ML081970392

Edwin I. Hatch, Transmittal of Responses to Request for Additional Information Addition of License Conditions to Operating Licenses for Request to Implement an Alternative Source Term

ML081970392
Person / Time
Site:	Hatch
Issue date:	07/14/2008
From:	Stinson L M Southern Nuclear Operating Co
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
NL-08-1080
Download: ML081970392 (32)

Text

L. M. Stinson {Mike) Southern Nuclear Vice President Operating Company. Inc. Fleet Operations Support 40 Inverness Center Parkway Post Office Box Birmingham.

Alabama Tel Fax SOUTHERN A .COMPANY July 14, 2008 Energy to Serve lOur World'" Docket 50-321 U. S. Nuclear Regulatory A TIN: Document Control Washington, D. C.

Edwin I. Hatch Nuclear Request to Implement an Alternative Source Response to Request for Additional Information Regarding Addition of License Conditions to the Units 1 and 2 Operating Ladies and Gentlemen:

On August 29, 2006 Southern Nuclear Operating Company (SNC) submitted request to revise the Edwin I. Hatch Nuclear Plant (HNP) licensing/design with a full scope implementation of an alternative source term (AST). By dated November 6,2006, November 27,2006, January 30,2007, June July 16, 2007, August 13, 2007, October 18.2007, December 11, January 24, 2008, February 4, 2008, February 25, 2008, February 27, March 13, 2008, April 1, 2008, May 5, 2008, and June 25, 2008 SNC submitted further information to support the NRC review of the HNP By letter dated July 9,2008 the NRC requested additional information the confirmation of completion of certain actions supporting the revision of HNP licensing and design bases to incorporate AST. The enclosures to this contain the SNC response to the referenced NRC request for information Specifically, in response to the referenced RAI and pursuant to 10 CFR SNC hereby requests a revision to the HNP Units 1 and 2 Operating (OL) DPF-57 and NPF-5, respectively, as justified by implementation of AST the previously referenced submitted information.

The proposed revision add several AST related license conditions to sections 2.C of the HNP Units and 2 OLs to confirm completion of certain actions by specific schedules support of HNP AST The 10 CFR 50.92 evaluation and the justification for the categorical from performing an environmental assessment that were included in August 29, 2006 submittal continue to remain valid and are applicable to proposed OL U. S. Nuclear Regulatory Commission NL-08-1080 Page 2 SNC requests approval of the proposed license amendment by August 29, 2008 as part of NRC approval of AST implementation.

The proposed changes would be implemented as part of HNP AST implementation as described further in the enclosures to this letter. Mr. L. M. Stinson states he is a Vice President of Southern Nuclear Operating Company, is authorized to execute this oath on behalf of Southern Nuclear Operating Company and to the best of his knowledge and belief, the facts set forth in this letter are true. This letter contains no NRC commitments.

If you have any questions, please advise. Respectfully submitted, :-" (, SOUTHERN NUCLEAR OPERATING COMPANY L. M. Stinson Vice President Fleet Operations Support 8'1:10 and subscribed before me this i!!.-day

.....' 2008.'4 J Notary Public My commission expires: Jw y<hi/) LMS/CL T/daj

Enclosures:

1. Response to Request for Additional Information Regarding the Addition of License Conditions to the Units 1 and 2 Operating Licenses 2. Basis for Proposed Change 3. Operating Licenses Marked-up Pages 4. Operating Licenses Clean Typed Pages '.. ".. : '( '... ,':.t .::: '-.

U. S. Nuclear Regulatory Commission NL-08-1080

Page 3 cc: Southern Nuclear Operating Company Mr. J. T. Gasser, Executive Vice President Mr. D. R. Madison, Vice President - Hatch Mr. D. H. Jones, Vice President - Engineering RType: CHA02.004 U. S. Nuclear Regulatory Commission Mr. L. A. Reyes, Regional Administrator Mr. R. E. Martin, NRR Project Manager - Hatch Mr. J. A. Hickey, Senior Resident Inspector - Hatch State of Georgia Mr. N. Holcomb, Commissioner - Department of Natural Resources

