ML20213D836
| ML20213D836 | |
| Person / Time | |
|---|---|
| Site: | Vogtle  |
| Issue date: | 11/04/1986 |
| From: | Bailey J GEORGIA POWER CO. |
| To: | Youngblood B Office of Nuclear Reactor Regulation |
| References | |
| GN-1162, NUDOCS 8611120263 | |
| Download: ML20213D836 (4) | |
Text
. _...
Georgia Fbwer Company Fbst Offic] Bc4 282 Waynesboro, Georgia 30830 Telephone 404 554-9961 404 724-8114 Southern Company Services, Inc.
Fbst Office Box 2625 h
Birmingham, Alabama 35202 Telephone 205 870-6011 yqg pw g
I November 4, 1986 Director of Nuclear Reactor Regulation File: X7BC35 Attention:
Mr. B. J. Youngblood Log:
GN-1162 PWR Project Directorate #4 Division of PWR Licensing A U. S. Nuclear Regulatory Commission Washington, D.C.
20555 NRC DOCKET NUMBERS 50-424 AND 50-425 CONSTRUCTION PERMIT NUMBERS CPPR-108 AND CPPR-109 V0GTLE ELECTRIC GENERATING PIANT - UNITS 1 AND 2 ASME CODE EDITION
Dear Mr. Denton:
Georgia Power Company (owner) in accordance with the requirements of Subarticle NA/NCA-1140 of the ASME Code has approved the use of following later code editions and/or addenda provisions:
1.
Use of the 1983 version of Article 3000, Subsection NF,Section III of the ASME Boiler and Pressure Code for the as-built reconciliation analysis of the supports on the pressurizer safety and relief valve (PSARV) system.
The ASME Certificate Holder for this system is Westinghouse Electric Corporation.
The original design analysis of the PSARV discharge piping system was based on loadings generated prior to the EPRI testing program conducted in response to the NRC post TMI requirements. Upon completion of the test program, data was made available for benchmarking the thermal hydraulic and structural dynamic analysis computer programs for eventual utilization in the piping and support qualification. Whenever the benchmarked programs were used, higher analytical loads were calculated for the safety and relief valve discharge events. The piping qualification was performed to the Level B service limits for the combined OBE and relief valve discharge event which are higher than the Level A service limits. Since the state-of-the-art technology is applied to the qualification of the system, the use of a later version of the Code for the NF supports is justified, thus, permitting higher oupport allowable stresses for Level B conditions and ensuring consistency between piping and support allowables.
!M"PDas! MEANP Bei A
p
Director of Nuclear Reactor Regulation File: X7BC35
^
November 4,1986 Log:
GN-1162 Page 2 The Code of Record for this scope of the Project is the 1977 Edition including Addenda through the Winter of 1977. Westinghouse has performed the necessary reviews of the 1983 Code and concluded that the adoption and use of Article 3000 of Subsection NF of that Code Edition is not dependent upon nor does it require any additional technical or quality stipulations above and beyond the Code of Record. The changes in the 1983 code in Subsection NF corrected a disparity between the ASME and AISC Codes by bringing the ASME working stress allowable limits more in line with the AISC structural code and the requirements of the piping code. The principle change was an increase in the Service Level B limits of 33%,
Service Level C limits of 12.8% and Service Level D limits of 11% for the materials used for the PSARV supports. These changes were implemented in the Code as an independent improvement and were not dependent on changes to other requirements of the Code. Other changes incorporated in the 1983 Edition do not impact the analysis of the PSARV support structure.
Furthermore,'10 CFR 50.55a published on March 30, 1984 which was in effect at the time of the evaluation endorsed Section III of the 1SME Boiler and Pressure Vessel Code including editions through 1983.
The analysis of the PSA1V piping system uses one model to represent the piping from the pressure through the ring header, which is supported by the supports in question, and then continues to the pressurizer relief tank. The supports on the piping from the header to the tank are evaluated using the rules of the AISC code since this piping is NNS.
Westinghouse has reviewed the piping system analysis and has concluded
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that a change in the code for analysis of the header supports has no impact on the validity of the piping system analysis.
