PNP 2019-011, ASME Section XI 90-Day Owner'S Activity Report

ASME Section XI 90-Day Owner'S Activity Report

ML19081A002
Person / Time
Site:	Palisades
Issue date:	03/22/2019
From:	Hardy J Entergy Nuclear Operations
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
PNP 2019-011
Download: ML19081A002 (8)

Text

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~Entergr.

Entergy Nuclear Operations, Inc.

Palisades Nuclear Plant 27780 Blue Star Memorial Highway Covert, MI 49043-9530 Tel 269-764-2000 Jeffery A. Hardy Regulatory Assurance Manager 10 CFR 50.4 PNP 2019-011 March 22, 2019 ATTN: Document Control Desk U. S. Nuclear Regulatory Commission Washington, DC 20555-0001

Subject:

ASME Section XI 90-Day Owner's Activity Report Palisades Nuclear Plant Docket 50-255 Renewed Facility Operating License No. DPR-20 In accordance with the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code,Section XI, Code Case N-532-5, Repair/Replacement Activity Documentation Requirements and Inservice Inspection Summary Report Preparation and Submission,Section XI, Division 1, Entergy Nuclear Operations, Inc. (Entergy) herein submits the Owner's Activity Report for the Palisades Nuclear Plant (PNP). The report contains a listing of 17 items with flaws or relevant conditions that required evaluation for continued service, and an abstract of four repair/replacement activities that were required for continued service. These activities were performed during the PNP twenty-sixth fuel cycle and the subsequent 2018 refueling outage (1 R26). The PNP refueling outage was completed on December 27,2018.

This letter identifies no new regulatory commitments.

Should you have any questions or require additional information, please contact Jim Miksa, regulatory assurance engineer at (269) 764-2945.

Respectfully, 94\-\~

Jeffery A. Hardy JAH/jpm

Enclosure:

Palisades Nuclear Plant Form OAR-1 Owner's Activity Report

PNP 2019-011 Page 2 of 2 cc: NRC Region III Regional Administrator NRC Senior Resident Inspector - Palisades NRC Project Manager - Palisades

Enclosure to PNP 2019-011 Palisades Nuclear Plant Form OAR-1 Owner's Activity Report 5 pages follow

Enclosure to PNP 2019-011 Page 1 of 5 FORM OAR-l OWNER'S ACTIVITY REPORT Report Number: PLP-IR26-0AR-I Plant: Palisades Nuclear Plant Unit No: Commercial Service Date: 12/3111971 Refueling Outage No.: IR26

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(if applicable)

Current Inspection Interval: IWB, IWC, IWD, IWF: 51h IWE, IWL: 2nd (1st, 2nd, 3rd, 4th, Other)

Current Inspection Period: IWB, IWC, IWD, IWF: lSI 1 2nd IWE, IWL: 3rd (1st, 2nd, 3rd)

Edition and Addenda of Section XI applicable to the Inspection Plans:

lSI activities related to Pressure Testing (PT), and Nondestructive Examination (NDE) from 1211312015 through 11130/2017 are to AS ME BPV Code,Section XI 2001 Edition through the 2003 Addenda lSI activities related to Pressure Testing (PT), and Nondestructive Examination (NDE) after 1113012017 are to AS ME BPV Code,Section XI, 2007 Edition with the 2008 Addenda lSI program related activities related to class I, 2, and 3 components and supports to the ASME BPV Code,Section XI, 2007 Edition with the 2008 Addenda lSI activities related to IWE and IWL to the ASME BPV Code,Section XI, Division I, Subsections IWE and IWL, 2004 Edition.

Date and Revision ofInspection Plans: IWB, IWC, IWD, IWF: 10/912018 Revision 7 IWE, IWL 611512016 Revision 6 Edition and Addenda of Section XI applicable to repairlreplacement activities, if different than the Inspection Plans:

lSI related activities related to Repair and Replacement (R&R) from 12113/2015 through 1113012017 are to ASME BPV Code,Section XI 2001 Edition through the 2003 Addenda lSI related activities related to Repair and Replacement (R&R) after 11130/2017 are to ASME BPV Code,Section XI, 2007 Edition with the 2008 Addenda Code Cases used for inspection and evaluation: N-532-5, N-638-6, N-705, N-706-1, N-716-1, N-722-1, N-729-4, N-770-2 (if applicable, including cases modified by Case N-532 and later revisions)

Enclosure to PNP 2019-011 Page 2 of 5 FORM OAR-l OWNER'S ACTIVITY REPORT Report Number: PLP-IR26-0AR-l Plant: Palisades Nuclear Plant Unit No: --;;;:----;---;-;-:--

Commercial Service Date: 12/31/1971 Refueling Outage No.: lR26 (if applicable)

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 AS ME Code,Section XI; and (c) the repair/replacement activities and evaluations supporting the completion of lR26 conform to the requirements of Section XI.

