ML19169A060
| ML19169A060 | |
| Person / Time | |
|---|---|
| Site: | Calvert Cliffs  |
| Issue date: | 06/13/2019 |
| From: | Laura Smith Exelon Generation Co |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| Download: ML19169A060 (5) | |
Text
June 13, 2019 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555
Subject:
Calvert Cliffs Nuclear Power Plant, Unit No. 1 Renewed Facility Operating License No. DPR-69 NRC Docket No. 50-318 lnservice Inspection Report Larry D. Smith Manager-Regulatory Assurance Calvert Cliffs Nuclear Power Plant 1650 Calvert Cliffs Parkway Lusby, MD 20657 410 495 5219 Office www.exeloncorp.com larry.smith2@exeloncorp.com
Reference:
- 1.
American Society of Mechanical Engineers, Boiler & Pressure Vessel Code,Section XI, Article IWA-6000 Pursuant to Reference 1, please find enclosed the lnservice Inspection Report for the Calvert Cliffs Nuclear Power Plant Unit 2.
There are no regulatory commitments contained in this letter.
Should you have questions regarding this matter, please contact Mr. Larry D. Smith at (410) 495-5219.
Respectf u I ly,
~~~
~arry rJ. Smith Manager - Regulatory Assurance LDS/KLG/lmd
Enclosure:
(1) 2019 Owner's Activity Report for 2-RF0-22 lnservice Examinations cc:
(Without Enclosure)
NRC Project Manager, Calvert Cliffs NRC Regional Administrator, Region I NRC Resident Inspector, Calvert Cliffs D. A. Tancabel, MD-DNA
ENCLOSURE (1) 2019 OWNER 1S ACTIVITY REPORT FOR 2-RF0-22 INSERVICE EXAMINATIONS Calvert Cliffs Nuclear Power Plant June 13, 2019
Report Number Plant Unit No.
2 (if applicable)
FORM OAR-1 OWNER'S ACTIVITY REPORT Commercial Service Date CC2R23 Calvert Cliffs Nuclear Power Plant April 1, 1977 Refueling Outage Number CC2R23 ISi and Pressure Testing (PT) Fourth lnservice Inspection Interval -October 10, 2009 to June 30, 2019; Current Inspection Interval Containment lnservice Inspection Interval - September 9, 2009 to June 30, 2019 (1, 2nd, 3rd, 4th, other)
ISi and Pressure Testing Third lnservice Inspection Period - October 10, 2016 to June 30, 2019; Containment (GISI)
Current Inspection Period Third lnservice Inspection Period September 9, 2016 to June 30, 2019 (1", 2nd, 3rd)
Edition and Addenda of Section XI applicable to the Inspection Plans 2004 Edition, No addenda ISi-Rev. 00200 Dated August 19, 2015 and Rev. 00300 Dated January 28, 2019; PT - Rev. 00200 Dated Date I Revision of Inspection Plans October 23, 2014 and Rev. 00300 Dated January 28, 2019; GISI - Rev. 00100 Dated February 6, 2014 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-504-4, N-513-3, N-513-4, N-526, N-532-4, N-552, N-552-1, N-561-2, N-562-2, N-566-2, N-586-1, N-593, N-593-2, N-613-1, N-616, N-619, N-624, N-638-6, N-639, N-641, N-643-2, N-648-1, N-653-1, N-664, N-686-1, N-705, N-716, N-722-1, N-729-1, N-729-4, N-739, N-731, N-733, N-747, N-751, N-753, N-762, N-770-1, N-770-2, N-773, N-786, N-786-1, N-789, N-798, N-800, N-805, N-823, N-825, N-845 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 CC2R23 conform to the requirements of Section XI (refueling outage number)
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Manager, CCNPP Nuclear Engineering Programs
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CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of Maryland The Hartford Steam Boiler of Hartford, Connecticut and employed by Inspection and Insurance Co.
