Submittal of Revision to Nuclear Station Security Plans, Training and Qualification Plans, and Safeguards Contingency Plans| ML091210080 |
| Person / Time |
|---|
| Site: |
Dresden, Peach Bottom, Oyster Creek, Byron, Three Mile Island, Braidwood, Limerick, Clinton, Quad Cities, LaSalle, 05000101 |
|---|
| Issue date: |
04/27/2009 |
|---|
| From: |
Simpson P
Exelon Infrastructure Services, Exelon Nuclear |
|---|
| To: |
Document Control Desk, Office of Nuclear Reactor Regulation |
|---|
| References |
|---|
| RS-09-052 |
| Download: ML091210080 (15) |
|
Similar Documents at Dresden, Peach Bottom, Oyster Creek, Byron, Three Mile Island, Braidwood, Limerick, Clinton, Quad Cities, LaSalle, 05000101 |
|---|
Category:Letter type:RS
MONTHYEARRS-24-004, Proposed Alternative to the Distribution Requirements of ASME Code Table IWC-2411-1 for the Steam Generators2024-01-11011 January 2024
Proposed Alternative to the Distribution Requirements of ASME Code Table IWC-2411-1 for the Steam Generators
RS-24-001, Response to Request for Additional Information Regarding Relief Request I5R-26, Inservice Inspection Program Relief Request Regarding Examination Coverage for the Fifth Inservice Inspection Interval2024-01-0303 January 2024
Response to Request for Additional Information Regarding Relief Request I5R-26, Inservice Inspection Program Relief Request Regarding Examination Coverage for the Fifth Inservice Inspection Interval
RS-23-128, Response to Request for Additional Information for the Emergency License Amendment Request Increase Technical Specifications Completion Time in TS 3.8.1.B.4 from 7 Days to 30 Days2023-12-15015 December 2023
Response to Request for Additional Information for the Emergency License Amendment Request Increase Technical Specifications Completion Time in TS 3.8.1.B.4 from 7 Days to 30 Days
RS-23-123, Emergency License Amendment Request - Increase Technical Specifications Completion Time in TS 3.8.1.B.4 from 7 Days to 30 Days2023-12-13013 December 2023
Emergency License Amendment Request - Increase Technical Specifications Completion Time in TS 3.8.1.B.4 from 7 Days to 30 Days
RS-23-121, Sixth Ten-Year Interval Inservice Testing Program2023-11-30030 November 2023
Sixth Ten-Year Interval Inservice Testing Program
RS-23-104, Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation2023-11-17017 November 2023
Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation
RS-23-120, Supplemental Information Letter for Part 73 Exemption Request - Responses to Request for Confirmatory Information2023-11-10010 November 2023
Supplemental Information Letter for Part 73 Exemption Request - Responses to Request for Confirmatory Information
RS-23-119, Supplemental Information Letter for Part 73 Exemption Request - Responses to Request for Confirmatory Information2023-11-10010 November 2023
Supplemental Information Letter for Part 73 Exemption Request - Responses to Request for Confirmatory Information
RS-23-118, Supplemental Information Letter for Part 73 Exemption Request - Responses to Request for Confirmatory Information2023-11-10010 November 2023
Supplemental Information Letter for Part 73 Exemption Request - Responses to Request for Confirmatory Information
RS-23-117, Supplemental Information Letter for Part 73 Exemption Request - Responses to Request for Confirmatory Information2023-11-10010 November 2023
Supplemental Information Letter for Part 73 Exemption Request - Responses to Request for Confirmatory Information
RS-23-107, Relief Request I5R-22, Inservice Inspection Program Relief Request Regarding Examination Coverage for the Fifth Inservice Inspection Interval2023-11-0808 November 2023
Relief Request I5R-22, Inservice Inspection Program Relief Request Regarding Examination Coverage for the Fifth Inservice Inspection Interval
RS-23-114, Proposed Alternative for Examination of Pressurizer Circumferential and Longitudinal Shell-to-Head Welds and Nozzle-to-Vessel Welds2023-11-0101 November 2023
Proposed Alternative for Examination of Pressurizer Circumferential and Longitudinal Shell-to-Head Welds and Nozzle-to-Vessel Welds
RS-23-113, Submittal of Updated Final Safety Analysis Report (Ufsar), Revision 17 and Fire Protection Report (Fpr), Revision 262023-10-20020 October 2023
