PNP 2014-055, 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
Entergy Nuclear Operations, Inc.
Palisades Nuclear Plant 1 tei 27780 Blue Star Memorial Highway Covert, MI 49043-9530 Tel 269 764 2000 Otto W Gustafson Director, Regulatory and Performance Improvement PNP 2014-055 June 12, 2014 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001
SUBJECT:
ASME Section Xl 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 Xl, Article IWA-6000, Records and Reports, and applicable code cases, attached is the Entergy Nuclear Operations, Inc. (ENO) 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 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. ENO 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 Activity Report cc:
Administrator, Region Ill, USNRC Project Manager, Palisades, USN RC Resident Inspector, Palisades, USN RC
~ Entergy PNP 2014-055 June 12, 2014 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Entergy Nuclear Operations, Inc.
Palisades Nuclear Plant 27780 Blue Star Memorial Highway Covert, MI 49043-9530 Tel 269 764 2000 Otto W Gustafson Director, Regulatory and Performance Improvement
SUBJECT:
ASME Section XI gO-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, Article IWA-6000, "Records and Reports," and applicable code cases, attached is the Entergy Nuclear Operations, Inc. (END) Owner's 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 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. END 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 Owner's Activity Report cc:
Administrator, Region III, USNRC Project Manager, Palisades, USN RC Resident Inspector, Palisades, USNRC
ATTACHMENT Palisades Nuclear Plant Owners Activity Report 5 pages follow ATTACHMENT Palisades Nuclear Plant Owner's Activity Report 5 pages follow
FORM OAR-I OWNERS ACTIVITY REPORT Report Number PLP-1R23-OAR-1 Plant Palisades Nuclear Plant Unit No.
1 Commercial service date 12131/1971 Refueling outage no.
1R23 (if applicable)
Current inspection interval 4
th (1st, 2nd, 3rd, 4th, other)
Current inspection period 3
rd (1st, 2nd, 3rd)
Edition and Addenda of Section Xl applicable to inspection plans 2001 with 2003 Addenda Date and revision of inspection plans 09/18/2012, Revision 0 Edition and Addenda of Section Xl applicable to repairlreplacement activities, if different than the inspection plans Not Applicable Code Cases used:
N-513-3, N-661-1. N-638-4, N-705, and N-729-1 (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 ASME Code,Section XI; and (c) the repair/replacement activities supporting the completion of 1 R23 (refueling outage number) conform to the requirements of Section XI.
Signed JCX1t Er\\
Date CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vesselpspectors and the State or Province of g1t C%iGi?J and employed by 1158 6 S of H/1K7FO.
4 D, C 7:
have inspected the items described in this Owners 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 in ry or pro damage or loss of any kind arising from or connected with this inspection.
/6 9
c4 hr Commissions AJI5 792/tJ3t liii 2OZ inspectors Signature National Board, State, Province, and Endorsements Date FORM OAR-1 OWNER'S ACTIVITY REPORT Report Number PLP-1 R23-0AR-1 Plant Palisades Nuclear Plant Unit No.
(if applcable)
Commercial service date
...-:.1,;;;;21;.,;;;3....;;1/;,...;1...;;;,9..;..71"'--___ _
Refueling outage no.
1R23 Current inspection interval (1st. 2nd. 3rd. 4th. other)
Current inspection period
--=3_
111 _______________
(1st. 2nd. 3rd)
Edition and Addenda of Section XI applicable to inspection plans 2001 with 2003 Addenda Date and revision of inspection plans 09/18/2012. Revision 0 Edition and Addenda of Section XI applicable to repair/replacement activities. if different than the inspection plans Not Applicable Code Cases used:
N-513-3. N-661-1. N-638-4. N-705. and N-729-1 (if applicable)
CERTIFICATE OF CONFORMANCE I certify that (a) the statements made in this report are correcti (b) the examinations and tests meet the Inspection Plan as required by the ASME Code, Section XIi and ec) the repair/replacement activities supporting the completion of
.....;.1.:..;R2=3--:--:--::----:-___,........,.. __ _
(refuelIng outage number)
CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure vess~JJlP.ectors and t.b.e State or Province of Ml til/CAN and employed by I/S8 Go S of H. lTFDRV1 c r.
have Inspected the items described in this Owner's Activity Report, and state that, to the best of my knowledge and belief, 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 the repairl replacement activities and evaluation described in this report. Furthermore, neither the Inspector nor his employer shall be liable In any manner for any personal in ry or pro damage or loss of any kind arising from or connected with this inspection.
f?
