RA-14-057, License Amendment Request Regarding the Cyber Security Plan Implementation Schedule for Milestone 8: Difference between revisions

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| issue date = 08/29/2014
| issue date = 08/29/2014
| title = License Amendment Request Regarding the Cyber Security Plan Implementation Schedule for Milestone 8
| title = License Amendment Request Regarding the Cyber Security Plan Implementation Schedule for Milestone 8
| author name = Gudger D T
| author name = Gudger D
| author affiliation = Exelon Generation Co, LLC
| author affiliation = Exelon Generation Co, LLC
| addressee name =  
| addressee name =  
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| page count = 27
| page count = 27
| project =  
| project =  
| stage = Other
| stage = Request
}}
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=Text=
=Text=
{{#Wiki_filter:200 Exelon Way Exelon Generation Kennett Square. PA 19348 www.exeloncorp.corn ATTACHMENTS 1, 3, AND 4 TRANSMITTED HEREWITH CONTAIN SECURITY-RELATED INFORMATION-WITHHOLD UNDER 10 CFR 2.390 RS-14-217 RA-14-057 TMl-14-096 August 29, 2014 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, D.C. 20555-0001 Braidwood Station, Units 1 and 2 Facility Operating License Nos. NPF-72 and NPF-77 USNRC Docket Nos. STN 50-456 and STN 50-457 Byron Station, Units 1 and 2 Facility Operating License Nos. NPF-37 and NPF-66 USNRC Docket Nos. STN 50-454 and STN 50-455 Calvert Cliffs Nuclear Power Plant, Units 1 and 2 Renewed Facility Operating License Nos. DPR-53 and DPR-69 USNRC Docket Nos. 50-317 and 50-318 Clinton Power Station, Unit 1 Facility Operating License No. NPF-62 USNRC Docket No. 50-461 Dresden Nuclear Power Station, Units 2 and 3 Renewed Facility Operating License Nos. DPR-19 and DPR-25 USNRC Docket Nos. 50-237 and 50-249 LaSalle County Station, Units 1 and 2 Facility Operating License Nos. NPF-11 and NPF-18 USNRC Docket Nos. 50-373 and 50-374 Limerick Generating Station, Units 1 and 2 Facility Operating License Nos. NPF-39 and NPF-85 USNRC Docket Nos. 50-352 and 50-353 Nine Mile Point Nuclear Station, Units 1 and 2 Renewed Facility Operating License Nos. DPR-63 and NPF-69 USN RC Docket Nos. 50-220 and 50-410 Oyster Creek Nuclear Generating Station Renewed Facility Operating License No. DPR-16 USNRC Docket No. 50-219 10 CFR 50.90 ATTACHMENTS 1, 3, AND 4 TRANSMITTED HEREWITH CONTAIN SECURITY-RELATED INFORMATION-WITHHOLD UNDER 10 CFR 2.390 U.S. Nuclear Regulatory Commission August 29, 2014 Page2  
{{#Wiki_filter:Exelon Generation                                          200 Exelon Way Kennett Square. PA 19348 www.exeloncorp.corn ATTACHMENTS 1, 3, AND 4 TRANSMITTED HEREWITH CONTAIN SECURITY-RELATED INFORMATION-WITHHOLD UNDER 10 CFR 2.390 10 CFR 50.90 RS-14-217 RA-14-057 TMl-14-096 August 29, 2014 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, D.C. 20555-0001 Braidwood Station, Units 1 and 2 Facility Operating License Nos. NPF-72 and NPF-77 USNRC Docket Nos. STN 50-456 and STN 50-457 Byron Station, Units 1 and 2 Facility Operating License Nos. NPF-37 and NPF-66 USNRC Docket Nos. STN 50-454 and STN 50-455 Calvert Cliffs Nuclear Power Plant, Units 1 and 2 Renewed Facility Operating License Nos. DPR-53 and DPR-69 USNRC Docket Nos. 50-317 and 50-318 Clinton Power Station, Unit 1 Facility Operating License No. NPF-62 USNRC Docket No. 50-461 Dresden Nuclear Power Station, Units 2 and 3 Renewed Facility Operating License Nos. DPR-19 and DPR-25 USNRC Docket Nos. 50-237 and 50-249 LaSalle County Station, Units 1 and 2 Facility Operating License Nos. NPF-11 and NPF-18 USNRC Docket Nos. 50-373 and 50-374 Limerick Generating Station, Units 1 and 2 Facility Operating License Nos. NPF-39 and NPF-85 USNRC Docket Nos. 50-352 and 50-353 Nine Mile Point Nuclear Station, Units 1 and 2 Renewed Facility Operating License Nos. DPR-63 and NPF-69 USN RC Docket Nos. 50-220 and 50-410 Oyster Creek Nuclear Generating Station Renewed Facility Operating License No. DPR-16 USNRC Docket No. 50-219 ATTACHMENTS 1, 3, AND 4 TRANSMITTED HEREWITH CONTAIN SECURITY-RELATED INFORMATION-WITHHOLD UNDER 10 CFR 2.390
 
U.S. Nuclear Regulatory Commission August 29, 2014 Page2 Peach Bottom Atomic Power Station, Units 2 and 3 Renewed Facility Operating License Nos. DPR-44 and DPR-56 USNRC Docket Nos. 50-277 and 50-278 Quad Cities Nuclear Power Station, Units 1 and 2 Renewed Facility Operating License Nos. DPR-29 and DPR-30 USNRC Docket Nos. 50-254 and 50-265 R. E. Ginna Nuclear Power Plant, Unit 1 Renewed Facility Operating License No. DPR-18 USNRC Docket No. 50-244 Three Mile Island Nuclear Station, Unit 1 Renewed Facility Operating License No. DPR-50 USNRC Docket No. 50-289


==Subject:==
==Subject:==
Peach Bottom Atomic Power Station, Units 2 and 3 Renewed Facility Operating License Nos. DPR-44 and DPR-56 USNRC Docket Nos. 50-277 and 50-278 Quad Cities Nuclear Power Station, Units 1 and 2 Renewed Facility Operating License Nos. DPR-29 and DPR-30 USNRC Docket Nos. 50-254 and 50-265 R. E. Ginna Nuclear Power Plant, Unit 1 Renewed Facility Operating License No. DPR-18 USNRC Docket No. 50-244 Three Mile Island Nuclear Station, Unit 1 Renewed Facility Operating License No. DPR-50 USNRC Docket No. 50-289 License Amendment Request regarding the Cyber Security Plan Implementation Schedule for Milestone 8  
License Amendment Request regarding the Cyber Security Plan Implementation Schedule for Milestone 8


==References:==
==References:==
: 1. Letter from J. S. Wiebe (U.S. Nuclear Regulatory Commission) to M. J. Pacilio, (Exelon Nuclear), "Issuance of Amendments Regarding the Exelon Cyber Security Plan," dated August 10, 2011 2. Letter from D. Pickett (U.S. Nuclear Regulatory Commission) to M. G. Korsnick, (Constellation Energy Nuclear Group, LLC), "Issuance of Amendments to Renewed Facility Operating Licenses (FOLs) Re: Cyber Security Plans," dated August 19, 2011 3. Memorandum from R. Felts, (U.S. Nuclear Regulatory Commission) to B. Westreich (U.S. Nuclear Regulatory Commission), "Review Criteria for Title 10 of the Code of Federal Regulations Part 73.54, Cyber Security Implementation Schedule Milestone 8 License Amendment Requests," dated October 24, 2013 In accordance with the provisions of 1 O CFR 50.4 and 1 O CFR 50.90, Exelon Generation Company, LLC (EGC) is submitting a request for an amendment to the Facility Operating Licenses (FOLs) listed above. This proposed amendment requests U.S. Nuclear Regulatory Commission (USNRC) approval of a change to the Cyber Security Plan (CSP) Milestone 8 full implementation date (hereinafter referred to as MS8), as set forth in CSP Implementation Schedule as approved by the USNRC in Reference Letters 1 and 2. Attachment 1 provides an evaluation of the proposed change that includes the criteria detailed in the USN RC memorandum, "Review Criteria for Title 1 O of the Code of Federal Regulations Part 73.54, Cyber Security Implementation Schedule Milestone 8 License Amendment Requests," dated October 24, 2013 (Reference 3).
: 1.     Letter from J. S. Wiebe (U.S. Nuclear Regulatory Commission) to M. J.
U.S. Nuclear Regulatory Commission August 29, 2014 Page 3 This amendment request includes the existing FOLs marked up to show the proposed changes (Attachment 2), the revised Cyber Security Commitments (Attachment 3), and the associated revised CSP Implementation Schedule (Attachment 4). These proposed changes have been reviewed and approved by each site's Plant Operations Review Committee and approved by the Nuclear Safety Review Board in accordance with the requirements of the EGC Quality Assurance Program. EGC considers Attachments 1, 3, and 4 to contain security-related information (SRI) which could reasonably be expected to be useful to potential adversaries.
Pacilio, (Exelon Nuclear), "Issuance of Amendments Regarding the Exelon Cyber Security Plan," dated August 10, 2011
Therefore, EGC requests that Attachments 1, 3, and 4 be withheld from public disclosure in accordance with 10 CFR 2.390. EGC requests approval of the proposed amendment by August 29, 2015. Once approved, the amendment shall be implemented within 60 days. Implementation of MS8 of the CSP will occur in accordance with the proposed commitments contained in Attachment  
: 2.     Letter from D. Pickett (U.S. Nuclear Regulatory Commission) to M. G.
: 3. In accordance with 10 CFR 50.91, a copy of this amendment request, with attachments, is being provided to the designated State Officials.
Korsnick, (Constellation Energy Nuclear Group, LLC), "Issuance of Amendments to Renewed Facility Operating Licenses (FOLs) Re: Cyber Security Plans," dated August 19, 2011
: 3.     Memorandum from R. Felts, (U.S. Nuclear Regulatory Commission) to B. Westreich (U.S. Nuclear Regulatory Commission), "Review Criteria for Title 10 of the Code of Federal Regulations Part 73.54, Cyber Security Implementation Schedule Milestone 8 License Amendment Requests,"
dated October 24, 2013 In accordance with the provisions of 10 CFR 50.4 and 10 CFR 50.90, Exelon Generation Company, LLC (EGC) is submitting a request for an amendment to the Facility Operating Licenses (FOLs) listed above. This proposed amendment requests U.S. Nuclear Regulatory Commission (USNRC) approval of a change to the Cyber Security Plan (CSP) Milestone 8 full implementation date (hereinafter referred to as MS8), as set forth in CSP Implementation Schedule as approved by the USNRC in Reference Letters 1 and 2. provides an evaluation of the proposed change that includes the criteria detailed in the USN RC memorandum, "Review Criteria for Title 1O of the Code of Federal Regulations Part 73.54, Cyber Security Implementation Schedule Milestone 8 License Amendment Requests," dated October 24, 2013 (Reference 3).
 
