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{{#Wiki_filter:Attachment B Corrections to Facility License No. R-106 Technical Specifications and Basis for the Oregon State TRIGA Reactor Docket No. 50-243 Additional Revisions Regarding the Request to Remove Instrumented Fuel Element Requirements OSTR R-106 License | {{#Wiki_filter:Attachment B Corrections to Facility License No. R -106 Technical Specifications and Basis for the Oregon State TRIGA Reactor Docket No. 50- 243 | ||
Additional Revisions Regarding the Request to Remove Instrumented Fuel Element Requirements | |||
OSTR R-106 License | |||
: 1. Section 2.C.(1) Remove the current text and in the pulse mode, with reactivity insertions not resulting in fuel temperature in excess of 830 degrees Celsius. Replace with and in the pulse mode, with reactivity insertions not to exceed $2.30. | : 1. Section 2.C.(1) Remove the current text and in the pulse mode, with reactivity insertions not resulting in fuel temperature in excess of 830 degrees Celsius. Replace with and in the pulse mode, with reactivity insertions not to exceed $2.30. | ||
Basis: With the removal of the IFE, OSTR will no longer measure fuel temperature. It is more appropriate to limit reactivity insertions by dollars as this value is currently measured. | Basis: With the removal of the IFE, OSTR will no longer measure fuel temperature. It is more appropriate to limit reactivity insertions by dollars as this value is currently measured. | ||
Technical Specifications Section 1: Definitions | Technical Specifications Section 1 : Definitions | ||
: 1. 1.19 Reactor Operating - Disregard the request from the 6/11/20 LAR letter of Replace whenever it is not secured or shut down with unless it is both secured and shut down. | : 1. 1.19 Reactor Operating - Disregard the request from the 6/11/20 LAR letter of Replace whenever it is not secured or shut down with unless it is both secured and shut down. | ||
Basis: Cancel the previous request as the original wording is consistent with ANSI 15.1. | Basis: Cancel the previous request as the original wording is consistent with ANSI 15.1. | ||
Technical Specifications Section 3: | Technical Specifications Section 3 : Limitin g Conditions of Operation | ||
: 1. 3.2.2 Table 1 Footnote (1) - Remove the current text: Any single Linear Power Level, Log Power Level or Power Level measuring channel may be inoperable while the reactor is operating for the purpose of performing a channel check, test, or calibration. Replace this with the following: Any single measuring channel (except the | : 1. 3.2.2 Table 1 Footnote (1) - Remove the current text: Any single Linear Power Level, Log Power Level or Power Level measuring channel may be inoperable while the reactor is operating for the purpose of performing a channel check, test, or calibration. Replace this with the following: Any single measuring channel (except the N vt-Circuit) may be inoperable while the reactor is operating for the purpose of performing a channel check, test, or calibration. Note that the Linear Power Level and Log Power Level are connected to the same detector and both become inoperable when performing a channel check, test, or calibration. | ||
Basis: Since the linear and log channels get their signal from the same fission chamber, this exception needs to apply to both channels simultaneously. | Basis: Since the linear and log channels get their signal from the same fission chamber, this exception needs to apply to both channels simultaneously. | ||
Technical Specifications Section 3: | Technical Specifications Section 3 : Limitin g Conditions of Operation | ||
: 1. 3.2.3 Table 2 Footnote (1) - Remove the requested text: Any single Linear Power Level, Log Power Level or Power Level safety channel may be inoperable while the reactor is operating for the purpose of performing a channel check, test, or calibration. Replace this with the following: The Safety Power channel or the Percent Power channel may be | : 1. 3.2.3 Table 2 Footnote (1) - Remove the requested text: Any single Linear Power Level, Log Power Level or Power Level safety channel may be inoperable while the reactor is operating for the purpose of performing a channel check, test, or calibration. Replace this with the following: The Safety Power channel or the Percent Power channel may be | ||
