ML20137V709
| ML20137V709 | |
| Person / Time | |
|---|---|
| Site: | 07007001 |
| Issue date: | 04/14/1997 |
| From: | Paperiello C NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| To: | |
| Shared Package | |
| ML20137V672 | List: |
| References | |
| NUDOCS 9704170379 | |
| Download: ML20137V709 (7) | |
Text
-
' - l 1
l 7590-01 U.S. NUCLEAR REGULATORY COMMISSIO.N NOTICE OF AMENDMENT TO CERTIFICATE OF COMPLIANCE GDP-1 FOR 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 i 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 Sdety and Safeguards,is prepared to issue an amendment to the Certificate of Compliance for the Paducah Gaseous Diffusion Plant. The staff has prepared a Compliance Evaluation Report which provides details of the staff's evaluation.
9704170379 970414 PDR ADOCK 07007001 C PDR
2 Th'e 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 I
environinental impact statement or environmental assessment need be prepared for this amendment.
USEC or any person whose interest may be affected may file a petition, not exceeding 30 pages, requesting review of the Director's Decisicn. The petition must be filed with the l Commission not later than 15 days after pubt; cation of this Federal Reaister Notice. 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 that interest may be affected by the Decision, including the reasons 1 why the petitioner should be permitted a review of the Decision; and (3) the petitioner's areas of concern about the activity that is the subject matter of the Decision. Any person i
described in this paragraph (USEC or any person who filed a petition) may file a response to any petition for review, not to exceed 30 pages, within 10 days after 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 after publication of this Egdg.ral r Reoister Notice.
i
3 A petition for review must be filed with the Secretary of the Commission, U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001 Attention: Docketing and Services i Branch, 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 see (1) the application for amendment and (2) the Commission's Compliance Evaluation Report. 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: December 23,1996 Brief description of amendment: The amendment changes the Technical Safety l Requirement surveillance for the Autoclave High Pressure Systems to reflect the ability to test allinner and outer penetration isolation valves.
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.
The proposed TSR changes reflect the autoclave piping modifications that permit independent testing of the inner and outer penetration isolation valves. Testing of these l
. _.__m_. .- . .m _ _ . - - . . . _ _ . _ _ _._ _._ _ _ _ . _ . . . ._ ._ __ _ __
i .
4 l 4 4
', o l valves demonstrates the ability to establish containment in the event of uranium hexafluoride leakage from the cylinder into the autoclave. The proposed changes provide enhanced assurance that the containment function will be available if needed. These i
changes have no impact on plant effluents and will not result in any impact to the environment.
- 2. The proposed amendment will not result in a significant increase in individual or i
cumulative occupational radiation exposure. ,
The proposed changes provide enhanced assurance that the autoclave containment ,
function will be available if needed. The changes will not result in increased individual or i
cumulative occupational radiation exposure.
- 3. The proposed amendment will not result in a significant construction impact.
The proposed changes will not result in any building construction, therefore, there will be no construction impacts.
- 4. The proposed amendment will not result in a significant increase in the potential for, or radiological or chemical consequences from, previously analyzed accidents.
The proposed changes allow testing of the inner and outer penetration isolation valves.
This testing of the autoclave containment function is not involved in any precursor to an
. - . .. .- - - - - ~ . . - .- -. .. - --. - ~ . - - -
! 4 i 1
I l
valves demonstrates the ability to establish containment in the event of uranium l
l hexafluoride leakage from the cylinder into the autoclave. The proposed changes provide I I
enhanced assurance that the containment function will be available if needed. These changes have no impact on plant effluents and will not result in any impact to the 1
environment. i l
l l
i
+
i r
! 2. The proposed amendment will not result in a significant increase in individual or cumulative occupational radiation exposure. j i
l l
4 The proposed changes provide enhanced assurance that the autoclave containment l
function will be available if needed. The changes will not result in increased individual or j cumulative occupational radiation exposure. 1
. 1 I
l
- 3. The proposed amendment will not result in a significant construction impact.
l l The proposed changes will not result in any building construction, therefore, there will be no construction impacts.
I l
- 4. The proposed amendment will not result in a significant increase in the potential for, or radiological or chemical consequences from, previously analyzed accidents.
The proposed changes allow testing of the inner and outer penetration isolation valves.