Edwin I. Hatch Nuclear Plant Request to Implement an Alternative Source Term Response to Request for Additional Information Regarding the Addition of License Conditions to the Units 1 and 2 Operating Licenses Enclosure 1 Response to Request for Additional Information Regarding the Addition of License Conditions to the Units 1 and 2 Operating Licenses Response to Request for Additional Information Regarding the Addition of License Conditions to the Units 1 and 2 Operating Licenses E1 - 1 NRC QUESTION As part of the proposed AST amendment for the Edwin I. Hatch Nuclear Plant, Unit Nos. 1 and 2 (HNP), license conditions would be added to Facility Operating

Licenses DPR-57 and NPF-5 as follows:

For HNP, Unit 1:

2.C(9) Alternate Source Term

1) Southern Nuclear Operating Com pany, Inc (SNC, the licensee) shall complete actions by April 30, 2010, as described in SNC's letters dated October 18, 2007, and March 13, 2008, to complete the design modifications to the HNP turbine building ventilation exhaust systems.

Specifically, the HNP Units 1 and 2 turbine building exhaust fans shall be capable of being manually switched over from normally operating power supplies, to a Class 1E circuit that will be isolated by an appropriately rated safety related, environmentally and seismically qualified thermal-magnetic circuit breaker. For further protection and isolation, the licensee shall also use fuses that will be located in a seismically qualified manual transfer switch housing. The aforementioned circuit breaker and fuses shall be adequately coordinated with the upstream load center breaker over the entire range. These devices shall be adequately rated to prevent adverse effects of a fault to the rest of the distribution system.

2) SNC shall complete actions by May 31, 2010, as described in Enclosure 1, page 4, of SNC's letter dated August 29, 2006, to modify the logic for cable spreading room fan control to automatically trip supply and exhaust fans on initiation of the pressurization mode in the main control room.

3) SNC shall complete actions by May 31, 2010, as described in SNC's letter response to Request for Additional Information number 20 in SNC's letter dated December 11, 2007, to walk down the HNP Unit Nos. 1 and 2 turbine building motor control centers credited in the analyses to validate their seismic characteristics.

4) SNC shall implement modifications by May 31, 2010, as described in Enclosure 1, section 2.7.3.2, of the LAR and section 5.7 of SNC's letter dated February 25, 2008 (NL 08-0175) to modify the design for the air supply to the turbine building exhaust ventilation dampers, such that operating air to the dampers will be supplied from a non-interruptible instrument air source to eliminate single failure point vulnerability to loss of system/instrument air.

5) SNC shall complete actions by May 31, 2010, as described in SNC's letter dated February 25, 2008 (NL-08-0175) to install and implement the capability for Standby Liquid Control System hand switch jumpers for HNP Units 1 and 2.

Response to Request for Additional Information Regarding the Addition of License Conditions to the Units 1 and 2 Operating Licenses E1 - 2 6) SNC shall complete actions by May 31, 2012 for HNP Unit 1, as described in SNC's letters dated February 25, 2008 (NL-08-0175) and July 2, 2008 (NL-08-1022), to modify the following Main Steam Isolation Valve alternate leakage treatment boundary valves, such that they can be closed in the event of a loss of offsite power without requiring local

operation:

1N38-F101A, 1N38-F101B, 1N33-F012, 1N33-F013

7) SNC shall implement actions by May 31, 2010, as described in SNC's letter dated February 27, 2008, to assure that temperature switches which monitor charcoal bed temperature meet the environmental qualification requirements of 10 CFR 50.49.

For HNP, Unit 2:

2.C.3(g) Alternate Source Term

1) Southern Nuclear Operating Com pany, Inc (SNC, the licensee) shall complete actions by April 30, 2010, as described in SNC's letters dated October 18, 2007, and March 13, 2008, to complete the design modifications to the HNP turbine building ventilation exhaust systems.

Specifically, the HNP Units 1 and 2 turbine building exhaust fans shall be capable of being manually switched over from normally operating power supplies, to a Class 1E circuit that will be isolated by an appropriately rated safety related, environmentally and seismically qualified thermal-magnetic circuit breaker. For further protection and isolation, the licensee shall also use fuses that will be located in a seismically qualified manual transfer switch housing. The aforementioned circuit breaker and fuses shall be adequately coordinated with the upstream load center breaker over the entire range. These devices shall be adequately rated to prevent adverse effects of a fault to the rest of the distribution system.

2) SNC shall complete actions by May 31, 2010, as described in Enclosure 1, page 4, of SNC's letter dated August 29, 2006, to modify the logic for cable spreading room fan control to automatically trip supply and exhaust fans on initiation of the pressurization mode in the main control room.

