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{{#Wiki_filter:eFF',C:A,'
{{#Wiki_filter:eFF',C:A,' US....         EURIYRIA:E           NI1IMT UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 February 1, 2007 Mr. Dennis L. Koehl Site Vice President Point Beach Nuclear Plant Nuclear Management Company, LLC 6610 Nuclear Road Two Rivers, WI 54241-9516
US.... EURIYRIA:E NI1IMT UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 February 1, 2007 Mr. Dennis L. Koehl Site Vice President Point Beach Nuclear Plant Nuclear Management Company, LLC 6610 Nuclear Road Two Rivers, WI 54241-9516


==SUBJECT:==
==SUBJECT:==
POINT BEACH NUCLEAR PLANT, UNITS 1 AND 2 -ADMINISTRATIVE CHANGE TO FACILITY OPERATING LICENSE IN CONJUNCTION WITH THE COMMISSION ORDER EA-06-037 REGARDING REVISIONS TO PHYSICAL SECURITY PLAN, TRAINING AND QUALIFICATION PLAN, AND SAFEGUARDS CONTINGENCY PLAN (TAC NOS. MD2263 AND MD2264)
POINT BEACH NUCLEAR PLANT, UNITS 1 AND 2 - ADMINISTRATIVE CHANGE TO FACILITY OPERATING LICENSE IN CONJUNCTION WITH THE COMMISSION ORDER EA-06-037 REGARDING REVISIONS TO PHYSICAL SECURITY PLAN, TRAINING AND QUALIFICATION PLAN, AND SAFEGUARDS CONTINGENCY PLAN (TAC NOS. MD2263 AND MD2264)


==Dear Mr. Koehl:==
==Dear Mr. Koehl:==
By letter to the Nuclear Regulatory Commission (NRC) dated May 10, 2006, Nuclear Management Company, LLC (NMC), submitted its revised security plans and confirmed the full implementation at Point Beach Nuclear Plant, Unit Nos. 1 and 2 (PBNP 1 and 2) of Order EA-06-037.
 
Order EA-06-037 provided an update to an adversary characteristic of the design-basis threat.The NRC staff has completed its review of the changes related to implementation of Order EA-06-037.
By letter to the Nuclear Regulatory Commission (NRC) dated May 10, 2006, Nuclear Management Company, LLC (NMC), submitted its revised security plans and confirmed the full implementation at Point Beach Nuclear Plant, Unit Nos. 1 and 2 (PBNP 1 and 2) of Order EA-06-037. Order EA-06-037 provided an update to an adversary characteristic of the design-basis threat.
As discussed in the enclosed safeguards evaluation (Enclosure 3), the NRC staff has determined that NMC's changes to the security plans meet the requirements of the NRC Order and Title 10 of the Code of Federal Regulations (10 CFR) Part 73 requirements and are, therefore, acceptable.
The NRC staff has completed its review of the changes related to implementation of Order EA-06-037. As discussed in the enclosed safeguards evaluation (Enclosure 3), the NRC staff has determined that NMC's changes to the security plans meet the requirements of the NRC Order and Title 10 of the Code of FederalRegulations (10 CFR) Part 73 requirements and are, therefore, acceptable. The effectiveness of these security provisions will continue to be the subject of NRC review and inspection:
The effectiveness of these security provisions will continue to be the subject of NRC review and inspection:
Consistent with the Order, administrative license changes to Renewed Facility Operating License Nos. DPR-24 and DPR-27 are being made to incorporate the reference to the revised Physical Security Plan, Safeguards Contingency Plan, and Training and Qualification Plan. The changes comply with the standards and requirements of the Atomic Energy Act of 1954, as OFFICIAL USE ,-L,,''     SECURITY RELATED"INFORMATION           .-
Consistent with the Order, administrative license changes to Renewed Facility Operating License Nos. DPR-24 and DPR-27 are being made to incorporate the reference to the revised Physical Security Plan, Safeguards Contingency Plan, and Training and Qualification Plan. The changes comply with the standards and requirements of the Atomic Energy Act of 1954, as OFFICIAL USE ,-L,,'' SECURITY RELATED" INFORMATION  
 
