ML20126A126
| ML20126A126 | |
| Person / Time | |
|---|---|
| Site: | FitzPatrick  |
| Issue date: | 12/10/1992 |
| From: | Boltz E, Chapman N, Ruddy D POWER AUTHORITY OF THE STATE OF NEW YORK (NEW YORK |
| To: | |
| Shared Package | |
| ML20126A121 | List: |
| References | |
| PROC-921210, NUDOCS 9212170245 | |
| Download: ML20126A126 (12) | |
Text
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- 3EEE1ENgg,g,y Attachment #1 ASME SECTION XI REPAIR PROGRAM FOR REPAIR OF THE RWCU VALVE 12RWC 1/2" EQUALIZATION LINE PLANT MODIFICATION M1-92-383 JAMES A.
FITZPATRICK NUCLEAR POWER PLANT PREPARED BY:
y I?-] W 42kOflb Ed Boltz f
Robert Per67 - WPO JAF Site Engineering Nuclear Maintenance ISI REVIEWED BY:
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!Yal Chapqdn Tom.Moskalyk
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JAF Site Welding Engineer JAF Site Engineering-Mechanical Supervisor APPROVED BY:
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YIY Dan Rud y Site Engineeri g Manager 1.0 DES _QRIPTION 9212170245 921264 PDR ADOCK 05000333 P
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o ASME SECTION XI REPAIR PROGRAM
1.0 DESCRIPTION
This repair program addresses the repair of the.1/2" bypass line on valve 12RWC-46.
The repair will be performed in accordance with the requirements of ASME_Section XI.
During post work testing on the RWCU system a leak was discovered on the equalization line pipe connection to the bonnet of the valve 12RWC-46.
The 1/2" equalization line is fabricated from stainless steel components while the valve is fabricated from ASTM A352 LCB. This repair program conforms to the requirements of the JAF ISI Program, Section 1.3.8.
In addition, a root cause evaluation shall be performed to ensure that the mode of failure has been clearly identified.
A root cause evaluation shall be completed prior to startup.
Non-Destructive Examinations (NDE) shall be performed on other similar components, if the root cause determination:
concludes that this failure mode could occur at other valves with this type of material configuration.
2.0 ORIGINAL CODE OF CONSTRUCTION The valve was installed under modification F1-84-053 and wcs designed and fabricated in accordance with ANSI B16.34, 1981 Edition.
The material of the valve body-is ASTM A352 LCU.
The 1/2" equalization line is constructed of ASTM A312 Type 316L for the pipe material.
The fittings are fabricated-in accordance with ANSI B16.11 of ASTM A182 Type F316L stainless steel material.
3.0 CODE OF REPAIR Pipe repair activities will be conducted in accordance with the JAF ISI Program and ASME Section XI 1980 Edition.through Winter 1981 Addenda-which;is the' code in effect at the FitzPatrick plant.
As allowed by ASME Section XI, paragraph' IWA-4120 the design code specified is.the 1986 Edition of ASME Section III, Subsection NB.
The design analysis results for this repair will meet all primary'and secondary-stress load limits.
A fatigue analysis shall also be performed to ensure that all components are within the usage factor requirements of ASME Section III for at least one fuel cycle of plant operation.
Page 2 of 6 9--
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l ASME SECTION XI REPAIR PROGRAM The design organization is Structural Integrity Associates (SIA).
All engineering calculations shall be performed in accordance with SIAs Quality Assurance program.
NYPA acceptance of all calculations performed by SIA shall be in accordance with the applicable Design Control Manual (DCMs) procedures.
The Authorized Nuclear Inservice Inspector (ANII) has been notified and accepted the use of this repair method in a memorandum dated 12/1/92.
The ANII has not specified any required' hold points during the repair process.(Attachment The ANII shall review the final completed modification
- 1).
package to ensure compliance with all applicable inspection and installation procedures.
4.0 REPAIR DETAILS ansist of a 1-1/2" Encapsulation' Pipe The repair shall assembly labricated from ASTM A312 Type 316L stainless steel pipe as shown in Attachment 2.