3) SNC shall complete actions by May 31, 2010, as described in SNC's letter response to Request for Additional Information number 20 in SNC's letter dated December 11, 2007, to walk down the HNP Unit Nos. 1 and 2 turbine building motor control centers credited in the analyses to validate their seismic characteristics.

4) SNC shall implement modifications by May 31, 2010, as described in Enclosure 1, section 2.7.3.2, of the LAR and section 5.7 of SNC's letter dated February 25, 2008, (NL 08-0175) to modify the design for the air Response to Request for Additional Information Regarding the Addition of License Conditions to the Units 1 and 2 Operating Licenses E1 - 3 supply to the turbine building exhaust ventilation dampers, such that operating air to the dampers will be supplied from a non-interruptible instrument air source to eliminate single failure point vulnerability to loss of system/instrument air.

5) SNC shall complete actions by May 31, 2010, as described in SNC's letter dated February 25, 2008 (NL-08-0175) to install and implement the capability for Standby Liquid Control System hand switch jumpers for HNP Units 1 and 2.

6) SNC shall complete actions by May 31, 2011, for HNP Unit 2, as described in SNC's letters dated February 25, 2008 (NL-08-0175) and July 2, 2008 (NL-08-1022), to modify the following Main Steam Isolation Valve alternate leakage treatment boundary valves, such that they can be closed in the event of a loss of offsite power without requiring local operation:

2N11-F004A, 2N11-F004B, 2N33-F003, 2N33-F004

7) SNC shall implement actions by May 31, 2010, as described in SNC's letter dated February 27, 2008, to assure that temperature switches which monitor charcoal bed temperature meet the environmental qualification requirements of 10 CFR 50.49.

SNC RESPONSE In the following Enclosures 2 - 4, the requested license conditions (LCs) are proposed for inclusion in the HNP Units 1 and 2 Operating Licenses. Of the seven proposed LCs for each unit, only the first LC is modified slightly from the NRC proposed words with the deletion of one word as discussed and justified in .

Edwin I. Hatch Nuclear Plant Request to Implement an Alternative Source Term Response to Request for Additional Information Regarding the Addition of License Conditions to the Units 1 and 2 Operating Licenses Enclosure 2 Basis for Proposed Change

Edwin I. Hatch Nuclear Plant Request to Implement an Alternative Source Term Response to Request for Additional Information Regarding the Addition of License Conditions to the Units 1 and 2 Operating Licenses Enclosure 2 Basis for Proposed Change Table of Contents

1.0 Summary

Description

2.0 Detailed

Description

3.0 Technical

Evaluation

4.0 Regulatory

Evaluation

4.1 Significant

Hazards Consideration

4.2 Applicable

Regulatory Requirements/Criteria

5.0 Environmental

Consideration

6.0 References

Basis for Proposed Change E2 - 2 1.0 Summary Description This evaluation supports a request to amend Operating Licenses (OL) DPF-57 and NPF-5 for Edwin I. Hatch Nuclear Plant (HNP) Unit 1 and Unit 2, respectively.

The proposed change will revise sections 2.C of the HNP Units 1 and 2 OLs to add several license conditions (LC) to confirm completion of certain actions by specific schedules in support of HNP Alternative Source Term (AST) implementation. These OL changes are being proposed in response to an AST related NRC request for additional information (RAI) dated July 9, 2008 (reference Enclosure 1 for the SNC response to the

RAI). SNC requests incorporation of the proposed LCs as part of NRC approval of AST implementation.

2.0 Detailed

Description

The proposed change will revise sections 2.C of the HNP Units 1 and 2 OLs to add several LCs to confirm completion of certain actions by specific schedules in support of HNP AST implementation. The seven LCs to be added to both units' OLs are the same between units with the exception of some unit specific technical details. Each of the LCs, described in more detail in the following section 3.0, covers either selected plant modifications or procedural changes necessary to support HNP AST implementation

3.0 Technical

Evaluation As indicated previously, seven LCs will be added specifically to Unit 1 OL section 2C(9) and Unit 2 OL section 2C(3)(g). The LCs will be numbered differently (alphabetically for the Unit 1 OL and numerically for the Unit 2 OL) based on the individual formatting of each OL. However, the LCs will be in the same order in each OL and are discussed below in their order of appearance in the OLs.

