ML20085H659
| ML20085H659 | |
| Person / Time | |
|---|---|
| Site: | Saxton File:GPU Nuclear icon.png |
| Issue date: | 12/02/1969 |
| From: | Cindy Montgomery SAXTON NUCLEAR EXPERIMENTAL CORP. |
| To: | |
| Shared Package | |
| ML20083L048 | List:
|
| References | |
| FOIA-91-17 NUDOCS 9110280336 | |
| Download: ML20085H659 (2) | |
Text
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SAXTON 1:UCLEAR EXPERIIIITAL C0!!!CRATIO!;
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Amendment !!o. 2 to Change Reports 15 and 16
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1.
On !!ovember 13, 1968, Applicant submitted C!nnge Reports 15 ard 16 describing the installation of a wter seal on the pressurizer safety valves and the $nstallation of a spilled coolant recirculation system.
2.
On July 8,1969, Applicant submitted one amendment each to Chance Reports 15 and 16 pro;)osing pressure tests to demonstrate the integrity of the above inctallatiot.c. The proposed pressure tests involved pressuritation of the reactor coolant systen, and both amendments presented arguments to support the adequacy of the tests and conform-ance with the applicable Codes.
3.
By letter dated C'etober 7,1969, Division of Reactor Licensing adviced Applicant of apparent inconsistencies bt. tween the supportinc argu.ents and the Technical Specifications, and rcquested clarifying infernation be provided.
4.
Applicant hereby submits Amendmont flo. 2 to Change Reports 15 and 16 providing the clarifying information requested by Division of Reactor Licensing.
MXTO!! ITUCLEAR EXPZ4113N'IAL CORFCRATICI!
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December 2, 1969 9110280336 c.10424 PDR FOI4 DEKOKol-1~7 PDR
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Change Pipsrts 15.
Pago 1 of 2 \\
gge3 Amendment ! o. 2 P,cne:+ e 15 and g I
On July 8,1969,.WEC submitted one amentaent each to Change f the pressurizer 16 proposing pretuuro tests to demonstrate the integrity olled coolant r safety valve water seal installation and the spiThe proposed pressure ited by the pressure
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system installation.of the reactor coolant system and, therefore, ucre lim
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capability of the reactor coolant system.
l t system In determining the raximum pressure capability of the reactor coo s
the following conditions were considered t
include Pressure retaining components in the reactor coolant sys em lloy steels.
austenitic stainless steel piping and fittings, and low a 1.
i that Paragraph U.3.a.(6) of the Technical Specifications specif es l the temperature rain coolant pressure shall not exgeed 500 psig until ductility transi-2.
of the rain coolant is at least 60 F aoove the niFor the reac tion temperature of the reactor vessel. nil ductility tran re:
30 Initial UDT temperature Gl' temperature shift due to the effects ofradiati 240 Fracture transition for clastic loading (FTE)
_ 330*F 60 _
temperature t
vessel Thus, NDT tenperature consideratiens fix the minimum reac e tecperature for the test at approximately 330 F.
t
- 3. The maximum pressure capability of the reactor coolant ii in the by the centrifuga11y cast austenitic stainless ste tion, and nuclcar erected in accordance with USAS B31.1 1955 EdiThe material propert system.
piping Cases N-9 and N-10 respectively.
therefore the data curves are the same for both componento;9 and U-10 are identical.
allowable stresses as set forth in Cases U-both the The allowable stress for austenitic stainless i es the l
work hardening characteristics of these materia sh 903 of the minimum allowab3e stress at elevated temperature to reac ture.
0.2% offsst yield strength (Sa) at~the specific design teuper that allowabic A footnote to. Tables A-1 and A-2 of USAS D31.1 loading conditions stress is 90j of yield strength, and for some Section III of the undesirable plastic deforcation could occur.AS!Z Bo titative rf 1.25x design warning by limiting any test pressure to the lesser 9C$ of the materia pressure er that which produces a stress equal toThe austen yield at the test temperature.
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