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| number = ML061460093
| number = ML061460093
| issue date = 04/12/2006
| issue date = 04/12/2006
| title = Rancho Seco License Amendment Request and License Termination Plan, Revision 0
| title = License Amendment Request and License Termination Plan, Revision 0
| author name = Bua M J
| author name = Bua M
| author affiliation = Sacramento Municipal Utility District (SMUD)
| author affiliation = Sacramento Municipal Utility District (SMUD)
| addressee name =  
| addressee name =  
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| page count = 14
| page count = 14
| project =  
| project =  
| stage = Other
| stage = Request
}}
}}


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=Text=
{{#Wiki_filter:SACRAMENTO MUNICIPAL UTILITY DISTRICT The Power To Do More.@ P.O. Box 15830, Sacramento, CA 95852-1 830; 1-888- 742-SMUD (7683) April 12,2006 U.S. Nuclear Regulatory Commission Attn.: Document Control Desk Washington, DC 20555 Docket No. 50-3 12 Rancho Seco Nuclear Generating Station License No. DPR-54 RANCHO SECO LICENSE AMENDMENT REQUEST AND LICENSE TERMINATION PLAN, REVISION 0 Attention: John Hickman In accordance with 10 CFR 50.82(a)(9) and 10 CFR 50.90, we are submitting Proposed Amendment No. 199 (PA-1 99) to the Rancho Seco Operating License (DPR-54) and the License Termination Plan (LTP) for Rancho Seco Nuclear Generating Station. The LTP demonstrates that the remaining decommissioning activities will be performed in accordance with the regulations in 10 CFR Part 50, will not be inimical to the common defense and security or to the health and safety of the public, and will not have a significant adverse effect on the quality of the environment.
{{#Wiki_filter:SACRAMENTO MUNICIPAL UTILITY DISTRICT The Power To Do More.@
P.O. Box 15830, Sacramento, CA 95852-1830; 1-888-742-SMUD(7683)
April 12,2006 U.S. Nuclear Regulatory Commission Attn.: Document Control Desk Washington, DC 20555 Docket No. 50-3 12 Rancho Seco Nuclear Generating Station License No. DPR-54 RANCHO SECO LICENSE AMENDMENT REQUEST AND LICENSE TERMINATION PLAN, REVISION 0 Attention: John Hickman In accordance with 10 CFR 50.82(a)(9) and 10 CFR 50.90, we are submitting Proposed Amendment No. 199 (PA-199) to the Rancho Seco Operating License (DPR-54) and the License Termination Plan (LTP) for Rancho Seco Nuclear Generating Station. The LTP demonstrates that the remaining decommissioning activities will be performed in accordance with the regulations in 10 CFR Part 50, will not be inimical to the common defense and security or to the health and safety of the public, and will not have a significant adverse effect on the quality of the environment.
Upon NRC approval of the LTP, the amendment to the operating license adds a license condition that establishes the criteria for determining when changes to the LTP require prior NRC approval.
Upon NRC approval of the LTP, the amendment to the operating license adds a license condition that establishes the criteria for determining when changes to the LTP require prior NRC approval.
As discussed in Attachment 2, we have concluded that the proposed amendment presents no significant hazards consideration under the standards set forth in 10 CFR 50.92(c).
As discussed in Attachment 2, we have concluded that the proposed amendment presents no significant hazards consideration under the standards set forth in 10 CFR 50.92(c).
Accordingly, a finding of "no significant hazards consideration" is justified.
Accordingly, a finding of "no significant hazards consideration" is justified.
Attachment 1 provides the insertion/removal instructions for the affected pages. Attachment 2 provides a description of the proposed change, the No Significant Hazards Consideration, and an environmental impact consideration determination.
Attachment 1 provides the insertion/removal instructions for the affected pages.
Attachment 3 RANCHO SECO NUCLEAR PLANT 14440 Twin Cities Road, Herald, CA 95638-9799; (209) 333-2935 provides a copy of the revised affected pages to the operating license. Included after the proposed license amendment is the Rancho Seco License Termination Plan.
Attachment 2 provides a description of the proposed change, the No Significant Hazards Consideration, and an environmental impact consideration determination. Attachment 3 RANCHO SECO NUCLEAR PLANT 14440 Twin Cities Road, Herald, CA 95638-9799; (209)333-2935
In accordance with 10 CFR 50.9 1 (b)(l), we have informed the Radiological Health Branch of the California State Department of Health Services of the proposed amendment by sending them a copy of this submittal package. You or members of your staff with questions requiring additional information or clarification may contact Robert Jones at (9 16) 732-4843.
 
Sincerely, Manager, Plant Closure and Decommissioning  
provides a copy of the revised affected pages to the operating license. Included after the proposed license amendment is the Rancho Seco License Termination Plan.
(~ctin~)'
In accordance with 10 CFR 50.9 1(b)(l), we have informed the Radiological Health Branch of the California State Department of Health Services of the proposed amendment by sending them a copy of this submittal package.
Attachments (4) Cc W/ attachments:
You or members of your staff with questions requiring additional information or clarification may contact Robert Jones at (9 16) 732-4843.
B. S. Mallett, NRC, Region N Director, Radiological Health Branch, California State Department of Health Services  
Sincerely, Manager, Plant Closure and Decommissioning ( ~ c t i n ~ ) '
' In accordance with the process outlined in SMUD procedure SDP 3.3, Michael J. Bua is authorized to sign for Steve Redeker in his absence (See SMUD Letter MPC&D 06-002).
Attachments (4)
ALL-PURPOSE ACKNOWLEDGMENT State of County of ~ADOA /Vd+din7 ALgp C) . On /B?&&LZL)O(D . before me.d-h@h Y d~~jl (name, title of officer), personalli appeared /37/c/LA5~  
Cc W/attachments:         B. S. Mallett, NRC, Region N Director, Radiological Health Branch, California State Department of Health Services
: d. ni.LA - I o personally known to me -OR - o proved to me on the basis of satisfactory evidence to be the person(s) whose name(s) islare subscribed to the within instrument and acknowledged to me that helshelthey executed the same in his/ herltheir authorized capacity(ies), and that by hislhedtheir signature(s) on the instrument the person(s), or the entity uporr behalf of which the Ijerson(s) acted, executed the instrument.
  ' In accordance with the process outlined in SMUD procedure SDP 3.3, Michael J. Bua is authorized to sign for Steve Redeker in his absence (See SMUD Letter MPC&D 06-002).
* I Attachment I Removal and lnserfion lnstructions for Proposed License Amendment No.
 
