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=Text=
=Text=
{{#Wiki_filter:I Adnow ANNEMW ANOW Exelon Generation.                                           Kenneth F. Robinson Manager-Engineering Services Calvert Cliffs Nuclear Power Plant 1650 Calvert Cliffs Parkway Lusby, MD 20657 410 495 5208 Office 443 532 5709 Mobile www.exeloncorp.com ken.robinson@exelon.com June 17, 2014 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555 Calvert Cliffs Nuclear Power Plant, Unit No. 1 Renewed Facility Operating License No. DPR-53 NRC Docket No. 50-317
{{#Wiki_filter:I Adnow ANNEMW ANOW Exelon Generation.
Kenneth F. Robinson Manager-Engineering Services Calvert Cliffs Nuclear Power Plant 1650 Calvert Cliffs Parkway Lusby, MD 20657 410 495 5208 Office 443 532 5709 Mobile www.exeloncorp.com ken.robinson@exelon.com June 17, 2014 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555 Calvert Cliffs Nuclear Power Plant, Unit No. 1 Renewed Facility Operating License No. DPR-53 NRC Docket No. 50-317


==Subject:==
==Subject:==
Inservice Inspection Report
Inservice Inspection Report
: 1.
American Society of Mechanical Engineers, Boiler & Pressure Vessel Code, Section Xl, Article IWA-6000


==Reference:==
==Reference:==
: 1. American Society of Mechanical Engineers, Boiler & Pressure Vessel Code, Section Xl, Article IWA-6000 Pursuant to Reference 1, please find enclosed the Inservice Inspection Report for the Calvert Cliffs Nuclear Power Plant Unit 1.
Pursuant to Reference 1, please find enclosed the Inservice Inspection Report for the Calvert Cliffs Nuclear Power Plant Unit 1.
There are no regulatory commitments contained in this letter.
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.
Should you have questions regarding this matter, please contact Mr. Douglas E. Lauver at (410) 495-5219.
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==Enclosure:==
==Enclosure:==
(1) 2014 Owner's Activity Report for RFO-21 Inservice Examinations cc:     Mr. Robert McGeeney (Without Enclosure)
(1) 2014 Owner's Activity Report for RFO-21 Inservice Examinations cc:
CCNPP Project Manager, NRC                   CCNPP Resident Inspector, NRC Region 1 Administrator, NRC                  S. Gray, DNR Ac7
Mr. Robert McGeeney (Without Enclosure)
CCNPP Project Manager, NRC Region 1 Administrator, NRC CCNPP Resident Inspector, NRC S. Gray, DNR Ac7


ENCLOSURE (1) 2014 OWNER'S ACTIVITY REPORT FOR RFO-21 INSERVICE EXAMINATIONS I
ENCLOSURE (1) 2014 OWNER'S ACTIVITY REPORT FOR RFO-21 INSERVICE EXAMINATIONS I
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Calvert Cliffs Nuclear Power Plant, LLC 1650 Calvert Cliffs Parkway Lusby, MD 20657
Calvert Cliffs Nuclear Power Plant, LLC 1650 Calvert Cliffs Parkway Lusby, MD 20657
                          -- Exeton Generation, Fourth Interval I Second Period Inservice Inspection Program and Second Interval I Second Period Containment IWE/L Program 2014 Owner's Activity Report for RFO-21 Inservice Examinations Commercial Service Date: May 8, 1975 NRC Docket Number:         50-317 Document Number: CCNPP-1-OAR-004-021 Revision Number: 00 Prepared by:.
-- Exeton Generation, Fourth Interval I Second Period Inservice Inspection Program and Second Interval I Second Period Containment IWE/L Program 2014 Owner's Activity Report for RFO-21 Inservice Examinations Commercial Service Date: May 8, 1975 NRC Docket Number:
Jeffrey"MMl         1-ac* p Site ISI Program Own er
50-317 Document Number: CCNPP-1-OAR-004-021 Revision Number:
:n Reviewed by:
00 Prepared by:.
Ange   eyes-     z   Site ISI Program Owner Reviewed by:
Reviewed by:
Kurt Bodine - G.S. Nuclear Engineering Programs
Reviewed by:
Jeffrey"MMl
:n 1-ac* p Site ISI Program Own Ange eyes-z Site ISI Program Owner er Kurt Bodine - G.S. Nuclear Engineering Programs


