ML17164A181

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Fourth Inservice Inspection Interval, Third Inservice Inspection Period 2017 Owner'S Activity Report for RF0-24 Inservice Examinations
ML17164A181
Person / Time
Site: Nine Mile Point Constellation icon.png
Issue date: 06/06/2017
From: Maryam Khan
Exelon Generation Co
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
NMP1L 3159
Download: ML17164A181 (12)
v • d • e


Text

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p Exelon Generation 10 CFR 50.55a NMP1L3159 June 6, 2017 U.S. Nuclear Regulatory Commission Attn
Document Control Desk Washington, DC 20555-0001 Nine Mile Point Nuclear Station, Unit 1 Renewed Facility Operating License No. DPR-63 Docket No. 50-220

Subject:

Fourth lnservice Inspection Interval, Third lnservice Inspection Period 2017 Owner's Activity Report for RF0-24 lnservice Examinations Pursuant to 10 CFR 50.55a, Nine Mile Point Nuclear Station, LLC (NMPNS) hereby submits the attached Fourth lnservice Inspection Interval, Third lnservice Inspection Period, 2017 Owner's Activity Report for RF0-24 lnservice Examinations, for Nine Mile Point Unit 1 (NMP1). The report is contained in Attachment 1 to this letter, and summarizes the results of examinations performed during the first refueling outage (RF0-24) of the Third lnservice Inspection Period of the Fourth Ten-Year Inspection Interval (August 23, 2009 through August 22, 2019).

This activity report meets the requirements of the American Society of Mechanical Engineers (ASME), Code Case N-532-4, "Alternative Requirements to Repair and Replacement Documentation Requirements and lnservice Summary Report Preparation and Submission as Required by IWA-4000 and IWA-6000,Section XI, Division 1," as approved for use by Regulatory Guide 1.147, "lnservice Inspection Code Case Acceptability, ASME Section XI, Division 1."

There are no regulatory commitments contained in this letter.

Should you have any questions regarding the information in this submittal, please contact Dennis Moore, Site Regulatory Assurance Manager, at (315) 349-5219.

  • Sincerely, Mohamed N. Khan Engineering Director, Nine Mile Point Nuclear Station Exelon Generation Company, LLC MNK/KJK

Attachment:

Fourth lnservice Inspection Interval, Third lnservice Inspection Period 2017 Owner's Activity Report for RF0-24 lnservice Examinations

.f'*

NMP1 Owner's Activity Report for RF0-24 June 6, 2017 Page 2 cc: Regional Administrator, Region I, USNRC Project Manager, USNRC Resident Inspector, USNRC

Attachment

. Fourth lnservice Inspection Interval, Third lnservice Inspection Period 2017 Owner's Activity Report for RF0-24 lnservice Examinations

~-~ Exelon Generation.

FOURTH INSERVICE INSPECTION INTERVAL THIRD INSERVICE INSPECTION PERIOD 2017 OWNER'S ACTIVITY REPORT FOR RF0-24 INSERVICE EXAMINATIONS Prepared For Nine Mile Point Nuclear Station Unit 1 P.O. Box 63, Lake Road Lycoming, New York 13093 Commercial Service Date: December 26, 1969 NRC Docket Number: 50-220 Document Number: NMP1 -OAR-004-024 Revision Number: 00 Date: May 16, 2017 Preparedby: L.JLJ \,.

Ronald P. Fabin -

~f~-

MPNS ISi~

Manager 5/11,/.Jc,17 Approved by:_**-~-----------------..__.................___ _ _ _ __

Todd L. Davis - NMPNS ISi Back up Program Manager Approved by: 5- / 1- 2 O/

Michael Faivus - Manager Engineering Programs

Nine Mile Point Nuclear Station Unit 1 NMP1-0AR*004*24

...=" Exelon Generation.

FOURTH INSERVICE INSPECTION INTERVAL 2017 OWNER'S ACTIVITY REPORT Rev. 00 Date: May 16, 2017 FOR Page 2 of 9 INSERVICE EXAMINATIONS TABLE OF CONTENTS Table of Contents .................................................................................................................................................... 2 Record of Revision ..................................................................................................................................................... 3 Abstract ...................................................................................................................................................................... 4 Form OAR-1 Owner's Activity Report for ASME Section XI Inspection & Testing Plans ........................................ 6 Table 1 Items with Flaws or Relevant Conditions that Required Evaluation for Continued Service ........................ 7 Table 2 Abstract of Repairs, Replacements, or Corrective Measures Required for Continued Service .................. 8

Nine Mile Point Nuclear Station Unit 1 NMP1-0AR-004-24

,::'!' Exelon Generation.

