ML20024A557
| ML20024A557 | |
| Person / Time | |
|---|---|
| Site: | Maine Yankee |
| Issue date: | 06/08/1983 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20023B345 | List: |
| References | |
| NUDOCS 8306170472 | |
| Download: ML20024A557 (9) | |
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UNITED STATES ew* d.'
NUCLEAR REGULATORY COMMISSION WASHINGTON. D. C. 20555
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SAFETY EVALUATION BY THE
-l OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO REQUESTS FOR RELIEF' FROM INSERVICE INSPECTION REQUIREMENTS MAINE YANKEE ATOMIC POWER PLANT MAINE YANKEE ATOMIC POWER COMPANY DOCKET NO. 50-309 i
INTRODUCTION Technical-Specification 4.7 for.the Maine Yankee Atomic Power Plant states that inservice examination of ASME Code Class 1, 2, and 3 compo-nents shall be performed in accordance with Section XI of the ASME Boiler and Pressure Vessel Code and applicable Addenda as required by 10 CFR 50.55a(g) except where specific written relief.has been granted by the Commission.
Certain requirements of later editions end addenda of Section XI are impractical to perform on older plants because of-the
' plants' design, component geometry, and materials of construction.
Thus,1Q CFjt 50.55a(g)(6)(1) authorizes the Commission to grant relief from-those requirements upon making the necessary findings.
~ By letters dated May 13, 1976, February 15, 1978, March 28, September 4 and 21, 1979, April 30, May 27, and October 12, 1982, Maine Yankee Atomic Power Company submitted its inservice inspection program, revisions, or additional'information related to' request for relief from certain Code requirements determined to b'e impractical to perform on the Maine
' Yankee Atomic Power Plant during the inspection interval.
The program is based on the'1974 Edition through Summer of 1975 Addenda of Section XI of the ASME Code, and covers the 40-month inservice inspection period from August 28, 1979 to December 28, 1982.
Although the date of appli-cability of this Code edition and addenda has expired,-the relief requests evaluated in this report may still be valid because all examinations required to be performed during the ten year interval may not have been completed or.because the examination requirements in the.later edition and addenda of'Section XI may be the same as those for which relief has been requested.
The relief requests for the next 120-month inspection interval to be submitted for review should factor the information pre-sented in this report into consideration.
EVALUATION Requests for relief from the requirements of Section XI which have been 7
determined to be impractical to perform have been reviewed by the Staff's contractor, Battelle,' Pacific Northwest Laboratory.
The contractor's tevaluations of the licensee's requests for relief and his recommendations are presented in the Technical-Evaluation Report (SER) attached (ATTACH-MENT 1). The staff has reviewed the TER and agrees with the evaluations and; recommendations.
A summary of the determinations made by'the staff is presented in the following tables:
r306170472 830600 i
PDR ADOCK 05000309 0
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TABLE 1 CLASS 1 COMPONENTS I
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Licensee Proposed Relief IWB-2600 IWB-2500 System or Area to be Required Alternative Request Item No.
Exam. Cat.
Component Examined Method Exam Status Bl.2 B-B Reactor Circumferen-Volumetric Volumetric Granted Vessel tial and as access-meridional ible welds 81.4 B-D Reactor Nozzle to Volumetric Volumetric Granted Vessel vessel welds 81.18 B-0 Reactor CR0 welds Volumetric Surface Granted Vessel B1.13 B-I-1 Reactor Closure Head (1) Visual and Visual Grantfed l
Vessel Cladding surface, or (2) Volumetric Bl.14 B-I-1 Reactor Vessel Visual Visual Granted Vessel Cladding Bl.12 B-H Reactor Integrally-Volumetric Surface Granted Vessel Welded Supports 83.7 B-H Heat Exchangers Integral,1y-Volumetric Surface Granted and Steam Welded Supports Generators B4.9 B-K-1 Piping Integrally-Volumetric Surface Granted Welded Supports
TABLE 1 CLASS 1 COMPONENTS Licensee Proposed Relief IWB-2600 IWB-2500 System or Area to be Required Alternative Request item No.
Exam. Cat.
Component Examined Method Exam Status.
84.10 B-K-2 Piping Support Visual Visual Relief Not Components Necessary B5.4 B-K-1 Pumps Integrally-Volumetric Surface Granted Welded Supports B5.5 B-K-2 Pumps Support Visual Visual Relief Not Components Necessary 86.4 B-K-1 Valves Integrally-Volumetric Surface Granted Welded Supports B6.5 B-K-2 Valves-Support Visual Visual Relief Not Components Necessary B4.1 B-F Piping Safe-end Welds Surface &
Surface &
Granted (Relief
.(SA 351 - CF8M Volumetric Volumetric Request Portion) from Nozzle Side No. 5) 84.1 B-F Piping Nozzle to Volumetric &
Surface &
Granted I
(Relief safe end and Surface Volumetric on Request safe -end-to forging and pipe No. 10) pipe welds side, surface on SA351-CF8M and SA451-CPF8M materials 84.5 B-J Piping Circumferential Volumetric Surface Not Granted and Longitudinal i
I Welds i
TABLE 1 CLASS _1 COMPONENTS Licensee Proposed Relief IWB-2600 IWB-2500 System or Area to be Required Alternative Request Item No.
