NA2 SS Q.Qm.

1M.6.

0.9434 OAGI0001230 00011

1 2

2 3

3 4

5 6

Table 4.3-14 NL-10-082 Docket Nos. 50-247 and 50-286 Page 3 of 4 IP3.Cumulative'Usage Factors for NUREGlCR-6260 Limiting Locations Per NUREGlCR-6583 or IP3 Plant-Material

. CUFot NUREGlCR-5704 NUREG-6260 Location Specific Location Type Record Fen Environmentally Adjusted CUF Vessel shell and lower Bottom head to head shell LAS 0.02 2.45 0.05 Vessel inlet and outlet Reactor vessel 2.45 nozzles inlet nozzle LAS 0.049 0.12 Vessel inlet and outlet Reactor vessel nozzles outlet nozzle LAS 0.259 2.45 0.64 Pressurizer surge line Pressurizer surge

~ 2-:4&

~

nozzles line nozzle LAS 0.0903 '

1.74 0.157 Pressurizer surge line Surge line piping o;e

~

9-:2+

piping to safe end weld SS 0.0411 14.45 0.594 RCS piping charging NA NAa

~

NAa system nozzle SS 0.1812 3.98 0.722 RCS piping safety NA NAa

~

NAa injection nozzle SS 0.1709 5.0117 0.8565 RHR Class 1 piping

,NA SS NAa

~

NAa 0.1279 7.79 0.9961

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OAGI0001230 00012

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NL-10-082 Docket Nos. 50-247 and 50-286 Page 4 of 4,.

As described in LAA Section 4.3.3 and shown in Tables 4.3-13 and 4.3-14, the CUFs for the reactor vessel locations were not changed. The evaluation documented in the LRA used bounding Fens applied to the CUFs of record fo(the bottom head to shell region, the reactor vessel inlet nozzle and the reactor vessel outlet nozzle. The tables show the Cumulative Usage Factors are all below 1.0 for these three locations for both units.

The stress and fatigue evaluations for the remaining piping components listed in Table 4.3-13 and 4.3-14 were performed using standard methods of the ASME Code, Section til. Detailed stress models of the surge line hot leg nozzle, pressurizer surge nozzle, reactor coolant piping charging system nozzle, reactor coolant piping safety injection nozzle, and the AHA system

, class*1 piping locations were prepared. The analyst developed detailed stress history inputs for all transients considered in the evaluation, which were subsequently used to provide detailed inputs used in the EAF evaluations. The ASME Code evaluations were performed for the piping components to reduce conservatism in the analyses or because the current licenSing basis (CLB) qualification was to the ANSI 831.1 Power Piping Code, which did not require a fatigue usage factor calculation. The evaluations were limited to the stress qualifications related tothe fatigue requirements of the ASME Code. The primary stress qualifications documented in the CLB remain applicable for the components evaluated.

The evaluation of EAF was accomplished through the application of Fen factors, as described in NUREG/CR~5704 for the stainless steels in the pressurizer surge line, the reactor coolant piping charging and safety injection system nozzles, and the RHA system Class 1-piping. In addition, Fen factors for the pressurizer surge nozzle dissimilar metal weld also considered the carbon steel factors in NUREG/CR-6583. The Fen factors are calculated based on detailed inputs described in the applicable NUREG and are directly applied tothe ASME Code fatigue results.

The refined fatigLie analyses of the Indian Point Unit 2 and Unit 3 piping locations corresponding to the locations identified in NUREG/CR-6260 for older vintage Westinghouse plants demonstrate that cumulative fatigue usage factors including consideration of reactor water environmental effects are below a value of 1.0 for transients postulated for 60 years of operation.

The results of this evaluation resolve commitment number33 in the NRC Safety Evaluation Aeport on license renewal for Indian Point Nuclear Generating Unit 2 and Unit 3.

OAGI0001230 00013

ATTACHMENT 2 TO-NL-l0-082 List of Regulatory Commitments ENTERGY NUCLEAR OPERATIONS, INC INDIAN POINT NUCLEAR GENERATING UNITS 2 AND 3 DOCKET NOS, 50-247 & 50-286 _

OAGI0001230 00014

1 2

. Attachment 2 NL-10-082 Docket Nos. 50-247 and 50-286 Page 1 of17 _.

List of Regulatory Commitments Rev. 12 The following table identifies those actions committed to by Entergy in this document.

Changes are shown as strikethroughs for deletiens and underlines for additions.

