PNP 2014-055, ASME Section XI 90-Day Inservice Inspection Summary Report

ASME Section XI 90-Day Inservice Inspection Summary Report

ML14163A500
Person / Time
Site:	Palisades
Issue date:	06/12/2014
From:	Gustafson O Entergy Nuclear Operations
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
PNP 2014-055
Download: ML14163A500 (7)

Text

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~ Entergy

Entergy Nuclear Nuclear Operations, Inc.

Palisades Nuclear Nuclear Plant 27780 Blue Star Memorial Covert, MI 2000 Tel 269 764 2000 Otto W Gustafson Inc.

Memorial Highway MI 49043-9530 Gustafson Highway Director, Regulatory and Performance Improvement Performance Improvement PNP 2014-055 June 12, 2014 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001

SUBJECT:

ASME Section XI Xl gO-Day 90-Day Inservice Inspection Summary Report Palisades Nuclear Plant Docket 50-255 License No. DPR-20

Dear Sir or Madam:

In accordance with the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code,Section XI, Xl, Article IWA-6000, "Records Records and Reports,"

Reports, and applicable code cases, attached is the Entergy Nuclear Operations, Inc. (END) (ENO) Owner's Owners Activity Report for the Palisades Nuclear Plant (PNP). The report contains a listing of nine examination indications that required evaluation for continued service, and an abstract of 15 15 repair/replacement activities that were required for continued service.

These activities were performed during the PNP twenty-third fuel cycle and the 2014 refueling outage. ENDENO completed the refueling outage on March 16, 2014.

This letter identifies no new commitments and no revisions to existing commitments.

Sincerely, owg/jse

Attachment:

Palisades Nuclear Plant Owners Owner's Activity Report cc: Administrator, Region III, Ill, USNRC Project Manager, Manager, Palisades, USN RC Resident Inspector, Palisades, USNUSNRC RC

ATTACHMENT ATTACHMENT Palisades Nuclear Palisades Nuclear Plant Plant Owners Activity Owner's Activity Report Report pages follow 55 pages follow

FORM OAR-1OAR-I OWNER'SOWNERS ACTIVITY REPORT Report Number PLP-1R23-OAR-1 PLP-1 R23-0AR-1 Plant Palisades Nuclear Plant Unit No. 1 Commercial service date . .-:.1,;12131/1971

21;.,;;;3.. .;;1/;,. .;1.. ;;;,9. ;. 71"'--_ _ __ Refueling outage no. 1R23 applicable)

(if applcable) th 4

Current inspection interval (1st, 2nd.

(1st. 2nd, 3rd.

3rd, 4th.

4th, other)

Current inspection period rd 3

--=3_

111 (1st, 2nd.

(1st. 2nd, 3rd)

Edition and Addenda of Section XI Xl applicable to inspection plans 2001 with 2003 Addenda Date and revision of inspection plans 09/18/2012, Revision 0 09/18/2012.

Edition and Addenda of Section XI Xl applicable to repair/replacement repairlreplacement activities.activities, if different than the inspection plans Not Applicable Code Cases used: N-513-3, N-661-1. N-638-4.

N-513-3. N-705, and N-729-1 N-638-4, N-705. N-729-1 (if applicable)

CERTIFICATE OF CONFORMANCE certify correct; (b) the examinations and tests meet the Inspection Plan as required by the I certify that (a) the statements made in this report are correcti ASME Code, Section XIi XI; and ec)

(c) the repair/replacement activities supporting the completion of 1 R23

.....;.1.:..;R2=3--:--:--::----:-___ ,........,.._ __

(refuelIng (refueling outage number) conform to the requirements of Section XI.

Signed JCX 1t Er\ Date CERTIFICATE OF INSERVICE INSPECTION a valid commission issued by the National Board of Boiler and Pressure vess~JJlP.ectors Vesselpspectors and t.b.e the State or c r.

I, the undersigned, holding a Province of Ml til/CAN g1t C%iGi?J and employed by I/S8 1158 Go 6S H. lTFDRV of H/1K7FO.