Submittal of Updated Final Safety Analysis Report (Ufsar), Revision 17 and Fire Protection Report (Fpr), Revision 26
RS-23-102, Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation2023-10-16016 October 2023
Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation
RS-23-100, Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation2023-10-13013 October 2023
Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation
RS-23-103, Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation2023-10-13013 October 2023
Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation
RS-23-097, Constellation Energy Generation, LLC, Advisement of Leadership Changes and Submittal of Updated Standard Practice Procedures Plans2023-10-12012 October 2023
Constellation Energy Generation, LLC, Advisement of Leadership Changes and Submittal of Updated Standard Practice Procedures Plans
RS-23-108, Proposed Alternative for Examinations of Examination Categories B-B, B-D, and C-A Steam Generator Pressure Retaining Welds and Full Penetration Welded Nozzles2023-10-11011 October 2023
Proposed Alternative for Examinations of Examination Categories B-B, B-D, and C-A Steam Generator Pressure Retaining Welds and Full Penetration Welded Nozzles
RS-23-105, Proposed Alternative for Examinations of Examination Category C-B Steam Generator Nozzle-to-Shell Welds and Nozzle Inside Radius Sections2023-10-10010 October 2023
Proposed Alternative for Examinations of Examination Category C-B Steam Generator Nozzle-to-Shell Welds and Nozzle Inside Radius Sections
RS-23-093, License Amendment to Braidwood Station, Units 1 and 2, and Byron Station, Units 1 and 2, Technical Specifications 3.7.15, Spent Fuel Pool Boron Concentration, 3.7.16, Spent Fuel.2023-09-29029 September 2023
License Amendment to Braidwood Station, Units 1 and 2, and Byron Station, Units 1 and 2, Technical Specifications 3.7.15, Spent Fuel Pool Boron Concentration, 3.7.16, Spent Fuel.
RS-23-094, Relief Request I4R-24, Alternative for Post-Peening Reexamination Frequency for Reactor Pressure Vessel Head Penetration Nozzle Number 752023-09-29029 September 2023
Relief Request I4R-24, Alternative for Post-Peening Reexamination Frequency for Reactor Pressure Vessel Head Penetration Nozzle Number 75
RS-23-091, Relief Request I4R-25, Alternative Requirements for Reactor Pressure Vessel Inservice Inspection Intervals2023-09-26026 September 2023
Relief Request I4R-25, Alternative Requirements for Reactor Pressure Vessel Inservice Inspection Intervals
RS-23-090, Annual Report of Emergency Core Cooling System Evaluation Model Changes and Errors for Clinton Power Station2023-09-0707 September 2023
Annual Report of Emergency Core Cooling System Evaluation Model Changes and Errors for Clinton Power Station
RS-23-089, Sixth Ten-Year Interval Inservice Testing Program2023-09-0505 September 2023
Sixth Ten-Year Interval Inservice Testing Program
RS-23-071, Application to Adopt TSTF-564, Safety Limit MCPR2023-08-30030 August 2023
Application to Adopt TSTF-564, Safety Limit MCPR
RS-23-080, Constellation Energy Generation, LLC, Application to Revise Technical Specifications to Adopt TSTF-264-A, Revision 0, 3.3.9 and 3.3.10 - Delete Flux Monitors Specific Overlap Requirement SRs2023-08-30030 August 2023
Constellation Energy Generation, LLC, Application to Revise Technical Specifications to Adopt TSTF-264-A, Revision 0, 3.3.9 and 3.3.10 - Delete Flux Monitors Specific Overlap Requirement SRs
RS-23-086, Relief Request I5R-26, Inservice Inspection Program Relief Request Regarding Examination Coverage for the Fifth Inservice Inspection Interval2023-08-28028 August 2023
Relief Request I5R-26, Inservice Inspection Program Relief Request Regarding Examination Coverage for the Fifth Inservice Inspection Interval
RS-23-081, Request for License Amendment to Revise Technical Specifications Related to Reactor Water Cleanup Isolation Instrumentation2023-08-21021 August 2023
Request for License Amendment to Revise Technical Specifications Related to Reactor Water Cleanup Isolation Instrumentation
RS-23-087, Revision to Approved Alternatives Associated with the Use of the BWRVIP Guidelines in Lieu of Specific ASME Code Requirements on Reactor2023-08-0404 August 2023