The design will ensure that-the repair is capable of meeting all primary and secondary stress loads.
The encapsulation pipe as installed will provide a pressure and structural integrity boundary for the 1/2" stainless steel pipe.
Prior to installation of the encapsulation pipe, the weld that has the through wall defect will be seal welded to prevent leakage during installation of_the repair assembly.
Seal welding has been performed to prevent through wall leakage in piping components during installation of Modification F1-88-041,
" Installation of Weld Overlays on the Reactor Recirculation This seal System and Core Spray System" at FitzPatrick.
weld technique has worked with much success during application of weld overlays.
An encapsulation pipe of the same design will be installed on the other leg of the 1/2" pipe which has not experienced-failure at the valve connection. - This is being-performed as
,I recommended by the stress analysis.
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All installation activities including welding shall be An performed under the JAF Quality Assurance Program.
installation procedure shall be issued in-accordance with h
applicable plant procedures.
Mockup testing shall be l
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performed prior to performing the production welds to minimize radiation exposure (ALARA) and to familiarize the craft personnel with the installation procedures.
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Page 3 of 6
L' ASME SECTION XI REPAIR PROGRAM 5.0 WELDINQlEATERI A',
REQUIREMENTS Material chall be purchased in accordance with the requirements for QA Category 1 components.
Welding and Welder qualifications shall be performed in accordance with the JAF Site Welding Program, approved welding procedures and ASME Section IX, latest Edition and Addenda.
After completion of welding all welds of the encapsulation assembly shall be examined in accordance with the inspection requirements of ASME Section XI, IWA-7530, IWB-2200 and Table IWB-2500-1, Code Category B-J.
A surface examination shall be performed for all welds.
All Non-Destructive Examinations (NDE) shall be performed in accordance with the JAF Quality Assurance Program inspection procedures by personnel qualified in the specific discipline.
The JAF Quality Assurance Program is not required to be updated to perform this work (Attachment 3 or IWA-7000 of ASME Section XI).
Pressure Testing shall be performed in accordance with the requirements of ASME Section XI 1980 Edition through Winter 1981 Addenda, Article IWB-5000.
After the hydrostatic test threaded pipe plugs will be installed and seal welded for pressure boundary integrity.
Inspections shall be performed in accordance with JAF Quality Assurance Program.
6.0 OUALITY ASSURANCE REOUIREMENTS All work shall be performed in accordance with the JAF Quality Assurance Program.
The JAF Quality Assurance Program conforms to the requirements set forth in:
The U.S. Code of Federal Regulations, 10CFR50, Appendix B, " Quality Assurance Criteria for Nuclear Power Plants".
U.S.
ANSI N45.2-1971, " Quality Assurance Requirements for Nuclear Power Plants".
Page 4 of 6
d ASME SECTION XI' REPAIR PROGRAM 4
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'7.O DoCVliEllTATlD11 The following plant records shall be maintained at:the FitzPatrick Nuclear Power Plant:
1.
Certified. Material Test Reports-(CMTRs)-for the filler.
material.and pipe material, j
2.
Welding procedure specifications and qualification records.
3.
Certification records of welder qualification.
4.
NDE examination procedures and personnel qualifications.
5.
NDE inspection reports including system pressure test records..
6.
All Modification documentation.
7.
Work Control Documents (i.e. weld data sheets, inspection reports, and Work Requests).
8.0 91 rg?ncts 1.
JAF Inservice Inspection Program,. latest revision.
2.
ASME Boiler and Pressure Vessel Codo, Section'XI,-1980 Edition-through Winter 1981 Addenda.
ASME Boiler and Pressure Vessel' Code,Section III, 1986 3.
Edition.
4.-
ASME Boiler and Pressure Vessel Code,Section IX, Latest Revision.
5.
JAF Final Saf.ny Analysis Report (ESAR), Section 16.5',
" Pressure Integrity of Piping Equipment 7 Pressure Parts".
6.
!JAF Welding Program, latest Revision.
'7.