f99.to the Rancho Seco Operating License Remove Operating License Page 4 Insert 0perhg; License Pages 4 and 5 Attachment 2 Description of the Proposed Change, No Significanf Hazards Considerafion, and Environmental Impact Considerations Background The Sacramento Municipal Utility District (SMUD) shut down Rancho Seco Nuclear Generating Station permanently on June 7, 1989, after approximately 15 years of operation.
ALL-PURPOSE ACKNOWLEDGMENT State of County of     ~ A D O A
                                                                          /Vd+din7       ALgp C)
. On   /B?&&LZL)O(D                       . before m e . d - h @ h Y       d~~jl               (name, title of officer),
personalli appeared     / 3 7 / c / L A 5 ~ d. ni.LA                                 -                               I o personally known to me -OR - o proved to me on the basis of satisfactory evidence to be the person(s) whose name(s) islare subscribed to the within instrument and acknowledged to me that helshelthey executed the same in his/
herltheir authorized capacity(ies), and that by hislhedtheir signature(s) on the instrument the person(s), or the entity uporr behalf of which the Ijerson(s) acted, executed the instrument.
I
 
Attachment I Removal and lnserfion lnstructions for Proposed License Amendment No. f99.to the Rancho Seco Operating License Remove Operating License     Insert 0 p e r h g ; License Page 4                          Pages 4 and 5
 
Attachment 2 Description of the Proposed Change, No Significanf Hazards Considerafion, and Environmental Impact Considerations
 
===Background===
The Sacramento Municipal Utility District (SMUD) shut down Rancho Seco Nuclear Generating Station permanently on June 7, 1989, after approximately 15 years of operation.
On August 29, 1989, SMUD formally informed the NRC that the plant was shut down permanently. On May 20,1991, SMUD submitted the Rancho Seco decommissioning plan and on March 20,1995, the NRC issued an Order approving the decommissioning plan and authorizing the decommissigning of Rancho Seco.
On August 29, 1989, SMUD formally informed the NRC that the plant was shut down permanently. On May 20,1991, SMUD submitted the Rancho Seco decommissioning plan and on March 20,1995, the NRC issued an Order approving the decommissioning plan and authorizing the decommissigning of Rancho Seco.
SMUD began actively decommissioning Rancho Seco in February 1997, and completed the transfer of all of the spent nuclear fuel to the 10 CFR Part 72 licensed Independent Spent Fuel Storage Installation (ISFSI) on'August 21,2002. Accordingly, the only quality- related structures, systems, or components (SSCs) at the Rancho Seco 10 CFR P.art 50 licensed site are the radioactive sources used to calibrate the instrumentation used to measure radioactivity in gaseous and liquid effluents. Plant dismantlement is substantially complete and most of the SSCs that were safety- related or important-to-safety have been removed fiom the plant and shipped for disposal. The pressurizer was shipped to ~ner~~~olutions' for disposal in April 2004, one steam generator was shipped to EnergySolutions in December 2004, and the second steam generator was shipped to EnergySolutions in April 2005. Reactor vessel internals segmentation is in'progress and activities in preparation for the reactor vessel segmentation are underway. Mobilization of the reactor vessel segmentation contractor is scheduled to begin in mid-2006.
SMUD began actively decommissioning Rancho Seco in February 1997, and completed the transfer of all of the spent nuclear fuel to the 10 CFR Part 72 licensed Independent Spent Fuel Storage Installation (ISFSI) on'August 21,2002. Accordingly, the only quality-related structures, systems, or components (SSCs) at the Rancho Seco 10 CFR P.art 50 licensed site are the radioactive sources used to calibrate the instrumentation used to measure radioactivity in gaseous and liquid effluents.
Reason for the Proposed Change NRC Regulation 10 CFR 50.82(a)(9) requires that a licensee submit an application for the termination of the 10 CFR Part 50 license. The application for termination of the license must be accompanied or preceded by a License Termination Plan (LTP) to be submitted for NRC EnergySolutions was formerly Envirocare of Utah approval.
Plant dismantlement is substantially complete and most of the SSCs that were safety-related or important-to-safety have been removed fiom the plant and shipped for disposal.
The LTP is a supplement to the Rancho Seco Defueled Safety Analysis Report @SARI. i I We are submitting Proposed Amendment No. 199 (PA-199) to satisfy the requirements of 10 CFR 50.82(a)(10) for approval of the License Termination Plan by License amendment.
The pressurizer was shipped to ~ n e r ~ ~ ~ o l u t ifor o ndisposal s'       in April 2004, one steam generator was shipped to EnergySolutions in December 2004, and the second steam generator was shipped to EnergySolutions in April 2005. Reactor vessel internals segmentation is in'progress and activities in preparation for the reactor vessel segmentation are underway. Mobilization of the reactor vessel segmentation contractor is scheduled to begin in mid-2006.
SMUD is not submitting its application for termination of the Rancho Seco license at this time. Description of the Proposed License Change 1 1 As discussed in LTP Section 1.6, SMUD may make changes to the LTP, without prior NRC approval, urider the provisions in 10 CFR 50.59,10 CFR 50.82(a)(6), and 10 CFR 50.82(a)(7).
Reason for the Proposed Change NRC Regulation 10 CFR 50.82(a)(9) requires that a licensee submit an application for the termination of the 10 CFR Part 50 license. The application for termination of the license must be accompanied or preceded by a License Termination Plan (LTP) to be submitted for NRC EnergySolutions was formerly Envirocare of Utah
PA-199 amends the Rancho Seco operating license to include the criteria for when changes to the LTP require prior NRC approval.
 