FOURTH INSERVICE INSPECTION INTERVAL 2017 OWNER'S ACTIVITY REPORT Rev. 00 Date: May 16, 2017 FOR Page 3 of 9 INSERVICE EXAMINATIONS RECORD OF REVISION REVISION DATE AFFECTED REASON FOR REVISION No. PAGES*

00 MAY 17, 2017 Entire Initial issue of Owner's Activity Report for ASME Document Section XI lnservice Inspection, Containment lnservice Examinations, and Pressure Tests and Alternate Risk-Informed Inspection in accordance with the requirements of ASME Code Case N-532-4.

Nine Mile Point Nuclear Station Unit 1 NMP1-0AR-004-24 FOURTH INSERVICE INSPECTION Rev. 00

,::::r Exelon INTERVAL Generation. 2017 OWNER'S ACTIVITY REPORT Date: May 16, 2017 FOR Page 4 of 9 INSERVICE EXAMINATIONS ABSTRACT ASME Section XI Code Case N-532-4 requires submission of the Owner's Activity Report to the regulatory and enforcement authorities having jurisdiction at the plant site within 90 calendar days of the completion of each refueling outage.

This Owner's Activity Report summarizes the results of the Nine Mile Point Nuclear Station (NMPNS), Unit 1, American Society of Mechanical Engineers (ASME)Section XI In-service Inspection, Risk-Informed Inspection, Containment In-service Examinations, and Pressure Tests performed during Refueling Outage Twenty-Four (RF0-24), from March 20, 2017 through April 6, 2017, and the First outage of the Third In-service Inspection Period that started on August 23, 2016 and is scheduled to end on August 22, 2019.

The attached Table 1 and 2 include flaws and conditions (those meeting the requirements of Code Case N-532-

4) identified since the last Owner's Activity Report following Refueling Outage RF0-23.

As an alternate to the requirements of the ASME, Boiler and Pressure Vessel Code (B&PVC),Section XI, Article IWA-6000, NMPNS is implementing ASME Code Case N-532-4, Alternative. Requirements to Repair and Replacement Documentation Requirements and In-service Summary Report Preparation and Submission as Required by IWA-4000 and IWA-6000,Section XI, Division 1". Regulatory Guide 1.147, Revision 16, approved ASME Code Case N-532-4 for use. This Report complies with the requirements of Code Case N-532-4 and the conditions identified in RG 1.147.

OWNER'S ACTIVITY REPORTS - FORM OAR-1 Owner's Activity Reports Form OAR-1 's were prepared and certified upon completion of the Nine Mile Point Unit 1, 2017 refueling outage (RF0-24) examination activity in accordance with the following NMPNS inspection plans and schedules:

  • NMPHSl-004, Fourth Ten-Year In-service Inspection Plan and Implementing Schedule, (includes the Alternate Risk-Informed Inspection Program
  • NMP1 -CISl-002, Second Coritainment In-service Inspection Plan and Implementing Schedule.
  • NMP1-PT-003, lnservice Pressure Testing Program Plan In addition to the Owner's Activity Report, Form OAR-1, the following Tables are also included:
a. Items with Flaws or Relevant Conditions that Require Evaluation for Continued Service, Table 1, provides a listing of item(s) with flaws or relevant conditions that required evaluation to determine acceptability for continued service, whether or not the flaw or relevant condition was discovered during a scheduled examination or test, and provides such information as Examination Category, Examination Item Number, Item Description, Flaw Characterization (as required by IWA-3300).

Nine Mile Point Nuclear Station Unit 1 NMP1-0AR-004-24

-" Exelon Generation.

