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'. 7590-01 U.S. NUCLEAR REGULATORY COMMISSION NOTICE OF AMENDMENT TO l CERTIFICATE OF COMPLIANCE GDP 1 FOR l | |||
-THE U.S. ENRICHMENT CORPORATION PADUCAH GASEOUS DIFFUSION PLANT PADUCAH, KENTUCKY DOCKET 70 7001 The Director, Office of Nuclear Material Safety and Safeguards, has made a determination that the following amendment request is not significant in accordance with 10 CFR 76.45. | |||
In making that determination, the staff concluded that: (1) there is no change in the types or significant increase in the amounts of any effluents that may be released offsite; (2) there is no significant increase in individual or cumulative occupational radiation exposure; (3) there is no significant construction impact; (4) there is no significant increase in the potential for, or radiological or chemical consequences from, previously analyzed accidents; (5) the proposed changes do not result in the possibility of a new or different kind of accident; (6) there is no significant reduction in any margin of safety; and (7) the proposed changes will not result in an overall decrease in the effectiveness of the plant's safety, safeguards or security programs. The basis for this determination for the amendment request is shown below. | |||
The NRC staff has reviewed the certificate amendment application and concluded that it provides reasonable assurance of adequate safety, safeguards, and security, and compliance with NRC requirements. Therefore, the Director, Office of Nuclear Material Safety and Safeguards, is prepared to issue an amendment to the Certificate of Compliat..e for the Paducah Gaseous Diffusion Plant. The staff has prepared a Compliance Evaluation | |||
- Report which provides details of the staff's evaluation, 9712150322 97120e "* | |||
PDR ADOCK 07ooyoog-PDR- | |||
s-2 The NRC staff has determined that this amendment satisfies the criteria for a categorical exclusion in accordance with 10 CFR 51.22. Therefore, pursuant to 10 CFR 51.22(b), no environmentalimpact statement or environmental assessment need be prepared for this amendment. | |||
USEC or any person whose interest may be affected ma file a petition, not exceeding 30 pages, requesting review of the Director's Decision. The petition must be filed with the l ' Commission not later than 15 days after publication of this Federal Reaister Notico. A petition for review of the Director's Decision shall set forth with particularity the interest of the petitioner and how that interest may be affected by the results of the decision. The petition should specifically explain the reasons why review of the Decision should be permitted with particular reference to the following factors: (1) the interest of the petitioner; (2) how thst interest may be affected by the Decision, including the reasons why the petitioner should be permitted a review of the Decision; and (3) the petitinner's areas of concern about the activity that is the subject matter of the Decision. Any person described in this paragraph (USEC or any person who filed a petition) may file a response to any petition for revisw, not to exceed 30 pages, within 10 days af ter filing of the petition. | |||
if no petition is received within the designated 15-day period, the Director will issue the final amendment to the Certificate of Compliance without further delay, if a petition for review is received, the decision on the amendment application will become finalin 60 days, unless the Commission grants the petition for review or otherwise acts within 60 days af ter publication of this Federal Reaister Notice. | |||
4 5 3 | |||
A petition for review must be filed with the Secretary, U.S. Nuclear Regulatory 1 l | |||
Commission, Washington, DC 20555 0001, Attention: Rulemakings and Adjudicationa i | |||
Staff, or may be delivered to the Commission's Public Document Room, the Gelman Building, 2120 L Street, NW, Washington, DC, by the above date. | |||
For further details with respect to the action s.te (1) the application for amendment and (2) the Commission's Compliance Evaluation Reoort. These items are available for public inspection at the Commission's Public Document Room, the Gelman Building, 2120 L Street, NW, Washington, DC, and at the Local Public Document Room. | |||
Date of amendment request: August 29,1997 Brief description of amendment: The amendment proposes to revise the Technical Safety Requirements (TSRs) for the uranium hexafh.oride release detection systems located in Zones 1 and 4 of Building C 360. The revision is to include operability and surveillance requirements for additional valves that are required to close upon C 360 Zone 1 or 4 uranium hexafluoride detection. | |||
Basis for finding of no significance: | |||
: 1. The proposed amendment will not result in a change in the types or significant increase | |||
- in the amounts of any effluents that may be released offsite. | |||
.i 4 | |||
The proposed changes establishes limiting conditions for operation and associated | |||
