L-21-017, Eighteenth Inservice Inspection Summary Report
| ML21181A075 | |
| Person / Time | |
|---|---|
| Site: | Perry  |
| Issue date: | 06/29/2021 |
| From: | Penfield R Energy Harbor Corp |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| L-21-017 | |
| Download: ML21181A075 (6) | |
Text
energy harbor Rod L. Penfield Site Vice President, Perry Nuclear June 29, 2021 L-21-017 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 10 Center Road P.O. Box 97 Perry, Ohio 44081 440-280-5382 10 CFR 50.55a(g)
Perry Nuclear Power Plant Eighteenth lnservice Inspection Summary Report In accordance with 10 CFR 50.55a, "Codes and standards," and the American Society of Mechanical Engineers Boiler and Pressure Vessel Code,Section XI, "lnservice Inspection," 2001 Edition through 2003 Addenda, Article IWA-6000, 2013 Edition, and ASME Code Case N-532-5, enclosed please find the inservice inspection summary report for examinations performed prior to and during the eighteenth refueling outage at Perry Nuclear Power Plant (PNPP). This submittal provides the PNPP inservice inspection summary for the timeframe of April 7, 2019, to April 8, 2021.
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, Manager - Fleet Licensing, at (330) 696-7208.
Sincerely, 1i/l<Yt.'
Rod L. Penfield 1
Perry Nuclear Power Plant L-21-017 Page 2
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-21-017 Form OAR-1 Owners Activity Report (3 Pages Follow)
Report Number Plant Unit No.
(if applicable)
Current inspection interval Current inspection period FORM OAR-1 OWNER'S ACTIVITY REPORT PY-OARl-18 Perry Nuclear Power Plant, 10 Center Road, Perry, OH 44081 Report No.: PY-OARI-18 Commercial service date November 18, 1987 Refueling outage no.
1Rl8 4th (I st, 2nd, 3rd, 4th, other) 1st (1st, 2nd, 3rd)
Edition and Addenda of Section XI applicable to the inspection plans 2001 Edition Through 2003 Addenda (3'* Interval, 3rd period), 2013 Edition (4th Interval, 1st Period)
Inservice Examination Plan (ISEP) Revision 21 dated 1/24/2019 (3'* Interval, 3rd period),
Date and revision of inspection plans Revision 22 dated 5/17/19 (4th Interval, l Period), and Revision 23 dated 2/9/21 (4"' Interval, 1 st Period Edition and Addenda of Section XI applicable to repair/replacement activities, if different than the inspection plans of the 2017 Edition via relief request: NRC SE ML20279A440.
IWA-4540(b)
Code Cases used for inspection and evaluation:
The following are permitted by the !SEP: N-513-4, N-532-5, N-561-2, N-562-2 (if applicable, including cases modified by Case N532 and later revisions)
N-597-3, N-613-2, N-648-2, N-661-3, N-666-1, N-695-1, N-716-1, N-735, N-747, N-786-1, N-789-2, N-798, N-800, N-8231-1, N-825 N-831, and N-854 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 confonn to the requirements of the ASME Code,Section XI.
Signed Date CERTIFICATE OF INSERVICE INSPECTION 1R18 (refueling outage number) 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 Company of Hartford, CT having 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 the ASME Code, Section XL 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 liabl manner for any personal injury or property damage or a loss of any kind arising from or connect with this inspection.
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Page 1 of 3 c___,.....