The first proposed LC concerns the addition of an alternate safety related power supply to HNP Units 1 and 2 turbine building (TB) ventilation exhaust system with a manual switchover from the normal power supply. The provision of an alternate power supply from an emergency source backed up by an emergency diesel generator further ensures that the AST credited dose mitigation function of the TB ventilation exhaust systems will be available within the required 9 hours1.041667e-4 days <br />0.0025 hours <br />1.488095e-5 weeks <br />3.4245e-6 months <br /> in the highly unlikely event that offsite power cannot be restored within the required time period. The LC requires completion of the associated plant modifications for both units by April 30, 2010. The LC is consistent with the information previously provided to support NRC review of the HNP AST submittal in References 1, 2 and 6.

Only one change has been made to the NRC proposed words for the first LC (reference Enclosure 1 for the NRC RAI). The word thermal-magnetic has been deleted since that term is simply a descriptor associated with a preliminary design as SNC indicated in Reference 6. This minor change was discussed verbally with the NRC Licensing Project

Manager for Hatch on July 10, 2008.

Basis for Proposed Change E2 - 3 The second proposed LC concerns completion of plant modifications to provide automatic securing of the cable spreading room supply and exhaust fans on automatic initiation of pressurization of the main control room by the main control room environmental control system (MCREC). This modification replaces operator action to secure the cable spreading room fans to preclude a potential malfunction of those fans which could impact the capability to maintain the control room at a positive pressure. This second proposed LC exactly duplicates the NRC proposed words (reference Enclosure 1 for the NRC RAI).

However, regarding the second proposed LC, it is noted that the cable spreading room fan modification has been completed as committed in Enclosure 7 of Reference 1. Since the cable spreading room, like the main control room, is common to both HNP units, the second proposed LC has already been met for both HNP Units 1 and 2.

SNC completed implementing this modification in October 2007 and the Hatch Unit 2 Final Safety Analysis Report (FSAR) has been updated to so reflect. Unit 2 FSAR section 6.4.1.2.2.1, which is applicable to both HNP units, describes the pressurization mode of the MCREC and now includes the following paragraph:

The cable spreading room supply and exhaust fans are secured to preclude a potential malfunction of those fans which could potentially impact the capability to maintain the MCR at a positive pressure relative to the surrounding turbine building. Following automatic trip of the cable spreading room supply and exhaust fans, the fans are confirmed tripped.

In addition, applicable Hatch drawings have been updated.

Since the cable spreading room modification has been completed, SNC proposes that consideration be given to deletion of the second proposed LC.

The third proposed LC concerns completion of plant walkdowns of selected HNP Units 1 and 2 motor control centers (MCCs) credited in the analyses to validate their seismic characteristics. As documented in Reference 1 Enclosure 1 section 2.7.3.2 and as committed to in Reference 1 Enclosure 7, these plant walkdowns were done to verify that the MCCs associated with the normal power supply to the TB ventilation exhaust systems were seismically adequate to withstand the HNP design basis earthquake. This third proposed LC exactly duplicates the NRC proposed words (reference Enclosure 1 for the NRC RAI).

However, regarding the third proposed LC, it is noted that the referenced plant walkdowns have been completed for both HNP Units 1and 2 as committed in of Reference 1.

Specifically with respect to HNP Unit 1, Panel 1R24-S016 is a 600VAC motor control center and distribution panel located on elevation 164'0" of the HNP Unit 1 reactor building. Distribution panel 1R25-S120 is contained in, and is a part of, 1R24-S016.

Panel 1R24-S016 is classified as non-safety related, but was evaluated for seismic acceptability per the above commitment. The walkdown to gather information on the MCC, its anchorage, and any potential seismic interactions was conducted in April 2008 Basis for Proposed Change E2 - 4 with a final evaluation issued on June 4, 2008. This panel was evaluated using appropriate seismic qualification utility group (SQUG) criteria, and determined to be acceptable for the applicable seismic design requirements "as-is" with no need for modification.

With respect to HNP Unit 2, Panel 2R24-S016 is a 600/208VAC motor control center and distribution panel located on elevation 164'0" of the Hatch Unit 2 reactor building. Distribution panel 2R25-S106 is contained in, and is a part of, 2R24-S016. Panel 2R24-S016 is classified as non-safety related, but was evaluated for seismic acceptability per the above commitment. Walkdowns were conducted in spring 2007 and spring 2008 to gather information on the MCC, its anchorage, and any potential seismic interactions. The final evaluation was issued on June 4, 2008. This panel was evaluated using appropriate SQUG criteria, and determined to be acceptable for the applicable seismic design requirements "as-is" with no need for modification.

