ML20076B497

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Forwards Response to 610602 Question Re Materials of Const of Saxton Reactor Core & CRD Mechanisms
ML20076B497
Person / Time
Site: Saxton File:GPU Nuclear icon.png
Issue date: 06/09/1961
From: Hetrick D
SAXTON NUCLEAR EXPERIMENTAL CORP.
To: Kline S, Spencer G
US ATOMIC ENERGY COMMISSION (AEC)
Shared Package
ML20071H103 List:
References
FOIA-91-17 NUDOCS 9107120001
Download: ML20076B497 (12)
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Text

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i m a SAXTON NUCLEAR EXPERIMENTAL CORPORATION e

4 GENERAL PU B LIC UTILITIES OYSTEM I Janety cantant Powtn a uowt comea=,

/ $NfC htw Jansty Powse e Dent Couta4Y s

g Pehmstkvawia EktCtmeC CoupAN, PE JC u si.e.ogir. S o,eo= com.a m, P.O. Box Sjgx)wl,** 352 Saxton, Penna. Tel*Ph one@;ns .'iW'w," ?i^(

g Melrose 52937

/

/ June 9, 1961 itomic Energy Cot =nission Germantown, Maryland

/

Attn / r.M George Spencer Mr. Stanley Kline Dear Sirs; In regard to your question of June 2,1961, concerning materials of construction of the Saxton Reactor Core and Control Rod Drive mechanisms, Westing-house has checked the materials used. Although there are a few parts made of 17-4-PH stainless steel these applications do not raise a question of reactor safety.

The following information is enclosedt

1. 14tter No. RD-D-M-1371 dated May 31, 1961, fran S. Kmonk to E. U.

Powell (both of Westinghouse) along with Process Specification 292082 In this letter Mr. Kmonk identifies ten "Conoseal" clamping rings on the outside of the reactor vessel head which are made of 17-4-PH stainless steel.

2. Letter No. PD-G-1188 dated May 15, 1961, from R. L. Whitney to E.

U. Powell (both of Westinghouse) along with drawing No. 618J698 (General Assembly Magnetic Control Rod Drive) and a materials list identifying each numbered item shown on the drawing. Inspection of this list of materials will show that no precipitation hardened stainless steel is used anywhere in the control rod drive mechanisein.

Very truly yours,

h. { / $?-

DEH/pl D. E. Hetrick y.4 9107120001 910506 PDR FOIA /

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o SAXT01! f U012Mt r;PErtit!DITAL CORPOMTION_

Survey Date Surveyor Survey No.1 Survey Time: ..,.

Incations Floor Plan Attached () i i

l Type of Instrument Used:

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Description of Survey  !

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Specini Instructions: Discharge Pennit #

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1999,1-209 - CHEMICAL ADDITION SISTEM A. Ihnetion  !

t The chemical addition system is designed to propAre and supply a source of boric acid as a neutron poison material for the main coolant system during cold shutdown, to prepare and supply borated water to the [

storage well system, to add hydrazine and lithitas ly&ede or potassium ,

hydroxide as required to adntain the czygen content and pH cf the = min l coolant water, and to add, if necessary, decont-inant solutiotu to remove radioactive corrosion products from the various plant systems.  !

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B. Description The system consists of a steam heated boric acid tank, a centrifugal piamp for =iving and ciresisting the boric acid and decon-l t-inant solutions, a chemical addition tank to supply other chemicals, l and the associated piping, valves, fittings and insth. tion. >

system is located outside the cont =1==nt vessel. Figure 209-1 is'a flow diagram for this system.

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C. Components [
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! 1. Boric Acid Tank  ;

r The boric acid tank is a right circular, cyYinrtrical vessel l

) 40 .1 canseity with a dished bottaa and flat too. half j i

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' 210 - SAMPLIN; A3D 1EAK DEIECIION STSIEN A. Function i

The samnling and leak detection system is designed to provide a source of utin coolant system vater for annivsis; to provide a source of pretsurizer vessel water for analysis; to provide a sample for detensination of boric acid and purification demineralizer efficiency; to provide a sample .

for determination of storage well demineralizer efficiency; to provide a source of stony;e vell water for analysis; to provide indication of leaan6e l' past the inner reactor vessel head gasket; to provide 1witestica of lealm6e past the inner gaskets of the pressurizer vessel spray flange, prestsrizer vessel heater flange, min coolant pap end plate, main coolant pump casin6 flange, and stesa generator manvays; to provide indication of leaka6e th:tr@

main coolant system and anviliary syr.".es valve leskoff connecticcs; and to provide an indicaticn of reactor vessel shell leaka6 -

B. Descripticn

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1. Geneml The system consists of piping and equi; ment located both inside 3 and outside the ccatatmaant vessel. The s= ling portion of the system is composed of piping, valving and instrumentation necessary for tansportin6 the , samples fr a the source to the sampling station. Two sample coolers azw provided to cool the high Lenim, high pressure semple bomb effluent,

- ani a vacum pacp is provided to evacuate the sample bombs.  ;

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