. COMMITMENT IMPLEMENTATION SOURCE SCHED.ULE Enhance the Aboveground Steel Tanks Program for IP2:

NL-07-039 Iseptember 28, IP2 and IP3 to perform thickness measurements of 12013 the bottom surfaces of the condensate storage tanks, city water tank, and fire water tanks once during the IP3:

first ten years of the period of extended operation.

December 12, Enhance the Aboveground Steel Tanks Program for 12015 IP2 and IP3 to require trending of thickness measurements when material loss is detected.

Enhance the Bolting Integrity Program for IP2 and IP3 IP2:

NL~07-039

~eptember 28, to clarify that actual yield strength is used in selecting

~013 materials for low susceptibility to sec and clarify the prohibition on use of lubricants containing MoS2 for IP3:

NL-07-153 bolting.

December 12, The Bolting Integrity Program manages loss of 2015 preload and loss of material for all external boltino.

RELATED LRASECTION I AUDIT ITEM A.2.1.1 A.3.1.1 B.1.1 A.2.1.2 A.3.1.2 B.1.2 Audit Items 201,241,.

270 OAGI0001230 00015

COMMITMENT 3

Implement the Buried Piping and Tanks Ihspection Program for IP2 and IP3 as described in LRA Section B.l.6.

This new program will be implemented consistent with the corresponding program described in NUREG-1801 Section XI,M34, Buried Piping and Tanks Inspection.

Include in the Buried Piping and Tanks Inspection Program described in LRA Section B.l.6 a risk assessment of in-scope buried piping and tanks that includes consideration of the impacts of buried piping or tank leakage and of conditions affecting the risk for corrosion. Classify pipe segments and tanks as having a high, medium or low impact of leakage based on the safety class, the hazard posed by fluid contained in the piping and the impact of leakage on reliable plant operation. Determine corrosion risk through consideration of piping or tank material, soil resistivity, drainage, the presence of cathodic protection and the type of coating. Establish inspection priority and frequency for periodic inspections of the in-scope piping and tanks based on the results of the risk assessment. Perform inspections using inspection techniques with demonstrated effectiveness.

NL-l0-082 Docket Nos. 50-247 and 50-286 Page 2 of 17,

IMPLEMENTATION SOURCE RELATED SCHEDULE LRASECTION I AUDIT ITEM IP2:

NL-07-039 A.2.1.5

!September 28, A.3.1.5

~013 B.l.6 NL-07-153 Audit Item IP3:

173 December 12, 12015 NL-09-106 NL-09-111 OAGI0001230 00016

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COMMITMENT 4

Enhance the Diesel Fuel Monitoring Program to include cleaning and inspection of the IP2 GT-1 gas turbine fuel oil storage tanks, IP2 and IP3 E;DGfuel oil, day tanks, IP2 SSO/Appendix R diesel generator fuel oil day tank, and IP3 AppendixR fuel oil storage tank and day tank once every ten years.

Enhance the Diesel Fuel Monitoring Program to include quarterly sampling and analysis of the IP2 SSO/Appendix R diesel generator fuel oil day tank, IP2 security diesel fuel oil storage tank, IP2'security diesel fuel oil day tank, and IP3 Appendix R fuel oil storage tank. Particulates, water and sediment checks will be performed on the samples. Filterable solids acceptance criterion will be less than or equal to 10mg/1. Water and sediment acceptance criterion will be less than or equal to 0.05%.*

Enhance the Diesel Fuel Monitoring Program to include thickness measurement of the bottom of the following tanks. once every ten years. IP2: EDG fuel oil storage tanks, EDG fuel oil day tanks, SSO/Appendix R diesel generator fuel oil day tank, GT-1 gas turbine fuel oil storage tanks, and diesel fire pump fuel oil storage tank; I P3: EDG fuel oil day tanks, EDG fuel oil storage tanks, Appendix R fuel oil storage tank, and diesel fire pump fuel oil storage tank.

Enhance the Diesel Fuel Monitoring Program to change the analysis for water and,particulatesto a quarterly frequency for the following tanks. IP2: GT-1 gas turbine fuel oil storage tanks and diesel fire pump fuel oil storage tank; IP3: Appendix R fuel oil day tank and diesel fire pump fuel oil storage tank.

Enhance the Diesel Fuel Monitoring Program to specify acceptance criteria for thickness measurements of the fuel oil storage tanks within the scope of the program.

Enhance the Diesel Fuel Monitoring Program to direct samples be taken'~nd include direction to remove water when detected.

Revise applicable procedures to direct sampling of the onsite portable fuel oil contents prior to transferring' the contents to the storage tanks.

Enhance the Diesel Fuel Monitoring Program to direct the addition of chemicals including biocide when the presence of biological activity is confirmed.