. surveillance requirements to demonstrate the operability of containment isolation valves. | |||
-The change has no effect on the generation or disposition of effluents. Therefore, the proposed TSR modifications will not result in a change to the types or amount of effluents that may be released offsite. | |||
L | |||
: 2. .The proposed amendment will not result in a significant increase in individual or cumulative occupational radiation exposure. | |||
The proposed changes will not significantly increase any exposure to radiation. Therefore, the changes will not result in a significant increase in individual or cumulative radiation exposure. | |||
: 3. The proposed arnendment will not result in a significant constructior, impact. | |||
The proposed changes will not result in any construction, only procedure modification, therefore, there will be no corstruction impacts. | |||
: 4. The proposed arnendment will not result in a significant increase in the potential for, or radiological or chemical consequences from, previously analyzed accidents. | |||
I Accidents of concern involve the reluase of uranium hexafluoride in the C-360 laboratory area (Zone Il and the basement transfer room (Zone 4). The proposed TSR | |||
* y - " g - + - , | |||
l O | |||
5 i changes ensure that the TSRs adequately address the current plant configuration by establishing limiting conditions for operation and associated surveillance requirements to demonstrate the operability of containment isolation valves. These changes will enhance the overall plant safety. The changes will not increase the probability of occurrence or consequence of any postulated accident currently identified in the safety analysis report. | |||
: 5. The proposed amendment will not result in the possibility of a new or different kind of accident. | |||
The proposed TSR modifications are necessary to reflect the fact that multiple valves on the autoclave transfer and sampling piping willisolate upon detection of uranium hexafluoride. The current TSR does not reflect recent modification: requiring closure of at least two isolation valves on each transfer / sampling pathway. The propored changes will not create the possibility of a different type of equipment malfunction or a different type of accident. | |||
: 6. The proposed amendment will not result in a significant reduction in any margin of safety. | |||
The proposed changes to the TSRs ensure that the TSRs adequately address the current plant configuration by establishing limiting conditions for operation and associated surveillance requirements to demonstrate the operability of containment isolation valves that are required to close upon detection of uranium hexafluoride. These changes do not decrease the margins of safety, | |||
6 | |||
: 7. The proposed amendment will not result in an overall decrease in the effectiveness of the plant's safety, safeguards or security programs, implementation of the proposed changes do not change the safety, safeguards, or security programs. Theref".,re, the ef fectiveness of the safety, safeguards, and security programs is not decreased. | |||
Effective date: The amendment to Certificate of Compliance GDP 1 becomes effective 30 days af ter being signed by the Director, Office of Nuclear Materiai Safety and Safeguards. | |||
Certificate of Conspliance No. GDP 1: Amendment will revise TSR 2.1.4.1 and 2.1.4.2a to establish operability and surveillance requirements for additional valves required to close upon C 300 Zone 1 or 4 urar6m hexafluoride detection. | |||
Local Public Document Rocm location: Paducah Public Ubrary,555 Washington Street, P6ducah, Kentucky 42003. | |||
Dated at Rockville, Maryland, this h day of h.1997. | |||
FOR THE NUCLEAR REGULATORY COMMISSION Odginal Signed By CarI J. Papenello, Director Office of Nuclear Material Safety and Safeguards DISTRibOTION: | |||
NRC FILE CENTER PUBLIC NMSS r/f FCSS r# | |||
SPB r/f K'OBrien, Rill CCn, nilh NMSS Dir. Off r/f A_:\FRN AMD17. PAD 4/ | |||
OFC SPB Spr; (, SPB, ,8 SPB, [ $65h N M SS,_ /' | |||
NAME born:ij prJoadiey d b rtin _ | |||
e ETe Eyck CPherfello DATE lA /3/97 hM3/97 /Zd/97 l7/b7 (1-/5/97 !?/ 497 C = COVER E = COVER & ENCLOSURE N = NO COPY OFFICIAL RECORD COPY l | |||
. _ - _ - . - _ _ _ _ _ _ _ _ _ _ - a}} |
Latest revision as of 02:13, 1 January 2021
ML20203C486 | |
Person / Time | |
---|---|
Site: | 07007001 |
Issue date: | 12/08/1997 |
From: | Paperiello C NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
To: | |
Shared Package | |
ML20203C447 | List: |
References | |
NUDOCS 9712150322 | |
Download: ML20203C486 (6) | |
Text
. _ - - ._ _ _ ._ _ _. _ _ ~ _ . _ . _~ __ _
'. 7590-01 U.S. NUCLEAR REGULATORY COMMISSION NOTICE OF AMENDMENT TO l CERTIFICATE OF COMPLIANCE GDP 1 FOR l
-THE U.S. ENRICHMENT CORPORATION PADUCAH GASEOUS DIFFUSION PLANT PADUCAH, KENTUCKY DOCKET 70 7001 The Director, Office of Nuclear Material Safety and Safeguards, has made a determination that the following amendment request is not significant in accordance with 10 CFR 76.45.