Plant Drawings 6.37-231 and 232, Valve 12RWCU-46 i
Page 5 of 6
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ASME SECTION XI REPAIR PROGRAM
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8.
Plant Modification F1-84-053, "RHR/RWCU Pipe and Valve Replacement Activities."
9.
Plant Modification M1-92-383, "Encapsulization of 12RWC-46 Bypass Equalization Line" 9.0 ATTACHMENTS 1.
Memorandum from the ANII, dated 12/1/92, Discussing the
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repair method.
2.
Drawing of 12RWCU-46, Detailing the repair installation.
Code Interpretation XI-1-86-44R, Discussing ASME 3.
Section XI Repair Options.
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0 OfTICE MEMORANDUM ATTAcansur i
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ATTACHMENT 1 ACTION PLAN FOR REPAIR OF RWCU BUCTION VALVE EQUALI2ING LINE (12RWC-46)
PROBLEM STATEMENT A pin hole leak in the pipe weld for the bonnet equalizing line was being repaired (welded).
A metal fragment broke away frem the equalizing pipe leaving a hole.
A three foot stream of water exited the hole until a temporary repair was made.
Leakage was slowed but net secured.
Task is to determine cause of the failure and implement a permanent repair.
Three cptions are being pursued:
1)
Trprove isolation to al':w for replace =ent of the equalizing line.
2)
Faoricate a clamshell repair to encompass the f ailed pipe and weld.
3)
Assess requirements for installing the recire plug to achieve isolation and repair.
Acticn plans for each option are attached.
The overall lead for all efforts to repair 12RWC-46 is the Joe DeRoy.
Maintenance Department 1
i November 30, 1992 ow-*e 1
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4 ATTACILMINT #3 xi.146.Jte, xi.1.ck44a secwn xl - interpretaucas % 22 Interpretatlom XI.146 39R Sub;Kt:
Section XI Diwsion I, iWA.7210(ct: Use of Portens of Later fditions and Addeoda (1977 Edition With Addenda Through Sumrner 1978, and Later Editions and Addentsa Througn Summer 1985)
Date issed:
January 28, 1988 Me BC55 525C' Question: When making replacements in accordance with Section XI, lWA.7210 allows use of later ecitions of the Cor'struction Code e:ther in its entirely or pomons thereof. Is it permis9ble uncer Section Al to apply only specibe port.ons of f ater editions of the Construct!on Code)
Reply: Yes, provided the requirements of lWA.7210(c)(1), (2), and t3) and all related requirements of the respe<tive edit >ons and addenda are met, interpretatJon XI.1 86-44R Sv::iect:
Section XI, Division 1, IWA.4000 and IWA.7000: Repair arv8 Replacement Parts - Stamping (1980 Ed tion With Addenda Through Wir ter 1981)
Date lisoed:
January 28, 1988 File =
IN66 015' Question f't if a nuc! ear power plant was constructed to a Code which did not require stampir g ano re Owrer dec ces to do the $ec:ron XI repa>rs ilWA 4000) to Section lit,1960 Edition with Acdenda through Summer 1982,is stampens requiredi Rep y (1) N o.
Question (2): In the above situation, it it mandatory to invoke a Section Ill, NCA 3800 Quality Amrance Program on matettal suppliers / material manufacturetti Reply (2) No, it is not mandatory to trDdale Your QVality Assurance Program. However, if you do not, you would st.ll have to meet the origitul Comtruction Codes Quality Assurance Program.
Question (3h When rnaking replacements in accordance with $ection XI, IWA.7210 allows use ci later editions of the Construction Code either in its entirety or portions thereof. Is it permissible uncer Section XI to apply only specific portions oflater editions of the Construction Codei Reply (3): Yes, provided the requirements of IWA 7210(cXI) (2), and (3) and all related recuirements ci the respective editions and addenda are met.
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4 New York Power Authority James A. FitzPatrick Nuclear Power Plant ATTACHMENT 4 to JPN 92-007 i
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i NYPA Drawing, MSK-3002 Sh. 2 of 2 Reactor Water Recirculation System T
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