.-
OFFICIAL USE ONLY' - SEeURIli'     RELATED !NFORMATI3EN--
OFFICIAL USE ONLY' -SEeURIli' RELATED !NFORMATI3EN--
D. Koehl                                     amended, and the Commission's rules and regulations set forth in 10 CFR Chapter i. Please replace Page 4 of the PBNP 1 and 2 Renewed Facility Operating Licenses with the enclosed pages (Enclosures 1 and 2). Enclosure 3 to this letter is designated exempt from public disclosure under 10 CFR 2.390(d)(1).
D. Koehl amended, and the Commission's rules and regulations set forth in 10 CFR Chapter i. Please replace Page 4 of the PBNP 1 and 2 Renewed Facility Operating Licenses with the enclosed pages (Enclosures 1 and 2). Enclosure 3 to this letter is designated exempt from public disclosure under 10 CFR 2.390(d)(1).
Please contact me at (301) 415-1457 if you have any questions on this issue.
Please contact me at (301) 415-1457 if you have any questions on this issue.Sincerely, Patrick D. Milano, Senior Project Manager Plant Licensing Branch Il1-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-266 and 50-301  
Sincerely, Patrick D. Milano, Senior Project Manager Plant Licensing Branch Il1-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-266 and 50-301


==Enclosures:==
==Enclosures:==
: 1. Revised Page 4 of License DPR-24 2. Revised Page 4 of License DPR-27 3. Safeguards Evaluation cc w/encls 1, 2, and 3: Brian Kopetsky, Security Manager, PBNP Patrick Loudon, Region IIl cc w/encls 1 and 2 only: See next page OFFICGIAL UGE O)NL=Y SECR RELATED INFORMATION  
: 1. Revised Page 4 of License DPR-24
.
: 2. Revised Page 4 of License DPR-27
Point Beach Nuclear Plant, Units 1 and 2 cc: Jonathan Rogoff, Esquire Vice President, Counsel & Secretary Nuclear Management Company, LLC 700 First Street Hudson, WI 54016 Mr. F. D. Kuester President  
: 3. Safeguards Evaluation cc w/encls 1, 2, and 3: Brian Kopetsky, Security Manager, PBNP Patrick Loudon, Region IIl cc w/encls 1 and 2 only: See next page OFFICGIAL UGE O)NL=Y SECR           RELATED INFORMATION           .
& Chief Executive Officer WE Generation 231 West Michigan Street Milwaukee, WI 53201 Regulatory Affairs Manager Point Beach Nuclear Plant Nuclear Management Company, LLC 6610 Nuclear Road Two Rivers, WI 54241 Mr. Ken Duveneck Town Chairman Town of Two Creeks 13017 State Highway 42 Mishicot, WI 54228 Chairman Public Service Commission of Wisconsin P.O. Box 7854 Madison, WI 53707-7854 Regional Administrator, Region III U.S. Nuclear Regulatory Commission Suite 210 2443 Warrenville Road Lisle, IL 60532-4351 Resident Inspector's Office U.S. Nuclear Regulatory Commission 6612 Nuclear Road Two Rivers, WI 54241 Mr. Jeffery Kitsembel Electric Division Public Service Commission of Wisconsin P.O. Box 7854 Madison, WI 53707-7854 Nuclear Asset Manager Wisconsin Electric Power Company 231 West Michigan Street Milwaukee, WI 53201 Michael B. Sellman President and Chief Executive Officer Nuclear Management Company, LLC 700 First Street Hudson, MI 54016 Douglas E. Cooper Senior Vice President
 
