1CAN032302, Inspection Summary Report for the Thirtieth Refueling Outage (1R30)
| ML23079A129 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 03/20/2023 |
| From: | Keele R Entergy Operations |
| To: | Office of Nuclear Reactor Regulation, Document Control Desk |
| References | |
| 1CAN032302 | |
| Download: ML23079A129 (1) | |
Text
~ entergy 1CAN032302 March 20, 2023 ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555 Riley D. Keele, Jr.
Manager, Regulatory Assurance Arkansas Nuclear One Tel 479-858-7826
Subject:
lnservice Inspection Summary Report for the Arkansas Nuclear One, Unit 1 Thirtieth Refueling Outage (1 R30)
Arkansas Nuclear One - Unit 1 NRC Docket No. 50-313 Renewed Facility Operating License No. DPR-51 Article IWA-6000 of Section XI of the 2007 Edition with the 2008 Addenda of the American Society of Mechanical Engineers (ASME) Code requires an lnservice Inspection Summary Report be submitted to the regulatory and enforcement authorities having jurisdiction at the plant site. The summary report is to contain the completed Form NIS-1, "Owner's Report for lnservice Inspection," and Form NIS-2, "Owner's Report for Repair or Replacement Activity."
This 2007 Edition with the 2008 Addenda of the ASME Code is the code of record for the fifth 10-year Interval at Arkansas Nuclear One, Unit 1 (ANO-1)
ASME Code Case N-532 allows Entergy Operations, Inc., to prepare an Owner's Activity Report Form OAR-1 in place of the Code-required NIS-1 and NIS-2 forms. The latest revision of this code case used in this report, N-532-5, is listed in Regulatory Guide 1.147, "lnservice Inspection Code Case Acceptability, ASME Section XI, Division 1," Revision 20, Table 1, "Acceptable Section XI Code Cases." Therefore, prior NRC approval to implement this code case is not required.
This report is to be prepared at the completion of a refueling outage and submitted within 90 calendar days of the completion of the refueling outage. In this case the report is to the thirtieth refueling outage for ANO-1 (1 R30). This outage was completed on December 30, 2022.
Enclosed is the completed Form OAR-1 for 1 R30 for your information. Included with the form are tables listing the "Items of Repair/ replacement Activities for Continued Service" in accordance with Code Case N-532-5. Attached to Form OAR-1 is the Analytical Evaluation of the Pressurizer Heater Bundle bolts in accordance with ASME Section XI, IWB-3142.4.
This letter contains no new commitments.
Entergy Operations, Inc. 1448 SR 333, Russellville, AR 72802
1CAN032302 Page 2 of 2 By means of this submittal, the reporting requirements of the ASME Code,Section XI, Article IWA-6000 are fulfilled for 1 R30.
Should you have any questions or require additional information, please contact Riley Keele, Manager, Regulatory Assurance, at (479) 858-7826.
Respectfully,
/~PJ!(4.
Riley Keele RDK/rwc
Enclosure:
Form OAR-1, Owner's Activity Report Attachment Analytical Evaluation of Pressurizer Heater Bundle Bolts cc:
NRC Region IV Regional Administrator NRC Senior Resident Inspector - Arkansas Nuclear One NRC Project Manager - Arkansas Nuclear One
ENCLOSURE 1CAN032302 FORM OAR-1, OWNER'S ACTIVITY REPORT (3 Pages)
FORM OAR-1 OWNERS ACTIVITY REPORT Report Number: __
...;:O:..:.A..:..:R..a.*...a1"'5""2=2 Page _1_ of _ _l_
Plant: __
.._A""'rk~a"--n=s=as~N=u~cl=e=ar'""O=---ne"'-'--/.....
