ML100540154: Difference between revisions

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| author name = Haghighat A
| author name = Haghighat A
| author affiliation = Univ of Florida
| author affiliation = Univ of Florida
| addressee name = Hardesty D A
| addressee name = Hardesty D
| addressee affiliation = NRC/Document Control Desk, NRC/NRR/DPR/PRTA
| addressee affiliation = NRC/Document Control Desk, NRC/NRR/DPR/PRTA
| docket = 05000083
| docket = 05000083
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| document type = Letter
| document type = Letter
| page count = 2
| page count = 2
| project =
| stage = Request
}}
}}


=Text=
=Text=
{{#Wiki_filter:L I" UF UNIVERSITY of College of Engineering 202 Nuclear Science Bldg.Department of Nuclear & Radiological Engineering PO Box 118300 University of Florida Training Reactor Gainesville, FL 32611-8300 352-392-1401 x306 352-392-3380 Fax haghighat@ufl.edu February 17, 2010 Document Control Desk U. S, Nuclear Regulatory Commission Washington, DC 20555 Attn: Mr. Duane Hardesty  
{{#Wiki_filter:L I"
UF     UNIVERSITY of College of Engineering                                             202 Nuclear Science Bldg.
Department of Nuclear & Radiological Engineering                   PO Box 118300 University of Florida Training Reactor                             Gainesville, FL 32611-8300 352-392-1401 x306 352-392-3380 Fax haghighat@ufl.edu February 17, 2010 Document Control Desk U.S, Nuclear Regulatory Commission Washington, DC 20555 Attn: Mr. Duane Hardesty


==Dear Mr. Hardesty,==
==Dear Mr. Hardesty,==


==Subject:==
==Subject:==
License Amendment Request (LAR) for Digital Control System Upgrade (1" batch of documents)  
License Amendment Request (LAR) for Digital Control System Upgrade (1" batch of documents) - University of Florida Training Reactor (UFTR), DOCKET NO. 50-83 As a follow up to our meetings on Oct. 16, 2009 and Jan 19, 2010, I am submitting the first batch of documents in support of the UFTR LAR for Digital Control System Upgrade. This I" batch contains the following documents:
-University of Florida Training Reactor (UFTR), DOCKET NO. 50-83 As a follow up to our meetings on Oct. 16, 2009 and Jan 19, 2010, I am submitting the first batch of documents in support of the UFTR LAR for Digital Control System Upgrade. This I" batch contains the following documents:
          - UFTR-QA1-01, "Software Quality Assurance Plan (SQAP)"
-UFTR-QA1-01, "Software Quality Assurance Plan (SQAP)"-UFTR-QA1-02, "Software Configuration Management Plan (SCMP)"-UFTR-QA1-05, "Software Safety Plan (SSP)"-UFTR-QA1-06.
          - UFTR-QA1-02, "Software Configuration Management Plan (SCMP)"
1, "Software Test Plan -SIVAT Plan"-UFTR-QA1-105, "TELEPERM XS Cyber Security" It is important to note that for the UFTR, the "reactor safety" or "safety-related" terminology, does not have the same safety significance of like a power reactor. According to ANSIIANS 15.1 standard, the Reactor Safety Systems are defined: "those systems, including their associated input channels that are designed to initiate automatic protective action or to provide information for initiation of manual protective action." Further, as discussed at our aforementioned Oct and Jan meetings, the UFTR has unique safety features as follow: Low power (the peak power per bundle = 5 kW)Thin, metallic fuel plates with high thermal conductivity Low fuel temperature  
          - UFTR-QA1-05, "Software Safety Plan (SSP)"
(-50 C)Even under unprotected insertion of 0.6%, after 300 seconds, core reaches an equilibrium power level of about 600 kW; the peak fuel temperature is -108C (fuel melting point is 582 C)Negative coefficients of reactivity The Foundation for The Gator A.Jation  
          - UFTR-QA1-06. 1, "Software Test Plan - SIVAT Plan"
-4.-In addition to the control blade scram mechanism, the reactor can be shutdown by dumping the coolant.Because of the above features, for the UFTR digital protection system, the following applies:-No need for Engineering Safety Features Actuate System (ESFAS),-One train protection and control system,-No concern for Common Cause Failure (CCF), because no redundancy is required,-No EQ or seismic qualification required, and-No safety-related power supply necessary.
          - UFTR-QA1-105, "TELEPERM XS Cyber Security" It is important to note that for the UFTR, the "reactor safety" or "safety-related" terminology, does not have the same safety significance of like a power reactor. According to ANSIIANS 15.1 standard, the Reactor Safety Systems are defined: "those systems, including their associated input channels that are designed to initiate automatic protective action or to provide information for initiation of manual protective action."
If you need further information, please do not hesitate to contact me at haghighat@ufl.
Further, as discussed at our aforementioned Oct and Jan meetings, the UFTR has unique safety features as follow:
edu or (352)392-1401 x306.I declare under penalty of perjury that the foregoing is true and correct.Executed on 2--/ l- /1to Sincerely, Alireza Haghighat, PhD FP&L Endowed Chair Professor Director of UFTR Cc Jack Donohue, NRC Gabriel Ghita, UF David Hintenlang, Interim Chair Brian Shea, UFTR Manager Glenn Sjoden, RSRS Chair Eric Wallace, AREVA UFTR -NRC file 71 Lisa L. P urvis lift LComiTlssiof
Low power (the peak power per bundle = 5 kW)
# DD608673 SExpires November 3, 2010 IC Troy Fuin~ -Iinsurance, Inc. fiO-385.701}}
Thin, metallic fuel plates with high thermal conductivity Low fuel temperature (-50 C)
Even under unprotected insertion of 0.6%, after 300 seconds, core reaches an equilibrium power level of about 600 kW; the peak fuel temperature is -108C (fuel melting point is 582 C)
Negative coefficients of reactivity The Foundation for The Gator A.Jation
 