& Chief Nuclear Officer Nuclear Management Company, LLC 700 First Street Hudson, WI 54016 Site Director of Operations Nuclear Management Company, LLC 6610 Nuclear Road Two Rivers, WI 54241  D. Physical Protection NMC 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).
Point Beach Nuclear Plant, Units 1 and 2 cc:
The combined set of plans, which contain Safeguards Information protected under 10 CFR 73.21, is entitled: "Nuclear Management Company Point Beach Nuclear Plant Physical Security Plan, (Revision 4)," submitted by letter dated May 10, 2006.E. Safety Injection Logic The licensee is authorized to modify the safety injection actuation logic and actuation power supplies and related changes as described in licensee's application for amendment dated April 27, 1979, as supplemented May 7, 1979. In the interim period until the power supply modification has been completed, should any DC powered safety injection actuation channel be in a failed condition for greater than one hour, the unit shall thereafter be shutdown using normal procedures and placed in a block-permissive condition for safety injection actuation.
Jonathan Rogoff, Esquire                 Mr. Jeffery Kitsembel Vice President, Counsel & Secretary     Electric Division Nuclear Management Company, LLC         Public Service Commission of Wisconsin 700 First Street                         P.O. Box 7854 Hudson, WI 54016                         Madison, WI 53707-7854 Mr. F. D. Kuester                       Nuclear Asset Manager President & Chief Executive Officer     Wisconsin Electric Power Company WE Generation                           231 West Michigan Street 231 West Michigan Street                 Milwaukee, WI 53201 Milwaukee, WI 53201 Michael B. Sellman Regulatory Affairs Manager               President and Chief Executive Officer Point Beach Nuclear Plant               Nuclear Management Company, LLC Nuclear Management Company, LLC          700 First Street 6610 Nuclear Road                       Hudson, MI 54016 Two Rivers, WI 54241 Douglas E. Cooper Mr. Ken Duveneck                         Senior Vice President & Chief Nuclear Town Chairman                           Officer Town of Two Creeks                       Nuclear Management Company, LLC 13017 State Highway 42                   700 First Street Mishicot, WI 54228                       Hudson, WI 54016 Chairman                                 Site Director of Operations Public Service Commission               Nuclear Management Company, LLC of Wisconsin                           6610 Nuclear Road P.O. Box 7854                           Two Rivers, WI 54241 Madison, WI 53707-7854 Regional Administrator, Region III U.S. Nuclear Regulatory Commission Suite 210 2443 Warrenville Road Lisle, IL 60532-4351 Resident Inspector's Office U.S. Nuclear Regulatory Commission 6612 Nuclear Road Two Rivers, WI 54241
 
D. Physical Protection NMC 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: "Nuclear Management Company Point Beach Nuclear Plant Physical Security Plan, (Revision 4)," submitted by letter dated May 10, 2006.
E. Safety Injection Logic The licensee is authorized to modify the safety injection actuation logic and actuation power supplies and related changes as described in licensee's application for amendment dated April 27, 1979, as supplemented May 7, 1979. In the interim period until the power supply modification has been completed, should any DC powered safety injection actuation channel be in a failed condition for greater than one hour, the unit shall thereafter be shutdown using normal procedures and placed in a block-permissive condition for safety injection actuation.
F. NMC shall implement and maintain in effect all provisions of the approved fire protection program as described in the FSAR for the facility and as approved in the Safety Evaluation Report dated August 2, 1979 (and supplements dated October 21, 1980, January 22, 1981, and July 27, 1988) and the safety evaluation issued January 8, 1997, for Technical Specification Amendment No. 170, subject to the following provision:
F. NMC shall implement and maintain in effect all provisions of the approved fire protection program as described in the FSAR for the facility and as approved in the Safety Evaluation Report dated August 2, 1979 (and supplements dated October 21, 1980, January 22, 1981, and July 27, 1988) and the safety evaluation issued January 8, 1997, for Technical Specification Amendment No. 170, subject to the following provision:
NMC 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. Secondary Water Chemistry Monitoring Program NMC shall implement a secondary water chemistry monitoring program to inhibit steam generator tube degradation.
NMC 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.
This program shall include: 1. Identification of a sampling schedule for the critical parameters and control points for these parameters;
G. Secondary Water Chemistry Monitoring Program NMC shall implement a secondary water chemistry monitoring program to inhibit steam generator tube degradation. This program shall include:
: 2. Identification of the procedures used to quantify parameters that are critical to control points;3. Identification of process sampling points;4. Procedure for the recording and management of data;5. Procedures defining corrective actions for off control point chemistry condition; and Renewed License No. DPR-24 Revised by letter dated February 1, 2007 D. Physical Protection NMC 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).
: 1. Identification of a sampling schedule for the critical parameters and control points for these parameters;
The combined set of plans, which contain Safeguards Information protected under 10 CFR 73.21, is entitled: "Nuclear Management Company Point Beach Nuclear Plant Physical Security Plan, (Revision 4)," submitted by letter dated May 10, 2006.E. Safety Iniection Logic The licensee is authorized to modify the safety injection actuation logic and actuation power supplies and related changes as described in licensee's application for amendment dated April 27, 1979, as supplemented May 7, 1979. In the interim period until the power supply modification has been completed, should any DC powered safety injection actuation channel be in a failed condition for greater than one hour, the unit shall thereafter be shut down using normal procedures and placed in a block-permissive condition for safety injection actuation.
: 2. Identification of the procedures used to quantify parameters that are critical to control points;
: 3. Identification of process sampling points;
: 4. Procedure for the recording and management of data;
: 5. Procedures defining corrective actions for off control point chemistry condition; and Renewed License No. DPR-24 Revised by letter dated February 1, 2007
 