4 D,1 C 7:

inspected the items described in this Owner's have Inspected Owners Activity Report, and state that, to the best of my knowledge and belief, the t~ 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, conceming concerning the repairl repair/

hr 4

replacement activities and evaluation described in this report. Furthermore, neither the Inspector nor his employer shall be liable In in any manner for any personal in ry or pro damage or loss of any kind arising from or connected with this inspection.

/6 c

9 f? inspectors Signature Commissions AJI5 792/tJ3t National Board, liii 2OZ Board, State, Province, and Endorsements Date It - s-- z. 0 (q

TABLE 1I TABLE ITEMS WITH ITEMS WITH FLAWS FLAWS OR RELEVANT CONDITIONS OR RELEVANT CONDITIONS THAT THAT REQUIRED EVALUATION FOR REQUIRED EVALUATION COWINUED SERVICE FOR CONTINUED SERVICE Examination Examination Category and Category and Item Number Item Number Item Description Item Description Evaluation Description Evaluation Description Two pieces Two pieces of of aa Primary Primary Coolant Pump Coolant Pump Impeller Impeller located in located in the reactor reactor vessel. One vessel. piece lying One piece lying onon the bottom the bottom head region and head region one piecepiece located located behind behind Flow Skirt the Flow Skirt atat 45° 45° location.

location.

The one piece lying lying on the bottom head region was removed. The one piece removed. piece located behind the flow skirt located skirt N-50 N-50 was left in place and left in Reactor Pressure Vessel evaluated as being S-N-I Category B-N-1 Interior acceptable under IWB- IWB Item No. B13.10 Code Item B13.l0 Class 11 3142.4 T-58 Leakage from Tank.

Safety Injection Refueling Evaluation in accordance Category C-H Water Tank with ASME Code Case N-Code Item C7.10 Code C7.I0 Class 2 705. Leaking tank was Statically Pressurized subsequently repaired Pressure boundary leakage on pipe to blank flange.

Evaluation in accordance Category D-B Service Water Blind with ASME Code Case N-Code Item 02.10 D2.l0 Flange Tee Piping 513-3. Leaking blind flange Class 3 tee piping was replaced.

Pressure boundary leakage on valve body of MV- MV SW135. Evaluation Evaluation MV-SW135 MV-SW135 performed under Palisades Palisades Category D-B E-54A Service Water Water Relief Request 4-17.

Code Item D2.102.100 Outlet CV-0823 Bypass Leaking valve was Class Class 33 subsequently replaced.replaced.

Pressure boundary leakage Pressure boundary leakage from valve body.

Evaluation performed in in MV-SW136 accordance accordance with with Relief Relief E-54B E-54B Service Service Water Water Request PNP Request PNP 2012-087.

Category Category D-B D-B Outlet Outlet CV-0826 CV-0826 Bypass Bypass Leaking Leaking valve valve waswas Code Code ItemItem D2.10 02.10 Class Class 33 subsequently subsequently replaced.

A loose nut A nut onon the bolting bolting connecting connecting the variable variable spring spring support support cancan to to the the angle angle beam.

beam.

Evaluation Evaluation determined determined that that CVC-2-LDL-2B1-2OPR CVC-2-LDL-2B 1-20PR component component was was acceptable acceptable (H-2.1), Chemical (H-2.1), Chemical for for service service without without Volume Volume and and Control Control corrective corrective measures measures in in Category Category F-A F-A System Class System Class 11 Pipe Pipe accordance accordance with with IWFIWF-Code Code ItemItem F1.1OC F1.10C Restraint Restraint 3122.3 3122.3 The The spring spring support support settings settings were were outside outside thethe design design and and construction construction limits.

limits.

Evaluation Evaluation determined determined that that component component was was acceptable acceptable FWS-4-AWS-1S1-FWS-4-AWS-1S1- for for service service without without 251PR(H51),

251PR(H51), Auxiliary Auxiliary corrective corrective measures measures inin Category Category F-A F-A Feedwater System Class Feedwater System Class accordance accordance with with IWFIWF-Code Code ItemItem F1.20A F1.20A 22 Pipe Pipe Restraint Restraint 3122.3 3122.3 Category Category F-A F-A ESS-6-SIS-2A1-ESS-6-SIS-2A1- The spring support The spring support settings settings

TABLE 1I TABLE ITEMS WITH ITEMS WITH FLAWS FLAWS OR RELEVANT CONDITIONS OR RELEVANT CONDITIONS THAT THAT REQUIRED EVALUATION REQUIRED EVALUATION FOR FOR CONTINUED CONTINUED SERVICE SERVICE Code Item Code F1.20C Item F1.20C FRi (H704.2),

PR1 (H704.2), Low Low were outside were outside the the design design Pressure Safety Pressure Injection Safety Injection and construction and construction limits.

limits.

