ML18009A434

Submittal of T1R22 Refueling Outage Lnservice Inspection Owner'S Activity Report

ML18009A434
Person / Time
Site:	Three Mile Island
Issue date:	01/08/2018
From:	Callan E Exelon Generation Co
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
TMl-17-114
Download: ML18009A434 (6)

Text

Exelon Generation TMl-17-114 January 8, 2018 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Three Mile Island, Unit 1 Renewed Facility Operating License No. DPR-50 NRC Docket No. 50-289

Subject:

Three Mile Island Nuclear Station, Unit 1 T1R22 Refueling Outage lnservice Inspection (ISi) Owner's Activity Report and Attachments The purpose of this letter is to provide the Three Mile Island Nuclear Station Owner's Activity Report {OAR-1) for lnservice Inspections as required by the American Society of Mechanical Engineers (ASME) Code,Section XI, 2004 Edition with no Addenda and ASME Code Case N-532-5 Repair/Replacement Activity Documentation Requirements and lnservice Summary Report Preparation and Submission - Section XI, Division 1. is the ISi Owner's Activity Report covering ISi activities associated with T1R22 Refueling Outage which started on September 18, 2017 and was the 2nd outage of the 2nd period of the 4th ISi inspection interval.

There are no commitments in this letter.

Should you have any questions concerning this letter, please contact Mr. Michael Fitzwater at (717) 948-8228.

Respectfully, cwCL-E.W. Callan Site Vice President, Three Mile Island Unit 1 Exelon Generation Co., LLC - ISi Owner's Activity Report - T1R22 Outage cc: USNRC, Regional Administrator, Region I USNRC, Senior Project Manager, NRR USNRC, Senior Resident Inspector, TMI Roger R. Smith, The Hartford Steam Boiler Inspection and Insurance Company

T1R22 Refueling Outage lnservice Inspection {ISi)

Owner's Activity Report Page 2 Attachment 1 ISi Owner's Activity Report -T1R22 Outage

FORM OAR-1 OWNER'S ACTIVITY REPORT Report Number: _T.:.:1""R==2=-2----------------------------

Plant: Three Mlle Island Nuclear Station. Route 441 South, Londonderry Township. Mlddletown, PA 17057 Unit No: -'1=--____Commerclal service date: September 2, 1974 Refueling Outage No: _T1.._..R=22_ __

(If applicable)

Current Inspection Interval: ...ll~Sli..;;=;;...;4~th_,/;..:C=:a1S::l.;;;=~2,_"d---------------------

l1", 2"', 3", 411', other)

Current Inspection period: ..Jl::Sli..;;=..,2,,_"d..../r..;C::l..,Sl._=...2 . _ " d - - - - - - - - - - - - - - - - - - - - -

ll",2"',31CJ Edition and Addenda of Section XI appllcable to the Inspection plans: 2004 Edition with No Addenda Date and revision of Inspection plans: . 10/27/2015 Rev. 3A; 10/03/2016, Rev. 4; 9/14/2017, Rev. 4A Edition and Addenda of Section XI applicable to repair/replacement activities, If different than the Inspection plan~

N Code Cases used for Inspection and evaluation: N-432-1. N-460. N-504-4, N-508-4. N-513-3, N-516-3 1 N-517*1, N*

526, N-528-1, N-532-s, N-552, N-557-1, N-561-2, N-562-2, N-566-2, N-569-1, N-58§:1, N-593, N-597-2, N-600, N-613-1 1 N-619, N-624. N-629, N-638-4. N-639. N-641, N-643-2, N-648-1. N-651, N-661*1, N-661-2, N-665.

N-666. N-686-1, N-695. N-696. N-705, N-706-1. N-722*1, N-729-4. N-731, N-733. N-735, N-739. N-739-1. N-751.

N-753. N-770-2, N-773. N-786. and N-789 llf appllcable, Jncludl111 cases modified by N-532 and later l'l!Vlslans)

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 T1R22 conform to the requirements of Section XI.

(refuellns autaae number)

Signed Mark Weis, Fleet ISi Program Owner 6lYLQ(\,Q; Date \/, /zo1t, Owner ar Owner's Deslsnee, Title CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission Issued by the National Board of Boller and Pressure Vessel Inspectors and employed bv. The Hartford Steam Boller Inspection and Insurance Company 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 personnel Injury or property damage or a loss of any kind arising from or connected with th~~pectlon.