U.S. Nuclear Regulatory Commission August 29, 2014 Page 3 This amendment request includes the existing FOLs marked up to show the proposed changes (Attachment 2), the revised Cyber Security Commitments (Attachment 3), and the associated revised CSP Implementation Schedule (Attachment 4).
These proposed changes have been reviewed and approved by each site's Plant Operations Review Committee and approved by the Nuclear Safety Review Board in accordance with the requirements of the EGC Quality Assurance Program.
EGC considers Attachments 1, 3, and 4 to contain security-related information (SRI) which could reasonably be expected to be useful to potential adversaries. Therefore, EGC requests that Attachments 1, 3, and 4 be withheld from public disclosure in accordance with 10 CFR 2.390.
EGC requests approval of the proposed amendment by August 29, 2015. Once approved, the amendment shall be implemented within 60 days. Implementation of MS8 of the CSP will occur in accordance with the proposed commitments contained in Attachment 3.
In accordance with 10 CFR 50.91, a copy of this amendment request, with attachments, is being provided to the designated State Officials.
If you should have any questions regarding this submittal, please contact Ms. Wendy Croft at 610-765-5726.
If you should have any questions regarding this submittal, please contact Ms. Wendy Croft at 610-765-5726.
I declare under penalty of perjury that the foregoing is true and correct. Executed on the 29th day of August 2014. Respef}fully, ,/ ql!c-J-r David T. Gudger . . Manager -Licensing and Regulatory Affairs Exelon Generation Company, LLC Attachment 1 -Evaluation of Proposed Change Attachment 2 -Proposed Facility Operating License Changes (Mark-Up)  -Revised Cyber Security Commitment  -Revised Cyber Security Plan Implementation Schedule cc: USNRC Region I, Regional Administrator USNRC Region Ill, Regional Administrator USNRC Project Manager, NRA -Braidwood Station USNRC Project Manager, NRA -Byron Station USNRC Project Manager, NRA -
I declare under penalty of perjury that the foregoing is true and correct. Executed on the 29th day of August 2014.
Respef}fully,              ,/
ql!c-J-r ~~
David T. Gudger . .                  ~
Manager - Licensing and Regulatory Affairs Exelon Generation Company, LLC  -  Evaluation of Proposed Change  -  Proposed Facility Operating License Changes (Mark-Up)  -  Revised Cyber Security Commitment  -  Revised Cyber Security Plan Implementation Schedule cc:    USNRC  Region  I, Regional Administrator USNRC  Region  Ill, Regional Administrator USNRC  Project Manager, NRA - Braidwood Station USNRC  Project Manager, NRA - Byron Station USNRC  Project Manager, NRA - Calvert Cliffs Nuclear Power Plant USNRC  Project Manager, NRA - Clinton Power Station USNRC  Project Manager, NRA - Dresden Nuclear Power Station USNRC  Project Manager, NRA - LaSalle County Station USNRC  Project Manager, NRA - Limerick Generating Station USNRC  Project Manager, NRA - Nine Mile Point Nuclear Station
 
U.S. Nuclear Regulatory Commission August 29, 2014 Page4 USNRC Project Manager, NRR - Oyster Creek Nuclear Generating Station
Peach Bottom Atomic Power Station, Unit 3 Renewed Facility Opera,tiw Licen!l,eNo DPR..56
Peach Bottom Atomic Power Station, Unit 3 Renewed Facility Opera,tiw Licen!l,eNo DPR..56
* lvJ r::xelon uenerat1on Company, pursuant to the Act and 10 CFR Parts 30 and 70. to possess, but not to separate, such byproduct and special nuclear material as may be produced by, operation of the facility, and such CJass B and Class C low-level, radioactive waste as may be produced by the operation of Limerick Generating Station, Units 1 and 2. C. This renewed license shafl be deemed to contain and is subject to the conditions specified in the following Commission regulations in 10 CFR Chapter I: Part 20, Section 30.34 of Part 30, Sectlon40.41 of Part 40, Section 50.54 of Part 50, and Section 70.32 of Part 70; all applicable provisions pfthe Act and the rules, regulations, and orders of the Commission now or hereafter in effect; and is subject to the additional conditions specified below: (1) Maximum Power Level Exelon Generation Company is authorized to operate the Peach Bottom Atomic Power Station, Unit No. 3, at steady state reactor core power levels not in excess of 3514 megawatts thermal. (2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 292, are hereby incorporated in the license. Exelon Generation Company shall operate the facility in accordance with the Technical Specifications.  
* lvJ         r::xelon uenerat1on Company, pursuant to the Act and 10 CFR Parts 30 and 70. to possess, but not to separate, such byproduct and special nuclear material as may be produced by, operation of the facility, and such CJass B and Class C low-level, radioactive waste as may be produced by the operation of Limerick Generating Station, Units 1 and 2.
(3) Pbvsieal Protection Exelon Generation Company shall fully implement and maintain in effect all provisions of the Commission-approved' physical security, training and qui:ilification, and safeguards contirigency plans including amendments made 'pu05uant tO provisions of thel\Ais°'llaneous Amendments and Search Requirements revisions to 10 CFR13.55 (51 FR 27817 and 27822), and the authority of 10 CFR 50;90 and 10 CFR 50.54(p).
C.       This renewed license shafl be deemed to contain and is subject to the conditions specified in the following Commission regulations in 10 CFR Chapter I: Part 20, Section 30.34 of Part 30, Sectlon40.41 of Part 40, Section 50.54 of Part 50, and Section 70.32 of Part 70; all applicable provisions pfthe Act and the rules, regulations, and orders of the Commission now or hereafter in effect; and is subject to the additional conditions specified below:
The comt)ined ,set of plans 2 , subr'riitted by letter dat.ed May 17, 2006, is enti11ed: "Peach Bottom Atomic Power St$tlon Security.
(1)         Maximum Power Level Exelon Generation Company is authorized to operate the Peach Bottom Atomic Power Station, Unit No. 3, at steady state reactor core power levels not in excess of 3514 megawatts thermal.
Plan, Training ancfQuafification Pla.n, Safeguards Contingency Plan, andlndependent Spent Fuel Storage Installation Security Program, Rev1sion 3." The set contains Safeguards Information protected under 10 CFR 73.21. Exelon Generation Company shall fully implement and' maintain in effect all provisions of the Commission-approved cyber security plan (CSP), including changes made pursuant to the authority of 10 CFR 50.90 and 10 CFR 50.54(p).
(2)         Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 292, are hereby incorporated in the license. Exelon Generation Company shall operate the facility in accordance with the Technical Specifications.
The Exelon Generation Company CSP was approved by License Amendment No. 283-/1:
(3)         Pbvsieal Protection Exelon Generation Company shall fully implement and maintain in effect all provisions of the Commission-approved' physical security, training and qui:ilification, and safeguards contirigency plans including amendments made 'pu05uant tO provisions of thel\Ais°'llaneous Amendments and Search Requirements revisions to 10 CFR13.55 (51 FR 27817 and 27822), and the authority of 10 CFR 50;90 and 10 CFR 50.54(p). The comt)ined ,set of plans2, subr'riitted by letter dat.ed May 17, 2006, is enti11ed: "Peach Bottom Atomic Power St$tlon Security. Plan, Training ancfQuafification Pla.n, Safeguards Contingency Plan, andlndependent Spent Fuel Storage Installation Security Program, Rev1sion 3." The set contains Safeguards Information protected under 10 CFR 73.21.
1 Licensed power level was revised by Amendment No. 250, dated November 22, 2002, and will be implemented following the 14th refueling outage currently scheduled for Fall 2003. 2 The training and Qualification Plan and Safeguards Contingency Plan are Appendices to the Security Plan Renewed License No .. DPR-56 Revised by letter dated October 28, 2094 Revised by letter dated November 5, 2004 Re\lfsed by letter dated May 29, 2007 Amendment No. 292 o .........
Exelon Generation Company shall fully implement and' maintain in effect all provisions of the Commission-approved cyber security plan (CSP),
'l Am. 251 06/20/13 B. c. Attachment 2 -Proposed Facility Operating License Changes (Mark-Up)
including changes made pursuant to the authority of 10 CFR 50.90 and 10 CFR 50.54(p). The Exelon Generation Company CSP was approved by License Amendment No. 283-/1:
Quad Cities Nuclear Power Station, Unit 1 Renewed Facility Operating License No. DPR-29 Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 251, are hereby incorporated into the renewed operating license. The licensee shall operate the facility in accordance with the Technical Specifications.
LJL..1a-=_n-=_d~m-=_-o_d-=_i=fi_1e-=_d-=_b~y-=_,.....,L_i,.....c_e-=_n-=_s-=_e-=_A~m-=_e-=_n-=_d-=_m-=_e-=_n-=_t-=_N~o-._-_-_--.-1
The licensee shall maintain the commitments made in response to the March 14, 1983, NUREG-0737 Order, subject to the following provision:
    ~~~~~~~~~~
The licensee may make changes to commitments made in response to the March 14, 1983, NUREG-0737 Order without prior approval of the Commission as long as the change would be permitted without NRG approval, pursuant to the requirements of 10 CFR 50.59. Consistent with this regulation, if the change results in an Unreviewed Safety Question, a license amendment shall be submitted to the NRG staff for review and approval prior to implementation of the change. D. Equalizer Valve Restriction NRG Ur E. 05/16/07 Am. 249 08/10/11 F. Three of the four valves in the equalizer piping between the recirculation loops shall be closed at all times during reactor operation with one bypass valve open to allow for thermal expansion of water. The licensee shall fully implement and maintain in effect all provisions of the Commission-approved physical security, training and qualification, and safeguards contingency plans including amendments made pursuant to provisions of the Miscellaneous Amendments and Search Requirements revisions to 10 CFR 73.55 (51 FR 27817 and 27822), and the authority of 10 CFR 50.90 and 10 CFR 50.54(p).
1 Licensed power level was revised by Amendment No. 250, dated November 22, 2002, and will be implemented following the 14th refueling outage currently scheduled for Fall 2003.
The combined sets of plans1, which contain Safeguards Information protected under 10 CFR 73.21, is entitled: "Quad Cities Nuclear Power Station Security Plan, Training and Qualification Plan, and Safeguards Contingency Plan, Revision 2," submitted by letter dated May 17, 2006. Exelon Generation Company shall fully implement and maintain in effect all provisions of the Commission-approved cyber security plan (CSP), including changes made pursuant to the authority of 10 CFR 50.90 and 10 CFR 50.54(p).
2 The training and Qualification Plan and Safeguards Contingency Plan are Appendices to the Security Plan Renewed License No.. DPR-56 Revised by letter dated October 28, 2094 Revised by letter dated November 5, 2004 Re\lfsed by letter dated May 29, 2007 Amendment No. 292 o ......... 'l
The Exelon Generation Company CSP was approved by License Amendment No. 249:-tjand modified by License Amendment No. . I The licensee shall implement and maintain in effect all provisions of the approved fire protection program as described in the Updated Final Safety Analysis Report for the facility and as approved in the Safety Evaluation Reports dated July 27, 1979, with supplements dated November 5, 1980, and 1 The Training and Qualification Plan and Safeguards Contingency Plan are Appendices to the Security Plan. Renewed License No. DPR-29 Amendment No. 264 Am. 246 06/20/13 B. C. Attachment 2 -Proposed Facility Operating License Changes (Mark-Up)
 
