NL-16-096, 2016 Form OAR-1 Owners Activity Report for Inservice Inspection and Repairs and Replacements

2016 Form OAR-1 Owners Activity Report for Inservice Inspection and Repairs and Replacements

ML16259A386
Person / Time
Site:	Indian Point
Issue date:	09/09/2016
From:	Vitale A Entergy Nuclear Operations
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
NL-16-096
Download: ML16259A386 (5)

Text

• ===* Entergx Entergy Nuclear Operations. Inc.

Indian Point Energy Center 450 Broadway, GSB P.O. Box 249 Buchanan, NY 10511-0249 Tel 914 254 6700 Anthony J. Vitale Site Vice President NL-16-096 September 9, 2016 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk 11545 Rockville Pike, TWFN-2 F1 Rockville, MD 20852-2738

Subject:

2016 Form OAR-1 Owners Activity Report for lnservice Inspection and Repairs and Replacements at Indian Point Unit No. 2 Indian Point Nuclear Generating Unit No. 2 Docket No. 50-24 7 License No. DPR-26

Dear Sir or Madam:

In accordance with ASME Section XI, Code Case N-532-5, "Repair/Replacement Activity Documentation Requirements and lnservice Inspection Summary Report Preparation and Submission," Indian Point Unit No. 2 herein submits the 2016 "Form OAR-1 Owners Activity Report." This report describes relevant conditions that required evaluation and repairs and replacements to be performed during the period April 2014 through June 2016.

There are no new commitments made by Entergy contained in this letter. If you have any questions, please contact Mr. Robert Walpole, Manager, Regulatory Assurance at (914) 254-6710.

Sincere!~~ '

~ f-* ~. v,?i,k AJV/gd

Enclosure:

Form OAR-1 Owners Activity Report cc: Mr. Daniel H. Dorman, Regional Administrator, NRC Region I Mr. Douglas V. Pickett, Senior Project Manager, NRC NRR DORL Ms. Bridget Frymire, New York State Department of Public Service Mr. John B. Rhodes, President and CEO, NYSERDA NRC Resident Inspectors

ENCLOSURE TO NL-16-096 Form OAR-1 Owners Activity Report ENTERGY NUCLEAR OPERATIONS, INC.

Indian Point Nuclear Generating Unit No. 2 Docket No. 50-247 License No. DPR-26

FORM OAR-1 OWNERS ACTMTY REPORT Report Number NL-16-096 Plant Indian Point Energy Center. Buchanan. New York 10511-0249 Unit No. _..,.2_ _ __ Commercial service date -----=0=..::8=/=0..:..:1/c...:1...:::9c.:..7_,_4____ Refueling outage no. 2R22 Current inspection interval ______ 4th_______________ (1st, 2nd, 3rd, 4th, Other)

Current inspection period -----"""3_rd_ _ _ _ _ _ _ _ _ _ _ _ _ _ ___.(1st, 2nd, 3rd)

Edition and Addenda of Section XI applicable to the inspection plans _ ___,2=0""'0"'"'1'-E=d=iti=o""'n..._.2=0=0=3"-'-A=d=d=e.:...:n=d=a_____

Date and revision of inspection plans: May 11. 2016 / IP2 Fourth Ten-Year ISl/Cll Program Plan. SEP-ISl-IP2-001 Rev 3. June 25, 2012 / IP2 Fourth Ten-Year ISl/Cll Program Plan. SEP-ISl-IP2-002 Rev 1 Edition and Addenda of Section XI applicable to repair/replacement activities, if different than the inspection plans ----'S=A_,,M=E-Code Cases used for inspection and evaluation: N-532-5, N-663, N-513-3, N-722-1, N-729-1, N-770-1 (if applicable, including cases modified by Case N-532 and later revisions)

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 2R22 conform to the requirements of Section XI.

(refueling outage number)

Signed ~ .* J....~ 1/ NUlON M;Ey&>o S\lf-\:~11o~<Toate e( 2.~(1{,

~ ~neror owner' s Deslgnee, Title I ~~c ~.l ---=.>.-----------

CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and employed by Hartford Steam Boiler Inspection and Insurance Company of Connecticut 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 liable in any manner for any personal injury or property damage or loss of any kind arising from or connected with this inspection.