PA-199 adds new License Condition 2.C(4), as follows: (4) License Termination Plan (LTP)
approval. The LTP is a supplement to the Rancho Seco Defueled Safety Analysis Report
@SARI.                                                         i               I We are submitting Proposed Amendment No. 199 (PA-199) to satisfy the requirements of 10 CFR 50.82(a)(10) for approval of the License Termination Plan by License amendment.
SMUD is not submitting its application for termination of the Rancho Seco license at this time.
Description of the Proposed License Change                     1 1
As discussed in LTP Section 1.6, SMUD may make changes to the LTP, without prior NRC approval, urider the provisions in 10 CFR 50.59,10 CFR 50.82(a)(6), and 10 CFR 50.82(a)(7). PA-199 amends the Rancho Seco operating license to include the criteria for when changes to the LTP require prior NRC approval.
PA-199 adds new License Condition 2.C(4), as follows:
(4)     License Termination Plan (LTP)
NRC License Amendment No. 133 approves the License Termination Plan.
NRC License Amendment No. 133 approves the License Termination Plan.
In addition to the criteria specified in 10 CFR 50.59 and 10 CFX 50.82(a)(6), a change to the LTP requiresprior NRC approval ifthe change: (a) Increases the probability ofmhking a Type I decision error above the level stated in the LTP (6) Increases the radionuclide-specific derived concentration guideline levels (DCGL) and related minimum detectable concentrations (c) Increases the radioactivity level, relative to the applicable DCGL, at which investigation occurs (4 Changes the statistical test applied other than the Sign Test or Wilcoxon Rank Sum Test. ~ Re-classijcation of survey areas from a less to a more restrictive classification (e.g., from a Class 3 to a Class 2 area) may be done without prior NRC notification; however, re-classiJication to a less restrictive i t I I classification (e.g., Class 1 to Class 2 area) will require NRC notification at least 14 days prior to implementation.
In addition to the criteria specified in 10 CFR 50.59 and 10 CFX 50.82(a)(6),
I No Significant Hazards Consideration SMUD has reviewed the proposed license amendment against each of the criteria in 10 CFR 50.92 and has concluded that the amendment request involves no significant hazards consideration.
a change to the LTP requiresprior NRC approval ifthe change:
The following provides SMUD's analysis of the issue of no significant hazards consideration:  
(a)   Increases the probability ofmhking a Type I decision error above the level stated in the LTP (6)     Increases the radionuclide-specific derived concentration guideline levels (DCGL) and related minimum detectable concentrations (c)     Increases the radioactivity level, relative to the applicable DCGL, at which investigation occurs (4
                                                                  ~
Changes the statistical test applied other than the Sign Test or Wilcoxon Rank Sum Test.
Re-classijcation of survey areasfrom a less to a more restrictive classification (e.g.,from a Class 3 to a Class 2 area) may be done without prior NRC notification; however, re-classiJicationto a less restrictive i               t I
I
 
classification (e.g., Class 1 to Class 2 area) will require NRC notification at least 14 days prior to implementation.         I No Significant Hazards Consideration SMUD has reviewed the proposed license amendment against each of the criteria in 10 CFR 50.92 and has concluded that the amendment request involves no significant hazards consideration. The following provides SMUD's analysis of the issue of no significant hazards consideration:
: 1. Does the proposed license amendment involve a significant increase in the probability or consequences of an accident previously evaluated?
: 1. Does the proposed license amendment involve a significant increase in the probability or consequences of an accident previously evaluated?
No. The proposed change is administrative.
No. The proposed change is administrative. The change allows for the a h o v a l of the LTP and provides the criteria for when changes to the ~ ~ ~ . r e ~       u iNRC prior r e approval.
The change allows for the ahoval of the LTP and provides the criteria for when changes to the ~~~.re~uire prior NRC approval.
This change does not affect possible initiating events for accidents previously evaluated or alter the configuration or operation of the facility. Safety limits, limiting safety system settings, and limiting control systems are no longer applicable to Rancho Seco in the permanently defueled mode, and are therefore not relevant.
This change does not affect possible initiating events for accidents previously evaluated or alter the configuration or operation of the facility.
The proposed change does not affect the boundaries used to evaluate compliance with liquid or gaseous effluent limits, and has no impact on plant operations. Therefore, the proposed license amendment does not involve a significant increase in the probability or consequences of an accident previously evaluated.             I             P
Safety limits, limiting safety system settings, and limiting control systems are no longer applicable to Rancho Seco in the permanently defueled mode, and are therefore not relevant.
: 2. Does the proposed license amendment create the possibility of a new or different kind of accident from any accident previously evaluated?
The proposed change does not affect the boundaries used to evaluate compliance with liquid or gaseous effluent limits, and has no impact on plant operations.
No. As described above, the proposed change is administrative and provides the criteria for when changes to the LTP require prior NRC approval. The safety analysis for the facility remains complete and accurate. There are no physical changes to the facility as a result of the proposed amendment and the plant conditio,nsfor which the design basis accidents have been evaluated are still valid.               I The operating procedures and emergency procedures are not affected. The proposed changes do not affect the emergency planning zone, the boundaries used to evaluate compliance with liquid or gaseous effluent limits, and have no impact on plant operations. Consequently, no new failure modes are introduced as the result of the I
Therefore, the proposed license amendment does not involve a significant increase in the probability or consequences of an accident previously evaluated.
I
I P 2. Does the proposed license amendment create the possibility of a new or different kind of accident from any accident previously evaluated?
 