NL-10-082 Docket Nos. 50-247 and 50-286 Page 3 of 17.~_

IMPLEMENTATION SOURCE RELATED SCHEDULE LRASECTION I AUDIT ITEM IP2:

NL-07-039 A.2.1.8 iSeptember 28, A.3.1.8

~013 S.1.9 NL..07-153 Audit items IP3:

128, 129, December 12,

132,

~015 NL-08-057 491,492, 510 OAGI0001230 00017

COMMITMENT 5

Enhance the External Surfaces Monitoring Program for IP2and IP3to include periodic inspections of systems in scope' and subject to aging managemenL review for license renewal in accordance with 10 CFR 54.4(a)(1) and (a)(3).' Inspections shall include areas surrounding the subject systems to identify hazards to those systems. Inspections of nearby systems that could impact the subject systemswill include SSCs that are in scope and subject to aging management review for license renewal in accordance with 10 CFR 54.4(a)(2).

6 Enhance the Fatigue Monitoring Program for IP2 to monitor steady state cycles and feedwater cycles*or perform an evaluation to determine monitoring IS not required. Review the number of allowed events and resolve discrepancies between reference documents and monitoring procedures.

Enhance the Fatigue Monitoring Program for IP3 to include all the transients identified. Assure all fatigue analysis transients are included with the lowest limiting numbers. Update the number of design transients accumulated to date.

7 Enhance the Fire Protection Program to inspect external surfaces of the IP3 RCP oil collection systems for loss of material each refueling cycle..

Enhance the Fire Protection Program to explicitly state that the IP2 and IP3 diesel fire pump engine sub-systems (including the fuel supply line) shall be observed while the pump is running. Acceptance criteria will be revised to verify that the diesel engine does not exhibit signs of degradation while running; such as fuel oil. lube oil, coolant, or exhaust gas leakage.

Enhance the Fire Protection Program to speCify that the IP2 and IP3 diesel fire pump engine carbon steel exhaust components are inspected for evidence of corrosion and cracking at least once each operating cycle.

Enhance the Fire Protection Program for IP3 to visually inspect the cable spreading room, 480V.

switchgear room, and EDG room CO2 fire suppression system for signs of degradation, such as corrosion and mechanical damage at least once every six months.

NL-10-082 Docket Nos. 50-247 and 50-286 Page 4 of 17 IMPLEMENTATION SOURCE*

RELATED SCHEDULE LRASECTION I AUDIT ITEM IP2:.

NL-07-039 A.2.1.10

~eptember 28.

A.3.t.10

~013 B.1.11 IP3:

December 12, 2015 IP2:

NL-07-039 A.2.1.11 September 28.

A.3.1.11 2013 8.1.12, NL-07-153 Audit Item 164 IP3:

pecember 12,

~O15 IP2:

NL-07-039 A.2.1.12 September 28, A.3.1.12

2013 B.l.13 IP3

December 12,.

2015 I

OAGI0001230 00018

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COMMITMENT 8

Enhance the Fire Water Program to include inspection of IP2 and IP.3 hose reels for evidence of corrosion.

Acceptance criteria will be revised to verify no unacceptable signs of degradation.

Enhance the Fire Water Program to replace all or test a sample of IP2 and IP3 sprinkler heads required for 10 CFR 50.48. using guidance of NFPA 25 (2002 edition), Section 5.3.1.1.1 before the end of the 50-year sprinkler head service life and at 10-year intervals thereafter during the extended period of operatio~ to ensure that signs of degradation, such as corrosion, are detected in a timely manner.

Enhance the Fire Water Program to perform wall thickness evaluations oflP2 and IP3 fire protection.

piping on system components using non-intrusive techniques (e.g., volumetric testing) to identify evidence of l.oss of material due to corrosion. These inspections will be performed before the end of the current operating term and at intervals thereafter during the period of extended operation. Results.of the initial evaluations will be used to determine the appropriate inspection interval to ensure aging effects are identified prior to loss of intended function.

Enhance the Fire Water Program to inspect the internal surface of foam based fire suppression tanks.

Acceptance criteria will be enhanced to verify no significant corrosion.

NL-10-082 Docket Nos. 50-247 and 50-286 Page 5 of 17 IMPLEMENTATION SOURCE RELATED SCHEDULE LRASECTION I AUDIT ITEM IP2:

NL-07-039 A.2.1.13 September 28, A.3.1.13 2013

. 8.1.14 NL-07-15~ Audit Items IP3:

105, 106 December 12, NL-08-014 2015 OAGI0001230 00019

COMMITMENT 9

Enhance the Flux Thimble Tube Inspection Program for IP2 and IP3 to implement comparisons to wear ra.tes identified in WCAP-12866~,Include provisions to, compare data to the previous performances and perform evaluations regarding 'change to test frequency and scope.