Quad Cities Nuclear Power Station, Unit 2 Renewed Facility Operating License No. DPR-30 Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 246, are hereby incorporated into this renewed operating license. The licensee shall operate the facility in accordance with the Technical Specifications.
Attachment 2 - Proposed Facility Operating License Changes (Mark-Up)
The license shall maintain the commitments made in response to the March 14, 1983, NUREG-0737 Order, subject to the following provision:
Quad Cities Nuclear Power Station, Unit 1 Renewed Facility Operating License No. DPR-29 B.      Technical Specifications Am. 251              The Technical Specifications contained in Appendix A, as revised through 06/20/13              Amendment No. 251, are hereby incorporated into the renewed operating license. The licensee shall operate the facility in accordance with the Technical Specifications.
The licensee may make changes to commitments made in response to the March 14, 1983, NUREG-0737 Order without prior approval of the Commission as long as the change would be permitted without NRC approval, pursuant to the requirements of 10 CFR 50.59. Consistent with this regulation, if the change results in an Unreviewed Safety Question, a license amendment shall be submitted to the NRC staff for review and approval prior to implementation of the change. D. Equalizer Valve Restriction NRC Ltr E. 05/16/07 Am. 244 08/10/11 F. Three of the four valves in the equalizer piping between the recirculation loops shall be closed at all times during reactor operation with one bypass valve open to allow for thermal expansion of water. The licensee shall fully implement and maintain in effect all provisions of the Commission-approved physical security, training and qualification, and safeguards contingency plans including amendments made pursuant to provisions of the Miscellaneous Amendments and Search Requirements revisions to 10 CFR 73.55 (51 FR 27817 and 27822), and the authority of 10 CFR 50.90 and 10 CFR 50.54(p).
: c.      The licensee shall maintain the commitments made in response to the March 14, 1983, NUREG-0737 Order, subject to the following provision:
The combined set of plans 1 , which contain Safeguards Information protected under 10 CFR 73.21, is entitled: "Quad Cities Nuclear Power Station Security Plan, Training and Qualification Plan, and Safeguards Contingency Plan, Revision 2," submitted by letter dated May 17, 2006. Exelon Generation Company shall fully implement and maintain in effect all provisions of the Commission-approved cyber security plan (CSP), including changes made pursuant to the authority of 10 CFR 50.90 and 10 CFR 50.54(p).
The licensee may make changes to commitments made in response to the March 14, 1983, NUREG-0737 Order without prior approval of the Commission as long as the change would be permitted without NRG approval, pursuant to the requirements of 10 CFR 50.59. Consistent with this regulation, if the change results in an Unreviewed Safety Question, a license amendment shall be submitted to the NRG staff for review and approval prior to implementation of the change.
The Exelon Generation Company CSP was approved by License Amendment No. 244.,. tjand modified by License Amendment No. . I The licensee shall implement and maintain in effect all provisions of the approved fire protection program as described in the Updated Final Safety Analysis Report for the facility and as approved in the Safety Evaluation Reports dated July 27, 1979 with supplements dated 1 The Training and Qualification Plan and Safeguards Contingency Plan are Appendices to the Security Plan.
D.     Equalizer Valve Restriction Three of the four valves in the equalizer piping between the recirculation loops shall be closed at all times during reactor operation with one bypass valve open to allow for thermal expansion of water.
* Renewed License No. DPR-30 Amendment No. 24-S   -Proposed Facility Operating License Changes (Mark-Up)
NRG Ur    E.      The licensee shall fully implement and maintain in effect all provisions of the 05/16/07          Commission-approved physical security, training and qualification, and safeguards contingency plans including amendments made pursuant to provisions of the Miscellaneous Amendments and Search Requirements revisions to 10 CFR 73.55 (51 FR 27817 and 27822), and the authority of 10 CFR 50.90 and 10 CFR 50.54(p). The combined sets of plans1, which contain Safeguards Information protected under 10 CFR 73.21, is entitled: "Quad Cities Nuclear Power Station Security Plan, Training and Qualification Plan, and Safeguards Contingency Plan, Revision 2," submitted by letter dated May 17, 2006.
R. E. Ginna Nuclear Power Plant, Unit 1 Renewed Facility Operating License No. DPR-18 Nuclear Power Plant Security Plan, Training and Qualification Plan, and Safeguards Contingency Plan," submitted by letter dated May 15, 2006. Exelon Generation shall fully implement and maintain in effect all provisions of the Commission-approved cyber security plan (CSP), including changes made pursuant to the authority of 10 CFR 50.90 and 10 CFR 50.54(p).
Am. 249            Exelon Generation Company shall fully implement and maintain in effect all 08/10/11          provisions of the Commission-approved cyber security plan (CSP), including changes made pursuant to the authority of 10 CFR 50.90 and 10 CFR 50.54(p).
The licensee's CSP was approved by License Amendment No. 113-: and modified by License Amendment No. . F. The p a e ina a e y na ys1s epo supp ement, submitted pursuant to 10 CFR 54.21 (d), describes certain future activities to be completed prior to the period of extended operation.
The Exelon Generation Company CSP was approved by License Amendment No. 249:- tjand modified by License Amendment No.                         . I F.      The licensee shall implement and maintain in effect all provisions of the approved fire protection program as described in the Updated Final Safety Analysis Report for the facility and as approved in the Safety Evaluation Reports dated July 27, 1979, with supplements dated November 5, 1980, and 1 The Training and Qualification Plan and Safeguards Contingency Plan are Appendices to the Security Plan.
Ginna LLC shall complete these activities no later than September 18, 2009, and shall notify the Commission in writing when implementation of these activities is complete and can be verified by NRC inspection.
Renewed License No. DPR-29 Amendment No. 264
The Updated Final Safety Analysis Report supplement, as revised, shall be included in the next scheduled update to the Updated Final Safety Analysis Report required by 10 CFR 50.71 (e)(4) following issuance of this renewed license. Until that update is complete, the licensee may make changes to the programs and activities described in the supplement without prior Commission approval, provided that the licensee evaluates each such change pursuant to the criteria set forth in 10 CFR 50.59 and otherwise complies with the requirements in that section. G. All capsules in the reactor vessel that are removed and tested must meet the test procedures and reporting requirements of ASTM E 185-82 to the extent practicable for the configuration of the specimens in the capsule. Any changes to the capsule withdrawal schedule, including spare capsules, must be approved by the NRC prior to implementation.
 
Any capsules placed in storage must be maintained for future insertion, unless approved by the NRC. H. This renewed license is effective as of the date of issuance and shall expire at midnight on September 18, 2029. FOR THE NUCLEAR REGULATORY COMMISSION Original Signed By J. E. Dyer, Director Office of Nuclear Reactor Regulation  
Attachment 2 - Proposed Facility Operating License Changes (Mark-Up)
Quad Cities Nuclear Power Station, Unit 2 Renewed Facility Operating License No. DPR-30 B.      Technical Specifications Am. 246            The Technical Specifications contained in Appendix A, as revised through 06/20/13          Amendment No. 246, are hereby incorporated into this renewed operating license. The licensee shall operate the facility in accordance with the Technical Specifications.
C.      The license shall maintain the commitments made in response to the March 14, 1983, NUREG-0737 Order, subject to the following provision:
The licensee may make changes to commitments made in response to the March 14, 1983, NUREG-0737 Order without prior approval of the Commission as long as the change would be permitted without NRC approval, pursuant to the requirements of 10 CFR 50.59. Consistent with this regulation, if the change results in an Unreviewed Safety Question, a license amendment shall be submitted to the NRC staff for review and approval prior to implementation of the change.
D.     Equalizer Valve Restriction Three of the four valves in the equalizer piping between the recirculation loops shall be closed at all times during reactor operation with one bypass valve open to allow for thermal expansion of water.
NRC Ltr    E.      The licensee shall fully implement and maintain in effect all provisions of the 05/16/07          Commission-approved physical security, training and qualification, and safeguards contingency plans including amendments made pursuant to provisions of the Miscellaneous Amendments and Search Requirements revisions to 10 CFR 73.55 (51 FR 27817 and 27822), and the authority of 10 CFR 50.90 and 10 CFR 50.54(p). The combined set of plans 1, which contain Safeguards Information protected under 10 CFR 73.21, is entitled: "Quad Cities Nuclear Power Station Security Plan, Training and Qualification Plan, and Safeguards Contingency Plan, Revision 2," submitted by letter dated May 17, 2006.
Am. 244            Exelon Generation Company shall fully implement and maintain in effect all 08/10/11          provisions of the Commission-approved cyber security plan (CSP), including changes made pursuant to the authority of 10 CFR 50.90 and 10 CFR 50.54(p).
The Exelon Generation Company CSP was approved by License Amendment No. 244.,. tjand modified by License Amendment No.                         . I F.      The licensee shall implement and maintain in effect all provisions of the approved fire protection program as described in the Updated Final Safety Analysis Report for the facility and as approved in the Safety Evaluation Reports dated July 27, 1979 with supplements dated 1 The Training and Qualification Plan and Safeguards Contingency Plan are Appendices to the Security Plan.
* Renewed License No. DPR-30 Amendment No. 24-S
 
Attachment 2 - Proposed Facility Operating License Changes (Mark-Up)
R. E. Ginna Nuclear Power Plant, Unit 1 Renewed Facility Operating License No. DPR-18 Nuclear Power Plant Security Plan, Training and Qualification Plan, and Safeguards Contingency Plan," submitted by letter dated May 15, 2006.
Exelon Generation shall fully implement and maintain in effect all provisions of the Commission-approved cyber security plan (CSP), including changes made pursuant to the authority of 10 CFR 50.90 and 10 CFR 50.54(p). The licensee's CSP was approved by License Amendment No. 113-:
and modified by License Amendment No.                   .
F. The p a e         ina a e y na ys1s epo supp ement, submitted pursuant to 10 CFR 54.21 (d), describes certain future activities to be completed prior to the period of extended operation. Ginna LLC shall complete these activities no later than September 18, 2009, and shall notify the Commission in writing when implementation of these activities is complete and can be verified by NRC inspection.
The Updated Final Safety Analysis Report supplement, as revised, shall be included in the next scheduled update to the Updated Final Safety Analysis Report required by 10 CFR 50.71 (e)(4) following issuance of this renewed license. Until that update is complete, the licensee may make changes to the programs and activities described in the supplement without prior Commission approval, provided that the licensee evaluates each such change pursuant to the criteria set forth in 10 CFR 50.59 and otherwise complies with the requirements in that section.
G. All capsules in the reactor vessel that are removed and tested must meet the test procedures and reporting requirements of ASTM E 185-82 to the extent practicable for the configuration of the specimens in the capsule. Any changes to the capsule withdrawal schedule, including spare capsules, must be approved by the NRC prior to implementation. Any capsules placed in storage must be maintained for future insertion, unless approved by the NRC.
H. This renewed license is effective as of the date of issuance and shall expire at midnight on September 18, 2029.
FOR THE NUCLEAR REGULATORY COMMISSION Original Signed By J. E. Dyer, Director Office of Nuclear Reactor Regulation


==Attachment:==
==Attachment:==
Appendix A- Technical Specifications Date of Issuance: May 19, 2004 Amendment No. 446- I


Appendix A-Technical Specifications Date of Issuance:
Attachment 2 - Proposed Facility Operating License Changes (Mark-Up)
May 19, 2004 Amendment No. 446-I    -Proposed Facility Operating License Changes (Mark-Up)
Three Mile Island Nuclear Station, Unit 1 Renewed Facility Operating License No. DPR-50 (2)   Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 281 are hereby incorporated in the license. The Exelon Generation Company shall operate the facility in accordance with the Technical Specifications.
Three Mile Island Nuclear Station, Unit 1 Renewed Facility Operating License No. DPR-50 (2) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 281 are hereby incorporated in the license. The Exelon Generation Company shall operate the facility in accordance with the Technical Specifications.  
(3)   Physical Protection Exelon Generation Company shall fully implement and maintain in effect all provisions of the Commission-approved physical security, training and qualification, and safeguards contingency plans including amendments made pursuant to provisions of the Miscellaneous Amendments and Search Requirements revisions to 10 CFR 73.55 (51 FR 27817 and 27822), and the authority of 10 CFR 50.90 and 10 CFR 50.54(p). The combined set of plans1, submitted by letter dated May 17, 2006, is entitled: "Three Mile Island Nuclear Station Security Plan, Training and Qualification Plan, and Safeguards Contingency Plan, Revision 3." The set contains Safeguards Information protected under 10 CFR 73.21.
(3) Physical Protection Exelon Generation Company shall fully implement and maintain in effect all provisions of the Commission-approved physical security, training and qualification, and safeguards contingency plans including amendments made pursuant to provisions of the Miscellaneous Amendments and Search Requirements revisions to 10 CFR 73.55 (51 FR 27817 and 27822), and the authority of 10 CFR 50.90 and 10 CFR 50.54(p).
Exelon Generation Company shall fully implement and maintain in effect all provisions of the Commission-approved cyber security plan (CSP), including changes made pursuant to the authority of 10 CFR 50.90 and 10 CFR 50.54(p). The Exelon Generation Company CSP was approved by License Amendment No.
The combined set of plans1, submitted by letter dated May 17, 2006, is entitled: "Three Mile Island Nuclear Station Security Plan, Training and Qualification Plan, and Safeguards Contingency Plan, Revision 3." The set contains Safeguards Information protected under 1 O CFR 73.21. Exelon Generation Company shall fully implement and maintain in effect all provisions of the Commission-approved cyber security plan (CSP), including changes made pursuant to the authority of 10 CFR 50.90 and 10 CFR 50.54(p).
and modified by License Amendment No.
The Exelon Generation Company CSP was approved by License Amendment No. (4) Fire Protection and modified by License Amendment No. Exelon Generation Company shall implement and maintain in effect all provisions of the Fire Protection Program as described in the Updated FSAR for TMl-1. Changes may be made to the Fire Protection Program without prior approval by the Commission only if those changes would not adversely affect the ability to achieve and maintain safe shutdown in the event of a fire. Temporary changes to specific fire protection features which may be necessary to accomplish maintenance or modifications are acceptable provided that interim compensate measures are implemented.  
(4)  Fire Protection Exelon Generation Company shall implement and maintain in effect all provisions of the Fire Protection Program as described in the Updated FSAR for TMl-1.
(5) The licensee shall implement a secondary water chemistry monitoring program to inhibit steam generator tube degradation.
Changes may be made to the Fire Protection Program without prior approval by the Commission only if those changes would not adversely affect the ability to achieve and maintain safe shutdown in the event of a fire. Temporary changes to specific fire protection features which may be necessary to accomplish maintenance or modifications are acceptable provided that interim compensate measures are implemented.
This program shall include: a. Identification of a sampling schedule for the critical parameters and control points for these parameters;  
(5)   The licensee shall implement a secondary water chemistry monitoring program to inhibit steam generator tube degradation. This program shall include:
: b. Identification of the procedures used to measure the values of the critical parameters;  
: a. Identification of a sampling schedule for the critical parameters and control points for these parameters;
: c. Identification of process sampling points; d. Procedure for the recording and management of data; 1 The Training and Qualification Plan and Safeguards Contingency Plan are Appendices to the Security Plan. Amendment No.-284 Renewed Operating License No. DPR-50}}
: b. Identification of the procedures used to measure the values of the critical parameters;
: c. Identification of process sampling points;
: d. Procedure for the recording and management of data; 1 The Training and Qualification Plan and Safeguards Contingency Plan are Appendices to the Security Plan.
Amendment No.-284 Renewed Operating License No. DPR-50}}

