ML14170A892

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Calvert Cliffs Nuclear Power Plant, Unit 1 - Inservice Inspection Report
ML14170A892
Person / Time
Site: Calvert Cliffs Constellation icon.png
Issue date: 06/17/2014
From: Robinson K F
Exelon Generation Co
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
CCNPP-1-OAR-004-021
Download: ML14170A892 (9)
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Text

IAdnowANNEMWANOWExelon Generation.

Kenneth F. RobinsonManager-Engineering ServicesCalvert Cliffs Nuclear Power Plant1650 Calvert Cliffs ParkwayLusby, MD 20657410 495 5208 Office443 532 5709 Mobilewww.exeloncorp.com ken.robinson@exelon.com June 17, 2014U. S. Nuclear Regulatory Commission ATTN: Document Control DeskWashington, DC 20555Calvert Cliffs Nuclear Power Plant, Unit No. 1Renewed Facility Operating License No. DPR-53NRC Docket No. 50-317

Subject:

Inservice Inspection Report1. American Society of Mechanical Engineers, Boiler & Pressure Vessel Code,Section Xl, Article IWA-6000

Reference:

Pursuant to Reference 1, please find enclosed the Inservice Inspection Report for the CalvertCliffs Nuclear Power Plant Unit 1.There are no regulatory commitments contained in this letter.Should you have questions regarding this matter, please contact Mr. Douglas E. Lauver at(410) 495-5219.

Respectfully, Kenneth F. RobinsonManager -Engineering ServicesKFR/PSF/bjd

Enclosure:

(1) 2014 Owner's Activity Report for RFO-21 Inservice Examinations cc: Mr. Robert McGeeney(Without Enclosure)

CCNPP Project Manager, NRCRegion 1 Administrator, NRCCCNPP Resident Inspector, NRCS. Gray, DNRAc7 ENCLOSURE (1)2014 OWNER'S ACTIVITY REPORT FORRFO-21 INSERVICE EXAMINATIONS ICalvert Cliffs Nuclear Power PlantJune 17, 2014 Calvert Cliffs Nuclear Power Plant, LLC1650 Calvert Cliffs ParkwayLusby, MD 20657-- Exeton Generation, Fourth Interval I Second PeriodInservice Inspection ProgramandSecond Interval I Second PeriodContainment IWE/L Program2014 Owner's Activity ReportforRFO-21 Inservice Examinations Commercial Service Date: May 8, 1975NRC Docket Number: 50-317Document Number: CCNPP-1-OAR-004-021 Revision Number: 00Prepared by:.Reviewed by:Reviewed by:Jeffrey"MMl

n p Site ISI Program OwnAnge eyes- z Site ISI Program OwnererKurt Bodine -G.S. Nuclear Engineering Programs Calvert Cliffs Nuclear Power Plant Unit IFourth Interval

/ First Period Inservice Inspection CCNPP-1-OAR-004-021 Second Interval

/ Second Period Containment Rev. 00Exton Generation 2014 Owner's Activity Report June 10, 2014for Page 2 of 7RFO-21 Inservice Examinations AbstractThis Owner's Activity Report (OAR) summarizes the results of the Calvert Cliffs Nuclear Power Plant (CCNPP),Unit 1, American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code (B&PVC),

SectionXl, Inservice Inspection (ISI) examinations performed in Refueling Outage twenty one (RFO-21) during the periodfrom April 9, 2012 through March 20, 2014 of the Second Inservice Inspection Period which began on October 10,2012 and is scheduled to end on October 9, 2016, and the Third outage of the Fourth Ten-Year Inservice Inspection Interval which began on October 10, 2009 and is scheduled to end on June 30, 2019.As an alternate to the requirements of the ASME B&PVC,Section XI, Article IWA-6000, CCNPP is implementing ASME Code Case N-532-4, "Alternative Requirements to Repair and Replacement Documentation Requirements and Inservice Summary Report Preparation and Submission as Required by IWA-4000 and IWA-6000, SectionXI, Division 1." Regulatory Guide 1.147, Revision 16 (Oct. 2010), approved ASME Code Case N-532-4 for use.This report complies with the requirements of ASME Code Case N-532-4.In accordance with ASME Section XI, IWB-2412(a),

IWC-2412(a),

IWD-2412(a),

IWE-2412(a),

and IWL-2421, andwith the exception of those examinations that are limited to components selected for examination underExamination Categories B-L-2 and B-M-2 and required only when the pump or valve is disassembled as specified in Table IWB-2500-1, IWC-2500-1, IWD-2500-1, IWF-2500-1, IWE-2500-1, and IWL-2500-1, including thoseexaminations which CCNPP has requested and received approval in the form of requests for relief or alternates, the required examinations in each examination category have been completed for the First outage of the SecondInspection Period of the Fourth Inspection Interval in accordance with Tables IWB-2412-1, IWC-2412-1, IWD-2412-1, IWE-2412-1, and IWL-2521-1.