Since the referenced plant walkdowns have been completed, SNC proposes that consideration be given to deletion of the third proposed LC.

The fourth proposed LC concerns completion of plant modifications to the air supply for the TB exhaust ventilation system dampers, such that operating air to the dampers will be supplied from a non-interruptible instrument air source to eliminate a potential TB exhaust ventilation system single failure point vulnerability to a loss of system/instrument air. This fourth proposed LC exactly duplicates the NRC proposed words (reference Enclosure 1 for the NRC RAI). The plant modifications referenced in the fourth proposed LC are described in more detail in section 5.7 of Reference 4.

The fifth proposed LC concerns installation of jumpers bypassing the standby liquid control (SLC) system hand switch. These jumpers will provide an alternative method to initiate SLC, as credited in AST for buffering of the suppression pool following a design basis loss-of-coolant accident (LOCA), in the unlikely event of a failure of the SLC

system hand switch. This fifth proposed LC exactly duplicates the NRC proposed words (reference Enclosure 1 for the NRC RAI). The jumper installation referenced in the fifth proposed LC is described in more detail in section 2.1 of Reference 4.

The sixth proposed LC concerns completion of plant modifications to the boundary valves for the HNP Units 1 and 2 main steam isolation valve (MSIV) alternate leakage treatment path to ensure the ability to close those boundary valves in the event of a loss of offsite power. The sixth proposed LC is unit specific with respect to the four valves per unit that need to be modified. Modification of these selected boundary valves assures that MSIV leakage post-LOCA is mitigated as credited in AST. This sixth proposed LC exactly duplicates the NRC proposed words (reference Enclosure 1 for the NRC RAI). The boundary valve modifications referenced in the sixth proposed LC are described in more detail in section 4.3 of Reference 4. It is noted that the boundary valve modifications will preclude the need for local operation in areas that would subject operators to doses in excess of regulatory limits following a loss of offsite power event concurrent with a LOCA.

The seventh and final proposed LC concerns the completion of plant modifications to assure that temperature switches which monitor TB exhaust ventilation system charcoal Basis for Proposed Change E2 - 5 bed temperature meet the environmental qualification requirements of 10 CFR 50.49. The temperature switch modification precludes a potential failure of these switches which would result in damper closure preventing TB purge flow as credited in AST for dose mitigation. This seventh proposed LC exactly duplicates the NRC proposed words (reference Enclosure 1 for the NRC RAI). The temperature switch modifications referenced in the seventh proposed LC are described in more detail in the response to NRC Question 1 in Reference 5.

4.0 Regulatory

Evaluation

4.1 Significant

Hazards Consideration The proposed change would revise sections 2.C of the HNP Units 1 and 2 OLs to add several LCs to confirm completion of certain actions by specific schedules in support of HNP AST implementation. Each of the AST related actions covered in the proposed LCs and their functions relative to AST implementation are documented in detail in the initial AST submittal and/or associated further information provided to support the NRC review of the HNP AST submittal (see References 1 - 7).

Therefore, the 10 CFR 50.92 evaluation included in the August 29, 2006 submittal continues to remain valid.

4.2 Applicable

Regulatory Requirements/Criteria AST implementation is governed by 10 CFR 50.67, the guidelines of the Standard Review Plan (SRP) section 15.0.1 revision 0, "Radiological Consequence Analyses Using Alternative Source Terms," and Regulatory Guide 1.183, "Alternative Radiological Source Terms for Evaluating Design Basis Accidents at Nuclear Power Reactors," dated July, 2000.

4.3 Precedent

The use of LCs to confirm completion of certain actions by specific schedules in support of a proposed license amendment request has precedent in the NRC staff review and approval of licensee power uprate requests, specifically referencing an NRC letter to Vermont Yankee concerning extended power uprate dated October 12, 2005 and a Susquehanna letter to the NRC concerning constant pressure power

uprate dated January 29, 2008.