D. Physical Protection NMC 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: "Nuclear Management Company Point Beach Nuclear Plant Physical Security Plan, (Revision 4)," submitted by letter dated May 10, 2006.
E. Safety Iniection Logic The licensee is authorized to modify the safety injection actuation logic and actuation power supplies and related changes as described in licensee's application for amendment dated April 27, 1979, as supplemented May 7, 1979. In the interim period until the power supply modification has been completed, should any DC powered safety injection actuation channel be in a failed condition for greater than one hour, the unit shall thereafter be shut down using normal procedures and placed in a block-permissive condition for safety injection actuation.
F. NMC shall implement and maintain in effect all provisions of the approved fire protection program as described in the FSAR for the facility and as approved in the Safety Evaluation Report dated August 2, 1979 (and supplements dated October 21, 1980, January 22, 1981, and July 27, 1988) and the safety evaluation issued January 8, 1997, for Technical Specifications Amendment No. 174, subject to the following provision:
F. NMC shall implement and maintain in effect all provisions of the approved fire protection program as described in the FSAR for the facility and as approved in the Safety Evaluation Report dated August 2, 1979 (and supplements dated October 21, 1980, January 22, 1981, and July 27, 1988) and the safety evaluation issued January 8, 1997, for Technical Specifications Amendment No. 174, subject to the following provision:
NMC 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. Secondary Water Chemistry Monitoring Program NMC shall implement a secondary water chemistry monitoring program to inhibit steam generator tube degradation.
NMC 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.
This program shall include: 1. Identification of a sampling schedule for the critical parameters and control points for these parameters;
G. Secondary Water Chemistry Monitoring Program NMC shall implement a secondary water chemistry monitoring program to inhibit steam generator tube degradation. This program shall include:
: 2. Identification of the procedures used to quantify parameters that are critical to control points;3. Identification of process sampling points;4. Procedure for the recording and management of data;5. Procedures defining corrective actions for off control point chemistry condition; and Renewed License No. DPR-27 Revised by letter date February 1, 2007}}
: 1. Identification of a sampling schedule for the critical parameters and control points for these parameters;
: 2. Identification of the procedures used to quantify parameters that are critical to control points;
: 3. Identification of process sampling points;
: 4. Procedure for the recording and management of data;
: 5. Procedures defining corrective actions for off control point chemistry condition; and Renewed License No. DPR-27 Revised by letter date February 1, 2007}}