2.
Use of NC/ND-3650 and 3670 of the 1979 Addendum to the 1977 Edition of ASME Section III Code of applicable material property values for thermal expansion and modules of elasticity. The Code of Record for this scope of i-the Project is the 1974 Edition through ' Summer 1974 Addenda. The ASME Certificate Holder for this scope is 'Bechtel Western Power Corporation (BWPC).
The 1975 Summer Addenda of the Code had major material groupings with more conservative thermal expansion factors. Expansion coefficients are physical properties of the material used. The later code breaks down the i
material groupings used by the earlier code, to individualize the specific l
values actually required for analysis of each piping material and, therefore, provides more realistic values.
Georgia Power Company has concurred with this change in November 1984 and i.
as part of the action taken to respond to NRC/I&E Unresolved Item 424, 425/84-31-01, " Discrepancies in piping stress analysis inputs" (See NRC/I&E Region II letter from Brownlee to Kelly, Report Nos. 50-424/84-31 and 50-425/84-31, dated November 28, 1984). This change was neither communicated to NRR nor was it incorporated into the FSAR.
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' Director of Nuclear Reactor Regulation File: X7BC35 November 4,- 1986 Log:
GN-1162 Page 3
.BWPC has performed the necessary reviews of the 1979 Addendum to the 1977 Edition of the ASME Code and concluded that the adoption and use of' NC/ND-3650 and 3670 of this Addendum is not dependent upon nor does it require any additional technical and/or quality stipulations above and
- beyond the Project Code of Record. These particular changes incorporated in 1979 Addendum of the Code were clarifications and improvements and were -
not dependent on any other changes reflected in the addendum.
,Furthermore, 10 CFR 50.55(a), published on March 30, 1984, which was in effect at the evaluation, endorsed Section III of the ASME Code including editions through the 1980 Edition, and addenda through the Summer 1982' Addenda.
3.
Use of NC/ND-3650 of the Summer 1979 Addendum to the 1977 edition of the ASME Section III Code for single nonrepeated anchor movement.
The Code of Record for this scope of the Project is the 1974 Edition through Summer 1975 Addenda. The ASME Certificate Holder for this scope is BWPC.
The Code of record does not provide any rule to evaluate the effect of piping design with respect to any single nonrepeated anchor movements.
The Summer 1979 Addenda Code provision added the equation (10a) for the above purpose, which can be used to assure adequacy of the piping design for predicted-building settlement.
BWPC has performed the necessary reviews of the Summer 1979 Addenda to the 1977 Edition of the ASME Code and concluded that the adoption and use of NC/ND-3650 'and 3670 of this Addenda is not dependent upon nor does it require any additional technical and/or quality stipulations above and beyond the Project Code of record. These particular changes incorporated in the Summer 1979 Addenda of the Code were clarifications and improvements and were not dependent on any other changes reflected in the Addenda. Furthermore,10 CFR 50.55(a), published on March 30, 1984, which was in effect at the evaluation, endorsed Section III of the ASME Code including Editions through the 1980 Edition, and Addenda through the Summer 1983 Addenda.
Georgia Power Company will update the FSAR to incorporate these changes.
Adoption ~and use of these later code sections are justified since they are either clarification or incorporation of more appropriate material information to the code, or resolution of the discrepancies between two closely related codes, or expansion of the code to provide the missing guidance for a design condition to be evaluated to assure the adequacy of the design. Adoption and use of these later code sections does neither alter nor degrade the level of quality provided by the Project Code of Record.
Director of Nuclear Reactor Regulation.
File:' X7BC35 GN'1162 November 4,1986 Log:
Page 4 If your staff has any questions, please inquire.
Sincerely,
.4 J. A. Bailey.
Project Licensing Manager JAB /sm xc:
R. E. Conway R. A. Thomas J. E. Joiner, Esquire B. W. Churchill, Esquire M. A. Miller (2)
B. Jones, Esquire G. Bockhold, Jr.
NRC Regional Administrator NRC Resident Inspector D. Feig R. W. McManus L. T. Gucwa Vogtle Project File 1
1 0845V
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