Calvert Cliffs Nuclear Power Plant Unit I Fourth Interval / First Period Inservice Inspection     CCNPP-1-OAR-004-021 Second Interval / Second Period Containment                     Rev. 00 Exton Generation                         2014 Owner's Activity Report                       June 10, 2014 for                                   Page 2 of 7 RFO-21 Inservice Examinations Abstract This Owner's Activity Report (OAR) summarizes the results of the Calvert Cliffs Nuclear Power Plant (CCNPP),
Calvert Cliffs Nuclear Power Plant Unit I Fourth Interval / First Period Inservice Inspection CCNPP-1-OAR-004-021 Second Interval / Second Period Containment Rev. 00 Exton Generation 2014 Owner's Activity Report June 10, 2014 for Page 2 of 7 RFO-21 Inservice Examinations Abstract This 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), Section Xl, Inservice Inspection (ISI) examinations performed in Refueling Outage twenty one (RFO-21) during the period from 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.
Unit 1, American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code (B&PVC), Section Xl, Inservice Inspection (ISI) examinations performed in Refueling Outage twenty one (RFO-21) during the period from 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, Section XI, Division 1." Regulatory Guide 1.147, Revision 16 (Oct. 2010), approved ASME Code Case N-532-4 for use.
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, Section XI, Division 1." Regulatory Guide 1.147, Revision 16 (Oct. 2010), approved ASME Code Case N-532-4 for use.
Line 51: Line 57:
: 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, and provides such information as Code Class, item description, description of work, date completed, and the repair replacement plan number.
: 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, and provides such information as Code Class, item description, description of work, date completed, and the repair replacement plan number.