Enhance the Flux Thimble Tube Inspection Program for IP2 and IP3 to specify the acceptance criteria as outlined in WCAP-12866 or other plant-specific values based,on evaluation of previous test results.

Enhance the Flux Thimble Tube Inspection Program for IP2 and IP3 to direct evaluation and performance of corrective actions based on tubes that exceed or are projected to exceed the acceptance criteria. Also stipulate that flux thimble tubes that cannot be inspected over the tube length and cannot be shown by analysis to be satisfactory for continued service, must be removed from service to ensure the integrity of,the reactor coolant system pressure boundary.

1 ' '

NL-10-082 '

Docket Nos. 50-247 and 50-286 '

Page 6 of 17.,

IMPLEMENTATION SOURCE RELATED SCHEDULE LRASECTION I AUDIT ITEM

'IP2:

NL-07~039 A.2.1.15 September 28, A.3.1.1S 2013 B.~.16 IP3:

, December 12, '

2015, '

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OAGI0001230 00020

~--.

COMMITMENT 10 Enhance the Heat Exchanger Monitoring Program for IP2 andlP3 to include the following heat exchangers in the. scope of the program.

Safety injection pump lube oil heat exchangers RHR heat exchangers RHR pump seal coolers Non-regenerative heat exchangers Charging pump seal water heat exchangers Charging pump fluid drive coolers

  • Charging pump crankcase oil coolers Spent fuel pit heat exchangers Secondary system steam generator sample coolers Waste gas compressor heat exchangers SBO/Appendix R diesel jacket water heat exchanger (IP20nly)

Enhance the Heat Exchanger Monitoring Program for IP2 and IP3to perform visual inspection on heat exchangers where non-destructive examination, such as eddy current inspection, is not possible due to heat exchanger design limitations.

Enhance the Heat Exchanger Monitoring Program for IP2 and IP3 to include consideration of material-environment combinations. when determining sample population of heat exchangers.

Enhance the Heat Exchanger Monitoring Program for IP2 and IP3 to establish minimum tube wall thickness for the new heat exchangers identified in the scope of the program. Establish acceptance criteria for heat exchangers visually inspected to include no indication of tube erosion, vibration wear, corrosion, pitting, fouling, or scaling.

11 Delete commitment.

NL-10-082 Docket Nos. 50-247 and 50-286 Page 70f 17 IMPLEMENTATION SOURCE RELATED SCHED,ULE LRASEcnON lAUDITITEM IP2:

NL-07-039 A.. 2.1.16

~eptember 28, A.3.1.16

~013 8.1.17,

'Nt::07-1'53 Audit Item IP3:,

52 December 12,

~015.

NL-09-018 NL-09-056 OAG 1000 1230_00021

COMMITMENT 12 Enhance the Masonry Wall Program for IP2 and IP3

. to specify that the I P1 intake structure is !ncluded in

  • the program.

13 Enhance the Metal-Enclosed Bus I nspection Program to add IP2 480V bus associated with substation A to the scope of bus inspected.

Enhance the Metal-Enclosed Bus Inspection Program for IP2 and IP3 to visually inspect the external surface of MEB enclosure assemblies for loss of material at least once every 10 years. The first inspection will occur prior to the period of extended operation and the acceptance criterion will be no significant loss of material.

Enhance the Metal-Enclosed Bus Inspection Program to add acceptance criteria for MEB internal visual inspections to include the absence of indications of dust accumulation on the bus bar. on the insulators, and in the duct, in addition to the absence of indications of moisture intrusion into the duct.

Enhance the Metal-Enclosed Bus Inspection Program for IP2 and IP3 to inspect bolted connections at least once every five years if performed visually or at least once every ten years using quantitative measurements such as thermography or contact resistance measurements. The first inspection will

\\

occur prior to the period of extended operation.

The plant will process*a change to applicable site procedure to remove the reference to "re-torquing" connections for phase bus maintenance and bolted connection maintenance.