In making that determination, the staff concluded that: (1) there is no change in the types or significant increase in the amounts of any effluents that may be released offsite; (2) there is no significant increase in individual or cumulative occupational radiation exposure; (3) there is no significant construction impact; (4) there is no significant increase in the potential for, or radiological or chemical consequences from, previously analyzed accidents; (5) the proposed changes do not result in the possibility of a new or different kind of accident; (6) there is no significant reduction in any margin of safety; and (7) the proposed changes will not result in an overall decrease in the effectiveness of the plant's safety, safeguards or security programs. The basis for this determination for the amendment request is shown below.
The NRC staff has reviewed the certificate amendment application and concluded that it provides reasonable assurance of adequate safety, safeguards, and security, and compliance with NRC requirements. Therefore, the Director, Office of Nuclear Material Safety and Safeguards, is prepared to issue an amendment to the Certificate of Compliat..e for the Paducah Gaseous Diffusion Plant. The staff has prepared a Compliance Evaluation
- Report which provides details of the staff's evaluation, 9712150322 97120e "*
PDR ADOCK 07ooyoog-PDR-
s-2 The NRC staff has determined that this amendment satisfies the criteria for a categorical exclusion in accordance with 10 CFR 51.22. Therefore, pursuant to 10 CFR 51.22(b), no environmentalimpact statement or environmental assessment need be prepared for this amendment.
USEC or any person whose interest may be affected ma file a petition, not exceeding 30 pages, requesting review of the Director's Decision. The petition must be filed with the l ' Commission not later than 15 days after publication of this Federal Reaister Notico. A petition for review of the Director's Decision shall set forth with particularity the interest of the petitioner and how that interest may be affected by the results of the decision. The petition should specifically explain the reasons why review of the Decision should be permitted with particular reference to the following factors: (1) the interest of the petitioner; (2) how thst interest may be affected by the Decision, including the reasons why the petitioner should be permitted a review of the Decision; and (3) the petitinner's areas of concern about the activity that is the subject matter of the Decision. Any person described in this paragraph (USEC or any person who filed a petition) may file a response to any petition for revisw, not to exceed 30 pages, within 10 days af ter filing of the petition.
if no petition is received within the designated 15-day period, the Director will issue the final amendment to the Certificate of Compliance without further delay, if a petition for review is received, the decision on the amendment application will become finalin 60 days, unless the Commission grants the petition for review or otherwise acts within 60 days af ter publication of this Federal Reaister Notice.
4 5 3
A petition for review must be filed with the Secretary, U.S. Nuclear Regulatory 1 l
Commission, Washington, DC 20555 0001, Attention: Rulemakings and Adjudicationa i
Staff, or may be delivered to the Commission's Public Document Room, the Gelman Building, 2120 L Street, NW, Washington, DC, by the above date.
For further details with respect to the action s.te (1) the application for amendment and (2) the Commission's Compliance Evaluation Reoort. These items are available for public inspection at the Commission's Public Document Room, the Gelman Building, 2120 L Street, NW, Washington, DC, and at the Local Public Document Room.