There are numerous precedents for NRC approval of AST implementation in accordance with 10 CFR 50.67. Amendment s similar to the HNP AST submittal were approved for Browns Ferry on September 27, 2004 and Vermont Yankee on March 29, 2005. In addition, the HNP application of AST incorporates elements of

the Columbia AST submittal approved on November 27, 2006 and the Oyster Creek AST submittal approved April 26, 2007.

4.4 Conclusions

In conclusion, based on the considerations discussed above, (1) there is reasonable assurance that the health and safety of the public will not be endangered by Basis for Proposed Change E2 - 6 operation in the proposed manner, (2) such activities will be conducted in compliance with the Commission's regulations, and (3) the issuance of the amendment will not be inimical to the common defense and security or to the health and safety of the

public. 5.0 Environmental Consideration The proposed change would revise sections 2.C of the HNP Units 1 and 2 OLs to add several LCs to confirm completion of certain actions by specific schedules in support of HNP AST implementation. Each of the AST related actions covered in the proposed LCs and their functions relative to AST implementation are documented in detail in the initial AST submittal and/or associated furt her information provided to support the NRC review of the HNP AST submittal (see References 1 - 7). Therefore, pursuant to 10 CFR 51.22(b), the justification for the categorical exclusion from performing an environmental assessment included in the August 29, 2006 submittal Enclosure 3 continues to remain

valid. 6.0 References

1. "Request to Implement an Alternative Source Term," NL-06-1637, August 29, 2006.

2. "Response to Request for Additional Information Regarding the Power Sources for the Turbine Building Ventilation System," NL-07-0894, October 18, 2007.

3. "Response to Request for Additional Information Regarding the Turbine Building Ventilation and Leakage Treatment Piping Seismic Evaluations," NL-07-1949, December 11, 2007.

4. "Response to Request for Additional Information Regarding Human Factors Aspects," NL-08-0175, February 25, 2008.

5. "Response to Request for Additional Information Regarding the Turbine Building Ventilation and Standby Liquid Control Systems," NL-07-1532, February 27, 2008.

6. "Response to Request for Additional Information Regarding the Power Sources for the Turbine Building Ventilation System," NL-08-0351, March 13, 2008.

7. "Request to Revise the Unit 1 and Unit 2 Operating Licenses to Extend the Interim Period for the Use of Potassium Iodide," NL-08-1022, July 2, 2008.

Edwin I. Hatch Nuclear Plant Request to Implement an Alternative Source Term Response to Request for Additional Information Regarding the Addition of License Conditions to the Units 1 and 2 Operating Licenses Enclosure 3 Operating Licenses Marked-up Pages Renewed License No. DPR-57 Amendment No.

249 program attribute not covered by the plant-specific surveillance material testing program. The plant-specific program, if needed, will include the following actions:

(a) Capsules will periodically be removed to determine the rate of embrittlement.

(b) Capsules will be removed at neutron fluence levels that provide relevant data for assessing the integrity of the Plant Hatch, Unit 1 reactor pressure vessel (in particular, for the determination of reactor pressure vessel pressure-temperature limits through the period of extended operation).

(c) Capsules will contain material to monitor the impact of irradiation on the Plant Hatch Unit 1 reactor pressure vessel and will contain dosimetry to monitor neutron fluence.

Before the renewal term begins, the licensee will notify the NRC of its decision to implement the integrated surveillance program or a plant-specific program, and provide the appropriate revisions to the Updated

Final Safety Analysis Report Suppl ement summary descriptions of the vessel surveillance material testing program.

(8) Design Bases Accident Radiological Consequences Analyses Southern Nuclear is authorized to credit administering potassium iodide to reduce the 30 day post-accident thyroid radiological dose to the operators in the main control room until May 31, 2010. Should design basis changes be completed rendering the crediting of potassium iodide no longer necessary prior to May 31, 2010, Southern Nuclear will remove the crediting of potassium iodide from the design basis accident radiological consequences analyses (reference Unit 2 FSAR paragraph 15.3.3.4.2.2) in the next Updated Final Safety Analysis Report update as required by 10 CFR 50.71(e).