No. As described above, the proposed change is administrative and provides the criteria for when changes to the LTP require prior NRC approval.
proposed changes. Therefore, the proposed'changes will not create the possibility of a new or different kind of accident from any accident previously evaluated.
The safety analysis for the facility remains complete and accurate.
: 3. Does the proposed license amendment involve a significant reduction in a margin of safety?
There are no physical changes to the facility as a result of the proposed amendment and the plant conditio,ns for which the design basis accidents have been evaluated are still valid. I The operating procedures and emergency procedures are not affected.
No. As described above, the proposed changes are administrative. There are no changes to the design or operation of the facility. The proposed changes do not affect the emergency planning zone, the boundaries used to evaluate compliance with liquid or gaseous effluent limits, and have no impact on plant operations. Accordingly, neither the design basis nor the accident assumptions in the Defueled Safety Analysis Report (DSAR), nor the Technical Specification Bases are affected. Therefore, the proposed changes do not involve a significant reduction in a margin of safety.
The proposed changes do not affect the emergency planning zone, the boundaries used to evaluate compliance with liquid or gaseous effluent limits, and have no impact on plant operations.
 
Consequently, no new failure modes are introduced as the result of the I I proposed changes. Therefore, the proposed'changes will not create the possibility of a new or different kind of accident from any accident previously evaluated.  
Environmenfal Impacf Consideration This amendment request satisfies the criteria specified in 10 CFR 51.22(~)(9)for a categorical exclusion from the requirements to perform an environmental assessment or to prepare an environmental impact statement. The criteria of 10 CFR 5 1.22(~)(9)are addressed as follows:
: 3. Does the proposed license amendment involve a significant reduction in a margin of safety? No. As described above, the proposed changes are administrative.
(i) The amendment involves no significant hazards consideration.
There are no changes to the design or operation of the facility. The proposed changes do not affect the emergency planning zone, the boundaries used to evaluate compliance with liquid or gaseous effluent limits, and have no impact on plant operations. Accordingly, neither the design basis nor the accident assumptions in the Defueled Safety Analysis Report (DSAR), nor the Technical Specification Bases are affected. Therefore, the proposed changes do not involve a significant reduction in a margin of safety.
As discussed in the No Significant Hazards Consideration section above, the proposed license amendment does not involve a significant hazards consideration.
Environmenfal Impacf Consideration This amendment request satisfies the criteria specified in 10 CFR 51.22(~)(9) for a categorical exclusion from the requirements to perform an environmental assessment or to prepare an environmental impact statement. The criteria of 10 CFR 5 1.22(~)(9) are addressed as follows: (i) The amendment involves no significant hazards consideration.
(ii) There is no significant change in the types or significant increase in the amounts of effluents that may be released offsite.
As discussed in the No Significant Hazards Consideration section above, the proposed license amendment does not involve a significant hazards consideration. (ii) There is no significant change in the types or significant increase in the amounts of effluents that may be released offsite. The proposed license amendment is consistent with the plant activities described in the Rancho Seco Post Shutdown Decommissioning Activities Report (PSDAR). The environmental impacts associated with radiation dose to members of the public related to decommissioning activities and site release for unrestricted use were considered in NUREG- 0586 "Final Generic Environmental Impact Statement on Decommissioning of Nuclear Facilities," NUREG-0586 Supplement 1, and NUREG-1496 "Generic Environmental Impact Statement in Support of the Rulemaking on Radiological Criteria for License Termination." In conjunction with the submittal of the original Rancho Seco Decommissioning Plan, the District submitted "Supplement to Rancho Seco Environmental Report - Post Operating License Stage." This environmental report compared Rancho Seco decommissioning attributes to those identified in NUREG-0586.
The proposed license amendment is consistent with the plant activities described in the Rancho Seco Post Shutdown Decommissioning Activities Report (PSDAR). The environmental impacts associated with radiation dose to members of the public related to decommissioning activities and site release for unrestricted use were considered in NUREG-0586 "Final Generic Environmental Impact Statement on Decommissioning of Nuclear Facilities," NUREG-0586 Supplement 1, and NUREG-1496 "Generic Environmental Impact Statement in Support of the Rulemaking on Radiological Criteria for License Termination."
NUREG-0586 provides a generic environmental assessment of decommissioning a reference nuclear facility.
In conjunction with the submittal of the original Rancho Seco Decommissioning Plan, the District submitted "Supplement to Rancho Seco Environmental Report - Post Operating License Stage." This environmental report compared Rancho Seco decommissioning attributes to those identified in NUREG-0586.
When the NRC issued the Decommissioning Rule in 1988, and based on the findings in NUREG-0586, it concluded a generic finding of "no significant (environmental) impact." The NRC further concluded that no additional Environmental Impact Statement (EIS) would need to be prepared in connection with decommissioning a particular nuclear site unless the impacts of a particular plant have site-specific considerations significantly different from those studied generically.
NUREG-0586 provides a generic environmental assessment of decommissioning a reference nuclear facility. When the NRC issued the Decommissioning Rule in 1988, and based on the findings in NUREG-0586, it concluded a generic finding of "no significant (environmental) impact." The NRC further concluded that no additional Environmental Impact Statement (EIS) would need to be prepared in connection with decommissioning a particular nuclear site unless the impacts of a particular plant have site-specific considerations significantly different from those studied generically.
The "Supplement to Rancho Seco Environmental Report - post Operating License Stage" concluded that all effluents, both radiological and non-radiological, will remain within regulatory limits as specified in applicable control documents and approvals throughout the decommissioning process. LTP Chapter 8 provides an updated assessment of the environmental effects of decommissioning Rancho Seco. The updated assessment also determined that the environmental effects fiom decommissioning Rancho Seco are minimal and there are no adverse effects outside the bounds of NUREG-0586 or the associated Supplement  
The "Supplement to Rancho Seco Environmental Report - post Operating License Stage" concluded that all effluents, both radiological and non-radiological, will remain within regulatory limits as specified in applicable control documents and approvals throughout the decommissioning process. LTP Chapter 8 provides an updated assessment of the environmental effects of decommissioning Rancho Seco. The updated assessment also
: 1. The conclusions contained in the "Supplement to Rancho Seco Environmental Report - Post Operating License Stage" are still valid. Based on the above, there will not be a significant change in the types or increase in the amounts of effluents released offsite for the remaining decommissioning activities. (iii) There is no significant increase in individual or cumulative occupational exposure.
 