Owner's Activity Reports -Form OAR-1Owner's Activity

Reports, Form OAR-1. were prepared and certified upon completion of the Calvert Cliffs NuclearPower Plant Unit 1, 2014 Refueling Outage (RFO-21) examination activity in accordance with the following inspection plans:Fourth Inservice Inspection Program PlanSecond Interval Containment Inservice Inspection Program PlanFourth Interval Inservice Inspection Pressure Testing Program PlanIn addition to the Owner's Activity
Reports, Form OAR-i, the following Tables are also included:
a. Items with Flaws or Relevant Conditions that Require Evaluation for Continued
Service, Table 1, whichprovides a listing of item(s) with flaws or relevant conditions that required evaluation to determine acceptability for continued
service, whether or not the flaw or relevant condition was discovered during ascheduled examination or test, and provides such information as Examination
Category, Examination ItemNumber, Item Description, Flaw Characterization (as required by IWA-3300).
b. Abstract of Repairs, Replacements or Corrective Measures Required for Continued
Service, Table 2,which identifies those items containing flaws or relevant conditions that exceeded the ASME XI acceptance criteria (IWB-3000, IWC-3000, IWD-3000, or IWL-3000) or in the case of supports, IWF-3000 acceptance criteria; even though the discovery of the flaw or relevant condition that necessitated the repair, replacement, or corrective
measure, may not have resulted from an examination or test required by ASME Section XI, andprovides such information as Code Class, item description, description of work, date completed, and therepair replacement plan number.

Calvert Cliffs Nuclear Power Plant Unit IFourth Interval

/ First Period Inservice Inspection CCNPP-1-OAR-004-021 Second Interval

/ Second Period Containment J e 00Exelon 2014 Owner'S Activity Report Page 3 of 7forRFO-21 Inservice Examinations FORM OAR-1 OWNER'S ACTIVITY REPORTFourth Interval/Second Period of Inservice Inspection ProgramAs required by the provisions of the ASME Code Case N-532-4Report NumberCCNPP-1u-OAR-004-021 PlantCalvert Cliffs Nuclear Power PlantUnit No. 1(it upplabtule)

Current Inspection IntervalCurrent Inspection PeriodCommercial ServiceDateMay 8, 1975Refueling OutageNumberRFO-21Fourth Inservice Inspection Interval

-October 10, 2009 to June 30, 2019(1-', 2-, 3", 4", other)Second Inservice Inspection Period -October 10, 2012 to October 9, 2016(1', 2-, 3")Edition and Addenda of Section XI applicable to the Inspection PlansDate / Revision of Inspection Plans2004 Edition, No addendaRev. I Ch. I Dated June 4, 2013Edition and Addenda of Section XI applicable to repair/replacement activities, if different than the Inspection plansN/ACode Casesused:N-460, N-532-4.

N-566-2, N-616. N-624, N-639, N-686-1, N-716, N-722-11, N-729-1, N-753, N-770-1CERTIFICATE 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 theASME Code, Section Xl; and (c) the repair/replacement activities and evaluations supporting the completion of RFO-21conform to the requirements of Section Xl , (refueling outage number)Signed Kurt Bodine -tDate4ibi.General Supervisor, CCNPP Nuclear Engineering ProgramsCERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State orProvince of Maryland and employed by HSB Global Standards of Hartford, Connecticut have Inspected the items described In this Owner's Activity Report, and state that to the best of my knowledge and belief, the Owner hasperformed all activities represented by this report In accordance with the requirements of Section XIBy 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 anymanner for any personal injury or property damage or a loss of any kind arising from or connected with this Inspection Commissions NB 9531 AN.I,C.IS (Inspector's Signature)

National Board. State, Province, and Endorsements Date i jile 21 4 J-Z41 Calvert Cliffs Nuclear Power Plant Unit IFourth Interval

/ First Period Inservice Inspection CCNPP-1-OAR-e04-021 Rev. 00Aam Second Interval

