ML20055J207
| ML20055J207 | |
| Person / Time | |
|---|---|
| Site: | National Bureau of Standards Reactor |
| Issue date: | 07/27/1990 |
| From: | NATIONAL INSTITUTE OF STANDARDS & TECHNOLOGY (FORMERL |
| To: | |
| Shared Package | |
| ML20055J205 | List: |
| References | |
| NUDOCS 9008010197 | |
| Download: ML20055J207 (3) | |
Text
_ _ _ _ _ _ _ _ _ _ _ _ _ _ _
- JA"1I0R!i BUPEAU OF STA!1IARDS TEQNICAL SPtrIFICATIONS Reactor Operations Section T.S.
6.1 to 6.2 SULLTICI's DESIGN FEA'IURSS Page L of 3 APPIOVED BY:
_ IATE ISSUED: f/16/84 SUPERSEDES ISSUE IATED:
7/31/70 f
6.1 Site Description The reactor shall have a minimum exclusion radius to the nearest site boundary of 400 m.
We reactor facility comlex shall be located within NBS grcunds and access to the reactor shall be controlled.
Basis:
The location and ownership of the reactor site ensures necessary auxiliary services such as fire and security protection are available.
The exclusion radius of 400 m is the distance on which all upper limit dose calculations are based (FSAR, NBSR 9, Addendum 1, Sections 2 and 3, Nov.1980).
Should this value decrease for any reason, a recalculation of upper limit doses would be necessary. Access to the reactor facility co mlex is controlled either by the facility staff or by a guard.
In addition, access to the entire NBS camus is restricted at other than normal working hours.
'Ihe reactor coolant system shall consist of a reactor vessel, a single cooling loop, containing one or two, shell and tube, heat exchangers, and appropriate purps and valves. All naterials, including those of the reactor vessel, in con-l tact with primary coolant (D 0), shall be aluminum alloys or stainless steel, 2
except gaskets and valve diaphragms. The reactor vessel shall be designed in
(
accordance with the American Society cf tiec.unical Engineers (AStE) Code for Unfired Pressure Vessels.
It shall be designed for 50 psig and 250 F.
Heat exchanger tubes shall be designed for 100 psig and a tenprature [tenperature]
of 150 F.
The connecting piping shall be designed for 125 psig and a tempera-ture of 150 F.
90cs010197 c06727 FDR ADOCK 05000184 P
FDC
taTION5L BUPEJdJ & tTISMf05 TLDNICAL SPECIFICATIONS T.S.
6.2 to 6.3 Reactor Operations Section SUBJDRs D131G4 FFATUPES page 2 of 3 DATE ISSUED: 05/16/84, SUPERSEDES ISSUE DATED:
7/31/70 APPIW ED BY 2
f Basis:
The reactor coolant system has been descrited and analyzed in the PSAR as a single 1 cop systera containing two heat exchangers. Materials of construc-tion, being primarily aluminum eJ.loys and stainless steel, are chemically com-patible with the D 0 coolant.
The stainless steel pumps are heavy-walled 2
members and are in areas of low stress, so they should not be susceptibic to chemical attack or s'.ress corrosion f ailures.
The failure of the gaskets and valve belicus, although undesirabb, would not result in catastrophic failure of the primry system; hence, strict material limitations are not required for technical specifications. %e decign, t merature, and pressure of the reactor vessel and other primary system components pr'.svide adequate margins over operating temperatures and pressures.
It le believed prudent to retain these mrgins to further reduce the probability of a primary system f ailure.
The reactor vessel was designed to Section VIII,1959 Edition, of the AStE Code for Unfired Pressure Vestsels. Subsequent cha1ges should be mde in accordance with the most recent edition of this Code.
Because the safety analysis is based on the reactor coolant system as presently designed and with the present margins, it is considered necessary to retain this design and these mrgins or to redo the analysis.
6.3 Reactor Core
%c reactor core my consist of up to 30 (3.0 x 3.3 in.) liTR curved-plate-type
)
fuel elements, except that the central 7-in. region of each fuel elemnt shall 1
contain no fuel. The middle 5 in, of aluminum in the unfueled region may be re-moved.