System Class System Class 22 Pipe Pipe Restraint Restraint Evaluation determined Evaluation determined thatthat component was component was acceptable acceptable for service for service without without corrective measures corrective measures in in accordance with accordance with IWF-IWF 3122.3 Indications of Indications of boron staining, scaling, staining, scaling, and and general corrosion.

general N-50 N-50 ASME Code Case N- Reactor Vessel Reactor Vessel Closure Acceptable for continued 729-1 Head service in accordance with Code Item B4.10 Class 11 N-729-1, Paragraph 3142.1 TABLE 2 REPAIRIREPLACEMENT ACTIVITIES REQUIRED FOR CONTINUED SERVICE ABSTRACT OF REPAIR/REPLACEMENT Item Description Date Repair/Replacement Code Class Description of Work Completed Plan Number CRDM-24 Control Rod Replace Control Rod Drive Mechanism Drive Mechanism 1 Upper Housing Upper Housing 8/29/12 8129/12 PLP00323898 Rev 3 3 Rejectable liquid SI POINT PCS lSI penetrant inspection LDL-2B1-1 0A, Pipe to LDL-2B1-10A, (PT) indication Elbow Weld on Let removed by superficial 1 Down Line surface conditioning. 1/30/14 1130/14 PLP372823 Rev 11 Mechanically Mechanically plug 13 13 tubes due to indications found E-50A, "An A Steam during Eddy Current 1 Generator Generator Testing. 2/6/14 2/6/14 PLP52436063 Rev 11 Mechanically Mechanically plug 10 10 tubes duedue to indications found E-50B, E-50B, "B" B Steam Steam during Eddy Current during 1 Generator Testing.

Testing. 2/6/14 2/6114 PLP52436015 Rev PLP52436015 Rev 11 CC5-H4.1, CC5-H4.1, RegenRegen Heat Heat Exchanger Exchanger To To 1 Primary Loop Loop Support Support Repair pipe restraint.

restraint. 2/1 5/14 2115/14 PLP373324 Rev 11 PLP373324 Replace Control Control RodRod Drive Drive Mechanism Mechanism Upper Upper Housings.

Housings. As As part part of of replacing replacing thethe identified identified items, items, all all upper upper housings housings replaced (44 replaced total) with (44 total) with the the exception exception of of Control Control Rod Rod Drive Drive CRDM-24 CRDM-24 Upper Upper Upper Upper Housings, Housings, Housing Housing previously previously CRDM CRDM Locations Locations 4,4, 5, 5, replaced replaced per per 6, 7, 8, 10, 17, 18, 23, 6,7,8,10,17,18,23, repair/replacement repair/replacement 25, 29, 32, 33, 35, 42, 25,29,32,33,35,42, plan plan PLP00323898 PLP00323898 PLP1 R23 CRDM PLP1R23 CRDM 1 43,45 43,45 Rev3.

Rev 3. 3/15/14 3/15/14 HOUSINGS HOUSINGS Replace Alloy Replace Alloy 600 600 weld weld and and flange flange with with Alloy Alloy 52M52M weldweld metal metal T-72 T -72 Pressurizer Press urizer and stainless and stainless steel steel Nozzle Nozzle to to Flange Flange for for flange flange using using Code Code RV-1041, RV-1 041, Pressurizer Pressurizer Case N-638-4 Case N-638-4 and and 1 Safety Safety Relief Relief Valve Valve Relief Request Relief Request RR RR 3/15/14 3/15/14 PLP374157 PLP374157

19 to 19 to apply apply buttering buttering to nozzle to nozzle using using ambient temperature ambient temperature temper bead temper bead technique.

techniQue.