14 Implement the Non-EO Bolted Cable Connections Program for IP2 and IP3 as described in LRA Section B.1.22.

r NL-10-082 Docket Nos. 50-247 and 50-286 Page 8 of 17 IMPLEMENTATION SOURCE RELATED SCHEDULE LRASECTION I AUDIT ITEM IP2:

NL-07-039 A.2.1.18 September 28, A.3.1.18 2013 B.1.19 IP3:

December 12,

~015 IP2:

NL-07-039 A.2.1.19 September 28, A.3.1.19 2013 B.1.20 NL-07-153 Audit Items IP3:

124, December 12, NL-08-057 133.519

~015 IP2:

NL-07-039 A.2.1.21 September 28, A.3.1.21 2013 B.1.22 IP3:

December 12, 12015 OAGI0001230 00022

15 16 17 18 NL-10-082 Docket Nos. 50-247 and 50-286 Page 9 of 17 COMMITMENT IMPLEMENTATION SCHEDULE IP2:

Implement the Non-EQ Inaccessible Medium-Voltage

~eptember 28, Cable Program forlP2 and IP3 as described in LRA

~013 Section B.1.23.

--.. ~ -

This new program will be implemented consistent with the corresponding program described in NUREG- _

1801 SectionXI.E3, Inaccessible Medium-Voltage Cables Not Subject To 10 CFR 50.49 Environmental Qualification Requirements.

IP3:

December 12,

~015 IP2:

Implement the Non-EQ Instrumentation Circuits Test September 28, Review Program for IP2 and IP3 as described in LRA 2013 Section B.1.24.

This new program will be implemented consistent with the corresponding program described in NUREG-1801 Section XI.E2, Electrical Cables and Connections NotSubject to 10 CFR 50.49 Environmental Qualification Requirements Used in Instrumentation Circuits.

IP3:

December 12, 2015 IP2:

Implement the Non-EQ Insulated Cables and Ie, Connections Program for IP2 and IP3 as described in peptember 28, LRA Section B.1.. 25.

~013 This new program will be implemented consistent with the corresponding program described in NUREG-1801-Section XI. E1, Electrical Cables and Connections Not Subject to 10 CFR 50.49 Environmental Qualification Requirements.

Enhance the Oil Analysis Program for IP2 to sample and analyze lubricating oil used in the SBO/Appendix R diesel generator consistent with oil analysis for other site diesel generators.

Enhance the Oil Analysis Program for IP2 and IP3 to sample and analyze generator seal oil and turbine hydraulic control oil.

Enhance the Oil Analysis Program for IP2 and IP3 to formalize preliminary oil screening for water and particulates and laboratory analyses including defined acceptance criteria for all components included in the scope of this program. The program will specify corrective actions in the event acceptance criteria are not met.

Enhance the,Oil Analysis Program for IP2 and IP3to formalize trending of preliminary oil screening results as well as data provided from independent laboratories.

IP3:

December 12,

~015 IP2:

~eptember 28,

~013 IP3:

December 12, 2015 SOURCE RELATED LRASECTION I AUDIT ITEM NL-07 -039 A.2.1.22 A.3.1.22 B.1.23 NL-07-153 Audit item 173 NL-07-039 A.2.1.2:3 A.3.1.23 B.1.24 NL-07-153 Audit item 173 NL-07-039 A.2.1.24 A.3.1.24 B.1.25 NL-07-153 Audit item 173 NL-07-039 A.2.1.25 A.3.1.25 B.1.26 OAGI0001230 00023

COMMITMENT 19 Implement the One-Time Insp~ction Program for IP2.;

and IP3 as described in LRA SectionB.1.27.

. This -new program will be implemented consistent with the corresponding program described in NUREG-1801,Section XI.M32, One-Time Inspection.

20 Implement the One-Time Inspection - Small Bore Piping Program for IP2 and IP3 as described in LRA Section B.1.28.

This new program will be implemented consistent with the corresponding program described in NUREG-1801,Section XI,M35, One-Time Inspection of ASME Code Class 'I Small-Bore PipinQ.

21 Enhance the Periodic Surveillance and Preventive Maintenance Program for IP2 and IP3 as necessary to assure that the effects of aging will be managed such that applicable components will continue to perform their intended functions consistent with the current licensing basis through the period of extended operation.

22 Enhance the Reactor Vessel Surveillance Program for IP2 and IP3 revising the specimen capsule withdrawal schedules to draw and test a standby capsule to cover the peak reactor vessel fluence expected through the end of the period of extended operation.

Enhance the Reactor Vessel Surveillance Program for IP2 and IP3 to require that tested and untested specimens from all capsules pulled from the reactor' vessel are maintained in storage.

23 Implement the Selective Leaching Program for I P2 and I P3 as described in LRA Section B.1.33.

This new program will be implemented consistent with the corresponding program described in NUREG-1801,Section XI.M33 Selective Leaching of Materials.