Latest revision as of 07:07, 11 November 2019

License Amendment Request Regarding the Cyber Security Plan Implementation Schedule for Milestone 8
ML14241A526
Person / Time
Site: Calvert Cliffs, Dresden, Peach Bottom, Nine Mile Point, Oyster Creek, Byron, Three Mile Island, Braidwood, Limerick, Ginna, Clinton, Quad Cities, LaSalle
Issue date: 08/29/2014
From: David Gudger
Exelon Generation Co
To:
Document Control Desk, Office of Nuclear Reactor Regulation
Shared Package
ML14241A524 List:
References
RA-14-057, RS-14-217, TMI-14-096
Download: ML14241A526 (27)


Text

Exelon Generation 200 Exelon Way Kennett Square. PA 19348 www.exeloncorp.corn ATTACHMENTS 1, 3, AND 4 TRANSMITTED HEREWITH CONTAIN SECURITY-RELATED INFORMATION-WITHHOLD UNDER 10 CFR 2.390 10 CFR 50.90 RS-14-217 RA-14-057 TMl-14-096 August 29, 2014 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, D.C. 20555-0001 Braidwood Station, Units 1 and 2 Facility Operating License Nos. NPF-72 and NPF-77 USNRC Docket Nos. STN 50-456 and STN 50-457 Byron Station, Units 1 and 2 Facility Operating License Nos. NPF-37 and NPF-66 USNRC Docket Nos. STN 50-454 and STN 50-455 Calvert Cliffs Nuclear Power Plant, Units 1 and 2 Renewed Facility Operating License Nos. DPR-53 and DPR-69 USNRC Docket Nos. 50-317 and 50-318 Clinton Power Station, Unit 1 Facility Operating License No. NPF-62 USNRC Docket No. 50-461 Dresden Nuclear Power Station, Units 2 and 3 Renewed Facility Operating License Nos. DPR-19 and DPR-25 USNRC Docket Nos. 50-237 and 50-249 LaSalle County Station, Units 1 and 2 Facility Operating License Nos. NPF-11 and NPF-18 USNRC Docket Nos. 50-373 and 50-374 Limerick Generating Station, Units 1 and 2 Facility Operating License Nos. NPF-39 and NPF-85 USNRC Docket Nos. 50-352 and 50-353 Nine Mile Point Nuclear Station, Units 1 and 2 Renewed Facility Operating License Nos. DPR-63 and NPF-69 USN RC Docket Nos. 50-220 and 50-410 Oyster Creek Nuclear Generating Station Renewed Facility Operating License No. DPR-16 USNRC Docket No. 50-219 ATTACHMENTS 1, 3, AND 4 TRANSMITTED HEREWITH CONTAIN SECURITY-RELATED INFORMATION-WITHHOLD UNDER 10 CFR 2.390

U.S. Nuclear Regulatory Commission August 29, 2014 Page2 Peach Bottom Atomic Power Station, Units 2 and 3 Renewed Facility Operating License Nos. DPR-44 and DPR-56 USNRC Docket Nos. 50-277 and 50-278 Quad Cities Nuclear Power Station, Units 1 and 2 Renewed Facility Operating License Nos. DPR-29 and DPR-30 USNRC Docket Nos. 50-254 and 50-265 R. E. Ginna Nuclear Power Plant, Unit 1 Renewed Facility Operating License No. DPR-18 USNRC Docket No. 50-244 Three Mile Island Nuclear Station, Unit 1 Renewed Facility Operating License No. DPR-50 USNRC Docket No. 50-289

Subject:

License Amendment Request regarding the Cyber Security Plan Implementation Schedule for Milestone 8

References:

1. Letter from J. S. Wiebe (U.S. Nuclear Regulatory Commission) to M. J.

Pacilio, (Exelon Nuclear), "Issuance of Amendments Regarding the Exelon Cyber Security Plan," dated August 10, 2011

2. Letter from D. Pickett (U.S. Nuclear Regulatory Commission) to M. G.

Korsnick, (Constellation Energy Nuclear Group, LLC), "Issuance of Amendments to Renewed Facility Operating Licenses (FOLs) Re: Cyber Security Plans," dated August 19, 2011

3. Memorandum from R. Felts, (U.S. Nuclear Regulatory Commission) to B. Westreich (U.S. Nuclear Regulatory Commission), "Review Criteria for Title 10 of the Code of Federal Regulations Part 73.54, Cyber Security Implementation Schedule Milestone 8 License Amendment Requests,"

dated October 24, 2013 In accordance with the provisions of 10 CFR 50.4 and 10 CFR 50.90, Exelon Generation Company, LLC (EGC) is submitting a request for an amendment to the Facility Operating Licenses (FOLs) listed above. This proposed amendment requests U.S. Nuclear Regulatory Commission (USNRC) approval of a change to the Cyber Security Plan (CSP) Milestone 8 full implementation date (hereinafter referred to as MS8), as set forth in CSP Implementation Schedule as approved by the USNRC in Reference Letters 1 and 2. provides an evaluation of the proposed change that includes the criteria detailed in the USN RC memorandum, "Review Criteria for Title 1O of the Code of Federal Regulations Part 73.54, Cyber Security Implementation Schedule Milestone 8 License Amendment Requests," dated October 24, 2013 (Reference 3).

U.S. Nuclear Regulatory Commission August 29, 2014 Page 3 This amendment request includes the existing FOLs marked up to show the proposed changes (Attachment 2), the revised Cyber Security Commitments (Attachment 3), and the associated revised CSP Implementation Schedule (Attachment 4).

These proposed changes have been reviewed and approved by each site's Plant Operations Review Committee and approved by the Nuclear Safety Review Board in accordance with the requirements of the EGC Quality Assurance Program.

EGC considers Attachments 1, 3, and 4 to contain security-related information (SRI) which could reasonably be expected to be useful to potential adversaries. Therefore, EGC requests that Attachments 1, 3, and 4 be withheld from public disclosure in accordance with 10 CFR 2.390.

EGC requests approval of the proposed amendment by August 29, 2015. Once approved, the amendment shall be implemented within 60 days. Implementation of MS8 of the CSP will occur in accordance with the proposed commitments contained in Attachment 3.

In accordance with 10 CFR 50.91, a copy of this amendment request, with attachments, is being provided to the designated State Officials.

If you should have any questions regarding this submittal, please contact Ms. Wendy Croft at 610-765-5726.

I declare under penalty of perjury that the foregoing is true and correct. Executed on the 29th day of August 2014.

Respef}fully, ,/

ql!c-J-r ~~

David T. Gudger . . ~

Manager - Licensing and Regulatory Affairs Exelon Generation Company, LLC - Evaluation of Proposed Change - Proposed Facility Operating License Changes (Mark-Up) - Revised Cyber Security Commitment - Revised Cyber Security Plan Implementation Schedule cc: USNRC Region I, Regional Administrator USNRC Region Ill, Regional Administrator USNRC Project Manager, NRA - Braidwood Station USNRC Project Manager, NRA - Byron Station USNRC Project Manager, NRA - Calvert Cliffs Nuclear Power Plant USNRC Project Manager, NRA - Clinton Power Station USNRC Project Manager, NRA - Dresden Nuclear Power Station USNRC Project Manager, NRA - LaSalle County Station USNRC Project Manager, NRA - Limerick Generating Station USNRC Project Manager, NRA - Nine Mile Point Nuclear Station

U.S. Nuclear Regulatory Commission August 29, 2014 Page4 USNRC Project Manager, NRR - Oyster Creek Nuclear Generating Station USNRC Project Manager, NRR - Peach Bottom Atomic Power Station USNRC Project Manager, NRR - Quad Cities Nuclear Power Station USNRC Project Manager, NRR - R. E. Ginna Nuclear Power Plant USNRC Project Manager, NRR -Three Mile Island Nuclear Station USNRC Project Manager, NRR - EGC Fleet USNRC Senior Resident Inspector - Braidwood Station USNRC Senior Resident Inspector - Byron Station USNRC Senior Resident Inspector - Calvert Cliffs Nuclear Power Plant USNRC Senior Resident Inspector - Clinton Power Station USNRC Senior Resident Inspector - Dresden Nuclear Power Station USNRC Senior Resident Inspector - LaSalle County Station USNRC Senior Resident Inspector - Limerick Generating Station USNRC Senior Resident Inspector - Nine Mile Point Nuclear Station USNRC Senior Resident Inspector - Oyster Creek Nuclear Generating Station USNRC Senior Resident Inspector - Peach Bottom Atomic Power Station USNRC Senior Resident Inspector - Quad Cities Nuclear Power Station USNRC Senior Resident Inspector - R. E. Ginna Nuclear Power Plant USNRC Senior Resident Inspector -Three Mile Island Nuclear Station R. R. Janati, Commonwealth of Pennsylvania S. Gray, State of Maryland

ATTACHMENT 2 Proposed Facility Operating License Changes (Mark-Up)

Braidwood Station, Units 1 and 2 Facility Operating License Nos. NPF-72 and NPF-77 Byron Station, Units 1 and 2 Facility Operating License Nos. NPF-37 and NPF-66 Clinton Power Station, Unit 1 Facility Operating License No. NPF-62 Calvert Cliffs Nuclear Power Plant, Units 1 and 2 Renewed Facility Operating License Nos. DPR-53 and DPR-69 Dresden Nuclear Power Station, Units 2 and 3 Renewed Facility Operating License Nos. DPR-19 and DPR-25 LaSalle County Station, Units 1 and 2 Facility Operating License Nos. NPF-11 and NPF-18 Limerick Generating Station, Units 1 and 2 Facility Operating License Nos. NPF-39 and NPF-85 Nine Mile Point Nuclear Station, Units 1 and 2 Renewed Facility Operating License Nos. DPR-63 and NPF-69 Oyster Creek Nuclear Generating Station Renewed Facility Operating License No. DPR-16 Peach Bottom Atomic Power Station. Units 2 and 3 Renewed Facility Operating License Nos. DPR-44 and DPR-56 Quad Cities Nuclear Power Station, Units 1 and 2 Renewed Facility Operating License Nos. DPR-29 and DPR-30 R. E. Ginna Nuclear Power Plant. Unit 1 Renewed Facility Operating License No. DPR-18 Three Mile Island Nuclear Station, Unit 1 Renewed Facility Operating License No. DPR-50

Attachment 2 - Proposed Facility Operating License Changes (Mark-Up)

Braidwood Station, Unit 1 Facility Operating License No. NPF-72 F. Exelon Generation Company shall fully implement and maintain in effect all provisions of the Commission-approved physical security, training and qualifications, and safeguards contingency plans including amendments made pursuant to provisions of the Miscellaneous Amendments and Search Requirements revisions to 10 CFR 73.55 (51 FR 27817 and 27822) and the authority of 10 CFR 50.90 and 10 CFR 50.54(p). The combined set of plans\

which contain Safeguards Information protected under 10 CFR 73.21, is entitled:

"Braidwood Station Security Plan, Training and Qualification Plan, and Safeguards Contingency Plan, Revision 3," submitted by letter dated May 17, 2006.

Exelon Generation Company shall fully implement and maintain in effect all provisions of the Commission-approved cyber security plan (CSP), including changes made pursuant to the authority of 10 CFR 50.90 and 10 CFR 50.54{p).

The Exelon Generation Company CSP was approved by License Amendment No. 16&~and modified by License Amendment No. I G. Deleted H. The licensee shall have and maintain financial protection of such type and in such amounts as the Commission shall require in accordance with Section 170 of the Atomic Energy Act of 1954, as amended, to cover public liability claims.

I. This license is effective as of the date of issuance and shall expire at midnight on October 17, 2026.

FOR THE NUCLEAR REGULATORY COMMISSION original signed by:

Thomas E. Murley, Director Office of Nuclear Reactor Regulation Attachments:

1. Appendix A - Technical Specifications (NUREG-1276)
2. Appendix B - Environmental Protection Plan
3. Appendix C - Additional Conditions Date of Issuance: July 2, 1987 1 The training and Qualification Plan and Safeguards Contingency Plan are Appendices to the Security Plan.