---

~=~-------_-_:-_-_-_-_-_-_commissions _ _.....N=B--:1=0-=-0"'"'"11...._..l."""N'--'-"N..._YS=--3.-08"""4_,__ __

Inspector's Signature National Board, State, Province, and Endorsements Date_____,qi+-/=-+1 I I l.......,lfe~

2R22 Refueling Outage IP2 Owner Activity Report Third Period Examination Category and  !~m Des.crltion Item Number CR-IP2-2016-01323 - The weld attached to the pipe is not fully welded as indicated In the support drawing.

D-AfD1 .20A Class 3 Welded Attachment - One Directional Support I CT 152-W Engineering evaluated the condition and the condition was accepted as is. The design drawing was updated to reflect as-built configuration via an EC.

• CR-IP2-2016-01996- There is a discrepancy between the as-built configuration and the as-built drawing. The drawing indicates anchor bolts on the base plate bracket attached to the concrete wall. The actual as-built F-AfF1 .1 OA Class 1 Piping Supports - One Directional/ RCH 66 configuration is the base plate bracket welded to a concrete embedment plate. Engineering evaluated the condition and the drawing was updated to reflect as-built configuration via an EC.

CR-IP2-2016-02047 - The Spring Can Hanger cold load setting was found out of tolerance. Engineering evaluated F-NF1.10C Class 1 Piping Supports-Thermal Movement/ SIH 179 the condition and the pipe support was readjusted to the cold setting shown in the design drawing.

CR-IP2-2016-01320 - The strut is not rotating due lo corrosion on the bearing and spacer. Engineering evaluated F-A I F1 .20A Class 2 Piping Supports - One Directional/ SR A-9 the condition. The condition was accepted as is.

CR-IP2-2016-01502 - The Spring Can Hanger cold load setting was found out of tolerance. Engineering evaluated F-A/ F1.20C Class 2 Piping Supports-Thermal Movement/ SIH 117 the condition and the spring support is operable and can perform its intended safety function in as found condition.

CR-IP2-2016-01499 - The Spring can hanger cold load setting was found out of tolerance. Engineering evaluated F-A I F1.20C Class 2 Piping Supports -Thermal Movement/ SIH 118 the condition and the pipe support was readjusted to the cold setting shown in the design drawing.

CR-IP2-2016-01306 -The strut is not rotating due to corrosion on the bearing and spacer, and it has a missing F-A I F1 .30A Class 3 Piping Suppcrts - One Directional/ SR 553 cotter pin on the load stud. Engineering evaluated the condition and the strut condition was accepted as Is and the missing cotter pin was replaced for future design configuration.

B/23/2016 OAR-1

2R22 Refueling Outage IP2 Owner Activity Report Third Period i~fili:~'Wfi~~~°kl~f4#ji,@:$ftfff~'t:filt't~Jtitft~t~@£#lM~~~;{tajirt~¥:4:;'..{~*,::~~,:~;~*i:it~  ; .. ' l~\~~~~il§:~~E"\%l!Mi:t@~iW-W.*lf.;;\~~~t1.W1wtti~4ARW:@&t%.msl~

ABSTRACT OF REPAIR/REPLACEMENT ACTIVITIES REQUIRED FOR CONTINUED SERVICE

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Code ' Q~~-  :~J!~r~~R!~fil-Rl<ID Hem ()ascription . ~ptiOf! ofWo.rk  :

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Perform a weld overlay IAW ASME CC N-666 upstream of 2 Vent Valve S-50 vent valve 850 2/24/15 15-2-16 3 Condensate Storage Tank Repair local pittinQ corrosion areas on base of CST 3/21/16 15-2-38 Replace sections of pitted 1" SS piping with 6% MoSS 3 Line #1576 material 9/9/15 N/A Replace sections of pitted 2" SS piping with 6% MoSS 3 Line #1579 material 10/4/15 15-2-70 3 Line#497 Reolace corroded elbow on 21 CRFMC SW outlet 12/23/15 15-2-86 3 23 EDG Jacket Water Cooler Repair leak and weld repair HX cover 2/2/16 16-2-3 3 Line#1704 Perform weld repair at elbow upstream of SWN-1142 3/23/16 16-2-7 3 Line #411 Perform weld repair at F-1924 3/19/16 16-2-17 2 SR-48 Repair bent base plate on suonort 4/1/16 16-2-27 1 21 RV Penetration #50 Mechanically remove indications in reactor vessel penetration 3/22/16 16-2-39 2 Valve 728A Cut out and replace drain line due to leakinc weld 4/21/16 N/A 3 496-H-51 Replace bent suooort rod 6/5/16 16-2-66 3 Line #411 Implement EC 65389 6/26/16 16-2-76 8/23/2016 OAR-1