14
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Unit No: __
1.,___ Commercial Service Date: December 19, 197 4 (1f applicable)
Current Inspection Interval:
Fifth (5th) Inspection Interval
( 1 SI. 2nd. 3rd. 4th. Other)
Current Inspection Period:
Second (2nd) Inspection Period (1S1. 2nd, 3rd)
Refueling Outage No.: 1 R30 Edition and Addenda of Section XI applicable to the Inspection Plans:
2007 Edition with 2008 Addenda Date and Revision of Inspection Plans: June 6 1 2022 I Revision 9 (SEP-ISI-ANO1-101)
Edition and Addenda of Section XI applicable to repair/replacement activities, if different than the Inspection Plans: =S-=a,.,_m-=-=e,_ __
Code Cases used for inspection and evaluation: N-513-4, N-532-5, N-722-1, N-752 (1f applicable. including cases mod1f1ed by Case N-532 and later revisions)
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 1 R30 conform to the requirements of Section XI.
(refueling outage number)
Signed: ~~ A~~er'sD~ig~.i\11. EtJvt ~ liE i\
Date: ol
- s ~ ;>e, d°3 CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and employed by The Hartford Steam Boiler Inspection and Insurance Company 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 loss of any kind arising from or connected with this inspection.
~
Commissions:
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Date:
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FORM OAR-1 OWNERS ACTIVITY REPORT Report Number: OAR-1522 Page 2 of 3 Plant: ___ Arkansas Nuclear One/ 1448 S.R. 333, Russellville, AR. 72802 Unit No: --'1 __ Commercial Service Date: December 19, 1974, Refueling Outage No.: 1 R30
( If applicable>
TABLE 1:
ITE:\IS WITH FLAWS OR RELEVANT CONDITIONS THAT REQl'IREI> E\'ALUA TIOS FOR CONTINllED SERVICE Examination Item Description Evaluation Description Category and Item Number CAT-D-B INSTALL HALF COUPLING Reference CR-ANO-C-2022-00841 ITEM NO.
DUE TO MIC THAU WALL LEAK D2.10 CAT B-G-2 Pressurizer Heater Bundle Analytical Evaluation required by IWB-3132.3 was Item 87.20 Bolting M-310 performed under EC 94473 CAT F-A EFW-1 variable spring support Reference CR-ANO-1-2022-02101 and EC 94072 Item F1.20C
FORM OAR-1 OWNERS ACTIVITY REPORT Report Numher: ---=O;.:..A.:.,..R.,__-..._15..,2:::.:2=------
Page 3 of 3 Plant: ___
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Unit No: __ 1.:.--- Commercial Service Date: December 19, 197 4 Refueling Outage No.:
1 R30 (if applicable)
TABLE 2:
ABSTRACT OF REPAIR/REPLACEMENT ACTIVITIES REQUIRED FOR CO:--:Tl:--:UED SERVICE Code Item Description Description of Work Date Repair/Replacement Class Completed Plan Numher 1
M-308 Replace Pressurizer Heater Bundle 11/28/22 00536783-01 and Fasteners 1
M-309 Replace Pressurizer Heater Bundle and 11/28/22 00536783-02 Fasteners 1
M-310 Replace Pressurizer Heater Bundle and 11/28/22 00536783-03 Fasteners 2
CV-1400 Repair Valve and Replace Fasteners 1/5/2023 00570709-01
ENCLOSURE,ATTACHMENT 1CAN032302 ANALYTICAL EVALUATION OF PRESSURIZER HEATER BUNDLE BOLTS
Analytical Evaluation Required by ASME Section XI EC-94473 Page 1 of 3 Description of Problem:
The Pressurizer Heater Bundles (PHB) were replaced in 1 R30. During disassembly of the PHB bolting, the B-G-2, Item 87.20, VT-1 of the PHB bolting was performed under WO 536783. As indicated on ISi report 1-ISI-VT-22-015, 5 of the bolts (2, 3, 6, 10, and 12) failed the VT-1 inspection due to damaged or sheared threads (reference pages 269-275). Entergy performed FCR 94020, ATC-02, to evaluate the effects of leaving the PHB bolting in place and not implementing a repair replacement strategy.