As stated above, the District submitted "Supplement to Rancho Seco Environmental Report - Post Operating License Stage" in conjunction with the submittal of the original Rancho Seco Decominissioning Plan. This environmental report compated Rancho Seco decommissioning attributes to those identified in NUREG-0586.
determined that the environmental effects fiom decommissioning Rancho Seco are minimal and there are no adverse effects outside the bounds of NUREG-0586 or the associated Supplement 1. The conclusions contained in the "Supplement to Rancho Seco Environmental Report - Post Operating License Stage" are still valid.
Based on the above, there will not be a significant change in the types or increase in the amounts of effluents released offsite for the remaining decommissioning activities.
(iii) There is no significant increase in individual or cumulative occupational exposure.
As stated above, the District submitted "Supplement to Rancho Seco Environmental Report -
Post Operating License Stage" in conjunction with the submittal of the original Rancho Seco Decominissioning Plan. This environmental report compated Rancho Seco decommissioning attributes to those identified in NUREG-0586.
The "Supplement to Rancho Seco Environmental Report - Post Operating License Stage" contained the following conclusions:
The "Supplement to Rancho Seco Environmental Report - Post Operating License Stage" contained the following conclusions:
The District will maintain annual occupational radiation exposure to individuals as low as reasonably achievable (ALARA). These exposures will be below historical levels for the operating phase of the plant. The District expects to maintain exposure to onsite workers and the offsite public as a result of waste transportation well below the levels projected by NUREG-0586.
The District will maintain annual occupational radiation exposure to individuals as low as reasonably achievable (ALARA). These exposures will be below historical levels for the operating phase of the plant.
LTP Chapter 8 provides an updated assessment of the environmental effects of decommissioning Rancho Seco. The updated assessment also determined that the environmental effects fiom decommissioning Rancho Seco are minimal and there are no adverse effects outside the bounds of NUREG-0586 or the associated Supplement  
The District expects to maintain exposure to onsite workers and the offsite public as a result of waste transportation well below the levels projected by NUREG-0586.
: 1. Additionally, the conclusions contained in the "Supplement to Rancho Seco Environmental Report - Post Operating License Stage" are still valid. Based on the above, there is no significant increase in individual or cumulative occupational exposure due to decommissioning Rancho Seco. .
LTP Chapter 8 provides an updated assessment of the environmental effects of decommissioning Rancho Seco. The updated assessment also determined that the environmental effects fiom decommissioning Rancho Seco are minimal and there are no adverse effects outside the bounds of NUREG-0586 or the associated Supplement 1.
Attachment 3 Revised Facility Operating License (3) Confirmatory Order The movement of nuclear fuel into the Reactor Building is prohibited without prior NRC approval. (Amendment 132 - 09/27/05)  
Additionally, the conclusions contained in the "Supplement to Rancho Seco Environmental Report - Post Operating License Stage" are still valid.
(4) License Termination Plan (LTP) NRC License Amendment No. 133 approves the License Termination Plan. In addition to the criteria specified in 10 CFR 50.59 and 10 CFR 50.82(a)(6), a change to the LTP requires prior NRC approval if the change: (a) Increases the probabilitv of making a Type I decision error above the level stated in the LTP (Ib) Increases the radionuclide-specific derived concentration guideline levels (DCGL) and. related minimum detectable concentrations (c) Increases the radioactivity level., relative to the applicable DCGL, at which investigation occurs (d) Changes the statistical test applied other than the Sign Test or Wilcoxon Rank Sum Test. Re-classification of survey areas from a less to a more restrictive classification Je.p., fiom a Class 3 to a Class 2 area) may be done without prior NRC ~iotification:
Based on the above, there is no significant increase in individual or cumulative occupational exposure due to decommissioning Rancho Seco. .
however, re-classification to a less restrictive classification (e.~., Class 1 to Class 2 area) will require NRC notification at least 14 days prior to implementation.
 