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
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CJ Comm;ss;oas NB 15304ANI, MD 1'!2B
'spector's Signature)
National Board, State, Province, and Endorsements Date b/JsJ/'\\
FORM OAR-1 OWNER'S ACTIVITY REPORT Table 1 Items with Flaws or Relevant Condition that Require Evaluation for Continued Service
. Examination Ev;a1u*atici11 "t~~~cription
- ¢ateg9ry and" I.tern Description*.
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- Item Numb.er
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',-,i Evaluated through-wall leaks and thinned areas in accordance with 0-A, 02.10 Salt Water Cooling Piping Code Case N-513-4 (reference Operability Evaluation 18-001 (issue reports 04138657 and 04139053)).
Chemical and Volume Boric acid deposits on and adjacent to the valve bolting were evaluated Control Valve 2-CV-517 8-P, 815.10 Bolting as acceptable per Code Case N-566-2 (reference ECP-19-000120).
Boric acid deposits at penetrations 72 and 73 were evaluated to be acceptable as required by Code Case N-729-4, -3142 (reference issue Reactor Vessel Closure report 04224776). The source of the deposits was determined to be a Code Case Head 2SYS064 misaligned flange at valve 2HVRC-104 that leaked prior to restart from N-729-4, 84.30 the 2017 refueling outage based on radiochemistry analysis and boric acid deposit observations. There was no wastage or ferritic steel wall reduction observed.
Boric Acid was identified on the 21 B RCP Studs, Nuts, and Seal Bolting.
Reactor Coolant Pump Evaluation ECP-19-000297, performed per Code Case N-566-2, RCP-21 B Main Flange concluded that the BACC deposits identified on the 21 B RCP Studs, 8-P, 815.10 Studs and Nuts and Seal Nuts, and Seal Bolting do not present any plant equipment operability Housing Bolts issues and no corrosion or degradation was identified to warrant further investigation.
Reactor Vessel (RV)120-degree Core Stabilizing Lug Shim Lockpin was Core Support Barrel discovered protruding and bent from its installed location. Approximately B-N-3, 813.70 Snubbers 9/16" of the length of the pin is hollowed and has broken off. ECP 000129 conclu.9~cj_ tb.?t the snubb.eLlugwilLbe_ableJo_per:form-its--.
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intended safety function in the event of shim bolt/shim pin failures.
The 180-degree Core Support barrel (CSB) Alignment Key and key retaining pin was discovered to be slightly backed out. The result of this Upper Guide Structure condition is that this one alignment key is no longer tight against the keyway face in the CSB flange. ECP-19-000134 concluded that the gap B-N-3, 813.70 Support Plate - (Top) &
of the Core Barrel Alignment Keys in the Core Support Barrel Flange is Keyways acceptable and that with the reactor internals assembled, there will be no potential for the key or retaining key pin to come loose.
2 3
3 3
FORM OAR-1 OWNER'S ACTIVITY REPORT Table 2 Abstract of Repairs, Replacements or Corrective Measures Required for Continued Service
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'-'. IJ~~J>e$cr!p!io,r, Cold Leg Charging Inlet Dissimilar Metal Weld 2-CV-2005-30 Shutdown Cooling Heat Exchanger 21 SDCHX Outlet Nozzle Salt Water Cooling Piping Spool Pieces 2-MC6-2004 and 2-MC6-2018 Component Cooling Heat Exchanger 2HXCC21 Salt Water Pump Discharge Check Valve 2CKVSW-103
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Performed full structural weld overlay repair. Reference February 11, 2019 Letter from Exelon Generation (Accession Number ML 19072AA096}
for Additional Information).
Removed dye penetrant indications by grinding. No welding was required and the indications were determined to be due to fabrication or handling damage.
Replaced 8" nominal pipe size pipe spool segments with stainless steel piping due to wall thinning and through-wall leak.
Replaced defective tubing.
Replaced valve with spare due to through-wall leak. Repaired/rebuilt removed valve.
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03/14/2019 03/01/2019 06/18/2018 03/05/2019 05/23/2018 2019-2-009 2019-2-008 2018-2-006 and 2018-2-007 2018-2-063 2017-2-043 and 2017-2-046