Revision to Approved Alternatives Associated with the Use of the BWRVIP Guidelines in Lieu of Specific ASME Code Requirements on Reactor
RS-23-085, Supplemental Information Related to Request for Partial Site Release2023-08-0303 August 2023
Supplemental Information Related to Request for Partial Site Release
RS-23-084, Response to Request for Additional Information Regarding the Application to Revise Design Basis to Allow Use of Plastic Section Properties in Lower Downcomer Braces Analysis2023-07-24024 July 2023
Response to Request for Additional Information Regarding the Application to Revise Design Basis to Allow Use of Plastic Section Properties in Lower Downcomer Braces Analysis
RS-23-083, Withdrawal - Proposed Alternatives Related to the Steam Generators2023-06-27027 June 2023
Withdrawal - Proposed Alternatives Related to the Steam Generators
RS-23-078, Supplement to License Amendment Request to Revise Technical Specification 3.1.4, Control Rod Scram Times2023-06-16016 June 2023
Supplement to License Amendment Request to Revise Technical Specification 3.1.4, Control Rod Scram Times
RS-23-077, Response to NRC Regulatory Issue Summary 2023-01, Preparation and Scheduling of Operator Licensing Examinations2023-06-16016 June 2023
Response to NRC Regulatory Issue Summary 2023-01, Preparation and Scheduling of Operator Licensing Examinations
RS-23-074, Supplement to Application for License Amendment to Braidwood Station, Units 1 and 2, Technical Specification 3.7.9, Ultimate Heat Sink2023-06-0909 June 2023
Supplement to Application for License Amendment to Braidwood Station, Units 1 and 2, Technical Specification 3.7.9, Ultimate Heat Sink
RS-23-060, Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems, and Components for Nuclear Power Reactors2023-06-0808 June 2023
Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems, and Components for Nuclear Power Reactors
RS-23-059, License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b2023-06-0808 June 2023
License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b
RS-23-073, Request for Partial Site Release2023-06-0707 June 2023
Request for Partial Site Release
RS-23-075, Application for Technical Specification Improvement to Extend the Completion Time for Condition B of Technical Specification 3.5.1, Accumulators, Using the Consolidated Line Item Improvement Process2023-06-0707 June 2023
Application for Technical Specification Improvement to Extend the Completion Time for Condition B of Technical Specification 3.5.1, Accumulators, Using the Consolidated Line Item Improvement Process
RS-23-042, Application to Revise Technical Specifications to Adopt TSTF-580, Provide Exception from Entering Mode 4 with No Operable RHR Shutdown Cooling2023-05-25025 May 2023
Application to Revise Technical Specifications to Adopt TSTF-580, Provide Exception from Entering Mode 4 with No Operable RHR Shutdown Cooling
RS-23-050, Supplement to Application to Revise Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam Generator Tube.2023-05-22022 May 2023
Supplement to Application to Revise Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam Generator Tube.
RS-23-070, Supplement to License Amendment Request Regarding Transition to GNF3 Fuel2023-05-16016 May 2023
Supplement to License Amendment Request Regarding Transition to GNF3 Fuel
RS-22-067, 10 CFR 50.46 Annual Report2023-05-0404 May 2023
10 CFR 50.46 Annual Report
RS-23-068, Response to Request for Additional Information for Quad Cities Relief Request I6R-11, Proposed Alternatives for a Temper Bead Weld Repair of the Mating Surfaces of the Reactor Pressure Vessel Head and Shell2023-04-28028 April 2023
Response to Request for Additional Information for Quad Cities Relief Request I6R-11, Proposed Alternatives for a Temper Bead Weld Repair of the Mating Surfaces of the Reactor Pressure Vessel Head and Shell
RS-23-058, Submittal of Sixth Inservice Inspection Interval Relief Request I6R-11 Proposed Alternatives for a Temper Bead Weld Repair of the Mating Surfaces of the Reactor Pressure Vessel Head and Shell Flanges2023-04-24024 April 2023