Amendment No. 1-63 j

Attachment 2 - Proposed Facility Operating License Changes (Mark-Up)

Braidwood Station, Unit 2 Facility Operating License No. NPF-77 F. Exelon Generation Company shall fully implement and maintain in effect all provisions of the Commission-approved physical security, training and qualifications, and safeguards contingency plans including amendments made pursuant to provisions of the Miscellaneous Amendments and Search Requirements revisions to 10 CFR 73.55 (51 FR 27817 and 27822) and the authority of 10 CFR 50.90 and 10 CFR 50.54(p). The combined set of plans\

which contain Safeguards Information protected under 10 CFR 73.21, is entitled:

"Braidwood Station Security Plan, Training and Qualification Plan, and Safeguards Contingency Plan, Revision 3," submitted by letter dated May 17, 2006.

Exelon Generation Company shall fully implement and maintain in effect all provisions of the Commission-approved cyber security plan (CSP), including changes made pursuant to the authority of 10 CFR 50.90 and 10 CFR 50.54(p).

The Exelon Generation Company CSP was approved by License Amendment No. 168: tjand modified by License Amendment No. I G. Deleted H. The licensee shall have and maintain financial protection of such type and in such amounts as the Commission shall require in accordance with Section 170 of the Atomic Energy Act of 1954, as amended, to cover public liability claims.

I. This license is effective as of the date of issuance and shall expire at midnight on December 18, 2027.

FOR THE NUCLEAR REGULATORY COMMISSION original signed by:

James H. Sniezek, Deputy Director Office of Nuclear Reactor Regulation Attachments:

1. Appendix A - Technical Specifications (NUREG-1276)
2. Appendix B - Environmental Protection Plan
3. Appendix C - Additional Conditions Date of Issuance: May 20, 1988 1 The training and Qualification Plan and Safeguards Contingency Plan are Appendices to the Security Plan.

Amendment No. 4S8

Attachment 2 - Proposed Facility Operating License Changes (Mark-Up)

Byron Station, Unit 1 Facility Operating License No. NPF-37

-4b-(22) Mitigation Strategy License Condition Develop and maintain strategies for addressing large fires and explosions and that include the following key areas:

(a) Fire fighting response strategy with the following elements:

1. Pre-defined coordinated fire response strategy and guidance
2. Assessment of mutual aid fire fighting assets
3. Designated staging areas for equipment and materials
4. Command and control
5. Training of response personnel (b) Operations to mitigate fuel damage considering the following:
1. Protection and use of personnel assets
2. Communications
3. Minimizing fire spread
4. Procedures for implementing integrated fire response strategy
5. Identification of readily-available pre-staged equipment
6. Training on integrated fire response strategy
7. Spent fuel pool mitigation measures (c) Actions to minimize release to include consideration of:
1. Water spray scrubbing
2. Dose to onsite responders D. The facility requires no exemptions from the requirements of 10 CFR Part 50.

E. Exelon Generation Company shall fully implement and maintain in effect all provisions of the Commission-approved physical security, training and qualification, and safeguards contingency plans including amendments made pursuant to provisions of the Miscellaneous Amendments and Search Requirements revisions to 10 CFR 73.55 (51 FR 27817 and 27822), and the authority of 10 CFR 50.90 and 10 CFR 50.54 (p).

The combined set of plans 1 , which contain Safeguards Information protected under 10 CFR 73.21, is entitled: "Byron Nuclear Power Station Security Plan, Training and Qualification Plan, and Safeguards Contingency Plan, Revision 3," submitted by letter dated May 17, 2006.

Exelon Generation Company shall fully implement and maintain in effect all provisions of the Commission-approved cyber security plan (CSP), including changes made pursuant to the authority of 10 CFR 50.90 and 10 CFR 50.54(p). The Exelon Generation Company CSP was approved by License Amendment No. 17~

land modified by License Amendment No. .

1The training and Qualification Plan and Safeguards Contingency Plan are Appendices to the Security Plan

  • Amendment No. 4-+&

Attachment 2 - Proposed Facility Operating License Changes (Mark-Up)

Byron Station, Unit 2 Facility Operating License No. NPF-66

-4b-(c) Actions to minimize release to include consideration of:

1. Water spray scrubbing
2. Dose to onsite responders D. The facility requires no exemptions from the requirements of 10 CFR Part 50.

An exemption was previously granted pursuant to 10 CFR 70.24. The exemption was granted with NRC materials license No. SNM-1916, issued March 4, 1985, and relieved the licensee from the requirement of having a criticality alarm system. Therefore, the licensee is exempted from the criticality alarm system provision of 10 CFR 70.24 so far as this section applies to the storage of fuel assemblies held under this licensee.

E. The licensee shall implement and maintain in effect all provisions of the approved fire protection program as described in the licensee's Fire Protection Report and the licensee's letters dated September 23, 1986, October 23, 1986, November 3, 1986, December 12 and 15, 1986, and January 21, 1987, and as approved in the SER dated February 1982 through Supplement No. 8, subject to the following provision:

The licensee may make changes to the approved fire protection program without prior approval of the Commission only if those changes would not adversely affect the ability to achieve and maintain safe shutdown in the event of a fire.

F. Exelon Generation Company shall fully implement and maintain in effect all provisions of the Commission-approved physical security, training and qualifications, and safeguards contingency plans including amendments made pursuant to provisions of the Miscellaneous Amendments and Search Requirements revisions to 10 CFR 73.55 (51 FR 27817 and 27822), and the authority of 10 CFR 50.90 and 10 CFR 50.54(p). The combined set of plans1, which contain Safeguards Information protected under 10 CFR 73.21, is entitled:

"Byron Nuclear Power Station Security Plan, Training and Qualification Plan, and Safeguards Contingency Plan, Revision 3," submitted by letter dated May 17, 2006. .

Exelon Generation Company shall fully implement and maintain in effect all provisions of the Commission-approved cyber security plan (CSP), including changes made pursuant to the authority of 10 CFR 50.90 and 10 CFR 50.54{p).

The Exelon Generation Company CSP was approved by License Amendment No.175.tjand modified by License Amendment No. I G. Deleted 1The training and Qualification Plan and Safeguards Contingency Plan are Appendices to the Security Plan Amendment No. 4+5

Attachment 2 - Proposed Facility Operating License Changes (Mark-Up)

Calvert Cliffs Nuclear Power Plant, Unit 1 Renewed Facility Operating License No. DPR-53 The licensee shall fully implement and maintain in effect all provisions of the Commission-approved cyber security plan (CSP), including changes made pursuant to the authority of 10 CFR 50.90 and 10 CFR 50.54(p). The licensee's CSP was a roved b License Amendment No. 298.,.

and modified by License Amendment No.

E. The licensee shall implement and maintain in effect all provisions of the approved fire protection program as described in the Updated Final Safety Analysis Report for the facility and as approved in the SER dated September 14, 1979 and Supplements dated October 2, 1980; March 18, 1982; and September 27, 1982; and Exemptions dated August 16, 1982; April 21, 1983; March 15, 1984; August 22, 1990; and April 7, 1999 subject to the following provision: The licensee may make changes to the approved fire protection program without prior approval of the Commission only if those changes would not adversely affect the ability to achieve and maintain safe shutdown in the event of a fire.

F. At the time of the next scheduled update to the FSAR required pursuant to 10 CFR 50.71(e)(4) following the issuance of this renewed license, the licensee shall update the FSAR to include the FSAR supplement submitted pursuant to 10 CFR 54.21(d), as amended and supplemented by the program descriptions in Appendix E to the Safety Evaluation Report, NUREG-1705. Until that FSAR update is complete, the licensee may make changes to the programs described in Appendix E without prior Commission approval, provided that the licensee evaluates each such change pursuant to the criteria set forth in 10 CFR 50.59 and otherwise complies with the requirements in that section.

G. Any future actions listed in Appendix E to the Safety Evaluation Report, NUREG-1705, shall be included in the FSAR. The licensee shall complete these actions by July 31, 2014, except for the volumetric inspections of the control element drive mechanisms, which must be completed no later than 2029 for Unit 1 (Appendix E, Item 65).

H. This renewed license is effective as of the date of issuance and shall expire at midnight on July 31, 2034.

FOR THE NUCLEAR REGULATORY COMMISSION Samuel J. Collins, Director Office of Nuclear Reactor Regulation Attachments:

Appendix A- Technical Specifications Appendix B - Environmental Protection Plan (non-radiological) Technical Specifications Appendix C - Additional Conditions Date of Issuance: March 23, 2000 Amendment No. ~ I

Attachment 2 - Proposed Facility Operating License Changes (Mark-Up)

Calvert Cliffs Nuclear Power Plant, Unit 2 Renewed Facility Operating License No. DPR-69

4. Procedures for implementing integrated fire response strategy
5. Identification of readily available pre-staged equipment
6. Training on integrated fire response strategy
7. Spent fuel pool mitigation measures (c) Actions to minimize release to include consideration of:
1. Water spray scrubbing
2. Dose to onsite responders D. The licensee shall fully implement and maintain in effect all provisions of the Commission-approved physical security, training and qualification, and safeguards contingency plans, including amendments made pursuant to provisions of the Miscellaneous Amendments and Search Requirements revisions to 10 CFR 73.55 (51 FR 27817 and 27822) and the authority of 10 CFR 50.90 and 10 CFR 50.54(p). The combined set of plans, which contain Safeguards Information protected under 10 CFR 73.21, is entitled: "Calvert Cliffs Nuclear Power Plant Security Plan, Training and Qualification Plan, and Safeguards Contingency Plan, Revision 1" submitted dated May 19, 2006.

The licensee shall fully implement and maintain in effect all provisions of the Commission-approved cyber security plan (CSP), including changes made pursuant to the authority of 10 CFR 50.90 and 10 CFR 50.54(p). The licensee's CSP was a roved b License Amendment No. 275-:

and modified by License Amendment No.

E. The a ve 1 s uc ear ower an , , s a implement and maintain in effect all provisions of the approved fire protection program as described in the Updated Final Safety Analysis Report for the facility and as approved in the SER dated September 14, 1979, and Supplements dated October 2, 1980; March 18, 1982; and September 27, 1982; and Exemptions dated August 16, 1982; April 21, 1983; March 15, 1984; August 22, 1990; and April 7, 1999 subject to the following provision: The Calvert Cliffs Nuclear Power Plant, LLC may make changes to the approved fire protection program without prior approval of the Commission only if those changes would not adversely affect the ability to achieve and maintain safe shutdown in the event of a fire.

F. At the time of the next scheduled update to the FSAR required pursuant to 10 CFR 50.71(e)(4) following the issuance of this renewed license, the licensee shall update the FSAR to include the FSAR supplement submitted pursuant to 10 CFR 54.21(d), as amended and supplemented by the program descriptions in Appendix E to the Safety Evaluation Report, NUREG-1705. Until that FSAR update is complete, the licensee may make changes to the programs described in Appendix E without prior Commission approval, provided that the licensee evaluates each such change pursuant to the criteria set forth in 10 CFR 50.59 and otherwise complies with the requirements in that section.

G. Any future actions listed in Appendix E to the Safety Evaluation Report, NUREG-1705, shall be included in the FSAR. The licensee shall complete these actions by August 13, 2016.

Amendment No. ~

Attachment 2 - Proposed Facility Operating License Changes (Mark-Up)

Clinton Power Station, Unit 1 Facility Operating License No. NPF-62

-8 An exemption was previously granted pursuant to 10 CFR 70.24. The exemption was granted with NRC Material License No. SNM-1886, issued November 27, 1985, and relieved the licensee from the requirement of having a criticality alarm system. Exelon Generation Company is hereby exempted from the criticality alarm system provision of 10 CFR 70.24 so far as this section applies to the storage of fuel assemblies held under this license.

These exemptions are authorized by law, will not present an undue risk to the public health and safety, and are consistent with the common defense and security. The exemptions in items (b) and (c) above are granted pursuant to 10 CFR 50.12. With these exemptions, the facility will operate, to the extent authorized herein, in conformity with the application, as amended, the provisions of the Act, and the rules and regulations of the Commission.

E. Exelon Generation Company shall fully implement and maintain in effect all provisions of the Commission-approved physical security, training and qualification, and safeguards contingency plans including amendments made pursuant to provisions of the Miscellaneous Amendments and Search Requirements revisions to 10 CFR 73.55 (51 FR 27817 and 27822), and the authority of 10 CFR 50.90 and 10 CFR 50.54(p). The combined set of plans1 which contain Safeguards Information protected under 10 CFR 73.21, is entitled:

"Clinton Power Station Security Plan, Training and Qualification Plan, and Safeguards Contingency Plan, Revision 2," submitted by letter dated May 17, 2006.