Calvert Cliffs Nuclear Power Plant Unit I Fourth Interval / First Period Inservice Inspection                       CCNPP-1-OAR-004-021 J      e 00 Second Interval / Second Period Containment Exelon Ge*leration,                                   2014 Owner'S Activity Report                                           Page 3 of 7 for RFO-21 Inservice Examinations FORM OAR-1 OWNER'S ACTIVITY REPORT Fourth Interval/Second Period of Inservice Inspection Program As required by the provisions of the ASME Code Case N-532-4 Report Number                                                             CCNPP-1u-OAR-004-021 Plant                                                             Calvert Cliffs Nuclear Power Plant Unit No.                 1               Commercial Service                 May 8, 1975                   Refueling Outage                   RFO-21 Date                                                              Number (it upplabtule)
Calvert Cliffs Nuclear Power Plant Unit I Fourth Interval / First Period Inservice Inspection CCNPP-1-OAR-004-021 Second Interval / Second Period Containment J
Current Inspection Interval                            Fourth Inservice Inspection Interval     - October 10, 2009 to June 30, 2019 (1-', 2-, 3", 4", other)
e 00 Exelon Ge*leration, 2014 Owner'S Activity Report Page 3 of 7 for RFO-21 Inservice Examinations FORM OAR-1 OWNER'S ACTIVITY REPORT Fourth Interval/Second Period of Inservice Inspection Program As required by the provisions of the ASME Code Case N-532-4 Report Number CCNPP-1u-OAR-004-021 Plant Calvert Cliffs Nuclear Power Plant Unit No.
Current Inspection Period                            Second Inservice Inspection Period - October 10, 2012 to October 9, 2016 (1', 2-, 3")
1 (it upplabtule)
Edition and Addenda of Section XI applicable to the Inspection Plans                                     2004 Edition, No addenda Date / Revision of Inspection Plans                                             Rev. I Ch. I Dated June 4, 2013 Edition and Addenda of Section XI applicable to repair/replacement activities, if different than the Inspection plans                           N/A Code Cases used:                     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-770-1 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 Xl; and (c) the repair/replacement activities and evaluations supporting the completion of                         RFO-21 conform to the requirements of Section Xl                                                                                   , (refueling outage number)
Current Inspection Interval Current Inspection Period Commercial Service Date May 8, 1975 Refueling Outage Number RFO-21 Fourth Inservice Inspection Interval - October 10, 2009 to June 30, 2019 (1-', 2-, 3", 4", other)
Signed       Kurt Bodine -         *
Second Inservice Inspection Period - October 10, 2012 to October 9, 2016 (1', 2-, 3")
* t                                                     Date         4ibi.
Edition and Addenda of Section XI applicable to the Inspection Plans Date / Revision of Inspection Plans 2004 Edition, No addenda Rev. I Ch. I Dated June 4, 2013 Edition and Addenda of Section XI applicable to repair/replacement activities, if different than the Inspection plans N/A Code Cases used:
General Supervisor, CCNPP Nuclear Engineering Programs CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province 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 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/
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-770-1 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 Xl; and (c) the repair/replacement activities and evaluations supporting the completion of RFO-21 conform to the requirements of Section Xl  
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 00/*",._                                               Commissions                             NB 9531 AN.I,C.IS (Inspector's Signature)                                       National Board. State, Province, and Endorsements Date             i
, (refueling outage number)
                        -            Z41J21 4jile
Signed Kurt Bodine -
t Date 4ibi.
General Supervisor, CCNPP Nuclear Engineering Programs CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province 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 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 00/*",._
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 I Fourth Interval / First Period Inservice Inspection                         CCNPP-1-OAR-e04-021 Rev. 00 Aam                                               Second Interval / Second Period Containment                                     June 10, 2014 "Exe~onGenrlation                                        2014 Owner's Activity Report                                               Page 4 of 7 for RFO-21 Inservice Examinations FORM OAR-1 OWNER'S ACTIVITY REPORT Second IntervallSecond Period of Containment IWEIL Inservice Inspection Program As required by the provisions of the ASME Code Case N-532-4 Report Number                                                               CCNP P-i -OAR-004-021 Plant                                                            Calvert Cliffs Nuclear Power Plant Unit No.                 1             Commercial Service                     May 8,1975                      Refueling Outage                  RFO-21 Date                                                                   Number (it applicable)
Calvert Cliffs Nuclear Power Plant Unit I Fourth Interval / First Period Inservice Inspection CCNPP-1-OAR-e04-021 Rev. 00 Aam Second Interval / Second Period Containment June 10, 2014 "Exe~on Genrlation 2014 Owner's Activity Report Page 4 of 7 for RFO-21 Inservice Examinations FORM OAR-1 OWNER'S ACTIVITY REPORT Second IntervallSecond Period of Containment IWEIL Inservice Inspection Program As required by the provisions of the ASME Code Case N-532-4 Report Number CCNP P-i -OAR-004-021 Calvert Cliffs Nuclear Power Plant Plant Unit No.
Current Inspection Interval                       Second In service Inspection Interval - September 9, 2009 to September 9, 2018 (1". 2"-. 3Y'. 4". other)
1 Commercial Service Date (it applicable)
Current Inspection Period                        Second In!service Inspection Period - September 9, 2011 to September 9, 2015 Edition and Addenda of Section XI applicable to the Inspection Plans                                       2004 Edition, No addenda Date / Revision of Inspection Plans                                                  Rev. 1 Dated Feb. 6. 2014 Edition and Addenda of Section Xl applicable to repair/replacement activities, if different than the inspection plans                             N/A Code Cases used:                                                                   N-532-4, N-624, N-666-1, N-739, N-753 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                             RFO-21 conform to the requirements of Section Xl                                                                                       (refueling outage number)
Current Inspection Interval Second In Current Inspection Period Second In!
Signed       Kurt Bodine -         "t V-..Jr                                                           Date       ý.!- -, i Ceireral Superviaor, CCNPP Nuclear Engineering Programs CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province 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 has performed all activities represented by this report in accordance with the requirements of Section Xl By signing this certificate neither the Inspector nor his employer makes any warranty expressed or implied concerning the repair/
May 8,1975 Refueling Outage Number RFO-21 service Inspection Interval - September 9, 2009 to September 9, 2018 (1". 2"-. 3Y'. 4". other) service Inspection Period - September 9, 2011 to September 9, 2015 Edition and Addenda of Section XI applicable to the Inspection Plans 2004 Edition, No addenda Rev. 1 Dated Feb. 6. 2014 Date / Revision of Inspection Plans Edition and Addenda of Section Xl applicable to repair/replacement activities, if different than the inspection plans N/A Code Cases used:
replacement activities and evaluation described in this report. Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personrlnjury or property damage or a loss of any kind arising from or connected with this inspection
N-532-4, N-624, N-666-1, N-739, N-753 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 RFO-21 conform to the requirements of Section Xl (refueling outage number)
___                                              Commissions                               NB 9531 A,N,I,C,IS (Inspector's Signature)                                     National Board. State. Province, and Endorsements Date                 l*"*'.     //-. 2,0/v
Signed Kurt Bodine -
"t V-..Jr Date  
ý.!- -, i Ceireral Superviaor, CCNPP Nuclear Engineering Programs CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province 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 has performed all activities represented by this report in accordance with the requirements of Section Xl 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 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 l*"*'.  
//-. 2,0/v


