NL-18-1000, Lnservice Inspection Program Owner'S Activity Report for Outage 1R28

Lnservice Inspection Program Owner'S Activity Report for Outage 1R28

ML18212A333
Person / Time
Site:	Farley
Issue date:	07/31/2018
From:	Gayheart C Southern Nuclear Company
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
NL-18-1000
Download: ML18212A333 (8)

Text

~ Southern Nuclear Cheryl A. Gayheart Regulatory Affairs Director 3535 Colonnade Parkway Birmingham, AL 35243 205 992 5316 tel 205 992 7601 fax JUL 3 1 2018 Docket Nos.: 50-348 NL-18-1000 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D. C. 20555-0001 Joseph M. Farley Nuclear Plant- Unit 1 lnservice Inspection Program Owner's Activity Report for Outage 1R28 Ladies and Gentlemen:

Enclosed is the ASME Section XI Code Case N-532-5 OAR-1 Owner's Activity Report for the 1R28 Refueling Outage. Table 1, "Items with Flaws or Relevant Conditions that Required Evaluation for Continued Service," lists evaluations performed for continued service, and is provided as Enclosure 2. Table 2, "Abstract of Repair/Replacement Activities Required for Continued Service," lists repair/replacement activities, and is provided as Enclosure 3.

This report is for the 1st period of the 51h Interval lSI activities (Interval 5, Period 1, Outage 1).

This letter contains no NRC commitments. If you have any questions, please contact Jamie Coleman at 205.992.6611.

Respectfully submitted, CAG/ndj/sm

Enclosure:

1. 1R28 Form OAR-1 Owner's Activity Report

2. 1R28 Form OAR-1 Owner's Activity Report, Table 1, Items with Flaws or Relevant Conditions that Required Evaluation for Continued Service

3. 1R28 Form OAR-1 Owner's Activity Report, Table 2, Abstract of Repairs/Replacement Activities Required for Continued Service

U.S. Nuclear Regulatory Commission NL-18-1 000 Page 2 cc: Regional Administrator, Region II NRR Project Manager- Farley Nuclear Plant Senior Resident Inspector- Farley Nuclear Plant RTYPE: CFA04.054

Joseph M. Farley Nuclear Plant- Unit 1 Enclosure 1 1R28 Form OAR-1 Owner's Activity Report

Form OAR-1 -Owner's Activity Report Report Number 1-5-1-1 (Unit 1, 51h Interval, 1"1 Period, 1"1 Report)

Plant Joseph M. Farley Nuclear Plant- 7388 North State Highway 95, Columbia, Alabama 36319 Unit No. ---;;;-:=7=::-:---- Commercial Service Date _ _...:;1.=2/;..:.1:....:/1~9,;,;77'----- Refueling Outage No. 1R28 (if appticable)

Current Inspection Interval (1 "* 2.". 3'". 411 , other)

Current inspection Period 1"1 (1". 2nd, 3'")

2001 Edition through 2003 Addenda (for NDE, PT, and R&R Activities performed prior to 12/01/2017) 2007 Edition through 2008 Addenda (for ALL Section XI Activities Edition and Addenda of Section XI applicable to the Inspection Plans starting on 12/01/2017)

Volume 1-3/15/2018 (Version 3.0), Volume 3-1/24/2018 (Version 1.0),

Volume 4- 12/20/2017 (Version 1.0), Volume 5- 3/15/2018 (Version 1.0),

Volume 6-1/4/,2018 (Version 1.0), Volume 7-11/27/2017 (Version 1.0),

1R28 Outage Plan -1/~6/2018 (Version 1.0), 1R28 Outage Plan Scope Change (SC-001)-

Date and revision of Inspection plans (Version 1.0), and 1R28 Outage Plan Scope Change (SC-002)- 517/2018 (Version 1.0)

Edition and Addenda of Section XI Applicable to Repair/Replacement Activities, If different than the Inspection Plans Same Code Cases Used for inspection and evaluation: N-513-3, N-532-5, N-716-1 , N-722-1, N-729-4, N-770-2, N-798, N-800, N-805, and N-854 (if applicable, Including case* 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 1R28 conform to the requirements of Section XI. (Refueling outage No)

V "'? /tt>9/ Z.tDI8 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 The Hartford Steam Boiler Inspection and Insurance Companv 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 a loss of any kind arising from or connected with this inspection.

Rodney Se~~~ Inspector's ~nature Commission 12603 C IN R, FL445 (National Board Number and Endorsement)

Date 01 /1 o / ~D/ S

Joseph M. Farley Nuclear Plant - Unit 1 Enclosure 2 1R28 Form OAR-1 Owner's Activity Report, Table 1, Items with Flaws or Relevant Conditions that Required Evaluation for Continued Service

Table 1 Items with Flaws or Relevant Conditions that Required Evaluation for Continued Service Joseph M. Farley Nuclear Plant- Unit 1 (Cycle 28)

Examination Category Item Description Evaluation Description and Item Number Two Through Wall leaks on U1 Service Water Strainer Flaw was evaluated in accordance with Code Case N-NIA backwash line located between Q1P16V567 and 513-3 and the impacted piping was replaced under Q1P16V568 SNC893839.

Flaw was evaluated in accordance with Code Case N-Through Wall leak on U1 A train Service Water NIA 513-3 and the impacted piping was replaced Miniflow piping.

under SNC929004.

ALA 1-11 OOC-BMV, During the RPV bottom head Evaluated as documented in IER-001 as leakage from inspection, in the reactor vessel sump, what appeared N-722 a previous reactor cavity seal leak and not a pressure to be boric acid residue was noted on the vessel wall 815.80 boundary leak. Accumulation cleaned in 1R2B under and containment liner. The accumulation was heavy, SNC938904.

dry, with some discoloration.

ALA2-4100-MS3-H6, The west spring can is out of design specification tolerance, but within operating Spring cans setting were evaluated in IER-002 and F-A range. West can has Cold Load Setting of 17690 lbs.

adjusted to meet cold setting tolerance per D-180040 F1.20C East can has a Cold Load Setting 17690 lbs. Per during 1R2B under SNC939544.

0180040 Rev.6.0 Cold Load Setting is 192941bs. +or

- 8851bs.

ALA 1-4304-7-RB, Weld #7 adjacent base material had Gouges were evaluated in IER-003 as rubbing from R-A multiple circumferential gouges approximately .0625" insulation joints. The gouges were removed via R1 .11116 in depth. polishing in 1R28 under SNC938667.

Tendon H-11AB was refurbished and reinstalled by L-B Unit 1 Containment hoop tendon H-11AB field anchor PSC. The field anchor head, shop anchor head, L2.30 head found cracked. bushing and 17 strands of the tendon were replaced under SNC858196.

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Joseph M. Farley Nuclear Plant- Unit 1 Enclosure 3 1R28 Form OAR-1 Owner's Activity Report, Table 2, Abstract of Repairs/Replacement Activities Required for Continued Service

Table 2 Abstract of Repair/replacement Activities Required for Continued Service Joseph M. Farley Nuclear Plant- Unit 1 (Cycle 28)

Code Class Item Description Description of Work Date Completed R&R Work Order 6" SWPiping Removed and Replaced all piping between Q1P16V567 and 3 4/6/2018 SNC893839 HBC-205 Q1P16V568.

8"SWPiping Removed and Replaced 'A' Train Service Water Miniflow 4/20/2018 SNC929004 3 HBC-214 Piping.

Stainless steel socket weld on line 1"-HCC-110, 3 Removed and Replaced 1" drain piping and valve. 3/27/18 SNC821074 upstream side of drain valve Q1G31V017 Page 1 of 1