Exam. Cat.
Component Examined Method Exas Status 84.6 B-J Piping Branch Pipe Volumetric Surface Not Granted Connection Welds Exceeding Six-Inch Diameter B4.5 B-J Pump Pump to valve Volumetric Surface Granted welds 86.6, B6.7 B-M-1, B-M-2 Valve Valve body Volumetric /
Visual and Granted welds Visual possibly Volumetric B5.6 B-L-1 Pump Casing Welds Volumetric None Not Granted 85.7 B-L-2 Pump Internal Visual None Not Granted Surfaces B6.6 B-M-1 Valves Valve-Body Volumetric Visual &
Not Granted Welds Volumetric if Possible B6.7 B-H-2 Valves Valve Bodies Visual Visual when Granted Internal Disassembled Surfaces 4
TABLE 2 CLASS 2 COMPONENTS Licensee Proposed Relief IWC-2600 IWC-2520 System or Area to be Required Alternative Request Item No.
Exam. Cat.
Component Examined Method Examination Method. Status C1.1 C-A Chemical and Pressure Volumetric Visual dur-Not Granted (RFR No.
volume control vessel ing hydro 13,'14, system welds
~15, 16, 17, 18' 19 & 20)
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TABLE 3 CLASS 3 COMPONENTS No Relief Requests t
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l TABLE 4 PRESSURE TEST IWA-5000, IW8-5000 Licensee IWC-5000 and Proposed Relief Alternative Request System or IWD-5000 Test Test Pressure Status Component Pressure Requirement Chemical and IWC-5000, 3438 psig 188 psig Granted Volume Con-trol System Components CH-24, 25, 26
& 27 Safety Injection IWB-5210 Leakage None Granted System Components Test SIH-20, 22, 24, 30, 31, 33, 34, 41, 42, RC-48, 49, 50, 51, 52 & 53 Chemical and IWD-1200 & IWC-1200 None Granted Volume Control Pressure Test Require-System Seal ments Water Return From Reactor Coolant Pump Line/ Components CH-77, 81, 82, 83, 92, 95, 249, 251, 253, 255, 257, 258, DRL-121 & 122 Various Class IWC-5220, temperature None Granted 2 Systems not less than 100 F Centrifugal IWC-5220(a), 1.25 P Test at suction Granted D
Pump Dis-side pressure charge Lines requirement Various Class IWA-5210(a), hold for Hold for 10 Granted
~2 and 3 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> minutes Class 2 or IWC-1210*
None Not NNS Penetra-Granted tions
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Feedwater IWC-5220(a), 1560 psig 1230 psig Granted System t
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- Relief is requested from performing pressure tests to Class II requirements on piping between containment isolation valves when the balance of system pipirig is Class III or non-nuclear.
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l TABLE 5-ULTRASONIC EXAMINATION TECHNIQUE
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Licensee Proposed Relief System or Alternative Request Component Requirement Examination Method Status No Relief Requests 4
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05/20/83 9
MAINE YANKEE INSERVICE INSPEC
t' TABLE 6 GENERAL RELIEF REQUESTS ALL CLASSES / COMPONENTS Licensee Proposed Relief System or Alternative Request Component Requirement Test Pressure Status No Relief Requests i
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P Based on the review summarized, the staff concludes that relief granted from the examination requirements and alternate methods imposed through this document give reasonable assurance of the piping and component pressure boundary and support structure integrity; that granting relief where the Code requirements are impractical is authorized by law and will not endanger life or property, or the common defense and security, and is otherwise in the public interest considering the burden that could result if they were imposed on the facility.
ENVIRONMENTAL CONSIDERATION We have determined that granting relief from specific ASME Section XI Code requirements does not authorize a change in effluent types or total amounts nor an increase in power level and will not result in any significant environmental impact.
Having made this determination, we have further concluded that this is an action which is insignificant from the standpoint of environmental impact and, pursuant to 10 CFR SSI.5(d)(4), that an environmental impact statement or negative declaration and environmental impact appraisal need not be prepared in connection with the granting of this relief.
CONCLUSION-We have concluded, based on the considerations discussed above, that:
(1) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner, and (2) such activities will be conducted in compliance with the Commission's regulations and the granting of this relief will not be inimical to the common defense and security or to the health and safety of the public.
Date: JUN 8 1983
Attachment:
Technical Evaluation Report Principal Contributor:
G. Johnson, DE