Calvert Cliffs Nuclear Power Plant Unit I Interval / First 4MMWCFourth          Fourh Period PriodInsrvie Iteral    IFirt Inservice Inspection InpecionRev.                  -OAR-004-021 00 AMW                             Second Interval / Second Period Containment                           June 10, 2014 Exeton Generation                     2014 Owner's Activity Report                               Page 5   7 for RFO-21 Inservice Examinations Table 1 Items with Flaws or Relevant Condition that Require Evaluation for Continued Service As required by the provisions of the ASME Code Case N-532-4 Examination   Item Number           Item Description                                 Evaluation Description Category F-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)
Calvert Cliffs Nuclear Power Plant Unit I 4MMWCFourth Interval / First Period Inservice Inspection  
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)
-OAR-004-021 Fourh Iteral IFirt PriodInsrvie InpecionRev.
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)
00 AMW Second Interval / Second Period Containment June 10, 2014 Exeton Generation 2014 Owner's Activity Report Page 5 7
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)
for RFO-21 Inservice Examinations Table 1 Items with Flaws or Relevant Condition that Require Evaluation for Continued Service As required by the provisions of the ASME Code Case N-532-4 Examination Item Number Item Description Evaluation Description Category F-A F1.1OB Component Support Acceptance by Design Evaluation per IWE-3510.4 (2-CV-1005-R-17)
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)
(Accepted 'as is' per ESR-14-000251)
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 P1.108 Component Support Acceptance by Design Evaluation per IWE-3510.4 (2-CV-1005-H-14)
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)
(Accepted 'as is' per ESR-14-000251)
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)
AFl.40C Component Support Acceptance by Design Evaluation per IWE-3510.4 F-A (11 A-1 SC)
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 '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)
Accepted by Responsible Engineer (RPE)
L-B           L2.1 0             Tendon 42H28                         (Evaluation per IWL-3300 and documented in CR-2012-009456)
L-B L2.1 0 Tendon 42H28 (Evaluation per IWL-3300 and documented in CR-2012-009456)