Date of amendment request: August 29,1997 Brief description of amendment: The amendment proposes to revise the Technical Safety Requirements (TSRs) for the uranium hexafh.oride release detection systems located in Zones 1 and 4 of Building C 360. The revision is to include operability and surveillance requirements for additional valves that are required to close upon C 360 Zone 1 or 4 uranium hexafluoride detection.
Basis for finding of no significance:
- 1. The proposed amendment will not result in a change in the types or significant increase
- in the amounts of any effluents that may be released offsite.
.i 4
The proposed changes establishes limiting conditions for operation and associated
. surveillance requirements to demonstrate the operability of containment isolation valves.
-The change has no effect on the generation or disposition of effluents. Therefore, the proposed TSR modifications will not result in a change to the types or amount of effluents that may be released offsite.
L
- 2. .The proposed amendment will not result in a significant increase in individual or cumulative occupational radiation exposure.
The proposed changes will not significantly increase any exposure to radiation. Therefore, the changes will not result in a significant increase in individual or cumulative radiation exposure.
- 3. The proposed arnendment will not result in a significant constructior, impact.
The proposed changes will not result in any construction, only procedure modification, therefore, there will be no corstruction impacts.
- 4. The proposed arnendment will not result in a significant increase in the potential for, or radiological or chemical consequences from, previously analyzed accidents.
I Accidents of concern involve the reluase of uranium hexafluoride in the C-360 laboratory area (Zone Il and the basement transfer room (Zone 4). The proposed TSR
- y - " g - + - ,
l O
5 i changes ensure that the TSRs adequately address the current plant configuration by establishing limiting conditions for operation and associated surveillance requirements to demonstrate the operability of containment isolation valves. These changes will enhance the overall plant safety. The changes will not increase the probability of occurrence or consequence of any postulated accident currently identified in the safety analysis report.
- 5. The proposed amendment will not result in the possibility of a new or different kind of accident.
The proposed TSR modifications are necessary to reflect the fact that multiple valves on the autoclave transfer and sampling piping willisolate upon detection of uranium hexafluoride. The current TSR does not reflect recent modification: requiring closure of at least two isolation valves on each transfer / sampling pathway. The propored changes will not create the possibility of a different type of equipment malfunction or a different type of accident.
- 6. The proposed amendment will not result in a significant reduction in any margin of safety.
The proposed changes to the TSRs ensure that the TSRs adequately address the current plant configuration by establishing limiting conditions for operation and associated surveillance requirements to demonstrate the operability of containment isolation valves that are required to close upon detection of uranium hexafluoride. These changes do not decrease the margins of safety,
6
- 7. The proposed amendment will not result in an overall decrease in the effectiveness of the plant's safety, safeguards or security programs, implementation of the proposed changes do not change the safety, safeguards, or security programs. Theref".,re, the ef fectiveness of the safety, safeguards, and security programs is not decreased.
Effective date: The amendment to Certificate of Compliance GDP 1 becomes effective 30 days af ter being signed by the Director, Office of Nuclear Materiai Safety and Safeguards.
Certificate of Conspliance No. GDP 1: Amendment will revise TSR 2.1.4.1 and 2.1.4.2a to establish operability and surveillance requirements for additional valves required to close upon C 300 Zone 1 or 4 urar6m hexafluoride detection.
Local Public Document Rocm location: Paducah Public Ubrary,555 Washington Street, P6ducah, Kentucky 42003.
Dated at Rockville, Maryland, this h day of h.1997.
FOR THE NUCLEAR REGULATORY COMMISSION Odginal Signed By CarI J. Papenello, Director Office of Nuclear Material Safety and Safeguards DISTRibOTION:
NRC FILE CENTER PUBLIC NMSS r/f FCSS r#
SPB r/f K'OBrien, Rill CCn, nilh NMSS Dir. Off r/f A_:\FRN AMD17. PAD 4/
OFC SPB Spr; (, SPB, ,8 SPB, [ $65h N M SS,_ /'
NAME born:ij prJoadiey d b rtin _
e ETe Eyck CPherfello DATE lA /3/97 hM3/97 /Zd/97 l7/b7 (1-/5/97 !?/ 497 C = COVER E = COVER & ENCLOSURE N = NO COPY OFFICIAL RECORD COPY l
. _ - _ - . - _ _ _ _ _ _ _ _ _ _ - a