Attachment 3 Revised Facility Operating License
 
(3)     Confirmatory Order The movement of nuclear fuel into the Reactor Building is prohibited without prior NRC approval.
(Amendment 132 - 09/27/05)
(4)     License Termination Plan (LTP)
NRC License Amendment No. 133 approves the License Termination Plan.
In addition to the criteria specified in 10 CFR 50.59 and 10 CFR 50.82(a)(6), a change to the LTP requires prior NRC approval if the change:
(a)   Increases the probabilitv of making a Type I decision error above the level stated in the LTP (Ib) Increases the radionuclide-specific derived concentration guideline levels (DCGL) and.related minimum detectable concentrations (c)   Increases the radioactivity level., relative to the applicable DCGL, at which investigation occurs (d)   Changes the statistical test applied other than the Sign Test or Wilcoxon Rank Sum Test.
Re-classification of survey areas from a less to a more restrictive classification Je.p., fiom a Class 3 to a Class 2 area) may be done without prior NRC
            ~iotification:however, re-classification to a less restrictive classification (e.~.,
Class 1 to Class 2 area) will require NRC notification at least 14 days prior to implementation.
D. This license is subject to the following additional condition for the protection of the environment:
D. This license is subject to the following additional condition for the protection of the environment:
If harmful effects or evidence of irreversible damage are detected by the monitoring programs included in the Rancho Seco Quality Manual, the Applicant will provide an analysis of the problem and a proposed course of action to alleviate the problem.
If harmful effects or evidence of irreversible damage are detected by the monitoring programs included in the Rancho Seco Quality Manual, the Applicant will provide an analysis of the problem and a proposed course of action to alleviate the problem.
E. This license is effective as of the date of issuance and shall expire at midnight, October 11,2008. FOR THE ATOMIC ENERGY COMMISSION IS/ ROGER BOYD for A. Giambusso, Deputy Director for Reactor Projects Directorate of Licensing Date of Issuance:
 
August 16,1974  
E. This license is effective as of the date of issuance and shall expire at midnight, October 11,2008.
FOR THE ATOMIC ENERGY COMMISSION IS/ROGER BOYD for A. Giambusso, Deputy Director for Reactor Projects Directorate of Licensing Date of Issuance:
August 16,1974


==Attachment:==
==Attachment:==


Appendix A - Technical Specifications (Amendment 120 - 10/13/92)
Appendix A - Technical Specifications (Amendment 120 - 10/13/92)
Orders for Modification of License Deleted (Amendment 132 - 09/27/05)
Orders for Modification of License Deleted (Amendment 132 09/27/05)
 
Attachment 4 License Termination Plan}}
Attachment 4 License Termination Plan}}

Latest revision as of 05:30, 14 March 2020

License Amendment Request and License Termination Plan, Revision 0
ML061460093
Person / Time
Site: Rancho Seco
Issue date: 04/12/2006
From: Bua M
Sacramento Municipal Utility District (SMUD)
To:
Document Control Desk, NRC/FSME
References
MPC&D 06-035, NQA 06-015
Download: ML061460093 (14)


Text

SACRAMENTO MUNICIPAL UTILITY DISTRICT The Power To Do More.@

P.O. Box 15830, Sacramento, CA 95852-1830; 1-888-742-SMUD(7683)

April 12,2006 U.S. Nuclear Regulatory Commission Attn.: Document Control Desk Washington, DC 20555 Docket No. 50-3 12 Rancho Seco Nuclear Generating Station License No. DPR-54 RANCHO SECO LICENSE AMENDMENT REQUEST AND LICENSE TERMINATION PLAN, REVISION 0 Attention: John Hickman In accordance with 10 CFR 50.82(a)(9) and 10 CFR 50.90, we are submitting Proposed Amendment No. 199 (PA-199) to the Rancho Seco Operating License (DPR-54) and the License Termination Plan (LTP) for Rancho Seco Nuclear Generating Station. The LTP demonstrates that the remaining decommissioning activities will be performed in accordance with the regulations in 10 CFR Part 50, will not be inimical to the common defense and security or to the health and safety of the public, and will not have a significant adverse effect on the quality of the environment.

Upon NRC approval of the LTP, the amendment to the operating license adds a license condition that establishes the criteria for determining when changes to the LTP require prior NRC approval.

As discussed in Attachment 2, we have concluded that the proposed amendment presents no significant hazards consideration under the standards set forth in 10 CFR 50.92(c).

Accordingly, a finding of "no significant hazards consideration" is justified.

Attachment 1 provides the insertion/removal instructions for the affected pages.

Attachment 2 provides a description of the proposed change, the No Significant Hazards Consideration, and an environmental impact consideration determination. Attachment 3 RANCHO SECO NUCLEAR PLANT 14440 Twin Cities Road, Herald, CA 95638-9799; (209)333-2935

provides a copy of the revised affected pages to the operating license. Included after the proposed license amendment is the Rancho Seco License Termination Plan.

In accordance with 10 CFR 50.9 1(b)(l), we have informed the Radiological Health Branch of the California State Department of Health Services of the proposed amendment by sending them a copy of this submittal package.

You or members of your staff with questions requiring additional information or clarification may contact Robert Jones at (9 16) 732-4843.

Sincerely, Manager, Plant Closure and Decommissioning ( ~ c t i n ~ ) '

Attachments (4)

Cc W/attachments: B. S. Mallett, NRC, Region N Director, Radiological Health Branch, California State Department of Health Services

' In accordance with the process outlined in SMUD procedure SDP 3.3, Michael J. Bua is authorized to sign for Steve Redeker in his absence (See SMUD Letter MPC&D 06-002).

ALL-PURPOSE ACKNOWLEDGMENT State of County of ~ A D O A

/Vd+din7 ALgp C)

. On /B?&&LZL)O(D . before m e . d - h @ h Y d~~jl (name, title of officer),

personalli appeared / 3 7 / c / L A 5 ~ d. ni.LA - I o personally known to me -OR - o proved to me on the basis of satisfactory evidence to be the person(s) whose name(s) islare subscribed to the within instrument and acknowledged to me that helshelthey executed the same in his/

herltheir authorized capacity(ies), and that by hislhedtheir signature(s) on the instrument the person(s), or the entity uporr behalf of which the Ijerson(s) acted, executed the instrument.