Exelon Generation Company shall fully implement and maintain in effect all provisions of the Commission-approved cyber security plan (CSP), including changes made pursuant to the authority of 10 CFR 50.90 and 10 CFR 50.54(p).

The Exelon Generation Company CSP was approved by License Amendment No. 194.~and modified by License Amendment No. . I F. Exelon Generation Company shall implement and maintain in effect all provisions of the approved fire protection program as described in the Final Safety Analysis Report as amended, for the Clinton Power Station, Unit No.1, and as approved in the Safety Evaluation Report (NUREG-0853) dated February 1982 and Supplement Nos. 1 thru 8 thereto subject to the following provision:

Exelon Generation Company may make changes to the approved fire protection program without prior approval of the Commission only if those changes would not adversely affect the ability to achieve and maintain safe shutdown in the event of a fire.

G. Deleted.

1The Training and Qualification Plan and Safeguards Contingency Plan are Appendices to the Security Plan.

Amendment No. ~

Attachment 2 - Proposed Facility Operating License Changes (Mark-Up)

Dresden Nuclear Power Station, Unit 2 Renewed Facility Operating License No. DPR-19 revisions to 10 CFR 73.55 (51 FR 27817 and 27822), and the authority of 10 CFR 50.90 and 10 CFR 50.54(p). The combined set of plans 1, which contain Safeguards Information protected under 10 CFR 73.21, is entitled: "Dresden Nuclear Power Station Security Plan, Training and Qualification Plan, and Safeguards Contingency Plan, Revision 2," submitted by letter dated May 17, 2006.

Exelon Generation Company shall fully implement and maintain in effect all provisions of the Commission-approved cyber security plan (CSP), including changes made pursuant to the authority of 10 CFR 50.90 and 10 CFR 50.54(p).

The Exelon Generation Company CSP was approved by License Amendment No. 238:-- tjand modified by License Amendment No. I G. Deleted H. The licensee shall have and maintain financial protection of such type and in such amounts as the Commission shall require in accordance with Section 170 of the Atomic Energy Act of 1954, as amended, to cover public liability claims.

I. Updated Final Safety Analysis Report The Exelon Generation Company, LLC Updated Final Safety Analysis Report supplement, submitted pursuant to 10 CFR 54.21 (d), describes certain future activities to be completed prior to the period of extended operation. The Exelon Generation Company, LLC shall complete these activities no later than December 22, 2009, and shall notify the NRC in writing when implementation of these activities is complete and can be verified by NRC inspection.

The Updated Final Safety Analysis Report supplement, as revised, shall be included in the next scheduled update to the Updated Final Safety Analysis Report required by 10 CFR 50.71(e)(4) following issuance of this renewed license. Until that update is complete, Exelon Generation Company, LLC may make changes to the programs and activities described in the supplement without prior Commission approval, provided that Exelon Generation Company, LLC evaluates such change pursuant to the criteria set forth in 10 CFR 50.59 and otherwise complies with the requirements in that section.

J. All capsules in the reactor vessel that are removed and tested must meet the test procedures and reporting requirements of ASTM E 185-82 to the extent practicable for the configuration of the specimens in the capsule. Any changes to the capsule withdrawal schedule, including spare capsules, must be approved by the NRC prior to implementation. All capsules placed in storage must be maintained for future insertion.

1 The Training and Qualification Plan and Safeguards Contingency Plan are Appendices to the Security Plan.

Renewed License No. DPR-19 Amendment No . .z.38

Attachment 2 - Proposed Facility Operating License Changes (Mark-Up)

Dresden Nuclear Power Station, Unit 3 Renewed Facility Operating License No. DPR-25 F. The licensee shall maintain the commitments made in response to the March 14, 1983, NUREG-0737 Order, subject to the following provision:

The licensee may make changes to commitments made in response to the March 14, 1983, NUREG-0737 Order without prior approval of the Commission as long as the change would be permitted without NRC approval, pursuant to the requirements of 10 CFR 50.59. Consistent with this regulation, if the change results in an Unreviewed Safety Question, a license amendment shall be submitted to the NRC staff for review and approval prior to implementation of the change.

G. The licensee shall implement and maintain in effect all provisions of the approved fire protection program as described in the Updated Final Safety Analysis Report for the facility and as approved in the Safety Evaluation Reports dated March 22, 1978 with supplements dated December 2, 1980, and February 12, 1981; January 19, 1983; July 17, 1987; September 28, 1987; and January 5, 1989, subject to the following provision:

The licensee may make changes to the approved fire protection program without prior approval of the Commission only if those changes would not adversely affect the ability to achieve and maintain safe shutdown in the event of a fire.

H. Physical Protection The licensee shall fully implement and*maintain in effect all provisions of the Commission-approved physical security, training and qualification, and safeguards contingency plans including amendments made pursuant to provisions of the Miscellaneous Amendments and Search Requirements revisions to 10 CFR 73.55 (51 FR 27817 and 27822), and the authority of 10 CFR 50.90 and 10 CFR 50.54(p). The combined set of plans 1, which contain Safeguards Information protected under 10 CFR 73.21, is entitled: "Dresden Nuclear Power Station Security Plan, Training and Qualification Plan, and Safeguards Contingency Plan, Revision 2," submitted by letter dated May 17, 2006.

Exelon Generation Company shall fully implement and maintain in effect all provisions of the Commission-approved cyber security plan (CSP), including changes made pursuant to the authority of 10 CFR 50.90 and 10 CFR 50.54(p).

The Exelon Generation Company CSP was approved by License Amendment No. 231~and modified by License Amendment No. . I 1 The Training and Qualification Plan and Safeguards Contingency Plan are Appendices to the Security Plan.

Renewed License No. DPR-25 Amendment No. 234

Attachment 2 - Proposed Facility Operating License Changes (Mark-Up)

LaSalle County Station, Unit 1 Facility Operating License No. NPF-11 Q8/1Q/11 License No. NPF-18 Letter dated (16) Industrial Security (Section 13.6, SER SSER #3, SSER #5) 05/16/07 Exelon Generation Company shall fully implement and maintain in effect all provisions of the Commission-approved physical security, training and qualification, and safeguards contingency plans including amendments made pursuant to provisions of the Miscellaneous Amendments and Search Requirements revisions to 10 CFR 73.55 (51 FR 27817 and 27822), and the authority of 10 CFR 50.90 and 10 CFR 50.54(p). The combined set of plans 1, which contain Safeguards Information protected under 10 CFR 73.21, is entitled: "LaSalle County Station Security Plan, Training and Qualification Plan, and Safeguards Contingency Plan, Revision 5," submitted by letter dated May 17, 2006.

Am.400 Exelon Generation Company shall fully implement and maintain in effect Q8/1Q/11 all provisions of the Commission-approved cyber security plan (CSP),

including changes made pursuant to the authority of 10 CFR 50.90 and 10 CFR 50.54(p). The Exelon Generation Company CSP was approved by License Amendment No. 19~

Am. 181 (17) DELETED and modified by License Amendment No.

08/28/09 Am. 181 (18) DELETED 08/28/09 Am. 181 (19) DELETED 08/28/09 Am. 181 (20) DELETED 08/28/09 Am. 133 (21) Deleted.

03/30/01 Am. 132 (22) EGC shall provide the Director of the Office of Nuclear Reactor 01/12/01 Regulation a copy of any application, at the time it is filed, to transfer (excluding grants of security interests or liens) from EGC to its direct or indirect parent, or to any other affiliated company, facilities for the production, transmission, or distribution of electric energy having a depreciated book valve exceeding ten percent (10%) of EGC's consolidated net utility plant, as recorded on EGC's books of account.

Am. 132 (23) EGC shall have decommissioning trust funds for LaSalle, Unit 2, in the 01/12/01 following minimum amount, when LaSalle, Unit 2, is transferred to EGC:

LaSalle, Unit 2 $221,885,059 1 The Training and Qualification Plan and Safeguards Contingency Plan are Appendices to the Security Plan.

Attachment 2 - Proposed Facility Operating License Changes (Mark-Up)

LaSalle County Station, Unit 2 Facility Operating License No. NPF-18 t>S1107'11 License No. NPF-11 Am.2re Exelon Generation Company shall fully implement and maintain in effect 08/101'11 all provisions of the Commission-approved cyber security plan (CSP),

including changes made pursuant to the authority of 10 CFR 50.90 and 10 CFR 50.54(p). The Exelon Generation Company CSP was approved by License Amendment No. 203-:-

Am. 194 (28) DELETED 08/28/09 Am. 194 (29) DELETED 08/28/09 Am. 194 (30) DELETED and modified by License Amendment No.

08/28/09 Am. 194 (31) DELETED 08/28/09 Am. 194 (32) DELETED 08/28/09 Am. 194 (33) DELETED 08/28/09 Am. 103 (34) DELETED 04/13/95 Am. 194 (35) DELETED 08/28/09 Am. 194 (36) DELETED 08/28/09 Am. 147 (37) DELETED 03/30/01 Am. 146 (38) Exelon Generation Company, LLC shall provide the Director of the Office 01/12/01 of Nuclear Reactor Regulation a copy of any application, at the time it is filed, to transfer (excluding grants of security interests or liens) from Exelon Generation Company, LLC to its direct or indirect parent, or to any other affiliated company, facilities for the production, transmission, or distribution of electric energy having a depreciated book valve exceeding ten percent (10%) of Exelon Generation Company, LLC's consolidated net utility plant, as recorded on Exelon Generation Company, LLC's books of account.

Am. 146 (39) Exelon Generation Company, LLC shall have decommissioning trust 01/12/01 funds, for LaSalle Unit 1, in the following minimum amount, when LaSalle, Unit 1, is transferred to Exelon Generation Company, LLC:

LaSalle, Unit 1 $226,262,522

Attachment 2 - Proposed Facility Operating License Changes (Mark-Up)

Limerick Generating Station, Unit 1 Facility Operating License No. NPF-39 9

life or property or the common defense and security and are otherwise in the public interest. Therefore these exemptions are hereby granted pursuant to 10 CFR 50.12 and 50.47(c). With the granting of these exemptions the facility will operate, to the extent authorized herein, in conformity with the application, as amended, the provision of the Act, and the rules and regulations of the Commission.

E. Exelon Generation Company shall fully implement and maintain in effect all provisions of the Commission-approved physical security, training and qualification, and safeguards contingency plans including amendments made pursuant to provisions of the Miscellaneous Amendments and Search Requirements revisions to 10 CFR 73.55 (51 FR 27817 and 27822), and the authority of 10 CFR 50.90 and 10 CFR 50.54(p). The combined set of plans1, submitted by letter, dated May 17, 2006, is entitled: "Limerick Generating Station Security Plan, Training and Qualification Plan, and Safeguards Contingency Plan, Revision 2." The set contains Safeguards Information protected under 10 CFR 73.21.

Exelon Generation Company shall fully implement and maintain in effect all provisions of the Commission-approved cyber security plan (CSP), including changes made pursuant to the authority of 10 CFR 50.90 and 10 CFR 50.54(p).

The Exelon Generation Company CSP was approved by License Amendment No. 204.- ~and modified by License Amendment No. I F. Deleted G. The licensee shall have and maintain financial protection of such type and in such amounts as the Commission shall require in accordance with Section 170 of the Atomic Energy Act of 1954, as amended, to cover public liability claims.

H. This license is effective as of the date of issuance and shall expire at midnight on October 26, 2024.

FOR THE NUCLEAR REGULATORY COMMISSION original signed by Darrell Eisenhut for Harold R. Denton, Director Office of Nuclear Reactor Regulation Attachments/Appendices:

1. Attachments 1-2
2. Appendix A - Technical Specifications (NUREG-1149)
3. Appendix 8 - Environmental Protection Plan
4. Appendix C - Additional Conditions Date of Issuance: August 8, 1985 1 The Training and Qualification Plan and Safeguards Contingency Plan are Appendices to the Security Plan.

Amendment No. 9;- ~ 434, 431, ~ -2.04-Revised by letter dated Ootober 28, 2004 Revised 9y letter dated December 10, 2004 Re>11sed by letter dated May 31, 2007

Attachment 2 - Proposed Facility Operating License Changes (Mark-Up)

Limerick Generating Station, Unit 2 Facility Operating License No. NPF-85 (4) Physical Security and Safeguards Exelon Generation Company shall fully implement and maintain in effect all provisions of the Commission-approves physical security, training and qualification, and safeguards contingency plans including amendments made pursuant to provisions of the Miscellaneous Amendments and Search Requirements revisions to 10 CFR 73.55 (51 FR 27817 and 27822), and the authority of 10 CFR 50.90 and 10 CFR 50.54(p). The combined set of plans1, submitted by letter dated May 17, 2006, is entitled: "limerick Generating Station Security Plan, Training and Qualification Plan, and Safeguards Contingency Plan, Revision 2." The set contains Safeguards Information protected under 10 CFR 73.21.