This testing of the autoclave containment function is not involved in any precursor to an l
1
-. . . . . - ~ ....__-. -
5 evaluated event; therefore, the potential of occurrence of an evaluated event is unaffected.
The proposed changes provide enhanced assurance that the function will be available if required; the consequences of previously evaluated accidents are not increased.
- 5. The proposed amendment will not result in the possibility of a new or different kind of accident.
' The autoclave piping configuration modifications permit independent testing of the inner and outer penetration isolation valves to demonstrate the ability to establish conteinment in the ev'ent of a leak from the cylinder into the autoclave. The changes affect only the autoclave isolation valves and create no new operating conditions or new plant configuration that could lead to a new or different type of accident.
- 6. The proposed amendment will not result in a significant reduction in any margin of safety.
The proposed changes reflect modifications that permit independent testing of the inner and outer penetration isolation valves. The proposed changes enhance the availability of the autoclave containment function. There is no reduction in the margin of safety.
- 7. The proposed amendment will not result in an overall decrease in the effecuveness of the plant's safety, safeguards or security programs.
6
- l. The proposed changes reflect the autoclave piping configuration modifications made to
. permit independent testing of inner and outer penetration isolation valves. Testing of these l valves demonstrates the ability to establish containment in the event of uranium hexafluoride leakage from the cylinder into the autoclave. The changes do not affect any j other equipment functions or administrative requirements. The testing of the autoclave l containment function is not addressed in the safeguards and security programs. The effectiveness of the safety, safeguards, and security programs is not decreased.
1 l
Effective date: 60 days after issuance of amendment l
1 4
Certificate of Compliance No. GDP-1: Amendment will revise the Technical Safety l Requirements.
1 1
) Local Public Document Room location: Paducah Public Library,555 Washington Street, l Paducah, Kentucky 42003.
I Dated at Rockville, Maryland, this /f day of Apr'ef1997.
] FOR THE NUCLEAR REGULATORY COMMISSION (0RIGINAL SIGNED BY)
Carl J. Paperiello, Director Office of Nuclear Material Safety and Safeguards Docket 70-7001 DISTRIBUTION:
NRC FILE CENTER PUBLIC NMSS r/f FCSS r/f SPB r/f K'OBrien, Rlli CCox, Rlli NMSS Dir. Off. r/f A:\FRNAMD3. PAD CP/ PROOFED /APRL 4,1997 OFC SPB' SPB* SPB* SPB+ FCSS *l NMSS NAME MHorn:ij DHoadley DMartin RPierson ETenEyck CPapesiello DATE 3/28/97 3/28/97 4/3/97 4/3/97 4/4/97 4 // $97 C = COVun E = COVIER & ENCLOSURE N = h O COPY OFFICIAL RECORD COPY
6 4
-The proposed changes reflect the autoclave piping configuration modifications made to l
- permit independent testing of inner and outer penetration isolation valves. Testing of -
these valves demonstrates the ability to establish containment in the event of uranium !
! hexafluoride leakage from the cylinder into the autoclave. The changes do not affect any s
ht er equipment functions or administrative requirements. The testing of the autoclave 1 l
4 containment function is not addressed in the safeguards and security programs. The effectiveness of the safety, safeguards, and security programs is not decreased.
\
'\
Effective date: 60 days after issuance of amendment ,
1 i
i Certificate of Com liance No. GDP-1: Amendment will revise the Technical Safety
)
Requirements.
- \
4 Local Public Document Room location: Paducah Public Library,555 Washington Street, N
Paducah, Kentucky 42003.
I 4
Dated at Rockville, Maryland, this day of 1997.
FOR THE N CLEAR REGULATORY COMMISSION s
Carl J. Paperiel g, Director Office of Nuclear Material Safety and Safeguards gg 7g DISTRIBUTION:
NRC FILE CENTER PUBLIC NMSS r/f FCSS r/f SPB r/f K'OBrien, Rlli CCox, Rlli \ NMSS Dir. Off, r/f A:\FRNAMD3. PAD \-
C OFC ,SPB yPB h SPJ, , SPB , FCSh y NMSS NAME NHorn:ij ..
hHoadley brb d ETen$yck\ CPaperiello DATE 1 /;397 3 /d/97 f/3/97 p/J/9 / k/k/97 s / /97 C = COVER E = COVIER & ENCLOSURE i N = IN O, COPY OFFICIAL IfECORD COPY \
\