Calvert Cliffs Nuclear Power Plant Unit I Fourth Interval First Period Inservce Inspection             CCNPP-1-OAR-004-021 ANN                                   Second Interval / Second Period Containment                 June 10, 2014 Exelon Generation                         2014 Owner's Activity Report                       Page 6 of 7 for RFO-21 Inservice Examinations Table 2 Abstract of Repairs. Replacements or Corrective Measures Required for Continued Service as required by the provisions of the ASME Code Case N-532-4 Code                                                                                                   Date       R&R Plan Class   Rem Description                                 Description of Work                     Completed     Number 1       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.
Calvert Cliffs Nuclear Power Plant Unit I Fourth Interval First Period Inservce Inspection CCNPP-1-OAR-004-021 ANN Second Interval / Second Period Containment June 10, 2014 Exelon Generation 2014 Owner's Activity Report Page 6 of 7 for RFO-21 Inservice Examinations Table 2 Abstract of Repairs. Replacements or Corrective Measures Required for Continued Service as required by the provisions of the ASME Code Case N-532-4 Code Date R&R Plan Class Rem Description Description of Work Completed Number 1
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.
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 1-41-09       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.
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.
I     2-CV-1005-R-15,       Spring can adjusted to within tolerance per CR-2014-002460.         3/11/14         N/A R-16, H-12 Component Support 1         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 Snubber 1-41-09 Install missing nut on snubber bracket 3/11/14 2014-1-021 I
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.
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           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.
I 2-CV-1005-R-15, Spring can adjusted to within tolerance per CR-2014-002460.
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.
3/11/14 N/A R-16, H-12 Component Support 1
2         Line Class         Modification of supports #1, #3 &#10 on 2-EB-6-1007 and #1           3/8/14     2014-1-010 EB-6 Supports       &#18 on 2-EB-6-1 008 2       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 Control Valve and the drain line drilled into the valve body. This indication was evaluated using ECP-12-000224-CN-001 and ECP-12-000224.
1-HVRC-265 Restore supports in accordance with drawing FSK-M-3/8/14 2014-1-026 Support 0063SH0014 and replace missing bolting material.
3         Line Class         Replace #14 CAC Concentric 8"x6" Reducer on HB-22-1228               3/7/14     2014-1-012 HB-22-1228         line.
1 1-RC-267 Reinstallation of 2"m tubing support clamp downstream of 1 -
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
3/8/14 2014-1-025 Tubing Support RC-267 per ECP-14-000232 1
_ 14-000197 CC         Containment         Containment tendon re-tensioned to above 95% the                   10/17/2012      N/A nr ,4i.t-   f*r,- n=gr rP.9Qn19.nnog A (42H26)
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, #3 & #10 on 2-EB-6-1007 and #1 3/8/14 2014-1-010 EB-6 Supports  
& #18 on 2-EB-6-1 008 2
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 Control Valve and the drain line drilled into the valve body. This indication was evaluated using ECP-12-000224-CN-001 and ECP-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 CC Containment Containment tendon re-tensioned to above 95% the nr,4i.t-f*r,-
n=gr rP.9Qn19.nnog A 10/17/2012 N/A (42H26)


Calvert Cliffs Nuclear Power Plant Unit I Fourth Interval I First Period Inservice Inspection CCNPP-1-OAR-004-021 Rev. 00 Second Interval / Second Period Containment           June 10,2014
Calvert Cliffs Nuclear Power Plant Unit I Fourth Interval I First Period Inservice Inspection CCNPP-1-OAR-004-021 Rev. 00 Second Interval / Second Period Containment June 10,2014
  -ExelonGeneration            2014 Owner's Activity Report                   Page 7 of 7 for RFO-21 Inservice Examinations CC     Containment Containment tendon re-tensioned to above 95% the         10/17/2012     N/A Tendons   predicted force per CR-2012-009438 (42H27)
-Exelon Generation 2014 Owner's Activity Report Page 7 of 7 for RFO-21 Inservice Examinations CC Containment Containment tendon re-tensioned to above 95% the 10/17/2012 N/A Tendons predicted force per CR-2012-009438 (42H27)
CC     Containment Containment tendon re-tensioned to above 95% the         10/17/2012     N/A Tendons   predicted force per CR-2012-009438 (42H28)
CC Containment Containment tendon re-tensioned to above 95% the 10/17/2012 N/A Tendons predicted force per CR-2012-009438 (42H28)
CC     Containment Containment tendon re-tensioned to above 95% the         10/17/2012     N/A Tendons   predicted force per CR-2012-009438 (42H29)                                                           1                     1 End of Owners Activity Report for Refueling Outage 21 (RFO-21)}}
CC Containment Containment tendon re-tensioned to above 95% the 10/17/2012 N/A Tendons predicted force per CR-2012-009438 (42H29) 1 1
End of Owners Activity Report for Refueling Outage 21 (RFO-21)}}

Latest revision as of 20:16, 10 January 2025

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


Text

I Adnow ANNEMW ANOW Exelon Generation.