/ Second Period Containment June 10, 2014"Exe~on Genrlation 2014 Owner's Activity Report Page 4 of 7forRFO-21 Inservice Examinations FORM OAR-1 OWNER'S ACTIVITY REPORTSecond IntervallSecond Period of Containment IWEIL Inservice Inspection ProgramAs required by the provisions of the ASME Code Case N-532-4Report NumberCCNP P-i -OAR-004-021 Calvert Cliffs Nuclear Power PlantPlantUnit No. 1 Commercial ServiceDate(it applicable)

Current Inspection Interval Second InCurrent Inspection Period Second In!May 8,1975Refueling OutageNumberRFO-21service Inspection Interval

-September 9, 2009 to September 9, 2018(1". 2"-. 3Y'. 4". other)service Inspection Period -September 9, 2011 to September 9, 2015Edition and Addenda of Section XI applicable to the Inspection Plans2004 Edition, No addendaRev. 1 Dated Feb. 6. 2014Date / Revision of Inspection PlansEdition and Addenda of Section Xl applicable to repair/replacement activities, if different than the inspection plansN/ACode Casesused:N-532-4, N-624, N-666-1, N-739, N-753CERTIFICATE 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 theASME Code, Section XI: and (c) the repair/replacement activities and evaluations supporting the completion of RFO-21conform to the requirements of Section Xl (refueling outage number)Signed Kurt Bodine -"t V-..JrDate ý.!- -, iCeireral Superviaor, CCNPP Nuclear Engineering ProgramsCERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State orProvince of Maryland and employed by HSB Global Standards of Hartford, Connecticut have inspected the items described in this Owners Activity Report, and state that to the best of my knowledge and belief, the Owner hasperformed all activities represented by this report in accordance with the requirements of Section XlBy 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 anymanner for any personrlnjury or property damage or a loss of any kind arising from or connected with this inspection

___ Commissions NB 9531 A,N,I,C,IS (Inspector's Signature)

National Board. State. Province, and Endorsements Date //-. 2,0/v Calvert Cliffs Nuclear Power Plant Unit I4MMWCFourth Interval

/ First Period Inservice Inspection

-OAR-004-021 Fourh Iteral IFirt PriodInsrvie InpecionRev.

00AMW Second Interval

/ Second Period Containment June 10, 2014Exeton Generation 2014 Owner's Activity Report Page 5 7forRFO-21 Inservice Examinations Table 1Items with Flaws or Relevant Condition that Require Evaluation for Continued ServiceAs required by the provisions of the ASME Code Case N-532-4Examination Item Number Item Description Evaluation Description CategoryF-A F1.1OB Component Support Acceptance by Design Evaluation per IWE-3510.4 (2-CV-1005-R-17)

(Accepted

'as is' per ESR-14-000251)

F-A P1.108 Component Support Acceptance by Design Evaluation per IWE-3510.4 (2-CV-1005-H-14)

(Accepted

'as is' per ESR-14-000251)

AFl.40C Component Support Acceptance by Design Evaluation per IWE-3510.4 F-A (11 A-1 SC) (Accepted

'as is' per Attachment 2 of ES-002)F-A F .40C Component Support Acceptance by Design Evaluation per IWE-3510.4 (11 A-2SC) (Accepted

'as is' per Attachment 2 of ES-002)Component Support Acceptance by Design Evaluation per IWE-3510.4 F-A F1.40C (11A-3SC)

(Accepted

'as is' per Attachment 2 of ES-002)F-A F1.40C Component Support Acceptance by Design Evaluation per IWE-3510.4 F-AF1.40C_.

(11 A-4SC) (Accepted

'as is' per Attachment 2 of ES-002)F-A F1.20A Component Support Acceptance by Design Evaluation per IWE-3510.4 (8-CS-I 205-H-5,R-3)

(Accepted

'as is' per CR-2014-001553)

Component Support Acceptance by Design Evaluation per IWE-3510.4 F-A F 1.20B (12-SC-1208-H-3)

(Accepted

'as is' per ECP-14-000291)

E-A E1. 1 Primary Containment Acceptance by Design Evaluation per IWE-3510.4 E- _ E1.11_ Liner (Elevation 69'-118')

(Accepted

'as is' per ESR-14-000208)

Accepted by Responsible Engineer (RPE)L-B L2.1 0 Tendon 42H28 (Evaluation per IWL-3300 and documented inCR-2012-009456)

Calvert Cliffs Nuclear Power Plant Unit IFourth Interval First Period Inservce Inspection CCNPP-1-OAR-004-021 ANN Second Interval

/ Second Period Containment June 10, 2014Exelon Generation 2014 Owner's Activity Report Page 6 of 7forRFO-21 Inservice Examinations Table 2Abstract of Repairs.