Latest revision as of 10:32, 23 November 2019

Administrative Change Without Safety Evaluation
ML070430289
Person / Time
Site: Point Beach  NextEra Energy icon.png
Issue date: 02/01/2007
From: Milano P
NRC/NRR/ADRO/DORL/LPLE
To: Koehl D
Nuclear Management Co
P. Milano X1457
References
TAC MD2263, TAC MD2264
Download: ML070430289 (5)


Text

eFF',C:A,' US.... EURIYRIA:E NI1IMT UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 February 1, 2007 Mr. Dennis L. Koehl Site Vice President Point Beach Nuclear Plant Nuclear Management Company, LLC 6610 Nuclear Road Two Rivers, WI 54241-9516

SUBJECT:

POINT BEACH NUCLEAR PLANT, UNITS 1 AND 2 - ADMINISTRATIVE CHANGE TO FACILITY OPERATING LICENSE IN CONJUNCTION WITH THE COMMISSION ORDER EA-06-037 REGARDING REVISIONS TO PHYSICAL SECURITY PLAN, TRAINING AND QUALIFICATION PLAN, AND SAFEGUARDS CONTINGENCY PLAN (TAC NOS. MD2263 AND MD2264)

Dear Mr. Koehl:

By letter to the Nuclear Regulatory Commission (NRC) dated May 10, 2006, Nuclear Management Company, LLC (NMC), submitted its revised security plans and confirmed the full implementation at Point Beach Nuclear Plant, Unit Nos. 1 and 2 (PBNP 1 and 2) of Order EA-06-037. Order EA-06-037 provided an update to an adversary characteristic of the design-basis threat.

The NRC staff has completed its review of the changes related to implementation of Order EA-06-037. As discussed in the enclosed safeguards evaluation (Enclosure 3), the NRC staff has determined that NMC's changes to the security plans meet the requirements of the NRC Order and Title 10 of the Code of FederalRegulations (10 CFR) Part 73 requirements and are, therefore, acceptable. The effectiveness of these security provisions will continue to be the subject of NRC review and inspection:

Consistent with the Order, administrative license changes to Renewed Facility Operating License Nos. DPR-24 and DPR-27 are being made to incorporate the reference to the revised Physical Security Plan, Safeguards Contingency Plan, and Training and Qualification Plan. The changes comply with the standards and requirements of the Atomic Energy Act of 1954, as OFFICIAL USE ,-L,, SECURITY RELATED"INFORMATION .-

OFFICIAL USE ONLY' - SEeURIli' RELATED !NFORMATI3EN--

D. Koehl amended, and the Commission's rules and regulations set forth in 10 CFR Chapter i. Please replace Page 4 of the PBNP 1 and 2 Renewed Facility Operating Licenses with the enclosed pages (Enclosures 1 and 2). Enclosure 3 to this letter is designated exempt from public disclosure under 10 CFR 2.390(d)(1).

Please contact me at (301) 415-1457 if you have any questions on this issue.

Sincerely, Patrick D. Milano, Senior Project Manager Plant Licensing Branch Il1-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-266 and 50-301

Enclosures:

1. Revised Page 4 of License DPR-24
2. Revised Page 4 of License DPR-27
3. Safeguards Evaluation cc w/encls 1, 2, and 3: Brian Kopetsky, Security Manager, PBNP Patrick Loudon, Region IIl cc w/encls 1 and 2 only: See next page OFFICGIAL UGE O)NL=Y SECR RELATED INFORMATION .

Point Beach Nuclear Plant, Units 1 and 2 cc:

