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| {{#Wiki_filter:FENOC Perry Nuclear Power Plant 10 Center Road | | {{#Wiki_filter:FENOC Perry Nuclear Power Plant 10 Center Road PO. Box 97 FirstEnergy Nuclear Operating Company Perry, Ohio 44081 June 26, 2019 L-19-119 10 CFR 50.55a(g) |
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| PO. Box 97 FirstEnergy Nuclear Operating Company Perry, Ohio 44081 June 26, 2019 L-19-119 10 CFR 50.55a(g) | |
| ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555-0001 | | ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555-0001 |
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Category:Letter type:L
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[Table view] |
Text
FENOC Perry Nuclear Power Plant 10 Center Road PO. Box 97 FirstEnergy Nuclear Operating Company Perry, Ohio 44081 June 26, 2019 L-19-119 10 CFR 50.55a(g)
ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555-0001
SUBJECT:
Perry Nuclear Power Plant Docket No. 50-440, License No. NPF-58 Perry Nuclear Power Plant Seventeenth lnservice Inspection Summary Report In accordance with the American Society of Mechanical Engineers Boiler and Pressure Vessel Code,Section XI, "lnservice Inspection," 2001 Edition through 2003 Addenda, Article IWA-6000, and ASME Code Case N-532-5, enclosed please find the Owner's Activity Report (Form OAR-1) covering inservice inspection (ISi) activities performed during operating cycle 17 and refueling outage 17 at the Perry Nuclear Power Piant (PNPP). This submittal provides the PNPP inservice inspection summary for the timeframe of April 4, 2017 to April 6, 2019.
There are no regulatory commitments contained in this submittal. If there are any questions or if additional information is required, please contact Mr. Phil H. Lashley, Acting Manager - Nuclear Licensing and Regulatory Affairs, at (330) 315-6808.
Enclosure:
Form OAR-1 Owner's Activity Report cc: NRC Region Ill Administrator NRC Resident Inspector NRC Project Manager Ohio Department of Commerce, Boiler Inspection Section
Enclosure L-19-119 Form OAR-1 Owner's Activity Reporl (3 Pages Follow)
Report No.: PY-OARI-17 FORM OAR-I OWNER'S ACTIVITY REPORT Report Number PY-OARl-17 Plant Perry Nuclear Power Plant, 10 Center Road, Perry, OH 44081 UnitNo. Commercial service date November 18. 1987 Refueling outage no. IR17 (if applicable)
Current inspection interval Third (lst;2nd, 3rd, 4th, other)
Current inspection period Third
( I st, 2nd, 3rd)
Edition and Addenda of Section XI applicable to the inspection plans 2001 Edition through 2003 Addenda Inservice Examination Plan (ISEP) Revision 18 dated 11/18/16, Revision 19 dated 9/6/17, Date and revision of inspection plans Revision 20 dated 11/15/18. and Revision 21 dated 1/24/19 Edition and Addenda of Section XI applicable to repair/replacement activities, if different than the inspection plans _N_/A_ _ _ __
Code Cases used for inspection and evaluation: The following are pennitted by the ISEP: N-461-1, N-513-3, N-513-4, N-526, (if applicable. including cases modified by Case N-532 and later revisions)
N-528-1, N-532-5, N-537, N-552, N-561-2, N-562-2, N-566-2. N-578, N-586-1, N-613-1, N-624, N-648-1, N-652-1, N-658, N-661-2, N-663, N-664, N-665, N-666, N-683, N-685, N-695, N-700, N-705, N-716-1, N-735, N-747 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 lRl 7 (refueling outage number)
Signed Date 04/40, CERTIFICATE OF INSERVICE INSPECTION 1, 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 of having inspected the items described in this Company Hartford, CT Owner's Activity Report, and state that, to the best ofmy knowledge and belief, the Owner has perfonned 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. Furthennore, neither the Inspector nor his employer shall be L i ~ ~ manner for any personal injury or property damage o.r a loss o:,_any kind arising fr~m or connect with this inspection.