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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 TAf ,Uc.r ~ S~~ ,OlUA :r~SAc.T"~.... .:t.Js~c.(i to-VAJl' of tI ~n.:rJ:"91C.O f c..r 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 loss of any kind arising from or connected with this inspection.

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Commissions: _ .....l-'-I(-=.s---'-'_~---'-N....::;U (National Board Number and Endorsement)

Date: ~/t.O 1"1..01, TABLE 1:

ITEMS WITH FLA WS OR RELEVANT CONDITIONS THAT REQUIRED EVALUATION FOR CONTINUED SERVICE Examination Item Description Evaluation Description Category and Item Number Category D-B E-54A CR-PLP-2018-0l375, Through wall leak on north end Code Item D2.1 0 Component Cooling Water (CCW) bell of E-54A CCW heat exchanger.

Heat Exchanger Class 3 Evaluation determined the component was acceptable for 52 months in accordance with ASME Code Case N-705.

The north end bell was replaced in refueling outage 1R26 under WO 52761276.

Enclosure to PNP 2019-011 Page 3 of 5 FORM OAR-! OWNER'S ACTIVITY REPORT Report Number: PLP-IR26-0AR-l Plant: Palisades Nuclear Plant Unit No: --::-::-----::,.---:-0-:---

Commercial Service Date: 12/31/1971 Refueling Outage No.: IR26 (if applicable)

TABLE 1:

ITEMS WITH FLAWS OR RELEVANT CONDITIONS THAT REQUIRED EVALUA T10N FOR CONTINUED SERVICE Examination Item Description Evaluation Description Category and Item Number Category F-A MSS-36-MSL-IS 1-211APRC(HI9) CR-PLP-2018-05329, Contact between the East side Code Item Class 2 spring can support rod and an adjacent metal F1.20C Plate.

Evaluation determined that the component was acceptable for service without corrective measures in accordance with IWF-3122.3.

Category F-A PCS-4-PRS-I P3-7PR(H-867) CR-PLP-2018-05417, Jam nut to sway strut barrel was Code Item Class 1 loose and backed off approximately 1 inch.

Fl.lOC Evaluation determined that the component was acceptable for service without corrective measures in accordance with IWF-3122.3.

Category F-A PCS-4-PRS-IP2-2PR(H-875) CR-PLP-2018-05418, Lower Jam nut to Sway Strut Code Item Class 1 Barrel was found loose.

Fl.lOC Evaluation determined that the component was acceptable for service without corrective measures in accordance with IWF-3122.3.

Category F-A MSS-8-MSV-2S2-208PR3(R55.1) CR-PLP-2018-05474, Thread engagement is less than Code Item Class 2 flush.

F1.20B Evaluation determined that the component was acceptable for service without corrective measures in accordance with IWF-3122.3.

Category F-A FWS-18-FWL-2S1-252PR(H34A) CR-PLP-2018-05636, The nut on the northwest spring Code Item Class 2 can to the embedded plate was found to be loose and F1.20C could be turned by hand.

Evaluation determined that the component was acceptable for service without corrective measures in accordance with IWF-3122.3.

Category F-A ESS-6-SIS-l B I-lPR 1(H702.2) CR-PLP-2018-05794, Misalignment noted on spring can Code Item Class 2 extension support tube.

F1.20C CR-PLP-2018-05989, Spring can setting out of tolerance

>10%.

Enclosure to PNP 2019-011 Page 4 of 5 FORM OAR-l OWNER'S ACTIVITY REPORT Report Number: PLP-IR26-0AR-l Plant: Palisades Nuclear Plant Unit No: Commercial Service Date: 12/31/1971 Refueling Outage No.: lR26 (if applicable)

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TABLE 1:

ITEMS WITH FLA WS OR RELEVANT CONDITIONS THAT REQUIRED EVALUATION FOR CONTINUED SERVICE Examination Item Description Evaluation Description Category and Item Number Evaluations determined that the component was acceptable for service without corrective measures in accordance with IWF-3122.3.

ASMECode N-50 NDE Report No. lR26-VT-18-11O- Staining consistent Case N-729-4 Reactor Vessel Closure Head with that identified during 2003 baseline exam Code Item B4.10 Class 1 Evaluation determined the component was acceptable for continued service in accordance with ASME Code Case N-729-4, Paragraph 3142.