Kenneth F. Robinson Manager-Engineering Services Calvert Cliffs Nuclear Power Plant 1650 Calvert Cliffs Parkway Lusby, MD 20657 410 495 5208 Office 443 532 5709 Mobile www.exeloncorp.com ken.robinson@exelon.com June 17, 2014 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555 Calvert Cliffs Nuclear Power Plant, Unit No. 1 Renewed Facility Operating License No. DPR-53 NRC Docket No. 50-317

Subject:

Inservice Inspection Report

1.

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 Calvert Cliffs 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. Robinson Manager - Engineering Services KFR/PSF/bjd

Enclosure:

(1) 2014 Owner's Activity Report for RFO-21 Inservice Examinations cc:

Mr. Robert McGeeney (Without Enclosure)

CCNPP Project Manager, NRC Region 1 Administrator, NRC CCNPP Resident Inspector, NRC S. Gray, DNR Ac7

ENCLOSURE (1) 2014 OWNER'S ACTIVITY REPORT FOR RFO-21 INSERVICE EXAMINATIONS I

Calvert Cliffs Nuclear Power Plant June 17, 2014

Calvert Cliffs Nuclear Power Plant, LLC 1650 Calvert Cliffs Parkway Lusby, MD 20657

-- Exeton Generation, Fourth Interval I Second Period Inservice Inspection Program and Second Interval I Second Period Containment IWE/L Program 2014 Owner's Activity Report for RFO-21 Inservice Examinations Commercial Service Date: May 8, 1975 NRC Docket Number:

50-317 Document Number: CCNPP-1-OAR-004-021 Revision Number:

00 Prepared by:.

Reviewed by:

Reviewed by:

Jeffrey"MMl

n 1-ac* p Site ISI Program Own Ange eyes-z Site ISI Program Owner er Kurt Bodine - G.S. Nuclear Engineering Programs

Calvert Cliffs Nuclear Power Plant Unit I Fourth Interval / First Period Inservice Inspection CCNPP-1-OAR-004-021 Second Interval / Second Period Containment Rev. 00 Exton Generation 2014 Owner's Activity Report June 10, 2014 for Page 2 of 7 RFO-21 Inservice Examinations Abstract This 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), Section Xl, Inservice Inspection (ISI) examinations performed in Refueling Outage twenty one (RFO-21) during the period from 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,Section XI, 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, and with the exception of those examinations that are limited to components selected for examination under Examination 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 those examinations 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 Second Inspection 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-1 Owner's Activity Reports, Form OAR-1. were prepared and certified upon completion of the Calvert Cliffs Nuclear Power Plant Unit 1, 2014 Refueling Outage (RFO-21) examination activity in accordance with the following inspection plans:

Fourth Inservice Inspection Program Plan Second Interval Containment Inservice Inspection Program Plan Fourth Interval Inservice Inspection Pressure Testing Program Plan In 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, which provides 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 a scheduled examination or test, and provides such information as Examination Category, Examination Item Number, 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, and provides such information as Code Class, item description, description of work, date completed, and the repair replacement plan number.

Calvert Cliffs Nuclear Power Plant Unit I Fourth Interval / First Period Inservice Inspection CCNPP-1-OAR-004-021 Second Interval / Second Period Containment J

e 00 Exelon Ge*leration, 2014 Owner'S Activity Report Page 3 of 7 for RFO-21 Inservice Examinations FORM OAR-1 OWNER'S ACTIVITY REPORT Fourth Interval/Second Period of Inservice Inspection Program As required by the provisions of the ASME Code Case N-532-4 Report Number CCNPP-1u-OAR-004-021 Plant Calvert Cliffs Nuclear Power Plant Unit No.

1 (it upplabtule)

Current Inspection Interval Current Inspection Period Commercial Service Date May 8, 1975 Refueling Outage Number RFO-21 Fourth 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 Plans Date / Revision of Inspection Plans 2004 Edition, No addenda Rev. I Ch. I Dated June 4, 2013 Edition and Addenda of Section XI applicable to repair/replacement activities, if different than the Inspection plans N/A Code Cases used:

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-770-1 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 Xl; and (c) the repair/replacement activities and evaluations supporting the completion of RFO-21 conform to the requirements of Section Xl

, (refueling outage number)

Signed Kurt Bodine -

t Date 4ibi.