Commissions National Board, State, Province, and Endorsements Date It -s-- z. 0 (q
TABLE I ITEMS WITH FLAWS OR RELEVANT CONDITIONS THAT REQUIRED EVALUATION FOR COWINUED SERVICE Examination Category and Item Number Item Description Evaluation Description Two pieces of a Primary Coolant Pump Impeller located in the reactor vessel. One piece lying on the bottom head region and one piece located behind the Flow Skirt at 45° location.
The one piece lying on the bottom head region was removed. The one piece located behind the flow skirt N-50 was left in place and Reactor Pressure Vessel evaluated as being Category S-N-I Interior acceptable under IWB Code Item No. B13.l0 Class 1 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.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 D2.l0 Flange Tee Piping 513-3. Leaking blind flange Class 3 tee piping was replaced.
Pressure boundary leakage on valve body of MV SW135. Evaluation MV-SW135 performed under Palisades Category D-B E-54A Service Water Relief Request 4-17.
Code Item D2.1 0 Outlet CV-0823 Bypass Leaking valve was Class 3 subsequently replaced.
Pressure boundary leakage from valve body.
Evaluation performed in MV-SW136 accordance with Relief E-54B Service Water Request PNP 2012-087.
Category D-B Outlet CV-0826 Bypass Leaking valve was Code Item D2.10 Class 3 subsequently replaced.
A loose nut on the bolting connecting the variable spring support can to the angle beam.
Evaluation determined that CVC-2-LDL-2B1-2OPR component was acceptable (H-2.1), Chemical for service without Volume and Control corrective measures in Category F-A System Class 1 Pipe accordance with IWF Code Item F1.1OC Restraint 3122.3 The spring support settings were outside the design and construction limits.
Evaluation determined that component was acceptable FWS-4-AWS-1S1-for service without 251PR(H51), Auxiliary corrective measures in Category F-A Feedwater System Class accordance with IWF Code Item F1.20A 2 Pipe Restraint 3122.3 Category F-A ESS-6-SIS-2A1-The spring support settings TABLE 1 ITEMS WITH FLAWS OR RELEVANT CONDITIONS THAT REQUIRED EVALUATION FOR CONTINUED SERVICE Examination Category and Item Number Item Description Evaluation Description Two pieces of a Primary Coolant Pump Impeller located in the reactor vessel. One piece lying on the bottom head region and one piece located behind the Flow Skirt at 45° location.
The one piece lying on the bottom head region was removed. The one piece located behind the flow skirt N-50 was left in place and Reactor Pressure Vessel evaluated as being Category B-N-1 Interior acceptable under IWB-Code Item No. B13.10 Class 1 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 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 Flange Tee Piping 513-3. Leaking blind flange Class 3 tee piping was replaced.
Pressure boundary leakage on valve body of MV-SW135. Evaluation MV-SW135 performed under Palisades Category D-B E-54A Service Water Relief Request 4-17.
Code Item 02.10 Outlet CV-0823 Bypass Leaking valve was Class 3 subsequently replaced.
Pressure boundary leakage from valve body.
Evaluation performed in MV-SW136 accordance with Relief E-54B Service Water Request PNP 2012-087.
Category D-B Outlet CV-0826 Bypass Leaking valve was Code Item 02.10 Class 3 subsequently replaced.
A loose nut on the bolting connecting the variable spring support can to the angle beam.
Evaluation determined that CVC-2-LDL-2B 1-20PR component was acceptable (H-2.1), Chemical for service without Volume and Control corrective measures in Category F-A System Class 1 Pipe accordance with IWF-Code Item F1.10C Restraint 3122.3 The spring support settings were outside the design and construction limits.
Evaluation determined that component was acceptable FWS-4-AWS-1S1-for service without 251PR(H51), Auxiliary corrective measures in Category F-A Feedwater System Class accordance with IWF-Code Item F1.20A 2 Pipe Restraint 3122.3 Category F-A ESS-6-SIS-2A1-The spring support settings
TABLE I ITEMS WITH FLAWS OR RELEVANT CONDITIONS THAT REQUIRED EVALUATION FOR CONTINUED SERVICE Code Item F1.20C FRi (H704.2), Low were outside the design Pressure Safety Injection and construction limits.
System Class 2 Pipe Restraint Evaluation determined that component was acceptable for service without corrective measures in accordance with IWF 3122.3 Indications of boron staining, scaling, and general corrosion.