Exelon Generation Company shall fully implement and maintain in effect all provisions of the Commission-approved cyber security plan (CSP),

including changes made pursuant to the authority of 10 CFR 50.90 and 10 CFR 50.54(p). The Exelon Generation Company CSP was approved by License Amendment No. 166.-

and modified by License Amendment No.

(5) Exelon Generation Company shall provide the Director of the Office of Nuclear Reactor Regulation a copy of any application, at the time it is filed, to transfer (excluding grants of security interests or liens) from Exelon Generation Company to its direct or indirect parent, or to any other affiliated company, facilities for the production, transmission or distribution of electric energy having a depreciated book value exceeding ten percent (10%) of Exelon Generation Company's consolidated net utility plant, as recorded on Exelon Generation Company's book of accounts.

(6) Exelon Generation Company shall have decommissioning trust funds for Limerick, Unit 2, in the following minimum amount, when limerick, Unit 2, is transferred to Exelon Generating Company:

Limerick, Unit 2 $59,687,081 (7) The decommissioning trust agreement for limerick, Unit 2, at the time the transfer of the unit to Exelon Generation Company is effected and thereafter, is subject to the following:

(a) The decommissioning trust agreement must be in a form acceptable to the NRC.

(b) With respect to the decommissioning trust fund, investments in the securities or other obligations of Exelon Corporation or affiliates thereof, or their successors or assigns are prohibited. Except for investments tied to market indexes or other non-nuclear sector mutual funds, investments in any entity owning one or more nuclear power plants are prohibited.

1 The Training and Qualification Plan and Safeguards Contingency Plan are Appendices to the Security Plan.

Amendment No. 98, it, 4G8;466-Re)1ised by letter dated October 28, 2004 Re¥ised by letter dated Oesemeer 10, 2004 Re*11sed by letter dated May 31, 2007

- Proposed Facility Operating License Changes (Mark-Up)

Nine Mile Point Nuclear Station, Unit 1 Renewed Facility Operating License No. DPR-63 D. This license is subject to the following additional conditions:

(1) The licensee will complete construction of a new radwaste facility in conformance with the design defined and evaluated in the FES, to be operational no later than June 1976.

(2) Deleted by License Amendment No. 51 (3) Deleted by License Amendment No. 51 (4) Security, Training and Qualification and Safeguards Contingency Plans The licensee shall fully implement and maintain in effect all provisions of the Commission-approved physical security, training and qualification, and safeguards contingency plans, including amendments made pursuant to the provisions of the Miscellaneous Amendments and Search Requirements revisions to 10 CFR 73.55 (51 FR 27817 and 27822) and to the authority of 10 CFR 50.90 and 10 CFR 50.54(p). The combined set of plans, which contain Safeguards Information protected under 10 CFR 73.21 is entitled "Nine Mile Point Nuclear Station, LLC Physical Security, Safeguards Contingency, and Security Training and Qualification Plan, Revision 1," and was submitted by letter dated April 26, 2006.

The licensee shall fully implement and maintain in effect all provisions of the Commission-approved cyber security plan (CSP), including changes made pursuant to the authority of 10 CFR 50.90 and 10 CFR 50.54(p).

The licensee's CSP was a roved b License Amendment No.~.

and modified by License Amendment No.

(5) Paragraph 2.D 5) o the license has been combined with paragraph 2.D(4) as amended above into a single paragraph.

(6) Recirculation System Safe-end Replacement The recirculation system and safe-end replacement program including the cutting and welding of the replacement components and the dose mitigation program (ALARA) is approved, subject to the following conditions:

a. The licensee shall complete the recirculation piping stress reanalysis prior to restart of Nine Mile Point Nuclear Power Station, Unit No. 1. The results of this analysis for selected representative portions of the recirculation system shall be submitted to the NRC prior to restart of the facility.
b. All fuel and control rods shall be removed from the reactor pressure vessel and stored in the spent fuel pool during the period that work on the safe-end and recirculation system replacement program is in progress.

- Proposed Facility Operating License Changes (Mark-Up)

Nine Mlle Point Nuclear Station, Unit 2 Renewed Facility Operating License No. DPR-69 vi) A schedular exemption to 10 CFR 50.55a(h) for the Neutron Monitoring System until completion of the first refueling outage to allow the operating licensee to provide qualified isolation devices for Class 1 E/non-1 E interfaces described in their letters of June 23, 1987 (NMP2L 1057) and June 25, 1987 (NMP2L 1058). (Section 7.2.2.10, SSER 6).

For the schedular exemptions in iv), v), and vi), above, the operating licensee, in accordance with its letter of October 31, 1986, shall certify that all systems, components, and modifications have been completed to meet the requirements of the regulations for which the exemptions have been granted and shall provide a summary description of actions taken to ensure that the regulations have been met. This certification and summary shall be provided 10 days prior to the expiration of each exemption period as described above.

The exemptions set forth in this Section 2.D are authorized by law, will not present an undue risk to public health and safety, and are consistent with the common defense and security. These exemptions are hereby granted. The special circumstances regarding each exemption are identified in the referenced section of the Safety Evaluation Report and the supplements thereto. The exemptions in ii) through vi) are granted pursuant to 10 CFR 50.12.

With these exemptions, the facility will operate to the extent authorized herein, in conformity with the application, as amended, the provisions of the Act, and the rules and regulations of the Commission.

E. Nine Mile Point Nuclear Station, LLC shall fully implement and maintain in effect all provisions of the Commission-approved physical security, training and qualification, and safeguards contingency plans, including amendments made pursuant to provisions of the Miscellaneous Amendments and Search Requirements revisions to 10 CFR 73.55 (51 FR 27817 and 27822) and to the authority of 10 CFR 50.90 and 10 CFR 50.54(p). The combined set of plans, which contain Safeguards Information protected under 10 CFR 73.21 is entitled "Nine Mile Point Nuclear Station, LLC Physical Security, Safeguards Contingency, and Security Training and Qualification Plan, Revision 1," and was submitted by letter dated April 26, 2006. Changes made in accordance with 10 CFR 73.55 shall be implemented in accordance with the schedule set forth therein.

Nine Mile Point Nuclear Station, LLC shall fully implement and maintain in effect all provisions of the Commission-approved cyber security plan (CSP), including changes made pursuant to the authority of 10 CFR 50.90 and 10 CFR 50.54(p).

The Nine Mile Point Nuclear Station's CSP was approved by License Amendment No.137~ ~---,

F. Nine Mile Point Nuclear Station, LLC shall implement and maintain in effect all provisions of the approved fire protection program as described in the Final Safety Analysis Report for the facility through Amendment No. 27 and as described in submittals dated March 25, May 7 and 9, June 10 and 25. July 11 and 16, August 19 and 22, September 5, 12, and 23, October 10, 21, and 22, and December 9, 1986, and April 10 and May 20, 1987, and as approved in the SER dated February 1985 (and Supplements 1 through 6) subject to the following provision:

Amendment 449 lssueel by letter dated January 25, 2012

- Proposed Facility Operating License Changes (Mark-Up)

Oyster Creek Nuclear Generating Station Renewed Facility Operating License No. DPR-16 (4) Exelon Generation Company shall fully implement and maintain in effect all provisions of the Commission-approved physical security, training and qualification, and safeguards contingency plans including amendments made pursuant to provisions of the Miscellaneous Amendments and Search Requirements revisions to 10 CFR 73.55 (51 FR 27817 and 27822), and the authority of 10 CFR 50.90 and 10 CFR 50.54(p). The combined set of plans 1, submitted by letter dated May 17, 2006, is entitled: "Oyster Creek Nuclear Generating Station Security Plan, Training and Qualification Plan, and Safeguards Contingency Plan, Revision 5." The set contains Safeguards Information protected under 10 CFR 73.21.

Exelon Generation Company shall fully implement and maintain in effect all provisions of the Commission-approved cyber security plan (CSP),

including changes made pursuant to the authority of 10 CFR 50.90 and 10 CFR 50.54(p). The Exelon Generation Company CSP was approved b Renewed License Amendment No. 280.:"

and modified by License Amendment No.

(5) Inspections of core spray spargers, piping and associated components will be performed in accordance with BWRVIP-18, "BWR Core Spray Internals Inspection and Flaw Evaluation Guidelines," as approved by NRC staff's Final Safety Evaluation Report dated December 2, 1999.

(6) Long Range Planning Program - Deleted (7) Reactor Vessel Integrated Surveillance Program Exelon Generation Company is authorized to revise the Updated Final Safety Analysis Report (UFSAR) to allow implementation of the Boiling Water Reactor Vessel and Internals Project reactor pressure vessel Integrated Surveillance Program as the basis for demonstrating compliance with the requirements of Appendix H to Title 1O of the Code of Federal Regulations Part 50, "Reactor Vessel Material Surveillance Program Requirements," as set forth in the licensee's application dated December 20, 2002, and as supplemented on May 30, September 10, and November 3, 2003.

All capsules in the reactor vessel that are removed and tested must meet the test procedures and reporting requirements of the most recent NRG-approved version of the Boiling Water Reactor Vessel and Internals Project Integrated Surveillance Program appropriate for the configuration of the specimens in the capsule. Any changes to the capsule withdrawal schedule, including spare capsules, must be approved by the NRC prior to implementation. All capsules placed in storage must be maintained for future insertion. Any changes to storage requirements must be approved by the NRC, as required by 10 CFR Part 50, Appendix H.

1The Training and Qualification Plan and Safeguards Contingency Plan are Appendices to the Security Plan.

Renewed License No. DPR-16 Amendment No.~

Attachment 2 - Proposed Facility Operating License Changes (Mark-Up)

Peach Bottom Atomic Power Station, Unit 2 Renewed Facility Operating License No. DPR-44 (5) Exelon Generation Company, pursuant to the Act and 10 CFR Parts 30 and 70, to possess, but not to separate, such byproduct and special nuclear material as may be produced by operation of the facility, and such Class B and Class C low-level radioactive waste as may be produced by the operation of Limerick Generating Station, Units 1 and 2.

C. This renewed license shall be deemed to contain and is subject to the conditions specified In the following Commission regulations in 10 CFR Chapter I: Part 20, Section 30.34 of Part 30, Section 40.41 of Part 40, Section 50.54 of Part 50, and Section 70.32 of Part 70; all applicable provisions of the Act and the rules, regulations, and orders of the Commission now or hereafter in effect; and is subject to the additional conditions specified below:

( 1) Maximum Power Level Exelon Generation Company is authorized to operate the Peach Bottom Atomic Power Station, Unit 2, at steady state reactor core power levels not in excess of 3514 megawatts thermal.

(2) Technical Scecjfications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 289, are hereby incorporated in the license. Exelon Generation Company shall operate the facility in accordance with the Technical Specifications.

(3) Physical Protection Exelon Generation Company shall fully implement and maintain in effect all provisions of the Commission-approved physical security, training and qualification, and safeguards contingency plans including amendments made pursuant to provisions of the Miscellaneous Amendments and Search Requirements revisions to 10 CFR 73.55 (51 FR 27817 and 27822), and the authority of 10 CFR 50.90 and 10 CFR 50.54(p). The combined set of plans 1, submitted by letter dated May 17, 2006, is entitled: "Peach Bottom Atomic Power Station Security Plan. Training and Qualification Plan, Safeguards Contingency Plan, and Independent Spent Fuel Storage Installation Security Program, Revision 3." The set contains Safeguards Information protected under 10 CFR 73.21.

Exelon Generation Company shall fully implement and maintain in effect all provisions of the Commission-approved cyber security plan (CSP), including changes made pursuant to the authority of 10 CFR 50.90 and 10 CFR 50.54(p).