Replacements or Corrective Measures Required for Continued Serviceas required by the provisions of the ASME Code Case N-532-4Code Date R&R PlanClass Rem Description Description of Work Completed Number1 Snubber 1-52-42 Replace worn pin and weld bracket at the pin connection to 3/5/14 2014-1-013 the steel I-Beam.1 Snubber 1-52-42A Replace worn pin and weld bracket at the pin connection to 3/5/14 2014-1-014 the steel I-Beam.1 Snubber 1-41-09 Install missing nut on snubber bracket 3/11/14 2014-1-021 I CC-8-1003-H-1 Restore piping support H1 on %" CC-8-1003 to original 3/7/14 2014-1-023 Piping Support configuration.

I 2-CV-1005-R-15, Spring can adjusted to within tolerance per CR-2014-002460.

3/11/14 N/AR-16, H-12Component Support1 1-HVRC-265 Restore supports in accordance with drawing FSK-M- 3/8/14 2014-1-026 Support 0063SH0014 and replace missing bolting material.

1 1-RC-267 Reinstallation of 2"m tubing support clamp downstream of 1 -3/8/14 2014-1-025 Tubing Support RC-267 per ECP-14-000232 1 1-HVRC-142 Modify tubing support for 1PDT123A downstream of 1 -RC- 3/10/14 2014-1-028 Support 142 per ECP-14-000232.

I 1-CV-628 Replacement of studs from Boric Acid degradation 312/14 2014-1-015 2 Line Class Replace fastener material on a I HC3-1007 piping class 3/10/14 2014-1-029 HC-3-1007 flanged connection below 1HVSI-311.

2 Line Class Modify 2" CC-7-1 019 Charging Loop support #3 location box 3/4/14 2014-1-007 CC-7-1019 frame per ECP-13-000971.

2 Line Class Modification of supports

  1. 1, #3 & #10 on 2-EB-6-1007 and #1 3/8/14 2014-1-010 EB-6 Supports

& #18 on 2-EB-6-1 0082 Snubber 1-83-69 Replace End Bracket.

(CR-2014-002309) 3/9/14 2014-1-030 3 1-CV-3986 Evaluation of a hairline indication on the internal filament 3/14/14 2013-1-016 between the inside bottom surface of 11 AFW Steam ControlValve and the drain line drilled into the valve body. Thisindication was evaluated using ECP-12-000224-CN-001 andECP-12-000224.

3 Line Class Replace #14 CAC Concentric 8"x6" Reducer on HB-22-1228 3/7/14 2014-1-012 HB-22-1228 line.3 1HXHVACCTCLR11 Restore 11 CAC Support Pedestal Column welds per ECP- 3/2/14 2014-1-016 14-000197 3 1HXHVACCTCLR12 Restore 12 CAC Support Pedestal Column welds per ECP- 3/2/14 2014-1-017 14-000197 3 1HXHVACCTCLR13 Restore 13 CAC Support Pedestal Column welds per ECP- 3/5/12 2014-1-018 14-000197 3 1HXHVACCTCLR14 Restore 14 CAC Support Pedestal Column welds per ECP- 314/14 2014-1-019

_ 14-000197 CCContainment Containment tendon re-tensioned to above 95% thenr ,4i.t- n=gr rP.9Qn19.nnog A10/17/2012 N/A(42H26)

Calvert Cliffs Nuclear Power Plant Unit IFourth Interval I First Period Inservice Inspection CCNPP-1-OAR-004-021 Rev. 00Second Interval

/ Second Period Containment June 10,2014-Exelon Generation 2014 Owner's Activity Report Page 7 of 7forRFO-21 Inservice Examinations CC Containment Containment tendon re-tensioned to above 95% the 10/17/2012 N/ATendons predicted force per CR-2012-009438 (42H27)CC Containment Containment tendon re-tensioned to above 95% the 10/17/2012 N/ATendons predicted force per CR-2012-009438 (42H28)CC Containment Containment tendon re-tensioned to above 95% the 10/17/2012 N/ATendons predicted force per CR-2012-009438 (42H29) 1 1EndofOwners Activity ReportforRefueling Outage 21 (RFO-21)

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