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Attachment I Removal and lnserfion lnstructions for Proposed License Amendment No. f99.to the Rancho Seco Operating License Remove Operating License Insert 0 p e r h g ; License Page 4 Pages 4 and 5

Attachment 2 Description of the Proposed Change, No Significanf Hazards Considerafion, and Environmental Impact Considerations

Background

The Sacramento Municipal Utility District (SMUD) shut down Rancho Seco Nuclear Generating Station permanently on June 7, 1989, after approximately 15 years of operation.

On August 29, 1989, SMUD formally informed the NRC that the plant was shut down permanently. On May 20,1991, SMUD submitted the Rancho Seco decommissioning plan and on March 20,1995, the NRC issued an Order approving the decommissioning plan and authorizing the decommissigning of Rancho Seco.

SMUD began actively decommissioning Rancho Seco in February 1997, and completed the transfer of all of the spent nuclear fuel to the 10 CFR Part 72 licensed Independent Spent Fuel Storage Installation (ISFSI) on'August 21,2002. Accordingly, the only quality-related structures, systems, or components (SSCs) at the Rancho Seco 10 CFR P.art 50 licensed site are the radioactive sources used to calibrate the instrumentation used to measure radioactivity in gaseous and liquid effluents.

Plant dismantlement is substantially complete and most of the SSCs that were safety-related or important-to-safety have been removed fiom the plant and shipped for disposal.

The pressurizer was shipped to ~ n e r ~ ~ ~ o l u t ifor o ndisposal s' in April 2004, one steam generator was shipped to EnergySolutions in December 2004, and the second steam generator was shipped to EnergySolutions in April 2005. Reactor vessel internals segmentation is in'progress and activities in preparation for the reactor vessel segmentation are underway. Mobilization of the reactor vessel segmentation contractor is scheduled to begin in mid-2006.

Reason for the Proposed Change NRC Regulation 10 CFR 50.82(a)(9) requires that a licensee submit an application for the termination of the 10 CFR Part 50 license. The application for termination of the license must be accompanied or preceded by a License Termination Plan (LTP) to be submitted for NRC EnergySolutions was formerly Envirocare of Utah

approval. The LTP is a supplement to the Rancho Seco Defueled Safety Analysis Report

@SARI. i I We are submitting Proposed Amendment No. 199 (PA-199) to satisfy the requirements of 10 CFR 50.82(a)(10) for approval of the License Termination Plan by License amendment.

SMUD is not submitting its application for termination of the Rancho Seco license at this time.

Description of the Proposed License Change 1 1

As discussed in LTP Section 1.6, SMUD may make changes to the LTP, without prior NRC approval, urider the provisions in 10 CFR 50.59,10 CFR 50.82(a)(6), and 10 CFR 50.82(a)(7). PA-199 amends the Rancho Seco operating license to include the criteria for when changes to the LTP require prior NRC approval.

PA-199 adds new License Condition 2.C(4), as follows:

(4) License Termination Plan (LTP)

NRC License Amendment No. 133 approves the License Termination Plan.

In addition to the criteria specified in 10 CFR 50.59 and 10 CFX 50.82(a)(6),

a change to the LTP requiresprior NRC approval ifthe change:

(a) Increases the probability ofmhking a Type I decision error above the level stated in the LTP (6) Increases the radionuclide-specific derived concentration guideline levels (DCGL) and related minimum detectable concentrations (c) Increases the radioactivity level, relative to the applicable DCGL, at which investigation occurs (4

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Changes the statistical test applied other than the Sign Test or Wilcoxon Rank Sum Test.

Re-classijcation of survey areasfrom a less to a more restrictive classification (e.g.,from a Class 3 to a Class 2 area) may be done without prior NRC notification; however, re-classiJicationto a less restrictive i t I

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classification (e.g., Class 1 to Class 2 area) will require NRC notification at least 14 days prior to implementation. I No Significant Hazards Consideration SMUD has reviewed the proposed license amendment against each of the criteria in 10 CFR 50.92 and has concluded that the amendment request involves no significant hazards consideration. The following provides SMUD's analysis of the issue of no significant hazards consideration:

1. Does the proposed license amendment involve a significant increase in the probability or consequences of an accident previously evaluated?

No. The proposed change is administrative. The change allows for the a h o v a l of the LTP and provides the criteria for when changes to the ~ ~ ~ . r e ~ u iNRC prior r e approval.

This change does not affect possible initiating events for accidents previously evaluated or alter the configuration or operation of the facility. Safety limits, limiting safety system settings, and limiting control systems are no longer applicable to Rancho Seco in the permanently defueled mode, and are therefore not relevant.

The proposed change does not affect the boundaries used to evaluate compliance with liquid or gaseous effluent limits, and has no impact on plant operations. Therefore, the proposed license amendment does not involve a significant increase in the probability or consequences of an accident previously evaluated. I P

2. Does the proposed license amendment create the possibility of a new or different kind of accident from any accident previously evaluated?

No. As described above, the proposed change is administrative and provides the criteria for when changes to the LTP require prior NRC approval. The safety analysis for the facility remains complete and accurate. There are no physical changes to the facility as a result of the proposed amendment and the plant conditio,nsfor which the design basis accidents have been evaluated are still valid. I The operating procedures and emergency procedures are not affected. The proposed changes do not affect the emergency planning zone, the boundaries used to evaluate compliance with liquid or gaseous effluent limits, and have no impact on plant operations. Consequently, no new failure modes are introduced as the result of the I

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proposed changes. Therefore, the proposed'changes will not create the possibility of a new or different kind of accident from any accident previously evaluated.

3. Does the proposed license amendment involve a significant reduction in a margin of safety?

No. As described above, the proposed changes are administrative. There are no changes to the design or operation of the facility. The proposed changes do not affect the emergency planning zone, the boundaries used to evaluate compliance with liquid or gaseous effluent limits, and have no impact on plant operations. Accordingly, neither the design basis nor the accident assumptions in the Defueled Safety Analysis Report (DSAR), nor the Technical Specification Bases are affected. Therefore, the proposed changes do not involve a significant reduction in a margin of safety.