The Exelon Generation Company CSP was approved by License Amendment No. 283:- ~and modified by License Amendment No. . I

{4) Fire Protection The Exelon Generation Company shall implement and maintain in effect all provisions of the approved fire protection program as described in the Updated Final Safety Analysis Report for the facility, and as approved in the NRC Safety Evaluation Report {SER) dated May 23. 1979. and Supplements dated August 14, September 15, October 10 and November 24, 1980, and in the NRC SERs dated September 16, 1993, and August 24, 1994, subject to the following provision:

1 The Training and Oualifrcation Plan and Safeguards Contingency Plan are Appendices to the Security Plan.

Rene*Ned License No. DPR 44 Re'lised by letter dated October 28, 2004 Revised by~

Amendment No. 289 Page3

- Proposed Facility Operating License Changes (Mark-Up)

Peach Bottom Atomic Power Station, Unit 3 Renewed Facility Opera,tiw Licen!l,eNo DPR..56

  • lvJ r::xelon uenerat1on Company, pursuant to the Act and 10 CFR Parts 30 and 70. to possess, but not to separate, such byproduct and special nuclear material as may be produced by, operation of the facility, and such CJass B and Class C low-level, radioactive waste as may be produced by the operation of Limerick Generating Station, Units 1 and 2.

C. This renewed license shafl be deemed to contain and is subject to the conditions specified in the following Commission regulations in 10 CFR Chapter I: Part 20, Section 30.34 of Part 30, Sectlon40.41 of Part 40, Section 50.54 of Part 50, and Section 70.32 of Part 70; all applicable provisions pfthe Act and the rules, regulations, and orders of the Commission now or hereafter in effect; and is subject to the additional conditions specified below:

(1) Maximum Power Level Exelon Generation Company is authorized to operate the Peach Bottom Atomic Power Station, Unit No. 3, at steady state reactor core power levels not in excess of 3514 megawatts thermal.

(2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 292, are hereby incorporated in the license. Exelon Generation Company shall operate the facility in accordance with the Technical Specifications.

(3) Pbvsieal Protection Exelon Generation Company shall fully implement and maintain in effect all provisions of the Commission-approved' physical security, training and qui:ilification, and safeguards contirigency plans including amendments made 'pu05uant tO provisions of thel\Ais°'llaneous Amendments and Search Requirements revisions to 10 CFR13.55 (51 FR 27817 and 27822), and the authority of 10 CFR 50;90 and 10 CFR 50.54(p). The comt)ined ,set of plans2, subr'riitted by letter dat.ed May 17, 2006, is enti11ed: "Peach Bottom Atomic Power St$tlon Security. Plan, Training ancfQuafification Pla.n, Safeguards Contingency Plan, andlndependent Spent Fuel Storage Installation Security Program, Rev1sion 3." The set contains Safeguards Information protected under 10 CFR 73.21.

Exelon Generation Company shall fully implement and' maintain in effect all provisions of the Commission-approved cyber security plan (CSP),

including changes made pursuant to the authority of 10 CFR 50.90 and 10 CFR 50.54(p). The Exelon Generation Company CSP was approved by License Amendment No. 283-/1:

LJL..1a-=_n-=_d~m-=_-o_d-=_i=fi_1e-=_d-=_b~y-=_,.....,L_i,.....c_e-=_n-=_s-=_e-=_A~m-=_e-=_n-=_d-=_m-=_e-=_n-=_t-=_N~o-._-_-_--.-1

~~~~~~~~~~

1 Licensed power level was revised by Amendment No. 250, dated November 22, 2002, and will be implemented following the 14th refueling outage currently scheduled for Fall 2003.

2 The training and Qualification Plan and Safeguards Contingency Plan are Appendices to the Security Plan Renewed License No.. DPR-56 Revised by letter dated October 28, 2094 Revised by letter dated November 5, 2004 Re\lfsed by letter dated May 29, 2007 Amendment No. 292 o ......... 'l

Attachment 2 - Proposed Facility Operating License Changes (Mark-Up)

Quad Cities Nuclear Power Station, Unit 1 Renewed Facility Operating License No. DPR-29 B. Technical Specifications Am. 251 The Technical Specifications contained in Appendix A, as revised through 06/20/13 Amendment No. 251, are hereby incorporated into the renewed operating license. The licensee shall operate the facility in accordance with the Technical Specifications.

c. The licensee shall maintain the commitments made in response to the March 14, 1983, NUREG-0737 Order, subject to the following provision:

The licensee may make changes to commitments made in response to the March 14, 1983, NUREG-0737 Order without prior approval of the Commission as long as the change would be permitted without NRG approval, pursuant to the requirements of 10 CFR 50.59. Consistent with this regulation, if the change results in an Unreviewed Safety Question, a license amendment shall be submitted to the NRG staff for review and approval prior to implementation of the change.

D. Equalizer Valve Restriction Three of the four valves in the equalizer piping between the recirculation loops shall be closed at all times during reactor operation with one bypass valve open to allow for thermal expansion of water.

NRG Ur E. The licensee shall fully implement and maintain in effect all provisions of the 05/16/07 Commission-approved physical security, training and qualification, and safeguards contingency plans including amendments made pursuant to provisions of the Miscellaneous Amendments and Search Requirements revisions to 10 CFR 73.55 (51 FR 27817 and 27822), and the authority of 10 CFR 50.90 and 10 CFR 50.54(p). The combined sets of plans1, which contain Safeguards Information protected under 10 CFR 73.21, is entitled: "Quad Cities Nuclear Power Station Security Plan, Training and Qualification Plan, and Safeguards Contingency Plan, Revision 2," submitted by letter dated May 17, 2006.

Am. 249 Exelon Generation Company shall fully implement and maintain in effect all 08/10/11 provisions of the Commission-approved cyber security plan (CSP), including changes made pursuant to the authority of 10 CFR 50.90 and 10 CFR 50.54(p).

The Exelon Generation Company CSP was approved by License Amendment No. 249:- tjand modified by License Amendment No. . I F. The licensee shall implement and maintain in effect all provisions of the approved fire protection program as described in the Updated Final Safety Analysis Report for the facility and as approved in the Safety Evaluation Reports dated July 27, 1979, with supplements dated November 5, 1980, and 1 The Training and Qualification Plan and Safeguards Contingency Plan are Appendices to the Security Plan.

Renewed License No. DPR-29 Amendment No. 264

Attachment 2 - Proposed Facility Operating License Changes (Mark-Up)

Quad Cities Nuclear Power Station, Unit 2 Renewed Facility Operating License No. DPR-30 B. Technical Specifications Am. 246 The Technical Specifications contained in Appendix A, as revised through 06/20/13 Amendment No. 246, are hereby incorporated into this renewed operating license. The licensee shall operate the facility in accordance with the Technical Specifications.

C. The license shall maintain the commitments made in response to the March 14, 1983, NUREG-0737 Order, subject to the following provision:

The licensee may make changes to commitments made in response to the March 14, 1983, NUREG-0737 Order without prior approval of the Commission as long as the change would be permitted without NRC approval, pursuant to the requirements of 10 CFR 50.59. Consistent with this regulation, if the change results in an Unreviewed Safety Question, a license amendment shall be submitted to the NRC staff for review and approval prior to implementation of the change.

D. Equalizer Valve Restriction Three of the four valves in the equalizer piping between the recirculation loops shall be closed at all times during reactor operation with one bypass valve open to allow for thermal expansion of water.

NRC Ltr E. The licensee shall fully implement and maintain in effect all provisions of the 05/16/07 Commission-approved physical security, training and qualification, and safeguards contingency plans including amendments made pursuant to provisions of the Miscellaneous Amendments and Search Requirements revisions to 10 CFR 73.55 (51 FR 27817 and 27822), and the authority of 10 CFR 50.90 and 10 CFR 50.54(p). The combined set of plans 1, which contain Safeguards Information protected under 10 CFR 73.21, is entitled: "Quad Cities Nuclear Power Station Security Plan, Training and Qualification Plan, and Safeguards Contingency Plan, Revision 2," submitted by letter dated May 17, 2006.

Am. 244 Exelon Generation Company shall fully implement and maintain in effect all 08/10/11 provisions of the Commission-approved cyber security plan (CSP), including changes made pursuant to the authority of 10 CFR 50.90 and 10 CFR 50.54(p).

The Exelon Generation Company CSP was approved by License Amendment No. 244.,. tjand modified by License Amendment No. . I F. The licensee shall implement and maintain in effect all provisions of the approved fire protection program as described in the Updated Final Safety Analysis Report for the facility and as approved in the Safety Evaluation Reports dated July 27, 1979 with supplements dated 1 The Training and Qualification Plan and Safeguards Contingency Plan are Appendices to the Security Plan.

  • Renewed License No. DPR-30 Amendment No. 24-S

Attachment 2 - Proposed Facility Operating License Changes (Mark-Up)

R. E. Ginna Nuclear Power Plant, Unit 1 Renewed Facility Operating License No. DPR-18 Nuclear Power Plant Security Plan, Training and Qualification Plan, and Safeguards Contingency Plan," submitted by letter dated May 15, 2006.

Exelon Generation shall fully implement and maintain in effect all provisions of the Commission-approved cyber security plan (CSP), including changes made pursuant to the authority of 10 CFR 50.90 and 10 CFR 50.54(p). The licensee's CSP was approved by License Amendment No. 113-:

and modified by License Amendment No. .

F. The p a e ina a e y na ys1s epo supp ement, submitted pursuant to 10 CFR 54.21 (d), describes certain future activities to be completed prior to the period of extended operation. Ginna LLC shall complete these activities no later than September 18, 2009, and shall notify the Commission in writing when implementation of these activities is complete and can be verified by NRC inspection.

The Updated Final Safety Analysis Report supplement, as revised, shall be included in the next scheduled update to the Updated Final Safety Analysis Report required by 10 CFR 50.71 (e)(4) following issuance of this renewed license. Until that update is complete, the licensee may make changes to the programs and activities described in the supplement without prior Commission approval, provided that the licensee evaluates each such change pursuant to the criteria set forth in 10 CFR 50.59 and otherwise complies with the requirements in that section.

G. All capsules in the reactor vessel that are removed and tested must meet the test procedures and reporting requirements of ASTM E 185-82 to the extent practicable for the configuration of the specimens in the capsule. Any changes to the capsule withdrawal schedule, including spare capsules, must be approved by the NRC prior to implementation. Any capsules placed in storage must be maintained for future insertion, unless approved by the NRC.

H. This renewed license is effective as of the date of issuance and shall expire at midnight on September 18, 2029.

FOR THE NUCLEAR REGULATORY COMMISSION Original Signed By J. E. Dyer, Director Office of Nuclear Reactor Regulation

Attachment:

Appendix A- Technical Specifications Date of Issuance: May 19, 2004 Amendment No. 446- I

Attachment 2 - Proposed Facility Operating License Changes (Mark-Up)

Three Mile Island Nuclear Station, Unit 1 Renewed Facility Operating License No. DPR-50 (2) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 281 are hereby incorporated in the license. The Exelon Generation Company shall operate the facility in accordance with the Technical Specifications.

(3) Physical Protection Exelon Generation Company shall fully implement and maintain in effect all provisions of the Commission-approved physical security, training and qualification, and safeguards contingency plans including amendments made pursuant to provisions of the Miscellaneous Amendments and Search Requirements revisions to 10 CFR 73.55 (51 FR 27817 and 27822), and the authority of 10 CFR 50.90 and 10 CFR 50.54(p). The combined set of plans1, submitted by letter dated May 17, 2006, is entitled: "Three Mile Island Nuclear Station Security Plan, Training and Qualification Plan, and Safeguards Contingency Plan, Revision 3." The set contains Safeguards Information protected under 10 CFR 73.21.

Exelon Generation Company shall fully implement and maintain in effect all provisions of the Commission-approved cyber security plan (CSP), including changes made pursuant to the authority of 10 CFR 50.90 and 10 CFR 50.54(p). The Exelon Generation Company CSP was approved by License Amendment No.

and modified by License Amendment No.

(4) Fire Protection Exelon Generation Company shall implement and maintain in effect all provisions of the Fire Protection Program as described in the Updated FSAR for TMl-1.

Changes may be made to the Fire Protection Program without prior approval by the Commission only if those changes would not adversely affect the ability to achieve and maintain safe shutdown in the event of a fire. Temporary changes to specific fire protection features which may be necessary to accomplish maintenance or modifications are acceptable provided that interim compensate measures are implemented.

(5) The licensee shall implement a secondary water chemistry monitoring program to inhibit steam generator tube degradation. This program shall include:

a. Identification of a sampling schedule for the critical parameters and control points for these parameters;
b. Identification of the procedures used to measure the values of the critical parameters;
c. Identification of process sampling points;
d. Procedure for the recording and management of data; 1 The Training and Qualification Plan and Safeguards Contingency Plan are Appendices to the Security Plan.

Amendment No.-284 Renewed Operating License No. DPR-50