FOURTH INSERVICE INSPECTION INTERVAL 2017 OWNER'S ACTIVITY REPORT Rev. 00 Date: May 16, 2017 FOR Page 5 of 9 INSERVICE EXAMINATIONS

b. Abstract of Repairs, Replacements or Corrective Measures Required for Continued Service, Table 2, identifies those items containing flaws or relevant conditions that exceeded Division 1 acceptance criteria shall be provided with the information and format of Table 2. This information is required even if the discovery of the flaw or relevant condition that necessitated the repair/replacement activity did not result from an examination or test required by Division 1. If the acceptance criterion for a particular item is not specified in Division 1, the provisions of IWA-3100(b) shall be used to determine which repair/replacement activities are required to be included in the abstract.

In accordance with ASME Section XI, IWB-2412(a), IWC-2412(a), IWD-2412(a), IWE-2412(a), and IWF-2410(b) and with the exception of the examinations that may be deferred until the end of the inspection interval as specified in Table IWB-2500-1, IWC-2500-1, IWD-2500-1, IWF-2500-1 and IWE-2500-1, including those examinations which NMPNS has requested and received approval in the form of relief request, the required examinations in each examination category have been completed for the First and Second In-service Inspection Period in accordance with Tables IWB-2412-1, IWC-2412-1, IWD-2412-1, IWE-2412-1, and IWF-2410-2.

Nine Mile Point Nuclear Station Unit 1 NMP1-0AR-004-24 FOURTH INSERVICE INSPECTION Rev. 00

~Exelon INTERVAL Gener*ation. 2017 OWNER'S ACTIVITY REPORT Date: May 16, 2017 FOR Page 6 of 9 INSERVICE EXAMINATIONS FORM OAR-1 OWNER'S ACTIVITY REPORT As required by the provisions of the ASME Code Case N-532-4 Report Number'-:----'N:...=..:..=.M'-'-P-=1--0~A"""R'--0=-0=-4_,__-=0=24-'-------

Plant _ _ _ _ _ _ __,_,N=in=e_,_M=i=le'-'P-=o=in~t'-'-N=u=c=le=a""-r~S=ta=ti=o~n.~P~.-=O=*~B=o=x~6=3~.~Lv~c=o~m=in~g~,_,_N=e=w'-Y~o=r~k-=1=3=0=93,,__ _ _ _~

(Name and Address of Plant)

Plant Unit-~-- Commercial Service Date December 26, 1969 Refueling Outage Number RF0-24 Current Inspection Interval 4th Interval for ISi & PT. 2"d Interval for CISI August 23. 2009 to August 22. 2019 (1st, 2nd, 3rd, 4th, Other)

Current Inspection Period -----'T'-'-h=ir-=d-"ln'"'"""*=se=rv-'-=ic=e_,_,In=s;,,,p=e=ct~io,_,_n,,,.,P-"e,,_,_r'-';io=d_ _ _ ___,_A=u~g=us=tc.=2=3"--.=20=-1_,_,6'-'t=o_,_A=u""g=us=t'-=2=2""-.=20=-1_,_,9'-

(1st, 2nd, 3rd)

Edition and Addenda of Section XI applicable to the Inspection Plans _ _ __,2,,_,0=0'--'4'-'E='d"'"it,,_,io=n!.L..-'-"'N=o_,_A_,,d=d=e"'-'-nd,,,,a,,___ _ __

Date and Revision of Inspection Plans NMPHSl-004. Revision 03. June 30. 2016 (ISi}, NMP1-CISl-002. Revision 02.

August 1. 2016 (Containment ISi}, NMP1-PT-003 Revision 05. Januarv 8. 2015 (Pressure Test)

Edition and Addenda of ASME Section XI applicable to Repair/Replacement activities, if different than the Inspection Plan N/A (same Code Edition/Addenda)

Code Cases used: N-716 N-648-1 & N-642-4 (if applicable)

CERTIFICATE OF CONFORMANCE I certify that (a) the statements made in this report are correct; (b) the examinations and tests meet the Inspection Plan as required by the ASME Code,Section XI; and (c) the repair/replacement activities and evaluations supporting the completion of RF0-24 conform to the requirements of Section XI.