NL-10-082 Docket Nos. 50-247 and 50-286 Page 10 of 17. '""

IMPLEMENTATION SOURCE RELATED SCHEDULE LRASECTION I AUDIT ITEM IP2:

NL-07-039 A.2.1.26 iSeptember 28, A.3.1.26 12013 B.1.27

. NL-07-153 Audit item IP3:

173 December 12, 2015 IP2:

NL-07-039 A.2.1.27 September 28, A.3.1.27 2013 B.1.28

. NL-07-153

'Audit item IP3:

173 December 12,

,~015 IP2:

NL-07-039 A.2.1.28

~eptember 28, A.3.1.28 12013 B.1.29 IP3:

Decembe,r 12, 2015 IP2:

NL-07-039 A.2.1.31

~eptember 28, A.3.1.31 12013 B.1.32 IP3:

December 12, 12015 IP2:

NL-07-039 A.2.1.32

~eptember 28, A.3.1.32

~013 B.1.33 NL-07-153 Audit item

'IP3:

173 December 12, 2015 OAGI0001230 00024

24 25 COMMITMENT Enhance the Steam Generator Integrity ~rogram for, IP2 and IP3 to require that the results of the condition monitoring assessment are compared to the operational assessment performed for the prior operating cycle with differences evaluated.

NL-10-082 Docket Nos. 50-247 and 50-286 Page 11 of 17 IMPLEMENTATION SCHEDULE IP2:

!september 28; 12013 IP3:

December 12,

~015 SOURCE RELATED LRASECTION I AUDIT ITEM NL-07-039 A.2.1.34 A.3.1.34 B.1.35 Enhance the Structures Monitoring Program to IP2:

explicitly specify that the following structures are September 28, NL-07-039 A.2.1.35 A.3.1.35 B.1.36 included in the program.

~013 Appendix R diesel generator foundation (IP3)

Appendix R diesel generator fuel oil tank vault (IP3)

Appendix R diesel generator switchgear and enclosure (IP3) city water storage tank foundation condensate storage tanks foundation (IP3) containment access facility and annex (IP3) discharge canal (I P2I3) emergency lighting poles and foundations (IP2I3) fire pumphouse (IP2) fire protection pumphouse(IP3) fire water storage tank foundations (IP2I3) gas turbine 1 fuel storage tank foundation maintenance and outage building-elevated passageway (IP2) new station security building (IP2) nuclear service building (I P1) primary water storage tank foundation (IP3) refueling water storage tank foundation (IP3) security access and office building (IP3) service water pipe chase (IP2I3) service water valve pit (I P3) superheater stack transformerlswitchyard support structures (IP2) waste holdup tank pits (IP2I3)

Enhance the Structures*Monitoring Program for IP2 and IP3 to clarify that in addition to structural steel and concrete, the following commodities (including their anchorages) are inspected for each structure as applicable.

cable trays and supports IP3:

December 12, 12015 NL-07-153 Audit items 86,87,88, NL-08-057 417 OAGI0001230 00025

COMMITMENT concrete portion of reactor vessel supports conduits and supports

  • cranes,rails and girders equipment pads and foundations
  • fire proofing (pyrocrete)
  • jib cranes
  • manholes and duct banks
  • 'manways, hatches and hatch covers monorails
  • new fuel storage racks
  • sumps, sump screens, strainers and flow barriers Enhance the Structures Monitoring Program for IP2 and IP3 to inspect inaccessible concrete areas that are exposed by excavation for any reason. IP2 and IP3 will also inspect inaccessible concrete areas in environments where observed conditions in accessible areas exposed to the same environment indicate that significant concrete degradation is occurring.

Enhance the Structures Monitoring Program for IP2 and IP3 to perform inspections of elastomers (seals, gaskets, seismic jOint filler, and roof elastomers) to identify cracking and change in material properties and for inspection of aluminum vents and louvers to identify loss of material.

Enhance the Structures Monitoring Program for IP2 and I P3 to perform an engineering evaluation of groundwater samples to assess aggressiveness of groundwater to concrete on a periodic basis (at least once every five years). IPEC will obtain samples from at least 5 wells that are representative of the ground water surrounding below-grade site structures and perform an engineering evaluation of the results from those samples for sulfates, pH and chlorides.

Additionally, to assess potential indications of spent fuel pool leakage, IPEC will sample for tritium in groundwater wells in close proximity to the IP2 spent fuel pool at least once every 3 months.

Enhance the Structures Monitoring Program for IP2 and I P3 to perform inspection of normally submerged NL-10-082 Docket Nos. 50-247 and 50-286 Page 12 of 17 IMPLEMENTATION SOURCE RELATED SCHEDULE LRA. SECTION I AUDIT ITEM NL-08-127 Audit Item 360 OAGI0001230 00026

COMMITMENT concrete portions of the intake structures at least onc.~

every 5 years. Inspect the baffling/grating partition and support platfqrm of the IP3 intake structure at least once every 5 years.