- 4.
        -   In addition to the control blade scram mechanism, the reactor can be shutdown by dumping the coolant.
Because of the above features, for the UFTR digital protection system, the following applies:
        - No need for Engineering Safety Features Actuate System (ESFAS),
        - One train protection and control system,
        - No concern for Common Cause Failure (CCF), because no redundancy is required,
        - No EQ or seismic qualification required, and
        - No safety-related power supply necessary.
If you need further information, please do not hesitate to contact me at haghighat@ufl. edu or (352) 392-1401 x306.
I declare under penalty of perjury that the foregoing is true and correct.
Executed on       2--/ l-   /1to Sincerely, 71 Alireza Haghighat, PhD FP&L Endowed Chair Professor Director of UFTR                                                     Lisa L. Purvis lift LComiTlssiof  # DD608673 Cc     Jack Donohue, NRC                                           SExpires November 3,2010 IC TroyFuin~      Inc.fiO-385.701
                                                                                  -Iinsurance, Gabriel Ghita, UF David Hintenlang, Interim Chair Brian Shea, UFTR Manager Glenn Sjoden, RSRS Chair Eric Wallace, AREVA UFTR - NRC file}}

Latest revision as of 22:39, 13 November 2019

Transmittal of License Amendment Request for Digital Control System Upgrade (1st Batch of Documents) - University of Florida Training Reactor (Uftr)
ML100540154
Person / Time
Site: 05000083
Issue date: 02/17/2010
From: Haghighat A
Univ of Florida
To: Duane Hardesty
Document Control Desk, Research and Test Reactors Licensing Branch
References
Download: ML100540154 (2)


Text

L I"

UF UNIVERSITY of College of Engineering 202 Nuclear Science Bldg.

Department of Nuclear & Radiological Engineering PO Box 118300 University of Florida Training Reactor Gainesville, FL 32611-8300 352-392-1401 x306 352-392-3380 Fax haghighat@ufl.edu February 17, 2010 Document Control Desk U.S, Nuclear Regulatory Commission Washington, DC 20555 Attn: Mr. Duane Hardesty

Dear Mr. Hardesty,

Subject:

License Amendment Request (LAR) for Digital Control System Upgrade (1" batch of documents) - University of Florida Training Reactor (UFTR), DOCKET NO. 50-83 As a follow up to our meetings on Oct. 16, 2009 and Jan 19, 2010, I am submitting the first batch of documents in support of the UFTR LAR for Digital Control System Upgrade. This I" batch contains the following documents:

- UFTR-QA1-01, "Software Quality Assurance Plan (SQAP)"

- UFTR-QA1-02, "Software Configuration Management Plan (SCMP)"

- UFTR-QA1-05, "Software Safety Plan (SSP)"

- UFTR-QA1-06. 1, "Software Test Plan - SIVAT Plan"

- UFTR-QA1-105, "TELEPERM XS Cyber Security" It is important to note that for the UFTR, the "reactor safety" or "safety-related" terminology, does not have the same safety significance of like a power reactor. According to ANSIIANS 15.1 standard, the Reactor Safety Systems are defined: "those systems, including their associated input channels that are designed to initiate automatic protective action or to provide information for initiation of manual protective action."

Further, as discussed at our aforementioned Oct and Jan meetings, the UFTR has unique safety features as follow:

Low power (the peak power per bundle = 5 kW)

Thin, metallic fuel plates with high thermal conductivity Low fuel temperature (-50 C)

Even under unprotected insertion of 0.6%, after 300 seconds, core reaches an equilibrium power level of about 600 kW; the peak fuel temperature is -108C (fuel melting point is 582 C)

Negative coefficients of reactivity The Foundation for The Gator A.Jation

- 4.

- In addition to the control blade scram mechanism, the reactor can be shutdown by dumping the coolant.

Because of the above features, for the UFTR digital protection system, the following applies:

- No need for Engineering Safety Features Actuate System (ESFAS),

- One train protection and control system,

- No concern for Common Cause Failure (CCF), because no redundancy is required,

- No EQ or seismic qualification required, and

- No safety-related power supply necessary.

If you need further information, please do not hesitate to contact me at haghighat@ufl. edu or (352) 392-1401 x306.

I declare under penalty of perjury that the foregoing is true and correct.

Executed on 2--/ l- /1to Sincerely, 71 Alireza Haghighat, PhD FP&L Endowed Chair Professor Director of UFTR Lisa L. Purvis lift LComiTlssiof # DD608673 Cc Jack Donohue, NRC SExpires November 3,2010 IC TroyFuin~ Inc.fiO-385.701

-Iinsurance, Gabriel Ghita, UF David Hintenlang, Interim Chair Brian Shea, UFTR Manager Glenn Sjoden, RSRS Chair Eric Wallace, AREVA UFTR - NRC file