N-50 ASME Code Case N-Reactor Vessel Closure Acceptable for continued 729-1 Head service in accordance with Code Item B4.10 Class 1 N-729-1, Paragraph 3142.1 TABLE 2 ABSTRACT OF REPAIRIREPLACEMENT ACTIVITIES REQUIRED FOR CONTINUED SERVICE Item Description Date Repair/Replacement Code Class Description of Work Completed Plan Number CRDM-24 Control Rod Replace Control Rod Drive Mechanism Drive Mechanism Upper Housing Upper Housing 8/29/12 PLP00323898 Rev 3 Rejectable liquid SI POINT PCS penetrant inspection LDL-2B1-1 0A, Pipe to (PT) indication Elbow Weld on Let removed by superficial Down Line surface conditioning.
1/30/14 PLP372823 Rev 1 Mechanically plug 13 tubes due to indications found E-50A, A Steam during Eddy Current Generator Testing.
2/6/14 PLP52436063 Rev 1 Mechanically plug 10 tubes due to indications found E-50B, B Steam during Eddy Current Generator Testing.
2/6/14 PLP52436015 Rev 1 CC5-H4.1, Regen Heat Exchanger To Primary Loop Support Repair pipe restraint.
2/1 5/14 PLP373324 Rev 1 Replace Control Rod Drive Mechanism Upper Housings. As part of replacing the identified items, all upper housings replaced (44 total) with the exception of Control Rod Drive CRDM-24 Upper Upper Housings, Housing previously CRDM Locations 4, 5, replaced per 6, 7, 8, 10, 17, 18, 23, repair/replacement 25, 29, 32, 33, 35, 42, plan PLP00323898 PLP1R23 CRDM 43,45 Rev3.
3/15/14 HOUSINGS Replace Alloy 600 weld and flange with Alloy 52M weld metal T-72 Pressurizer and stainless steel Nozzle to Flange for flange using Code RV-1041, Pressurizer Case N-638-4 and Safety Relief Valve Relief Request RR 3/15/14 PLP374157 TABLE 1 ITEMS WITH FLAWS OR RELEVANT CONDITIONS THAT REQUIRED EVALUATION FOR CONTINUED SERVICE Code Item F1.20C PR1 (H704.2), Low were outside the design Pressure Safety Injection and construction limits.
System Class 2 Pipe Restraint Evaluation determined that component was acceptable for service without corrective measures in accordance with IWF-3122.3 Indications of boron staining, scaling, and general corrosion.
N-50 ASME Code Case N-Reactor Vessel Closure Acceptable for continued 729-1 Head service in accordance with Code Item B4.10 Class 1 N-729-1, Paragraph 3142.1 TABLE 2 ABSTRACT OF REPAIR/REPLACEMENT ACTIVITIES REQUIRED FOR CONTINUED SERVICE 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 8129/12 PLP00323898 Rev 3 Rejectable liquid lSI POINT PCS penetrant inspection LDL-2B1-10A, Pipe to (PT) indication Elbow Weld on Let removed by superficial 1
Down Line surface conditioning.
1130/14 PLP372823 Rev 1 Mechanically plug 13 tubes due to indications found E-50A, "An Steam during Eddy Current 1
Generator Testing.
2/6/14 PLP52436063 Rev 1 Mechanically plug 10 tubes due to indications found E-50B, "B" Steam during Eddy Current 1
Generator Testing.
2/6114 PLP52436015 Rev 1 CC5-H4.1, Regen Heat Exchanger To 1
Primary Loop Support Repair pipe restraint.
2115/14 PLP373324 Rev 1 Replace Control Rod Drive Mechanism Upper Housings. As part of replacing the identified items, all upper housings replaced (44 total) with the exception of Control Rod Drive CRDM-24 Upper Upper Housings, Housing previously CRDM Locations 4, 5, replaced per 6,7,8,10,17,18,23, repair/replacement 25,29,32,33,35,42, plan PLP00323898 PLP1 R23 CRDM 1
43,45 Rev 3.
3/15/14 HOUSINGS Replace Alloy 600 weld and flange with Alloy 52M weld metal T -72 Press urizer and stainless steel Nozzle to Flange for flange using Code RV-1 041, Pressurizer Case N-638-4 and 1
Safety Relief Valve Relief Request RR 3/15/14 PLP374157
T-58, Safety Injection and Refueling Water Tank T-58, Safety Injection and Refueling Water Tank 19 to apply buttering to nozzle using ambient temperature temper bead technique.
Replaced K, L, and M nozzles; added reinforcing plates around E, F-East and F-West nozzles; added new nozzle pipe restraints and modified pre-existing nozzle restraints; severed J and N nozzles from tank floor followed by patch plates welded over nozzles; multiple welded repairs made on other welds associated with the tank bottom; cut holes in bottom plates to allow sand 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 used to justify continued operation until next refueling outage (due to increased leakage, did not reach refueling outage and further repairs performed in forced outage see repair/replacement plan PLP00350466 Rev 3).