Environmenfal Impacf Consideration This amendment request satisfies the criteria specified in 10 CFR 51.22(~)(9)for a categorical exclusion from the requirements to perform an environmental assessment or to prepare an environmental impact statement. The criteria of 10 CFR 5 1.22(~)(9)are addressed as follows:

(i) The amendment involves no significant hazards consideration.

As discussed in the No Significant Hazards Consideration section above, the proposed license amendment does not involve a significant hazards consideration.

(ii) There is no significant change in the types or significant increase in the amounts of effluents that may be released offsite.

The proposed license amendment is consistent with the plant activities described in the Rancho Seco Post Shutdown Decommissioning Activities Report (PSDAR). The environmental impacts associated with radiation dose to members of the public related to decommissioning activities and site release for unrestricted use were considered in NUREG-0586 "Final Generic Environmental Impact Statement on Decommissioning of Nuclear Facilities," NUREG-0586 Supplement 1, and NUREG-1496 "Generic Environmental Impact Statement in Support of the Rulemaking on Radiological Criteria for License Termination."

In conjunction with the submittal of the original Rancho Seco Decommissioning Plan, the District submitted "Supplement to Rancho Seco Environmental Report - Post Operating License Stage." This environmental report compared Rancho Seco decommissioning attributes to those identified in NUREG-0586.

NUREG-0586 provides a generic environmental assessment of decommissioning a reference nuclear facility. When the NRC issued the Decommissioning Rule in 1988, and based on the findings in NUREG-0586, it concluded a generic finding of "no significant (environmental) impact." The NRC further concluded that no additional Environmental Impact Statement (EIS) would need to be prepared in connection with decommissioning a particular nuclear site unless the impacts of a particular plant have site-specific considerations significantly different from those studied generically.

The "Supplement to Rancho Seco Environmental Report - post Operating License Stage" concluded that all effluents, both radiological and non-radiological, will remain within regulatory limits as specified in applicable control documents and approvals throughout the decommissioning process. LTP Chapter 8 provides an updated assessment of the environmental effects of decommissioning Rancho Seco. The updated assessment also

determined that the environmental effects fiom decommissioning Rancho Seco are minimal and there are no adverse effects outside the bounds of NUREG-0586 or the associated Supplement 1. The conclusions contained in the "Supplement to Rancho Seco Environmental Report - Post Operating License Stage" are still valid.

Based on the above, there will not be a significant change in the types or increase in the amounts of effluents released offsite for the remaining decommissioning activities.

(iii) There is no significant increase in individual or cumulative occupational exposure.

As stated above, the District submitted "Supplement to Rancho Seco Environmental Report -

Post Operating License Stage" in conjunction with the submittal of the original Rancho Seco Decominissioning Plan. This environmental report compated Rancho Seco decommissioning attributes to those identified in NUREG-0586.

The "Supplement to Rancho Seco Environmental Report - Post Operating License Stage" contained the following conclusions:

The District will maintain annual occupational radiation exposure to individuals as low as reasonably achievable (ALARA). These exposures will be below historical levels for the operating phase of the plant.

The District expects to maintain exposure to onsite workers and the offsite public as a result of waste transportation well below the levels projected by NUREG-0586.

LTP Chapter 8 provides an updated assessment of the environmental effects of decommissioning Rancho Seco. The updated assessment also determined that the environmental effects fiom decommissioning Rancho Seco are minimal and there are no adverse effects outside the bounds of NUREG-0586 or the associated Supplement 1.

Additionally, the conclusions contained in the "Supplement to Rancho Seco Environmental Report - Post Operating License Stage" are still valid.

Based on the above, there is no significant increase in individual or cumulative occupational exposure due to decommissioning Rancho Seco. .

Attachment 3 Revised Facility Operating License

(3) Confirmatory Order The movement of nuclear fuel into the Reactor Building is prohibited without prior NRC approval.

(Amendment 132 - 09/27/05)

(4) License Termination Plan (LTP)

NRC License Amendment No. 133 approves the License Termination Plan.

In addition to the criteria specified in 10 CFR 50.59 and 10 CFR 50.82(a)(6), a change to the LTP requires prior NRC approval if the change:

(a) Increases the probabilitv of making a Type I decision error above the level stated in the LTP (Ib) Increases the radionuclide-specific derived concentration guideline levels (DCGL) and.related minimum detectable concentrations (c) Increases the radioactivity level., relative to the applicable DCGL, at which investigation occurs (d) Changes the statistical test applied other than the Sign Test or Wilcoxon Rank Sum Test.

Re-classification of survey areas from a less to a more restrictive classification Je.p., fiom a Class 3 to a Class 2 area) may be done without prior NRC

~iotification:however, re-classification to a less restrictive classification (e.~.,

Class 1 to Class 2 area) will require NRC notification at least 14 days prior to implementation.

D. This license is subject to the following additional condition for the protection of the environment:

If harmful effects or evidence of irreversible damage are detected by the monitoring programs included in the Rancho Seco Quality Manual, the Applicant will provide an analysis of the problem and a proposed course of action to alleviate the problem.

E. This license is effective as of the date of issuance and shall expire at midnight, October 11,2008.

FOR THE ATOMIC ENERGY COMMISSION IS/ROGER BOYD for A. Giambusso, Deputy Director for Reactor Projects Directorate of Licensing Date of Issuance:

August 16,1974

Attachment:

Appendix A - Technical Specifications (Amendment 120 - 10/13/92)

Orders for Modification of License Deleted (Amendment 132 09/27/05)

Attachment 4 License Termination Plan