JAFP-19-0004, Inservice Inspection Summary Report Cycle 23

Inservice Inspection Summary Report Cycle 23

ML19004A353
Person / Time
Site:	FitzPatrick
Issue date:	01/04/2019
From:	Drews W Exelon Generation Co
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
JAFP-19-0004
Download: ML19004A353 (6)

Text

James A. FitzPatrick NPP Exelon Generation@ P.O. Box 110 Lycoming, NY 13093 Tel 315-342-3840 William C. Drews Regulatory Assurance Manager - JAF JAFP-19-0004 January 4, 2019 United States Nuclear Regulatory Commission Attn: Document Control Dek Washington, D.C. 20555 James A. FitzPatrick Nuclear Power Plant Renewed Facility Operating License No. DPR-59 NRC Docket No. 50-333

Subject:

lnservice Inspection Summary Report Cycle 23

Reference:

1) Entergy letter, Fourth Interval lnservice Inspection Program Plan, JAFP-07-0030, dated February 27, 2007

2) Exelon letter, Fifth Ten-Year lnservice Inspection Interval Program Plan, JAFP-18-0113, dated December 17, 2018

Dear Sir or Madam:

This letter submits the James A. FitzPatrick Nuclear Power Plant (JAF) Owner's Activity Report, Third Period, Fourth Interval and First Period, Fifth Interval which contains a summary of the lnservice Inspection (ISi) examinations conducted during the plant's 2018 Refuel Outage 23 (FP1 R23).

Table 1 of the enclosed report summarizes the items with flaws or relevant indications that required evaluation for continued service and Table 2 provides an abstract of repair/replacement activities required for continued service.

This report is being submitted in accordance with JAF's approved Fourth Interval lnservice Inspection Program Plan [Reference 1] and Fifth Interval lnservice Inspection Program Plan [Reference 2].

There are no new regulatory commitments contained in this letter. If you have any questions in this regard, please contact Mr. Michael Faivus, Programs Engineering Branch Manager, at (315) 349-1895.

• Very truly yours,

~~ cfa-,

William C. Drews Regulatory Assurance Manager WCD/mh

Enclosure:

JAF Owner's Activity Report (OAR) First Period, Fifth Interval cc: NRC Region 1 Administrator NRC Project Directorate NRC Resident Inspector NYSE RDA

JAFP-19-0004 ENCLOSURE JAF Owners Activity Report (OAR)

First Period, Fifth Interval (4 Pages)

FORM OAR-1 OWNER'S ACTIVITY REPORT Report Number FP1 R23 Plant _ _ _ _ _ _--=Ja=m"-'=es=A'-"-'.F~ig=-P=at~ri=ck~N~u~c-le=a_r~P~o=w=er~P~l=an=t~.2=6=B~L=a=k=e~R=d~**~L~vco~m=in=g~.~N=e=w-Y~o=~""""'13~0=9=3 Plant Unit,,--,,-...,.,,...,-- Commercial Service Date -------=J:.::u...,ly~2'""8._ . . . .,19._.7_,.5_ _ _ __ Refueling Outage Number R23 c;r applicable)

Current Inspection lnterval: _ _ _ _ _ _ _ _ _ _ _ _~F~ift=h~..,..,......,.._.....,.._--

1111. 2nd, 3rd, 41h, Olhat)

Current Inspection Period:_ _ _ _ _ _ _ __,_F"'irs"'t~--,,-:-::--:-:-::------------------------

c1s1, 2nd. 3rd)

Edition and Addenda of Section XI applicable to the Inspection Plan: 2001 Edition. 2003Addenda from Februarv 24. 2017 to July 31. 2017 and 2007 Edition. 2008 Addenda from August 1, 2017 to present.

Date and Revision of Inspection Plan: SEP-ISl-007. Revision 9. July 19. 2017 for the Fourth ISi Interval and ER-JF-330-1001. Rev. 1. November 30.

2018 for the Fifth ISi Interval Edition and Addenda of ASME Section XI applicable to Repairs and Replacements, if different than the Inspection Plan: Same Code Cases used: N-460. N-513-4. N-532-5, N-552-1. N-578-1 N-613-2. N-639. N-648-1, N-663. N-695. N-702, N-716-1. N-747. N-798. N-800. N-823,

~

(d applcable)

CERTIFICATE OF CONFORMANCE I certify that (a) statements made in this report are correct; (b) the examination 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 R23 canto the requirements of ection XI. (refuollng outago number)

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 New York and employed by The Hartford Steam Boiler Inspection and Insurance Company 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 evaluations 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 a loss of any kind arising from or connected with this inspection.

