ML20085H659

Amend 2 to Change Repts 15 & 16 to License DPR-4,describing Installation of Water Seal on Pressurizer Safety Valves & Spilled Coolant Recirculation Sys

ML20085H659
Person / Time
Site:	Saxton File:GPU Nuclear icon.png
Issue date:	12/02/1969
From:	Cindy Montgomery SAXTON NUCLEAR EXPERIMENTAL CORP.
To:
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References
FOIA-91-17 NUDOCS 9110280336
Download: ML20085H659 (2)

Text

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s,/ %ll Amendment !!o. 2 to Change Reports 15 and 16 ~

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. nd lo of 2 \ gge3 Pago 1 '

Amendment ! o. 2 P,cne:+ e 15 and g I On July 8,1969, .WEC submitted one amentaent f the each pressurizer to Change 16 proposing pretuuro tests to demonstrate the integrity olled coolant r safety valve water seal installation and the itedspiThe by the pressure proposed \!pressure system installation.of the reactor coolant system and, therefore, ucre lim capability of the reactor coolant system. l t system

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s In determining the raximum pressure capability of the reactor coo the following conditions were considered t include Pressure retaining components in the reactor coolant lloy steels. sys em

1. austenitic stainless steel piping and fittings, andi low thata ,

Paragraph U.3.a.(6) of the Technical Specifications l the temperature specif es

2. rain coolant pressure shall not exgeed 500 psig until ductility transi-of the rain coolant is at least 60 F aoove the re: niFor the reac tion temperature of the reactor vessel. nil30 ductility tran Initial UDT temperature 240 Gl' temperature shift due to the effects ofradiati Fracture transition for clastic loading (FTE) 60 _

temperature _ 330*F t vessel Thus, NDT tenperature consideratiens fix the minimum reac er tecperature for the test at approximately 330 F. t The maximum pressure capability of the ii reactor in the coolant 3.

by the centrifuga11y cast austenitic system.

tion, and nuclcar stainless ste erected in accordance with USAS B31.1 1955 EdiThe material propert piping Cases N-9 and N-10 respectively. therefore the data curves are the same for both componento;9 and U-10 are identical.

both the allowable stresses as set forth in Cases U- i es the The allowable stress for austenitic stainless l work hardening characteristics of these materia sh 903 ture. of the minimum allowab3e stress at elevated temperature to reac that allowabic 0.2% offsst yield strength (Sa) at~the specific design teuper loading conditions A footnote to . Tables A-1 and A-2 of USAS stress is 90j of yield strength, and for some Section IIItitative of the D31.1 undesirable plastic deforcation could rf 1.25x occur.AS!Z design Bo warning by limiting any test pressure to the lesser 9C$ of the material pressure er that which produces a stress equal toThe austen yield at the test temperature.

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