Removed T-58 from service per N-705 and performed the following repair/replacement activities. Replaced E, F-East, F-West, G andH nozzles.
Replaced entire floor of tank with exception of approximately 12 to 18 of outer annular ring of original floor plates. Removed and rewelded all original welds of remaining original floor plates.
Welded patch plate over excavated crack in roof plates. Welded patch plates over holes cut in roof (for insertion of new floor plates) and in new floor plate (for insertion of filler material for better support).
2 7/14/12 PLPOO3I 9746 Rev I 2
2 RV-0723, Main Steam Replace valve nozzle 3/14/14 PLPOO3I 91 05 Rev I 6/15/13 PLP00350466 Rev 3 19 to apply buttering to nozzle using ambient temperature temper bead techniQue.
Replaced "K", "L", and "M" nozzles; added reinforcing plates around "E", "F-Easf and "F-West" nozzles; added new nozzle pipe restraints and modified pre-existing nozzle restraints; severed" J" and uN" nozzles from tank floor followed by patch plates welded over nozzles; multiple welded repairs made on other welds associated with the tank bottom; cut holes in bottom plates to allow s 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 used to justify continued operation until next refueling outage (due to increased leakage, did not reach refueling outage and further repairs performed in forced outage - see T-58, Safety Injection repair/replacement and Refueling Water plan PLP00350466 2
Tank Rev 3).
7/14/12 PLP00319746 Rev 1 Removed T -58 from service per N-705 and performed the following repair/replacement activities. Replaced "E", F-East", "F-West",
"G" and "H" nozzles.
Replaced entire floor of tank with exception of approximately 12" to 18" of outer annular ring of original floor plates. Removed and rewelded all original welds of remaining Original floor plates.
Welded patch plate over excavated crack in roof plates. Welded patch plates over holes cut in roof (for insertion of new floor plates) and in new floor plate (for T -58, Safety Injection insertion of filler and Refueling Water material for better 2
Tank support).
6/15/13 PLP00350466 Rev 3 2
RV-0723, Main Steam Replace valve nozzle 3/14/14 PLP00319105 Rev 1
Relief Valve due to indication found in nozzle seating surface. Replacement of nozzle included performing seal weld of nozzle to valve body.
HB-23-1 6 Service Water Downstream of Perform weld overlay CV-0823, CCW Hx E-on elbow downstream 54A Service Water of CV-0823 per N-661-3 Outlet 1
8/27/12 PLP00324812 Rev2 MV-SW136, E-54B Service Water Outlet Replace valve and 3
CV-0826 Bypass flanges 11/6/12 PLP00327249 Rev I HB-23-6 Service Water Blind Flange Tee Piping Downstream of MV SW377, Diesel Branch connection Generator 1-1 & VC-with blind flange 11 Service Water replaced with straight 3
Supply section of pipe.
2/3/14 PLP356678 Rev I HB-23-1 6 Service Water Downstream of Replace flange and CV-0823, CCW Hx E-elbow downstream of 54A Service Water CV-0823 per Code PLP00324812 3
Outlet Case N-661-1.
2/15/14 ELBOW REPL Rev 2 Replace valve, MV-SW135, E-54A flanges, and section of Service Water Outlet pipe downstream of 3
CV-0823 Bypass valve.
2/15/14 PLP365955 Rev 3 Relief Valve due to indication found in nozzle seating surface. Replacement of nozzle included performing seal weld of nozzle to valve body.
HB-23-16 Service Water Downstream of Perform weld overlay CV-0823, "CCW Hx E-on elbow downstream 54A Service Water of CV-0823 per N-661-3 Outlet" 1
8/27/12 PLP00324812 Rev 2 MV-SW136, E-54B Service Water Outlet Replace valve and 3
CV-0826 Bypass flanges 11/6/12 PLP00327249 Rev 1 HB-23-6 Service Water Blind Flange Tee Piping Downstream of MV-SW377, Diesel Branch connection Generator 1-1 & VC-with blind flange 11 Service Water replaced with straight 3
Supply section of pipe.
213114 PLP356678 Rev 1 HB-23-16 Service Water Downstream of Replace flange and CV-0823, "CCW Hx E-elbow downstream of 54A Service Water CV-0823 per Code PLPOO324812 3
Outlet" Case N-661-1.
2115/14 ELBOW REPL Rev 2 Replace valve, MV-SW135, E-54A flanges, and section of Service Water Outlet pipe downstream of 3
CV-0823 B~j)ass valve.
2115/14 PLP365955 Rev 3