Enhance the Structures Monitoring Program for IP2 and I P3 to perform inspection of the degraded areas of the water control structure once per 3 years rather than the normal frequency.of once per 5 years during the PEO.

26. Implement the Thermal Aging Embrittlement of Cast Austenitic Stainless Steel (CASS) Program for IP2.

and IP3 as described in LRA Section B.1.37.

This new program will be implemented consistent with the corresponding program described in NUREG-1801,Section XI.M12, Thermal Aging Embrittlement of Cast Austenitic' Stainless Steel (CASS) Program.

27 Implement the Thermal Aging and Neutron Irradiation Embrittlement of Cast Austenitic Stainless Steel (CASS) Program for IP2 and IP3 as described in LRA Section B.1.38.

This new program will be implemented consistent with the corresponding program described in NUREG-1801 Section XI.M13, Thermal Aging and Neutron Embrittlement of Cast Austenitic Stainless Steel (CASS) Program.

28 Enhance the Water Chemistry Control-Closed Cooling Water Program to maintain water chemistry of the IP2 SBO/Appendix R diesel generator cooling system per EPRI guidelines.*

Enhance the Water Chemistry Control-Closed Cooling Water Program to maintain the IP2 and IP3 security generator and fire protection diesel cooling water pH and glycol within limits specified by EPRI guidelines.

29 Enhance the Water Chemistry Control - Primary and Secondary Program for IP2 to test sulfates monthly in the RWST with a limit of <150 ppb.

NL-10-082 Docket Nos. 50-247 and 50c286 Page 13 of 17 IMPLEMENTATION SOURCE RELATED SCHEDULE I,.RASECTION I AUDIT ITEM Audit Item 358 IP2:

NL~07-039 A.2.1.36 September 28, A.3.1.36 2013 8.1.37 NL-07-153 Audit item IP3:

173 December 12, 12015 IP2:

NL-07-039 A.2.1.37

~eptember 28, A.3.1.37 12013 B.1.38 NL-07-153 Audit item IP3:

173 December 12, 12015 IP2:

NL-07-039 A.2.1.39

~eptember 28, A.3.1.39 2013

. B.1.40 NL-08-057 Audit item IP3:

509 December 12, 2015 IP2:

NL-07-039 A.2.1.40 September 28, 8.1.41 2013 OAGI0001230 00027

COMMITMENT 30 For agirg management of the reactor vessel internals, IPEC will (1) participate in the industry programs for investigating and managing aging effects on reactor internals; (2) evaluate and implement the results of the industry programs as applicable to the reactor internals; and (3) upon completion of these programs, but not less than 24 months before entering the period of extended operation, submit an inspection plan for reactor internals to the NRC for review and approval.

31 Additional P-T curves will be submitted as required per 10 CFR 50, Appendix G prior to the period of extended operation as part of the Reactor Vessel Surveillance Program.

32 As required by 10 CFR 50.61 (b}(4), IP3 will submit a plant-specific safety analysis for plate 82803-3 to the NRC three years prior to reaching the RT PTS screening criterion. Alternatively, the site may choose to implement the revised PTSruie when approved.

. NL-10-082 Docket Nos. 50-247 and 50-286 Page 14 of 17 IMPLEMENTATION SOURCE RELATED SCHEDULE LRASECTION I AUDIT ITEM IP2:

NL-07-039 A.2.1.41

!September 28, A.3.1.41

~011 IP3:

December 12,

~013 IP2:

NL-07-039 A.2.2.1.2 September 28, A.3.2.1.2 2013 4.2.3 IP3:

December 12, 2015 IP3:

NL-07-039 A.3.2.1.4 December 12, 4.2.5 2015 NL-08-127 OAGI0001230 00028

COMMITMENT 33 At least 2 years prior to entering the period of extended operation, for the locations identified in LRA

- ~ '.~. Table 4.3-13 (IP2) and LRA Table 4.3-14 (IP3), under the Fatigue Monitoring Program, IP2 and IP3 will implement one or more of the following:

(1) Consistent with the Fatigue Monitoring Program, Detection of Aging Effects, update the fatigue usage calculations using refined fatigue analyses to determine valid CUFs less than 1.0 when accounting for the effects of reactor water environment. This includes applying the appropriate Fen factors to valid CUFs determined in accordance with one of the following:

1. For locations in LRA Table 4.3-13 (IP2) and LRA Table 4.3-14 (IP3), with existing fatigue analysis valid for the period of extended operation, use the existing CUF.
2. Additional plant-specific locations with a valid CUF may be evaluated. In particular, the pressurizer lower shell will be reviewed to ensure the surge nozzle remains the limiting component.
3. Representative eUF values from other plants, adjusted to or enveloping the IPEe plant specific external loads may be used if demonstrated applicable to IPEC.
4. An analysis using an NRC-approved version of the ASME code or NRC-approved alternative (e.g., NRC-approved code case) may be perfomled to detemline a valid CUF.