ASME Code Requirements:
The current ASME code of record for Arkansas Nuclear One, Unit 1 (ANO 1 ), is the 2007 Edition through the 2008 Addenda of ASME Section XI.
ASME Section XI, IWB-3142.4 states:
A component containing relevant conditions is acceptable for continued service if an analytical evaluation demonstrates the component's acceptability. The evaluation analysis and evaluation acceptance criteria shall be specified by the Owner. A component accepted for continued service based on analytical evaluation shall be subsequently examined in accordance with IWB-2420(b).
ASME Section XI, IWB-2420(b) states:
If a component is accepted for continued service in accordance with IWB-3132.3 or IWB-3142.4, the areas containing flaws or relevant conditions shall be reexamined during the next three inspection periods listed in the schedule of the Inspection Program of IWB-2400.
Alternatively, acoustic emission may be used to monitor growth of existing flaws in accordance with IWA-2234.
Analytical Evaluation of PHB Bolting IAW IWB-3142.4:
The damage to the PHB bolting was first observed during heater bundle removal as part of scheduled maintenance activities. Prior to disassembly of the PHB bolted connection a VT-2 (PT 6.9) was completed (WO 563624) and did not identify any evidence of leakage (1-ISI-VT-22-007).
Based upon industry experience and discussions with the vendor, the thread damage is consistent with galling between the stud/bolt and nut threads when nut removal was attempted.
After the nuts were removed, the stud regions with damaged threads were cleaned and chased so that they would be suitable for continued use.
FCR 94020, ATC-02, was initiated to justify the use of the existing studs by using washers to move the engagement region of the nut out to the point where the nuts will be positioned outboard of the damaged thread region.
Analytical Evaluation Required by ASME Section XI EC-94473 Page 2 of 3 Per CALC-ANO1-14-00012 Section 4.3 the evaluation on the damaged bolting showed:
- 1. The stud minimum diameter at the damaged thread location is greater than the diameter of the stud shank (Section 7.1 of Attachment 3).
- 2. Changing the grip length of the studs by 2.5" with washers is acceptable due to ample margin in the original design report of the Pressurizer (Section 7.2 of Attachment 3).
- 3. The stud usage factor will remain below the fatigue factor limits with the new grip length (Section 7.3 of Attachment 3).
- 4. The diaphragm plate will remain seated in the diaphragm plate opening with the washers (Section 7.4 of Attachment 3).
- 5. Thread stresses for nuts that engage with degraded studs were examined and found to be acceptable when considering several nuts and studs acting together (Section 7.5 of )
- 6. The Framatome evaluation provided a specification for washer stack height for each stud (Section 7.6 of Attachment 3).
The final conclusion of the evaluation is that it is acceptable to use the existing studs as-is if washers are used to move the nut engagement outward a maximum of 2.5" so that nuts engage with undamaged threads (See Section 8 of Attachment 3).
IAW EN-DC-115, a Reply Engineering Change is acceptable as this EC does not change plant documents, design or configuration, authorize the implementation of plant configuration change activities and is not being used as a source of design input.
==
Conclusion:==
The thread damage was not a result of the age of the studs. The degradation mechanism that created the thread damage (galling) will not occur during nut installation. An assumption of the analysis was that the nuts would turn freely on the stud through and beyond the expected region of engagement, which was verified by taking actions in the work order (refer to WO-536783 Task 03).
The successive inspections required by IWB-2420(b) will be performed in the next three inspection periods. In addition, a VT-2 will be performed on the PHB bolted connections each RFO IAW the ANO Pressure Testing Program.
References:
- 1) EC 81705
- 2) FCR 94020, ATC-02
- 3) CALC-ANO1-14-00012
- 4) ASME Section XI, 2007 edition with 2008 addenda
Analytical Evaluation Required by ASME Section XI EC-94473 Page 3 of 3
- 5) WO 536783
- 6) WO 563624
- 7) EN-DC-115, Engineering Change Process
Attachment:
None