Submittal of Sixth Inservice Inspection Interval Relief Request I6R-11 Proposed Alternatives for a Temper Bead Weld Repair of the Mating Surfaces of the Reactor Pressure Vessel Head and Shell Flanges
RS-23-056, Response to Request for Additional Information to Braidwood Station, Unit 1, and Byron Station, Unit 1, for Steam Generator License Renewal Response to Commitment 102023-04-20020 April 2023
Response to Request for Additional Information to Braidwood Station, Unit 1, and Byron Station, Unit 1, for Steam Generator License Renewal Response to Commitment 10
RS-23-057, Supplement to License Amendment Request Regarding Transition to GNF3 Fuel2023-04-17017 April 2023
Supplement to License Amendment Request Regarding Transition to GNF3 Fuel
RS-23-055, Annual 10 CFR 50.46 Report of Emergency Core Cooling System Evaluation Model Changes and Errors2023-04-10010 April 2023
Annual 10 CFR 50.46 Report of Emergency Core Cooling System Evaluation Model Changes and Errors
RS-23-052, License Amendment to Braidwood Station, Units 1 and 2, Technical Specification 3.7.9, Ultimate Heat Sink2023-03-24024 March 2023
License Amendment to Braidwood Station, Units 1 and 2, Technical Specification 3.7.9, Ultimate Heat Sink
RS-23-049, Constellation Energy Generation, LLC, Report on Status of Decommissioning Funding for Reactors and Independent Spent Fuel Storage Installations2023-03-23023 March 2023
Constellation Energy Generation, LLC, Report on Status of Decommissioning Funding for Reactors and Independent Spent Fuel Storage Installations
2024-01-03
[Table view] |
Text
SAF[EGUf.U~DS f.NFORMAT~ON Exelon Nuclear www.exeloncorp.com 4300 Winfield Road Nuclear Warrenville,lL 60555 RS-09-052 10 CFR 50.54(p)(2) 10 CFR 50.4(b)(4)
April 27, 2009 U. S. Nuclear Regulatory Commission ATrN: Document Control Desk Washington, DC' 20555-0001 Braidwood Station, Units 1 and 2 FaCility Operating License Nos. NPF-72 and NPF-77 NRC Docket Nos. STN 50-456 and 50-457 Byron Station, Units 1 and 2 .
Facility Operating License Nos. NPF-37 and NPF-66 NRC Docket Nos. 50-454, 50-455 and 72-68 Clinton Power Station, Units 1 Facility Operating License No. NPF-62 NRC Docket No. 50-461 Dresden Nuclear Power Station, Units 1, 2, and 3 Facility Operating License No. DPR-2 Renewed Facility Operating License Nos. DPR-19 and DPR-25 NRC Docket Nos.50-010, 50-237. 50-249 and 72-37 laSalle County Station, Units 1 and 2 Facility Operating License Nos.' NPF-11 and NPF-18 NRC Docket Nos. 50-373, 50-374 and 72-70 "Limerick Generating Station, Units 1 and 2 Facility Operating License Nos. NPF-39 and NPF-85 NRC Docket Nos. 50-352, 50-353, and 72-65 Oyster Creek Generating Station, Unit 1 Facility Operating License No. DPR-16 Renewed NRC Docket No. 50-219 and 72-15 IJ M-~:>b I SAFEGUARDS INFORMATION (J{fA S C)O I ATTACHMENTS 1 11 CQNTAUI SAFEGU,6RDS INFORMATION Sf/09 f.-J.t:..P-..
UPON SEPARATION THIS PAGE IS DECONTROLLED
- SAFEGUARDS INFORMATION April 27, 2009 U. S. NuclearRegulatory Commission Page 2 Peach Bottom Atomic Power Station, Units'1, 2, and 3 Facility Operating License No. DPR-12 Renewed Facility Operating License Nos. DPR-44 and DPR-56 NRC Docket Nos. 50-171. 50-277and 72-29 Quad Cities Nuclear Power Station, Units 1 and 2 Facility Operating License Nos. OPR-29 and OPR-30 Renewed NRC Docket Nos. 50-254, 50-265 and 72-53 Three Mile Island Station, Unit 1 Facility Operating License No. DPR-50 NRC Docket 1\10. 50-289
Subject:
Exelon Revision to Nuclear Station Security Plans, Training and Qualification Plans, and Safeguards Contingency Plans
Reference:
Letter from Richard P. Correia (NRC) to Chris Earls (NEI), Nuclear Energy Institute 03-01, "Nuclear Power Plant Access Authorization Program,"
Revision 2, dated December 11 , 2008 In accordance with the provision of 10 CFR 50.54, "Conditions of licenses," paragraph (p)(2), Exelon Generation Company, LLC (EGC) is submitting changes to the Nuclear Station Security Plans, Training and Qualification Plans, and Safeguards Contingency Plans for the stations listed above. Changes to these documents were implemented on March 30, 2009. In accordance with 10 CFR 50.54(p)(2), EGC is submitting these changes within two months of implementation (Le., no later than May 29, 2009).
