ML20148H918
| ML20148H918 | |
| Person / Time | |
|---|---|
| Site: | Yankee Rowe |
| Issue date: | 07/31/1975 |
| From: | Purple R Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20148H908 | List: |
| References | |
| NUDOCS 8011200180 | |
| Download: ML20148H918 (7) | |
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-_a YANkEEATOMICELECTRICCOMPANY-
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YANKEE NUCLEAR POWER STATI0ft (YANKEE-ROWEL
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AMENDMENT TD F/CILITY OPERATING LICENSE sa
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Amendment No.15 Ei License No. DPR-3 7
1.
The Nuclear Regulatory Commission (the Commission) has found thatt A.
The application for amendment by Yankee Atomic Electric Company
. s.p.g (the licensee) dated January 3,1974, complies with the standards
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and requirements of the Atomic Energy Act of 1954, as amended F.,
(the Act), and the Comission's rules and regulations set forth in 10 CFR Chapter I, B.
The facility will operate in conformity with the application, z.-
the provisions of the Act, and the rules and regulations of the Comission; C.
There is reasonable assurance (1) that the activities authorized
=E by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; and D.
The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public.
2.
Accord'ingly, the license is amended by a change to the Technical Specifications as indicated in the attachment to this license 5
amendment and Paragraph 3.A. (2) of Facility License No. DPR-3 is hereby amended to read as follows:
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?f CURN AMS W aate W W u. e sovannuswr ramrine orrics i.74.sa ies Forms ABC.Sta (Rev 9 53) AECM 0240
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"(2) Technical Specifications --
'Ihe Technical Specifications contained in Appendix A,i.
as revised, are hereby incorporated in the license.-
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The licendee shall operate the facility in accordance.
with the Jechnical Specifications, as revised by.
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" i' issued changes thereto through Change No.120 '
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'3.- This license amendment is effective as of the date of its issuance.
FOR 'IEE NUCLEAR REGULATURY COMMISSION -
a n ii j Original signed by R. A. Purple Robert A. Purple, Chief
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Operating Reactors Branch #1 Division of Reactor Licensing
Attachment:
Change No.120 to 'the Technical Specifications
=.2 Date of' Issuance: JUL 311975
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ATTACHMEW W LICENSE AMENDMEW NO.15 z,.=,,
CHANGE NO.120101ME TECHNICAL SPECIFICATIONS FACILITY OPERATING LICENSE NO. DPR-3
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DOCKET NO. S0-29
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Revise Appendix A as follows:
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Add Section G - page 2b and Table F-1.
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4 Form AEC.318 (Rev. 9 53) ABCM 0240 W u. e, sovrnwusur emwriwe orricas i 74.sa ise g
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... G. REACTOR COOLANT SYSTEM SURVEILLANCE TESTING Applicability: Applies to inservic.e structural surveillance of the reactor vessel and other reactor coolant' system components.
Objective:
The Inservice Inspection Program has been designed as a means of periodically checking to ensure that a failure does not occur.
Specilication: The Inservice Inspection Program described in Table 'G -1 shall be followed. The program will complete an inspection cycle within a 10 year period.
Basis:
Following issuance of Section XI of the ASME Boiler and Pressure Vessel Code on January 1, 1970, Yankee adopted 12(
an Inservice Inspection Program consistent with the re-quirements of the Code and' compatible with the "as constructed" plant. The adopted program, Table G-1 will complete an inspection cycle within the Code accepted 10 year completion period.
Table ' G '1 does not list those examination categories not applicable or accessible in the Yankee plant. The Code
.does not apply en toto to plants constructed prior to its adoption, since provision for component access have not been incorporated into all.
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INSERVICE INSPECTION PROGRAM FOR YANKEE R0hT Section XI Components and Parts Percent of Welds or Examination Category (1) to be Examined Method _
-Components to be Examined Reactor Vessel and Closure Head C
Vessel-to-flange and head-to-flange Volumetric 100%
a circumferential welds E-2 IIcad Penetrations Visual 25% '
G-1 Closure studs and nuts Volumetric and 1005 Visual or Surface
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5, G-1 Ligaments between threaded stud Volumetric 12 holes 0
100%
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G-1 Closure wishers, bushings Visual O
1sual 100%
G;2 Pressure retaining b'olting I-1 Closure head cladding Visual and Surface 6 Patches or Volumetric (36 sq. inches each):
Pressurizer B
Longitudinal and Circumfe'ential Visual and Volumetric 10% of Longitudinal welds 5% of Circumferential i
D Nozzle-to-Vessel welds Visual and Volumetric 100%
E-1 Heater nozzle to shell weld Visual and Volumetric 25%
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JUL 3119f5
Table G-1 continued).
INSERVICE INSPECTION PROGRAM FOR YANKEE R0WE i
Percent of Welds or Section XI Components and Parts zamination Category (1) to be Examined Method Components to be Examined Pressurizer (cont'd) i.,
200%
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G-2 Pressure retaining bolting
. Visual ;5 H
- Integrally welded vessel supports Visual and Volume.tric -
50%
n I-2 Vessel cladding.
Visualk 1 Patch (36 sq. inches)
Steam Generators S% of circumferential, B
Tube-sh,ect-to-head weld on the Visual weld each unit primary side
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' I Visual 100% -
D Primary nozzle-to-vessel head welds
,G-2 Pressyre retaining bolting Visual 100%
I Vessel cladding Visual 1 Patch (36 sq. inches c-each unit if opened for maintenance)
Piping Pressure Boundary -
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G-2 Pressure retaining bolting Visual 100%
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J Circumferential pipe welds Visual and Volumetric -
4 Loops.25% each 1
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- K-2 Piping Support and Hanger Visual 100%
Pump Pressuie Boundary Pressure retaining bolting Visual,
100%
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Tablo G-1 (continuad)
INSNRVICE INSPECTION PROGRAM l
FOR YANKEE ROKE
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Components and Parts Percent of Welds or Section XI Examinntion Category (1) to be Exanined Method Components to be Examined Pump Pressure Boundary (cont'd)
K-2 Supports and llangers Visual 100%
a L-2 Pump casing Visual
, one pump (if. opened for maintenance)
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Valve Pressure Boundary G-2 Pressure retaining bolting Visual 100%
X-2 Supports and Hangers Visual 100%
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'V.alve bodies Visual 100% of one valve of
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each class (if opened for maintenance)
(1) B ose examination categories not applicable or accessible are not listed.
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