(2) Consistent with the Fatigue Monitoring Program, Corrective Actions, repair or replace the affected locations before exceeding a CUF of 1,0.

34 IP2 SSO / Appendix R diesel generator will be installed and operational by April 30, 2008. This committed change to the facility meets the requirements of 10 CFR 50.59(c)(1) and, therefore, a license amendment pursuant to 10 CFR 50.90 is not required.

NL-10-082 Docket Nos. 50-247 and 50-286 Page 15 of.17. <

IMPLEMENTATION SOURCE RELATED SCHEDULE LRASECTION IAUD'T'TEM IP2:

NL-07-039*

A.2.2.2.3 September 28, A.3.2.2.3

~011 4.3.3

. NL-07-153 Audit item IP3:

146 December 12, NL-08-021

~013 ComQlete

. NL-10-082 April 30, 2008 NL-07-078 2.1.1.3.5 Complete NL-08-074 OAGI0001230 00029

COMMITMENT 35 Perform a one-time inspection of representative sample area of IP2 containment liner affected by the 1.973 event behind the insulation, prior to entering the extended period of operation, to assure liner degradation is not occurring in this area.

Perform a one-time inspection of representative sample area of the IP3 containment steel liner at the juncture with the concrete floor slab, prior to entering the extended period of operation, to assure liner degradation is not occurring in this area.

Any degradation will be evaluated for updating of the containment liner analyses as needed.

36 Perform a one-time Inspection and evaluation of a sample of potentially affected I P2 refueling cavity concrete prior to the period of extended operation.

The sample will be obtained by core boring the refueling cavity wall in an area that is susceptible to exposure to borated water leakage. The inspection will include an assessment of embedded reinforcing steel.

Additional core bore samples will be taken, if the leakage is not stopped, prior to the end of the first ten' years of the period of extended operation.

A sample of leakage fluid will be analyzed to determine the composition of the fluid. If additional core samples are taken prior to the end of the first ten years of the period of extended operation, a sample of leakage fluid will be analyzed.

37 Enhance the Containment Inservice Inspection (CII-IWL) Program to include inspections of the containment using enhanced characterization of degradation (i.e., quantifying the dimensions of noted indications through the use of optical aids) during the period of extended operation. The enhancement includes obtaining critical dimensional data of.

degradation where possible through direct measurement or the use of scaling technologies for.

photographs, and the use of consistent vantage points for visual inspections.

NL-10~082 Docket Nos. 50-247 and 50-286 Page 16 of 17. '~"

IMPLEMENTATION SOURCE RELATED SCHEDULE LRASECTION f AUDIT ITEM IP2:

NL-08-127 Audit Item

. ~eptember 28, 27

~013 IP3:

December 12,

~015 NL-09-018 IP2:

NL-08-127 Audit Item September 28,

\\

359 2013 NL-09-056 NL-09~079 IP2:

NL-08-127 Audit Item September 28, 361 2013 IP3:

December 12,

~015 OAGI0001230 00030

'\\.

P'I' COMMITMENT 38 For Reactor Vessel Fluence, should future core loading patterns invalidate the basis for the projected values of RTpts or CvUSE, updated calculations will be provided to the NRC.

39 Deleted 40 Evaluate plant specific and appropriate industry operating experience and incorporate lessons learned in establishing appropriate monitoring and inspection frequencies to assess aging effects for the new aging management programs. Documentation of the o~erating ~xperienc~ evaluated for each new program Will be available on site for NRC review prior.to the period of extended operation.

NL-10-082 Docket Nos. 50-247 and 50-286 Page 17 of 17, _,

IMPLEMENTATION SOURCE RELATED SCHEDULE LRASECTION I AUDIT ITEM

  • IP2:

NL-08-143 4.2.1

!September 28,

~013

.'_... _O*w IP3:

December 12, 12015 NL-09-079 IP2:

NL-09-106 B.1.6 September 28, B.1.22 12013 B.1.23 B.1.24 IP3:

B.1.25 December 12, 8;1.27 2015 B.1.28 B.1.33 8.1.37 8.1.38 OAGI0001230 00031

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