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- Commission .A(B IS <?a Z- tJ ff I 1--~!!!=!ii!=::=.>-~~;;.;..,.&::=~- (National Bolll'd Number and Endorsement)
Date ,/4-/4 f (06/11)
Page 1 of 3
Report No.: PY-OARl-17 TABLE 1
. h Fl awsor RI I terns wit e evan tCon d°f I IODS Th at . R eqmre
- dEva uabon fior ContmuedS erv1ce Examination Category and Item Number Item Description Evaluation Description CR-2017-08106 identified a through wall 3" ESW B Piping in Vicinity of leak that subsequently required evaluation for D-B /02.10 1P45F5466B continued operation in accordance with ASME Code Case N-513-3.
14" Emergency Service Water "B" Piping between 1P45F0541B CR-2017-08581 identified a through wall and heat exchanger 1P42B000 lB. leak that subsequently required evaluation for D-B /02.10 Also between valve 1P45F0541B continued operation in accordance with and second elbow downstream of ASME Code Case N-513-4.
the valve.
3" Emergency Service Water "ff' CR-2017-08736 identified wall thinning that D-B /02.10 Piping in the vicinity of was evaluated and determined to be above 1P45F5466B minimum wall thickness limits.
CR-2018-05504 identified a through wall 20" Emergency Service Water leak that subsequently required evaluation for D-B /02.10 "A" Piping between valves continued operation in accordance with 1P4SF0SS0A and 1P4SF0068A ASME Code Case N-513-3.
24" Emergency Service Water CR-2018-10362 identified wajl thinning that D-B /02.10 "A" Piping downstream of was evaluated and determined to be above discharge valve 1P45F0130A minimum wall thickness limits.
CR-2019-02328 identified a 2 in 2 area on the containment vessel interior surface with a damaged coating (checking). The evaluation E-A I El.11 Containment Surface 1T23-022-1 determined that containment structural integrity or leak tightness are not affected, and the condition is acceptable.
CR-2019-01634 identified this variable spring support being found outside of its design hot/cold settings. Previously F-A / Fl.SP Variable Spring 1E21-H0089 performed engineering analysis bounded this condition and therefore the condition is acceptable.
TABLEl Ab stract o fR epa1r . /Rep Iacement A ctlvities R eqmre . dfior C ontmuedS erv1ce Code Repair/Replacement Plan Class Item Descriotion Description of Work Date Completed Number High Pressure Core Spray Starting Air 3 Replace piping 07/18/2017 200691740 Piping with flange and hardware High Pressure Core Spray Piping elbow Weld overlay of 4" 2 downstream of orifice 03/01/2018 200737512 elbow 1E22D000 1 on HPCS Minimum Flow Line Control Complex Replace hex screws for 3 Chilled Water Chiller 03/01/2018 200617253 reassembly "B" Hardware Div. 1 Standby Diesel Generator Left Bank 3 Receiver Outlet Replaced valve disc 03/01/2018 200559512 Isolation Valve 1R44F0562A Page 2 of 3
Report No.: PY-OARI-17 High Pressure Core Spray Piping elbow 2 downstream of orifice Replace 4" elbow 06/12/2018 200737508 1E22D0001 on HPCS Minimum Flow Line Emergency Service Water "A" Piping Install reinforcing pad 3 between valves 10/09/2018 200757942 over leak in 20" piping 1P45F0550A and 1P45F0068A Fuel Pool Cooling and 3 Cleanup Pump 0041- Replace pump 01/25/2019 200251252 C0003B Emergency Service Patch piping using rolled 3 Water "B" Piping near 04/01/2019 200767679 plate valve 1P45F0541B
., Emergency Service Remove 3" bypass 3 Water "B" Piping in the 04/03/2019 200726587 piping/components vicinitv of 1P45F5466B Emergency Service Water "B" Piping between 1P45F0541B and heat exchanger 3 1P42B0001B. Also Replace 14" piping 04/03/2019 200726587 between valve 1P45F0541B and second elbow downstream of the valve.
Reactor Water Cleanup Piping between heat 3 exchangers Replace 4" piping 04/11/2019 200724734 1G33B0001C and 1G33B0002a Residual Heat Removal Replace stud and nut 2 04/16/2019 200007545 Valve IE12F0011B hardware Bolting Hardware for Reactor Core Isolation Cooling Head Spray Replace stud and nut 1 Piping Flanges # 1, #3, 05/01/2019 200694625 hardware
- 7, (IB13-N8-B, 1E51-0009-B, and 1821-0186-B)
Emergency Service Water "A" Piping 3 between valves Replace 20" piping 06/05/2019 200757843 1P45F0550A and 1P45F0068A Page 3 of 3