Replaced "K",

Replaced K, "L",

L, and and M nozzles; "M" nozzles; added added reinforcing plates reinforcing plates around "E",

around E, "F-Easf F-East and "F-West" and F-West nozzles; nozzles; added new added new nozzle nozzle pipe restraints pipe restraints and and modified pre-existing modified pre-existing nozzle restraints; nozzle restraints; severed J severed" and uN" J" and N nozzles from nozzles from tanktank floor floor followed by followed by patch patch plates welded plates welded over over multiple nozzles; multiple nozzles; welded repairs made on other welds on associated with the tank bottom; cut holes in bottom plates to allow ssand and to be inserted under tank floor followed by patch plates welded over holes. When source of leakage could not be found/repaired, Code Case N-705 N-705 used to justify continued operation until next refueling outage outage (due to increased leakage, did did not reach refuelingrefueling outage outage and and further repairs performed in in forced outage outage - see see T-58, T-58, Safety Safety Injection Injection repair/replacement and and Refueling Refueling Water Water plan plan PLP00350466 PLP00350466 22 Tank Tank Rev Rev 3).3). 7/14/12 7/14/12 PLP00319746 PLPOO3I Rev I1 9746 Rev Removed Removed T-58 T -58 from from service service per per N-705 N-705 and and performed performed the the following following repair/replacement repair/replacement activities.

activities. ReplacedReplaced E,

"E", F-East, F-East", F-West, "F-West",

G "G" andH and "H" nozzles.

nozzles.

Replaced Replaced entire entire floor floor of of tank tank with with exception exception of of approximately approximately 12 12" toto 1818" of of outer outer annular annular ring ring of of original original floor floor plates.

plates. Removed Removed and and rewelded rewelded all all original original welds welds of of remaining remaining original Original floor floor plates.

plates.

Welded Welded patch patch plate plate over over excavated excavated crack crack inin roof roof plates.

plates. Welded Welded patch patch platesplates overover holes holes cut cut inin roof roof (for (for insertion insertion of of new new floorfloor plates) plates) and and inin newnew floor floor plate plate (for (for T-58, T -58, Safety Safety Injection Injection insertion insertion of offiller filler and and Refueling RefuelingWater Water material materialfor for better better 22 Tank Tank support).

support). 6/15/13 6/15/13 PLP00350466 Rev PLP00350466 Rev33 22 RV-0723, RV-0723, Main Main Steam Steam Replace Replace valve valve nozzle nozzle 3/14/14 3/14/14 PLP00319105 PLPOO3I Rev I1 91 05 Rev

Relief Valve Relief Valve due to due to indication indication found found in nozzle in nozzle seating seating surface. Replacement surface. Replacement of nozzle of nozzle included included performing seal performing seal weld weld of nozzle of nozzle to to valve valve body.

body.

HB-23-1 6 Service HB-23-16 Service Water Downstream Water Downstream of of Perform weld Perform weld overlay overlay CV-0823, "CCW CV-0823, CCW Hx Hx E-E- on elbow on elbow downstream downstream 54A Service 54A Service Water Water of CV-0823 of CV-0823 per N-661-per N-661-33 Outlet Outlet" 11 8/27/12 8/27/12 PLP00324812 Rev PLP00324812 Rev2 2 MV-SW136, E-54B MV-SW136, E-54B Service Water Outlet Service Outlet Replace valve and Replace and 3 Bypass CV-0826 Bypass flanges flanges 11/6/12 11/6/12 PLP00327249 Rev Rev 1I HB-23-6 Service HB-23-6 Service Blind Flange Water Blind Flange Tee Piping Downstream of MV- MV SW377, Diesel Branch connection Generator 1-1 & & VC- with blind flange 11 Service Water 11 replaced with straight 3 Supply section of pipe. 2/3/14 213114 PLP356678 Rev 1I HB-23-1 6 Service HB-23-16 Water Downstream of Replace flange and CV-0823, "CCW CCW Hx E- elbow downstream of 54A Service Water CV-0823 per Code PLP00324812 PLPOO324812 3 Outlet Outlet" Case N-661-1. 2115/14 2/15/14 ELBOW REPL Rev 2 Replace valve, MV-SW135, E-54A flanges, and section of Service Water Outlet pipe downstream of 3 Bypass CV-0823 B~j)ass valve. 2115/14 2/15/14 PLP365955 Rev 3