The Nuclear Station Security Plans, Training and Qualification Plans, and Safeguards Contingency Plans have been revised to incorporate generic references to NEI 03-01, Revision 2. In the referenced letter, the NRC concluded NEI 03-01 is an acceptable method to comply with the requirements of subpart C of 10 CFR 26.
In addition, Revision 6 of the Byron Station Security Plan, Training and Qualification Plan, and Safeguards Contingency Plan, incorporated changes to reflect the addition of an independent spent fuel storage installation within the Protected Area. The implementation date for this revision was March 30, 2009.
EGC has concluded that the changes do not decrease the safeguards effectiveness of the Nuclear Station Security Plans, Training and Qualification Plans, and Safeguards Contingency Plans.
SAFEGUARDS INFORMATION GOr1 .~ L ATTACHMENTS 1 11 CONTAIN SAFIiGUARgS INFORMATION 7 £15/'0 ~
UPON SEPARATION TMIS PAGE IS QI5CONTROlUm
SAFEGUARDS INFORMATION April 27, 2009 U. S. Nuclear Regulatory Commission Page 3 Attachments 1 through 11 contain Safeguards Information. Therefore, EGC requests that this information be withheld from public disclosure in accord~nce with 10 CFR 2.390, "Public inspections, exemptions, requests for withholding," paragraph (d)(1), and 10 CFR 73.21, "Requirements for the protection of safeguards information," paragraph (b)(1 )(i).
The NRC Regional Administrators are receiving only the attachments for stations within the respective NRC Region consistent with 10 CFR 50.4.
Should you have any questions concerning this letter, please contact Mr. Benjamin E.
Brooks at (630) 657-2931.
wr.
Respectfully,
\
Patrick R. Simpson Manager - Licensing Attachments:
- 1. Braidwood Station Security Plan, Training and Qualification Plan, and Safeguards Contingency Plan, Revision 7 (Contains Safeguards Information)
- 2. Byron Station Security Plan, Training and Qualification Plan, and Safeguards Contingency plan, Revision 6 (Contains Safeguards Information)
- 3. Byron Station Security Plan, Training and Qualification Plan, and Safeguards Contingency Plan, Revision 7 (Contains Safeguards Information)
- 4. Clinton Power Station Security Plan, Training and Qualification Plan, and Safeguards Contingency Plan, Revision 6 (Contains Safeguards Information)
- 5. Dresden Nuclear Power Station Security Plan, Training and Qualification Plan, and Safeguards Contingency Plan, Revision 7 (Contains Safeguards Information)
- 6. LaSalle County Station Security Plan, Training and Qualification Plan, and Safeguards Contingency Plan, Revision 9 (Contains Safeguards Information)
- 7. Limerick Generating Station Security Plan, Training and Qualification Plan, and Safeguards Contingency Plan, Revision 6 (Contains Safeguards Information)
. SAFEGUARDS INFORMATION ATTACHMENTS 1 11 CONTAIN SAFiQUARDS INpORMATJON UPON SEPARATION THIS PAQi IS DeCONTROLLED
SAFEGUARDS INFORMATION April 27, 2009 U. S. Nuclear Regulatory Commission Page 4
- 8. Oyster Creek Generating Station Security Plan, Training and Qualification Plan, and Safeguards Contingency Plan, Revision 8 (Contains Safeguards Information)
- 9. Peach Bottom Atomic Power Station Security Plan, Training and Qualification Plan, and Safeguards Contingency Plan, Revision 6 (Contains Safeguards Information)
- 10. Quad Cities Nuclear Power Security Plan, Training and Qualification Plan, and Safeguards Contingency Plan, Revision 6 (Contains Safeguards Information)
- 11. Three Mile Island Station Security Plan, Training and Qualification Plan, and Safeguards Contingency Plan, Revision 8 (Contains Safeguards Information) cc: Regional Administrator - NRC Region III Regional Administrator- NRC Region I SAFEGUARDS INFORMATION ATTACHMliNTS 1 11 CONTAIN SAl&liQUARgS INFORMATION UPON SEPARATION TIolIS PAS&: IS 9ECONTnOLLED
SAFEGUARDS INFORMATION ATTACHMENT 1 Braidwood Station Security Plan, Training and Qualification Plan, and Safeguards Contingency Plan, Revision 7 (Contains Safeguards Information)
SAFEGUARDS INFORMATION 9~ v~
ATTACHMENTS 1 11 CONTAIN SAFEGUARDS INfORM
. UPON SEPARATION THIS PAGE IS DECONTROLLED ATJO~ -~,
SAFEGUARDS INFORMATION ATTACHMENT 2 Byron Station Security Plan, Training and Qualification Plan, and Safeguards Contingency Plan, Revision 6 (Contains Safeguards Information)
SAFEGUARDS INFORMATION AlTAC""M&:NTS 1 11 CONTAIN SAFEGUARDS INFORMATION
- UPON 8IiPP,RATIQN T""18 PAtSli 18 QIiCONTROLbED
SAFEGUARDS I~FORMATION ATTACHMENT 3 Byron Station Security Plan, Training and Qualification Plan, and Safeguards Contingency Plan, Revision 7 (Contains Safeguards Information)
SAFEGUARDS INFORMATION ATTACHMENTS 1 11 CONTAIN SAFEGUARDS INFORMATION UPON SEPARATION THIS.PAGE IS DECONTROLLED
- SAFEGUARDS INFORMATION ATTACHMENT 4 Clinton Power Station Security Plan, Training and Qualification Plan, and Safeguards Contingency Plan, Revision 6 (Contains Safeguards Information)
SAFEGUARDS INFORMA"FION ~11 S/s/o7 .