Jonathan Rogoff, Esquire Mr. Jeffery Kitsembel Vice President, Counsel & Secretary Electric Division Nuclear Management Company, LLC Public Service Commission of Wisconsin 700 First Street P.O. Box 7854 Hudson, WI 54016 Madison, WI 53707-7854 Mr. F. D. Kuester Nuclear Asset Manager President & Chief Executive Officer Wisconsin Electric Power Company WE Generation 231 West Michigan Street 231 West Michigan Street Milwaukee, WI 53201 Milwaukee, WI 53201 Michael B. Sellman Regulatory Affairs Manager President and Chief Executive Officer Point Beach Nuclear Plant Nuclear Management Company, LLC Nuclear Management Company, LLC 700 First Street 6610 Nuclear Road Hudson, MI 54016 Two Rivers, WI 54241 Douglas E. Cooper Mr. Ken Duveneck Senior Vice President & Chief Nuclear Town Chairman Officer Town of Two Creeks Nuclear Management Company, LLC 13017 State Highway 42 700 First Street Mishicot, WI 54228 Hudson, WI 54016 Chairman Site Director of Operations Public Service Commission Nuclear Management Company, LLC of Wisconsin 6610 Nuclear Road P.O. Box 7854 Two Rivers, WI 54241 Madison, WI 53707-7854 Regional Administrator, Region III U.S. Nuclear Regulatory Commission Suite 210 2443 Warrenville Road Lisle, IL 60532-4351 Resident Inspector's Office U.S. Nuclear Regulatory Commission 6612 Nuclear Road Two Rivers, WI 54241

D. Physical Protection NMC 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: "Nuclear Management Company Point Beach Nuclear Plant Physical Security Plan, (Revision 4)," submitted by letter dated May 10, 2006.

E. Safety Injection Logic The licensee is authorized to modify the safety injection actuation logic and actuation power supplies and related changes as described in licensee's application for amendment dated April 27, 1979, as supplemented May 7, 1979. In the interim period until the power supply modification has been completed, should any DC powered safety injection actuation channel be in a failed condition for greater than one hour, the unit shall thereafter be shutdown using normal procedures and placed in a block-permissive condition for safety injection actuation.

F. NMC shall implement and maintain in effect all provisions of the approved fire protection program as described in the FSAR for the facility and as approved in the Safety Evaluation Report dated August 2, 1979 (and supplements dated October 21, 1980, January 22, 1981, and July 27, 1988) and the safety evaluation issued January 8, 1997, for Technical Specification Amendment No. 170, subject to the following provision:

NMC 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. Secondary Water Chemistry Monitoring Program NMC shall implement a secondary water chemistry monitoring program to inhibit steam generator tube degradation. This program shall include:

1. Identification of a sampling schedule for the critical parameters and control points for these parameters;
2. Identification of the procedures used to quantify parameters that are critical to control points;
3. Identification of process sampling points;
4. Procedure for the recording and management of data;
5. Procedures defining corrective actions for off control point chemistry condition; and Renewed License No. DPR-24 Revised by letter dated February 1, 2007

D. Physical Protection NMC 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: "Nuclear Management Company Point Beach Nuclear Plant Physical Security Plan, (Revision 4)," submitted by letter dated May 10, 2006.

E. Safety Iniection Logic The licensee is authorized to modify the safety injection actuation logic and actuation power supplies and related changes as described in licensee's application for amendment dated April 27, 1979, as supplemented May 7, 1979. In the interim period until the power supply modification has been completed, should any DC powered safety injection actuation channel be in a failed condition for greater than one hour, the unit shall thereafter be shut down using normal procedures and placed in a block-permissive condition for safety injection actuation.

F. NMC shall implement and maintain in effect all provisions of the approved fire protection program as described in the FSAR for the facility and as approved in the Safety Evaluation Report dated August 2, 1979 (and supplements dated October 21, 1980, January 22, 1981, and July 27, 1988) and the safety evaluation issued January 8, 1997, for Technical Specifications Amendment No. 174, subject to the following provision:

NMC 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. Secondary Water Chemistry Monitoring Program NMC shall implement a secondary water chemistry monitoring program to inhibit steam generator tube degradation. This program shall include:

1. Identification of a sampling schedule for the critical parameters and control points for these parameters;
2. Identification of the procedures used to quantify parameters that are critical to control points;
3. Identification of process sampling points;
4. Procedure for the recording and management of data;
5. Procedures defining corrective actions for off control point chemistry condition; and Renewed License No. DPR-27 Revised by letter date February 1, 2007