Report No.: PY-OARl-18 It "th Fl ems w1 aws or RI e evan on I !ODS at eqmre tC dT TABLE 1 Th R
dE f
va ua 10n or on mue f
C t*
dS erv1ce Examination Category and Item Number C-B/C2.21 C-B/C2.22 F-A/Fl.SN F-A /F2.SN Ab stract o fR
. /R epair Code Class Item Description Emergency Service Water 3
Piping Downstream of IP45F0523 3
Reactor Water Cleanup Pump IG33C0001A Reactor Core Isolation 2
Cooling Waterleg Pump IE5JC0003 Standby Diesel Generator 3
Jacket Water Circulating Pumo 1R46C0005A 2
Service Air System Check Valve 1P51F0530 1
Main & Reheat Steam Snubber IN22H0015 1
Main & Reheat Steam Snubber IN22H0013 2
F eedwater Injection Line 1N27F0542A 2
Emergency Service Water Snubber IEl2H0365 1
Main & Reheat Steam Snubber 1N22H0J31 I
Main & Reheat Steam Snubber IN22H001 l Flex Hose Connected to 3
Safety Relief Valve 1B21F0041B Flex Hose Connected to 3
Safety Relief Valve IB21F00SIB Item and Flaw or Relevant Condition Descriotion Evaluation Descriotion CR 2020-04636 identified increased loads on the RHR Heat Exchanger N4 Nozzle exceeding vendor allowable limits. Based on RHR Heat Exchanger 1 E 12B000 IC review of available data and industry guidance, engineering has determined there is reasonable Nozzle N4 Increased Loads assurance that the heat exchanger is capable of performing its design function. CA-2020-04636-001 tracks resolution via repair for this condition.
CR 2020-06809 identified this snubber to be Snubber 182107091 As-Left Cold Set outside of its design cold set tolerance.
Found Outside of Design Tolerances Engineering surveillance and evaluation determined there is no operability concern with the As-Left Cold Set.
CR 2021-02348 identified this snubber to be outside of its design cold set tolerance.
Snubber IE12H0325 As-Left Cold Set Engineering evaluation determined there is no Found Outside of Design Tolerances operability concern with the As-Left Cold Set and that there is acceptable movement remaining.
ep acemen tA ctiv1t1es eqmre TABLE2 R
or on mue df Cf dS erv1ce Date Completed Repair/Replacement Description of Work (1)
Plan Number 200760600 Replace 8" Elbow, Piping, and Flange 06/04/2019 (2)
Replaced Pump 07/14/2020 200816464 Replaced Pump 09/15/2020 200783455 Replaced Pump 01/27/2021 200833955 Replace Poppet 04/12/2021 200812516 Replaced Snubber 04/20/2021 200798461 Replaced Snubber 04/20/2021 200798459 Replaced 3/4" Half Coupling 04/20/2021 200790601 Replaced Snubber 04/21 /2021 200740468 Replaced Snubber 04/21/2021 200798465 Replaced Snubber 04/21/2021 200798460 Replace 2" Flexible Metal Hose 04/26/2021 200847374 Replace 2" Flexible Metal Hose 04/26/2021 200847431 Page 2 of 3
Notes:
Report No.: PY-OARl-18 3
Fuel Pool Cooling Snubber I Replaced Snubber 04/26/2021 200740767 1G41H0450 Emergency Service Water 3
Pump A Discharge Valve Replace Piping 04/29/2021 200774864 1 P45FO 130A Downstream Piping Reactor Water Cleanup 3
Filter Demineralizer First Replaced Valve and Actuator 05/02/2021 200789608 Inlet Valve l G36F0002A Reactor Water Cleanup 3
Filter Demineralizer Second Replaced Valve and Actuator 05/02/2021 200789609 Inlet Valve 1G36F0001A 2
MSL D Shutoff Before Seat Rebuild Valve/Actuator/Replace Stem 05/04/2021 200789280 Drain 1N22F0420D Spool Piece Between 3
Emergency Service Water Replace 14" Spool Piece and 05/06/2021 200758363 ECC HX Bypass and Valve Downstream Piping 1P45F5466A Reactor Water Cleanup Pipe Spools Between 3
Regenerative Heat Replaced Pipe Spools 05/06/2021 200674600 Exchangers l 03380001 A and 1033800018 Bolting Hardware for l
Reactor Core Isolation Replace stud and nut hardware 05/06/2021 200779566 Cooling Head Spray Piping Flange 2 3
Reactor Water Cleanup Replace Pump/Motor Assembly 06/15/2021 200846004 Pump IG33C0001B (1)
"Date Completed" Is the date the final NIS-2A signature was applied. This date may be after the end of the reporting period for work that was physically completed within the reporting period.
(2)
Perry Nuclear Power Plant entered its Fourth Inspection Interval on May l 8ili, 2019. As such, the time between the end of !Rl 7 and the beginning of the Fourth Inspection Interval are governed by the 2001 Edition and 2003 Addendum of ASME Section XI.
These dates encompass April 7th, 2019 to May I ?ili, 2019.
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