~~----

---'-~;__-"Flns:::;p_ec.,...to"'"(s'"=s-,gl\ll--.-tur_e____________

Commissions 16158ANIRNY5570 Natiofllll Board, Slate, Province. and Endorsements Date f("'I / I q

Table 1:

Items with Flaws or Relevant Conditions That Required Evaluation for Continued Service Examination Category Item Description Evaluation Description and Item Number D-B/D2.10 Through-wall leak on line 15 IR 4138318 - Through wall leak on ESW WES-151-136 Line 3-WES-151-136 ASME Section XI Code Case N-513-4 was employed and concluded the flaw was caused by MIC. The section of pipe was replaced online. Extent-of-condition examinations were performed on 5 comparable locations and were completed satisfactorily.

D-B/D2.10 Low Reading on Supply/Return IR 4101455 - Low reading on supply/return Piping to 66UC-22F piping to 66UC-22F.

EC 623104 was developed to evaluate the wall thickness. The evaluation concluded the wall thicknesses to be acceptable.

D-B/D2.10 UT Readings Below Min Wall IR 4104026 - UT readings below min wall Acceptance Criteria for 66UC- acceptance criteria 22C EC 623104 was developed to evaluate the wall thickness of the supply and return lines to 66UC-22C. The evaluation concluded the wall thicknesses to be acceptable.

F-A/F1.10c 10-1-AS-210 Variable Spring IR 4175079 - ISI IWF Exam - Missing Support missing load indicator Load Indicator Scale.

scale An engineering evaluation was performed and attached to the IR as follows:

10-1-AS-210 is one of two identical BP VSIC spring cans (10-1-AS-210 and 10 AS-211) that constitute hanger PFSK-4644.

10-1-AS-210 is missing the load indicator plate. 10-1-AS-211 is the other spring can that has the load indicator the distance from the top can to the spring coil. A ruler was placed on the can to obtain the distance. The picture of the 10-1-AS-210 shows a distance of 1.18 inches. The picture of the 10-1-AS-211 shows a distance of 1.30 inches. The difference between those two readings is 10%. The tolerance per EC 9000067222 is 15%.

Additionally, the photos were taken from different angles, the position of the rulers is different, it seems to protrude more for 10-1-AS-211, giving the impression that the reading is 1.3, were the pictures taken (from the same angle) level with opening, the measurement might be closer or even the same.

Based on the above, it is concluded that 10-1-AS-210 is acceptable.

F-A/F1.20sc Non-Safety Related snubber IR 4161492 documented the installation of installed at location 10-8A-HS- a non-safety related snubber installed. EC 35A 625064 was performed to evaluate the snubber was acceptable to be installed.

F-A/F1.40 ISI Examination Results for IR 4174140 - ISI Examination Results for Pump Support 46P-2A Pump Support 46P-2A. Corrosion was noted on the support wall ID.

EC 9000048172 documents UT results from 2013. A PM (PMRQ # 00339914) was

generated to perform a UT within 10 years, based on the results of the EC. Work Order 81182753 is approved for the completion of the next UT, to be completed prior to 12/15/2023.

Table 2:

Abstract of Repair/Replacement Activities Required for Continued Service REPAIR/

DESCRIPTION REPLACEMENT CODE ITEM OF DATE PLAN CLASS DESCRIPTION WORK COMPLETED NUMBER 1 12-1-HS-20 Replace broken snubber 9/25/2018 18-138 12-1-HS-20 1 12-1-HS-19 Replace broken snubber 9/27/2018 18-060 12-1-HS-19 1 12-1-HS-18 Replace broken snubber 9/19/2018 18-137 12-1-HS-18 1 02-2-1A-AN-21 Replace missing hex nut 9/29/2018 18-145 on 02-2-1A-AN-21 2 10-8A-HS-35A Replace Non-SR 8/13/2018 18-149 snubber with SR snubber 3 70PCV-100B2 Replace 70PCV-100B2 4/10/2017 17-015 3 Piping Upstream of Replace piping 4/13/2017 17-017 46SWS-120E upstream of 46SWS-120E 3 67UC-16A Replace 67UC-16A coils 11/29/2017 17-026 3 46EXJ-10D Replace 46EXJ-10D 9/27/2018 17-021 expansion joint 3 66UC-22E Repair covers on 66UC- 12/1/2017 17-027 22E 3 66UC-22H Replace 66UC-22H 11/17/2017 17-036 Coils 3 66UC-22C Replace 66UC-22C 2/22/2018 17-034 Coils 3 67UC-16B Replace 67UC-16B 3/20/2017 17-012 Coils 3 10P-1C Replace degraded bolts 9/29/2018 18-144 on 10P-1C casing 3 10P-1A Replace degraded bolts 9/28/2018 18-143 on 10P-1A casing 3 46EXJ-10A Replace 46EXJ-10A 2/20/2018 17-020 Expansion Joint