The side plates, unfueled outer plates, and end adaptor castings of the fuel elemnts s1
'l be aluminum alloy; the fuel plates shall be uranium-aluminum i
alloy; aluminum-uranium oxide or uranium-aluminide clad with aluminum.
t{ATIQBL BUFEAU OF STNUJtDS TDONICAL SPECIFICATI0JS Reactor Operations Section T.S.
6.1 to 5.2 SUILTDCT: DESIQ4 FENIURES Page 1 of 3 APPROVED BY:
IMTE ISSUED: 05/16/84 SUPERSEDES ISSUE IATED:
7/31/70 f
6.1 Site Descriptico The reactor shall have a mininum exclusion radius to the nearest site boundary of 400 m.
We reactor facility conplex shall be located within NBS grounds and access to the reactor shall be controlled.
Basis 1 The location and ownership of the reactor site ensures necessary auxiliary services such as fire and security protection are available.
The exclusion radius of 400 m is the distance on which all upper limit dose calculations are insed (FSAR, NBSR 9, Addendum 1, Sections 2 and 3, Nov.1980).
Should this value decrease for any reason, a recalculation of upper limit doses would be necessary. Access to the reactor facility couplex is controlled either by the facility staff or by a guard.
In addition, access to the entire NBS canpas is restricted at other than nornal working hours.
'Ihe reactor coolant system shall consist of a reactor vessel, a single cooling loop, containing heat exchangers, and appropriate punps and valves. All anterials, including those of the reactor vessel, in con-tact with primary coolant (D 0), shall be aluminum alloys or stainless steel, 2
except gaskets and valve diaphragms. The reactor vessel shall be designed in accordance with the American Society of Mechanical Engineers (ASttC) Code for Unfired Pressure Vessels.
It shall be designed for 50 psig and 250 F.
Heat exchangershnkmaar shall be designed for 100 psig and a tenprature [tenperature) 0 of 150 F.
The connecting piping shall be designed for 125 psig and _ a tempera-ture of 150 F.
!MTIONAL BUREAU OF STANIWOS TfDNICAL SPirIFICATIOiS R,aactor Operatiors Section T.S.
6.2 to 6.3 j
SUEGLUrs DESIG4 FEA'IURES
_ Page 2 of 3 APPICVED BY IATE ISSUED: 05/16/84 SUPERSEDES ISSUE DATED:
7/31/70 Basis:
The reactor coolant system has been descrited and analyzed in the PSAR as a single loop system containingsteswheat exchangers. tiaterials of construc-tion, being primarily aluminum alloys and stainless steel, are chemically com-patible with the D 0 coolant.
The stainless steel pumps are heavy-walled 2
members and are in areas of low stress, so they should not be susceptible to chemical attack or stress corrosion failures. The failure of the gaskets and valve bellcus, although undesirable, would not result in catastrophic f ailure of the primry system; hence, strict material limitations are not required for technical specifications. The design, tenperature, and pressure of the reactor vessel and other primary system components provide adequate margins over operating temperatures and pressures.
It is believed prudent to retain these mrgins to further reduce the probability of a primary system failure.
The reactor vessel was designed to Section VIII,1959 Edition, of the ASME Code for Unfired Pressure Vessels.
Subsequent changes should be mde in accordance with the nost recent edition of this Code.
Because the safety analysis is based on the reactor coolant system as presently designed and with the present mrgins, it is considered necessary to retain this design and these mrgins or to redo the analysis.
6.3 Reactor Core
'Ihe reactor core my consist of up to 30 (3.0 x 3.3 in. ) MTR curved-plate-type 1
fuel elements, except that the central 7-in. region of each fuel elenent shall contain no fuel. The middle 6 in. of aluminum in the unfueled region my be re-moved.
The side plates, unfueled outer plates, and end adaptor castings of the fuel elenents shall be aluminum alloy; the fuel plates shall be uranium-aluminum alloy; aluminum-uranium oxide or uranium-aluminide clad with aluminum.