Roger Smith ~ ~~ Commission __N_B.._1..33-2_..8....A._N__I _ _ _ _ _ _ _ _ __

~ r ' s Slanature (Natlanal Baard Number and Endonement)

Date 1/s-l.zo1K

Table 1 Items with Flaws or Relevant Conditions That Required Evaluation for Continued Service Examination Item Description Evaluation Description Category and Item Number E-A, El.30 / E-A, E4.11 Containment liner moisture barrier Partial separation of moisture barrier and surface region rust were evaluated as acceptable for one cycle (reference issue report 04058749).

E-A, El.11 Containment liner 281-305, Minor rust not reducing remaining liner thickness Containment liner 305-326, and degraded coating areas were evaluated as Containment Liner 346-436 acceptable. (reference issue reports 4059230, 4055816,4055267,4055131,4054683,and 2583685)

F-A, Fl.20 Support DHH0133Support Misalignment and spring can settings evaluated as acceptable. (Reference issue report 4059311)

F-A, Fl.20 Support MUH0104Support Spring can settings, bent rod, and bolted connection conditions evaluated as acceptable.

F-A, Fl.40 Steam Generator Loose anchor bolting was tightened and RCHOOOlARCHlAlSupport expanded examination scope to (Support skirt anchor bolting) RCHOOOlBRCHlBl. (reference issue report 4055111)

F-A, Fl.40 Steam Generator Loose anchor bolting was tightened. (reference RCHOOOlBRCHlBlSupport issue report 4056688)

(Support skirt anchor bolting)

D-A, 02.10 Valve CA-V-173 Body to bonnet leak evaluated as acceptable and cleaned subsequent to discovery.

B-P, B15.10 Valve MU-V-lA Packing boron deposit cleaned and verified no active leakage after cleaning.

B-P, B15.10 Valve RC-V-17 Packing boron deposit cleaned, packing adjusted, and verified no active leakage after cleaning.

B-P, B15.10 Valve RC-V-21 Packing boron deposit cleaned and verified no active leakage after cleaning.

C-H, C7.10 Valve MU-V-12 Packing boron deposit verified no active leakage and evaluated as acceptable.

C-H, C7.10 Valve DH-V-38B Body to bonnet boron deposit cleaned and verified as inactive and acceptable after cleaning.

C-H, C7.10 Temperature Element DH6-TE-2 Threaded connection boron deposit inactive and evaluated as acceptable.

C-H, C7.10 Valve SF-V-19 Packing and body to bonnet boron deposits.

Valve cleaned and packing adjusted.

C-H, C7.10 24" Flange at Borated Water Boric acid deposit at flanged connection cleaned Storage Tank and evaluated as acceptable.

C-H, C7.10 Pump BS-P-lA Seal dried boron deposit evaluated as acceptable.

C-H, C7.10 Valve MU-V-1040 Two drops per minute packing leak evaluated as acceptable.

B-P, 815.10 MU9-FE-4 Dry white boron at tubing connection cleaned and fitting tightened.

Table 1 (continued)

Items with Flaws or Relevant Conditions That Required Evaluation for Continued Service Examination Item Description Evaluation Description Category and Item Number N/A NR-V-22C (151 Class 3) A CMTR for valve NR-V-22C was not provided with the purchase order. A CMTR is required as part of the owner's requirements. The valve material was verified to be correct using a material analyzer gun. The vendor was contacted, however a CMTR has not been provided.

Necessary corrective actions are documented in Issue Report 04089302.

--- - - - - - - - - - - - - - - - - - - - ~

Table 2 '

Abstract of Repair/Replacement Activities Required for Continued Service Code Item Description Description of Work Date Completed Repair/Replacement Class Plan Number 3 Strainer CA-S-8A Replaced bolting due to boric 04/05/2016 2600901-12, acid wastage. WO 4355815 (R2238962) 3 Piping adjacent Replaced piping adjacent valve 12/18/2017 2600901-21, valve NRV-53A NR-V-53A due to corrosion. WO 4193059 (M2415227) 1 Reactor Coolant Removed existing High Side 2/24/2017 2600901-24, Pump RC-P-lA Hi Pressure Tap Nozzle and WO 4574579 Pressure Tap installed a plug due to through Nozzle wall flaw in pressure tap.

3 24" Pipe Replaced piping in area that 9/23/2017 2600901-44, Upstream valve was evaluated acceptable per WO 4187450 NR-V-8D Code Case N-513-3 during Operating Cycle 21.

1 Steam Generator Plugged and stabilized 12/05/2017 2600901-72, RC-H-18 Tubing defective tubes with WO 4376261 mechanical plugs.