  • (refueling o~agfi\umber)

Signed ~Mc:...\.& ~ * ~b=:t Date 5 / l lb/ ;;>.o l ']

(Programs Man CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of PA and employed by The Hartford Steam Boiler Inspection & Insurance Co. of Hartford, CT. have inspected the items described in this Owner's Activity Report and state that to the best of my knowledge and belief, the Owner has performed all activities represented by this report in accordance with the requirements of Section XI. ,

By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the repair/replacement activities and evaluation described in this report. Furthermore, neither the Inspector nor his employer shall be liab e in any manner for any personal injury or property damage or a loss of any kind arising from or connect with this ~

Date*

Nine Mile Point Nuclear Station Unit 1 NMP1-0AR-004-24 FOURTH INSERVICE INSPECTION Rev. 00

~Exelon INTERVAL Generation. 2017 OWNER'S ACTIVITY REPORT Date: May 16, 2017 FOR INSERVICE EXAMINATIONS Page 7 of 9 TABLE 1 ITEMS WITH FLAWS OR RELEVANT CONDITIONS THAT REQUIRED EVALUATION FOR CONTINUED SERVICE As required by the provisions of the ASME Code Case N*532-4 EVALUATION DESCRIPTION EXAMINATION ITEM ITEM CATEGORY NUMBER DESCRIPTION B-N-2 B13.30 Reactor Vessel Interior Repeat inspections were performed on four steam dryer support Attachment Weld - bracket vessel attachments to comply with the successive Beyond Beltline Region inspection requirements defined in IWB-2420(b). Relevant (Steam Dryer Support indications in the dryer support brackets exceeding the acceptance Bracket) criteria of IWB-3520.2 were reported in the previous 2011, 2013 and 2015 NMP1 ISi Owner Activity Reports. Exelon re-inspected the four steam dryer support brackets during the Spring 2017 (N1 R24) refueling outage using EVT-1 and a qualified UT tool and procedure. As in previous outages three brackets contained reportable UT and EVT-1 indications and one bracket contained only a reportable UT indication. The UT indications remain relatively shallow, continue to be located entirely within the bracket base metal and run parallel or away from the vessel attachment weld such that they are not considered a threat to propagate into and/or through the vessel attachment weld toward the vessel.

The N 1 R24 UT data showed a small change in depth on one bracket indication as compared to N1 R23, with the depth change of 0.14 being less than the UT depth sizing uncertainty of 0.394 inches documented in the BWRVIP-03 demonstration and remains bounded by the one-cycle crack growth depth of 0.375 inches assumed in the flaw evaluation. The UT data showed essentially no change in length, with the maximum change in length documented at 0.08 inches. This small length change is less than the minimum NOE uncertainty of 0.105 inches and remains bounded by the one-cycle crack growth length of 0.852 inches assumed in the flaw evaluation.

Prior to the N1 R23 re-inspections, NMP revised the previous Engineering Evaluation using the N1 R22 UT/EVT-1 data to allow two-cycles of operation. The revised supporting Engineering Evaluation concluded that the indications are acceptable for continued service for at least two additional operating cycles. In accordance with IWB-3144(b) the Engineering Evaluation of the N1 R23 examination results was submitted as an attachment to the 2015 Owner's Activity Report for RF0-23 lnservice Examinations (ML15191A385). The repeat UT/EVT-1 exams in three successive outages confirm the crack growth depth and length changes are well below the conservative growth rates used in the 2-cycle flaw evaluation. All flaws remain acceptable under the previously submitted flaw evaluation.

Nine Mile Point Nucl~ar Station Unit 1 NMP1-0AR-004-24

~

FOURTH INSERVICE INSPECTION Rev. 00

~Exelon INTERVAL Generation. 2017 OWNER'S ACTIVITY REPORT Date: May 16, 2017 FOR Page 8 of 9 INSERVICE EXAMINATIONS TABLE 2 ABSTRACT OF REPAIR/REPLACEMENT ACTIVITIES REQUIRED FOR CONTINUED SERVICE As required by the provisions of the ASME Code Case N-532-4 REPAIR/REPLACE DESCRIPTION MENT CODE ITEM OF DATE PLAN NUMBER CLASS DESCRIPTION WORK COMPLETED None J

Nine Mile Point Nuclear Station Unit 1 NM P1-0AR-004-24

,:::::!" Exelon Generation.

FOURTH INSERVICE INSPECTION INTERVAL 2017 OWNER'S ACTIVITY REPORT Rev. 00 Date: May 16, 2017 FOR Page 9 of 9 INSERVICE EXAMINATIONS END OF INSERVICE INSPECTION OWNER'S ACTIVITY REPORT FOR REFUELING OUTAGE TWENTY-FOUR (RF0-24)

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