ArrACHMENTS 1 . 11 CONTAIN SAFEGUARDS INFORMATION UPON SEPARATION TillS PAGE IS DECONTROLLED
SAFEGUARDS INFORMATION ATTACHMENT 5
. \ .
Dresden Nuclear Power Station Security Plan, Training and Qualification Plan, and Safeguards Contingency Plan, Revision 7 (Contains Safeguards Information)
SAFEGUARDS INFORMATION ATTACMMENTS 1 11 CONTAIN SAIiiEGUARDS INIiiORMATION UPON SEPARATION TillS PAGE IS DECONTROLLED
SAFEGUARDS INFORMATION ATTACHMENT 6 LaSalle County Station Security Plan, Training and Qualification Plan, and Safeguards Contingency Plan, Revision 9 (Contains Safeguards Information)
SAFEGUARDS INFORMATION* (ftfA S/s/o?
ATTACHMENTS 1 11 CONTAIN SAFEGUARDS INFORMATION UPON SEPARATION THIS PAGE IS E>EGONTROllED
. SAFEGUARDS INFORMATION ATTACHMENT 7 Limerick Generating Station Security Plan, Training and Qualification Plan, and Safeguards Contingency Plan, Revision 6 (Contains Safeguards Information)
SAFEGUARDS INFORMATION ATTACliMENTS 1
- 11 CONTAIN SAFEGUARDS INFORMATION
. UPON SEPARATION THIS PA8E IS DECONTROLLED
- SAFEGUARDS INFORMATION' ATTACHMENT 8 Oyster Creek Generating Station Security Plan, Training and Qualification. Plan, and Safeguards Contingency Plan, Revision 8 (Contains Safeguards Information)
SAFEGUARDS INFORMATION
- AITACt-fMENTS 1
- 11 CONTAIN SAFEGUARDS INFORMATION UPON SEPARATION TI liS PAGE IS BECONTROLLED
SAFEGUARDS INFORMATION ATTACHMENT 9 Peach Bottom Atomic Power Station Security Plan, Training and Qualification Plan, an9 Safeguards Contingency Plan, Revision 6 (Contains Safeguards Information)
. SAFEGUARDS INFORMATION Gt£~ S/s/o ~
ATTAOIIMENTS 1 11 OONTAIN SAFEGUARDS INFORMATION
. UPON SEPARATION TillS PAGE IS DEOONTROLLED
SAFEGUARDS INFORMATION
.ATTACHMENT 10 Quad Cities Nuclear Power Security Plan, Training and Qualification Plan, and Safeguards Contingency Plan, Revision 6 (Contains Safeguards Information)
\ . SAFEGUARDS INFORMATION ATTACHMEN"FS 1 11 CONTAIN SAFEGUARDS INFORMATION
. UPON SEPARATION TillS PAGE IS ,DECONTROLLED
. SAFEGUARDS INFORMATION ATTACHMENT 11 Three Mile Island Station Security Plan, Training and Qualification Plan, and Safeguards Contingency Plan, Revision 8 (Contains Safeguards Information) .
. SAFEGUARDS INFORMATION ytJ/1 S/slo7
. ATTACHMENTS 1 11 CONTAIN SAFEGUARDS INFORMATION
. UPON SEPARATION TillS PAGE IS DECONTROLLED