Category L-B Vertical Tendon V-24 CR-PLP-2018-04302, water noticed in V-24 field end, Code Item Class CC approx. 32 oz. sample obtained. Grease replacement of L2.40 68.76% net tendon duct volume.

L2.50 CR-PLP-2018-04976, initial grease sample on the V-24 shop end (end on the top/dome) had a water content of 16%. A second sample was tested from the same location on V-24 and indicated a water content of 12%.

Evaluation determined the component was acceptable for continued service in accordance with IWL 3212.

Category L-B Vertical Tendon V-276 CR-PLP-2018-04305, grease replacement of 18.08% net Code Item Class CC tendon duct volume.

L2.40 Evaluation determined the component was acceptable for continued service in accordance with IWL 3212.

Category L-B Vertical Tendon V-20 CR-PLP-2018-04301, water noticed in V-20 field end Code Item Class CC (ground), approx. 6 oz. sample obtained. Grease L2.40 replacement of 47.64% net tendon duct volume.

L2.50 Evaluation determined the component was acceptable for continued service in accordance with IWL 3212.

Category L-B Vertical Tendon V-176 CR-PLP-2018-04303, Water noticed in V-176 field end Code Item Class CC (ground), approx. 1.5 oz. sample obtained. Grease L2.40 replacement of 10.15% net tendon duct volume.

L2.50 Evaluation determined the component was acceptable for continued service in accordance with IWL 3212.

Category L-B Vertical Tendon V-306 CR-PLP-2018-04306, grease replacement of 16.24% net Code Item Class CC tendon duct volume.

L2.40 Evaluation determined the component was acceptable for continued service in accordance with IWL 3212.

Enclosure to PNP 2019-011 Page 5 of 5 FORM OAR-l OWNER'S ACTIVITY REPORT Report Number: PLP-IR26-0AR-l Plant: Palisades Nuclear Plant Unit No: Commercial Service Date: 12/31/1971 Refueling Outage No.: lR26 (if applicable)

TABLE 1:

ITEMS WITH FLAWS OR RELEVANT CONDITIONS THAT REQUIRED EVALUATION FOR CONTINUED SERVICE Examination Item Description Evaluation Description Category and Item Number Category L-B Dome Tendon D2-03 CR-PLP-2018-04295, water noticed in D2-3 Shop End Code Item Class CC (southeast), approx. 4 oz. sample obtained. Water L2.50 noticed in D2-3 Field End (northeast), approx. 6 oz.

sample obtained.

Evaluation determined the component was acceptable for continued service in accordance with IWL 3212.

Category L-B Dome Tendon D3-54 CR-PLP-2018-04298, water noticed in D3-54 Shop End Code Item Class CC (east), approx. 16 oz. sample obtained.

L2.50 Evaluation determined the component was acceptable for continued service in accordance with IWL 3212.

Category L-B Vertical Tendon V -176 CR-PLP-2018-04303, water noticed in V-176 field end Code Item Class CC (ground), approx. 1.5 oz. sample obtained. Grease L2.40 replacement of 10.15% net tendon duct volume.

L2.50 Evaluation determined the component was acceptable for continued service in accordance with IWL 3212.

Category E-A Moisture Barrier CR-PLP-2018-06087, NDE Report No VT-18-065 Code Item Class MC identifies 4 locations where the moisture barriers are E1.30 peeling off the concrete or the metal liner on the containment.

Evaluation determined the component was acceptable for continued service in accordance with IWE-3122.3 TABLE 2:

ABSTRACT OF REPAIRIREPLACEMENT ACTIVITIES REQUIRED FOR CONTINUED SERVICE Code Item Description Description of Work Date RepairlReplacement Class Completed Plan Number E-50A, "A" Steam Mechanically plug 55 tubes due to indications 1112012018 PLP52779307 1 Generator found during Eddy Current Testing Rev 1 E-50B, "B" Steam Mechanically plug 12 tubes due to indications 1112012018 PLP52779308 1 Generator found during Eddy Current Testing Rev 1 Repair Primary Water Stress Corrosion 12/24/18 Reactor Head Cracks by replacing portion of nozzle with PLP00498495 Control Rod Drive through wall flaw using Ambient Temper Rev 2 1 Nozzles 25, 33, 36 Bead Welding E-54A, Component Replace north end bell due to pin hole leak 111712018 PLP52761276 Cooling Water Heat Rev 2 3 Exchanger