General Supervisor, CCNPP Nuclear Engineering Programs CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province 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 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 00/*",._

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 I Fourth Interval / First Period Inservice Inspection CCNPP-1-OAR-e04-021 Rev. 00 Aam Second Interval / Second Period Containment June 10, 2014 "Exe~on Genrlation 2014 Owner's Activity Report Page 4 of 7 for RFO-21 Inservice Examinations FORM OAR-1 OWNER'S ACTIVITY REPORT Second IntervallSecond Period of Containment IWEIL Inservice Inspection Program As required by the provisions of the ASME Code Case N-532-4 Report Number CCNP P-i -OAR-004-021 Calvert Cliffs Nuclear Power Plant Plant Unit No.

1 Commercial Service Date (it applicable)

Current Inspection Interval Second In Current Inspection Period Second In!

May 8,1975 Refueling Outage Number RFO-21 service Inspection Interval - September 9, 2009 to September 9, 2018 (1". 2"-. 3Y'. 4". other) service Inspection Period - September 9, 2011 to September 9, 2015 Edition and Addenda of Section XI applicable to the Inspection Plans 2004 Edition, No addenda Rev. 1 Dated Feb. 6. 2014 Date / Revision of Inspection Plans Edition and Addenda of Section Xl applicable to repair/replacement activities, if different than the inspection plans N/A Code Cases used:

N-532-4, N-624, N-666-1, N-739, N-753 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 RFO-21 conform to the requirements of Section Xl (refueling outage number)

Signed Kurt Bodine -

"t V-..Jr Date

ý.!- -, i Ceireral Superviaor, CCNPP Nuclear Engineering Programs CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province 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 has performed all activities represented by this report in accordance with the requirements of Section Xl 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 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 l*"*'.

//-. 2,0/v

Calvert Cliffs Nuclear Power Plant Unit I 4MMWCFourth Interval / First Period Inservice Inspection

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

00 AMW Second Interval / Second Period Containment June 10, 2014 Exeton Generation 2014 Owner's Activity Report Page 5 7

for RFO-21 Inservice Examinations Table 1 Items with Flaws or Relevant Condition that Require Evaluation for Continued Service As required by the provisions of the ASME Code Case N-532-4 Examination Item Number Item Description Evaluation Description Category F-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 in CR-2012-009456)

Calvert Cliffs Nuclear Power Plant Unit I Fourth Interval First Period Inservce Inspection CCNPP-1-OAR-004-021 ANN Second Interval / Second Period Containment June 10, 2014 Exelon Generation 2014 Owner's Activity Report Page 6 of 7 for RFO-21 Inservice Examinations Table 2 Abstract of Repairs. Replacements or Corrective Measures Required for Continued Service as required by the provisions of the ASME Code Case N-532-4 Code Date R&R Plan Class Rem Description Description of Work Completed Number 1

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/A R-16, H-12 Component Support 1

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

& #18 on 2-EB-6-1 008 2

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 Control Valve and the drain line drilled into the valve body. This indication was evaluated using ECP-12-000224-CN-001 and ECP-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 CC Containment Containment tendon re-tensioned to above 95% the nr,4i.t-f*r,-

n=gr rP.9Qn19.nnog A 10/17/2012 N/A (42H26)

Calvert Cliffs Nuclear Power Plant Unit I Fourth Interval I First Period Inservice Inspection CCNPP-1-OAR-004-021 Rev. 00 Second Interval / Second Period Containment June 10,2014

-Exelon Generation 2014 Owner's Activity Report Page 7 of 7 for RFO-21 Inservice Examinations CC Containment Containment tendon re-tensioned to above 95% the 10/17/2012 N/A Tendons predicted force per CR-2012-009438 (42H27)

CC Containment Containment tendon re-tensioned to above 95% the 10/17/2012 N/A Tendons predicted force per CR-2012-009438 (42H28)

CC Containment Containment tendon re-tensioned to above 95% the 10/17/2012 N/A Tendons predicted force per CR-2012-009438 (42H29) 1 1

End of Owners Activity Report for Refueling Outage 21 (RFO-21)

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