inoperable while the reactor is operating for the purpose of performing a channel check, test, or calibration. | 1 inoperable while the reactor is operating for the purpose of performing a channel check, test, or calibration. | ||
Basis: This is a requested revision to match the change in wording in Table 2 from Power Level to Safety | Basis: This is a requested revision to match the change in wording in Table 2 from Power Level to Safety P ower Level and Percent Power Level. | ||
Technical Specifications Section 6: Administrative Controls | Technical Specifications Section 6 : Administrative Controls | ||
: 1. 6.1.3a Staffing - Remove the current text: The minimum staffing when the reactor is operating shall be: Replace this with the following: The minimum staffing when the reactor is not secured shall be: | : 1. 6.1.3a Staffing - Remove the current text: The minimum staffing when the reactor is operating shall be: Replace this with the following: The minimum staffing when the reactor is not secured shall be: | ||
Basis: This is consistent with the requested reactor operating definition change to align with the ANS 15.1 definition. | Basis: This is consistent with the requested reactor operating definition change to align with the ANS 15.1 definition. | ||
2}} | 2}} | ||
Latest revision as of 23:44, 18 November 2024
| ML22019A300 | |
| Person / Time | |
|---|---|
| Site: | Oregon State University |
| Issue date: | 01/19/2022 |
| From: | Oregon State University |
| To: | Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML22019A297 | List: |
| References | |
| Download: ML22019A300 (2) | |
Text
Attachment B Corrections to Facility License No. R -106 Technical Specifications and Basis for the Oregon State TRIGA Reactor Docket No. 50- 243
Additional Revisions Regarding the Request to Remove Instrumented Fuel Element Requirements
OSTR R-106 License
- 1. Section 2.C.(1) Remove the current text and in the pulse mode, with reactivity insertions not resulting in fuel temperature in excess of 830 degrees Celsius. Replace with and in the pulse mode, with reactivity insertions not to exceed $2.30.
Basis: With the removal of the IFE, OSTR will no longer measure fuel temperature. It is more appropriate to limit reactivity insertions by dollars as this value is currently measured.
Technical Specifications Section 1 : Definitions
- 1. 1.19 Reactor Operating - Disregard the request from the 6/11/20 LAR letter of Replace whenever it is not secured or shut down with unless it is both secured and shut down.
Basis: Cancel the previous request as the original wording is consistent with ANSI 15.1.
Technical Specifications Section 3 : Limitin g Conditions of Operation
- 1. 3.2.2 Table 1 Footnote (1) - Remove the current text: Any single Linear Power Level, Log Power Level or Power Level measuring channel may be inoperable while the reactor is operating for the purpose of performing a channel check, test, or calibration. Replace this with the following: Any single measuring channel (except the N vt-Circuit) may be inoperable while the reactor is operating for the purpose of performing a channel check, test, or calibration. Note that the Linear Power Level and Log Power Level are connected to the same detector and both become inoperable when performing a channel check, test, or calibration.
Basis: Since the linear and log channels get their signal from the same fission chamber, this exception needs to apply to both channels simultaneously.
Technical Specifications Section 3 : Limitin g Conditions of Operation
- 1. 3.2.3 Table 2 Footnote (1) - Remove the requested text: Any single Linear Power Level, Log Power Level or Power Level safety channel may be inoperable while the reactor is operating for the purpose of performing a channel check, test, or calibration. Replace this with the following: The Safety Power channel or the Percent Power channel may be
1 inoperable while the reactor is operating for the purpose of performing a channel check, test, or calibration.
Basis: This is a requested revision to match the change in wording in Table 2 from Power Level to Safety P ower Level and Percent Power Level.
Technical Specifications Section 6 : Administrative Controls
- 1. 6.1.3a Staffing - Remove the current text: The minimum staffing when the reactor is operating shall be: Replace this with the following: The minimum staffing when the reactor is not secured shall be:
Basis: This is consistent with the requested reactor operating definition change to align with the ANS 15.1 definition.
2