D. Southern Nuclear shall not market or broker power or energy from Edwin I. Hatch Nuclear Plant, Unit 1.

3. This renewed license is effective as of the date of issuance and shall expire at midnight, August 6, 2034.

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

Appendix A - Technical Specifications Appendix B - Environmental Protection Plan Date of Issuance: January 15, 2002 Insert AST here Insert AST (9) Alternative Source Term (a) Southern Nuclear Operating Company, Inc (SNC, the licensee) shall complete actions by April 30, 2010, as described in SNC's

letters dated October 18, 2007, and March 13, 2008, to complete

the design modifications to the HNP turbine building ventilation

exhaust systems. Specifically, the HNP Units 1 and 2 turbine

building exhaust fans shall be capable of being manually switched

over from normally operating power supplies, to a Class 1E circuit

that will be isolated by an appropriately rated safety related, environmentally and seismically qualified circuit breaker. For

further protection and isolation, the licensee shall also use fuses

that will be located in a seismically qualified manual transfer

switch housing. The aforementioned circuit breaker and fuses

shall be adequately coordinated with the upstream load center

breaker over the entire range. These devices shall be adequately

rated to prevent adverse effects of a fault to the rest of the

distribution system.

(b) SNC shall complete actions by May 31, 2010, as described in , page 4, of SNC's letter dated August 29, 2006, to

modify the logic for cable spreading room fan control to

automatically trip supply and exhaust fans on initiation of the

pressurization mode in the main control room.

(c) SNC shall complete actions by May 31, 2010, as described in SNC's letter response to Request for Additional Information

number 20 in SNC's letter dated December 11, 2007, to walk

down the HNP Unit Nos. 1 and 2 turbine building motor control

centers credited in the analyses to validate their seismic

characteristics.

(d) SNC shall implement modifications by May 31, 2010, as described in Enclosure 1, section 2.7.3.2, of the LAR and section 5.7 of

SNC's letter dated February 25, 2008 (NL 08-0175) to modify the

design for the air supply to the turbine building exhaust ventilation

dampers, such that operating air to the dampers will be supplied

from a non-interruptible instrument air source to eliminate single

failure point vulnerability to loss of system/instrument air.

(e) SNC shall complete actions by May 31, 2010, as described in SNC's letter dated February 25, 2008 (NL-08-0175) to install and

implement the capability for Standby Liquid Control System hand

switch jumpers for HNP Units 1 and 2.

Insert AST (continued)

(f) SNC shall complete actions by May 31, 2012 for HNP Unit 1, as described in SNC's letters dated February 25, 2008 (NL-08-0175)

and July 2, 2008 (NL-08-1022), to modify the following Main

Steam Isolation Valve alternate leakage treatment boundary

valves, such that they can be closed in the event of a loss of

offsite power without requiring local operation:

1N38-F101A, 1N38-F101B, 1N33-F012, 1N33-F013

(g) SNC shall implement actions by May 31, 2010, as described in SNC's letter dated February 27, 2008, to assure that temperature

switches which monitor charcoal bed temperature meet the

environmental qualification requirements of 10 CFR 50.49.

Renewed License No. NPF-5 Amendment No.

193 Boiling Water Reactor Vessel Internals Project program or through a staff-approved plant-specific program. The plant-specific program, if needed, will be developed in a manner consistent with other aging management programs, will include consideration of the 10 program attributes utilized for other aging management programs, and will provide a technical justification for any program attribute not covered by the plant-specific surveillance material testing program. The plant-specific program, if needed, will include the following actions:

i. Capsules will periodically be removed to determine the rate of embrittlement.

ii. Capsules will be removed at neutron fluence levels that provide relevant data for assessing the integrity of the Plant Hatch Unit 2 reactor pressure vessel (in particular, for the determination of reactor pressure vessel pressure-temperature limits through the period of extended operation).

iii. Capsules will contain material to monitor the impact of irradiation on the Plant Hatch Unit 2 reactor pressure vessel and will contain dosimetry to monitor neutron fluence.

Before the renewal term begins, the licensee will notify the NRC of its decision to implement the integrated surveillance program or a plant-specific program, and provide the appropriate revisions to the Updated Final Safety Analysis Report Supplement summary de scriptions of the vessel surveillance material testing program.

(f) Design Bases Accident Radiological Consequences Analyses Southern Nuclear is authorized to credit administering potassium iodide to reduce the 30 day post-accident thyroid radiological dose to the operators in the main control room until May 31, 2010. Should design basis changes be completed rendering the crediting of potassium iodide no longer necessary prior to May 31, 2010, Southern Nuclear will remove the crediting of potassium iodide from the design basis accident radiological consequences analyses (reference Unit 2 FSAR paragraph 15.3.3.4.2.2) in the next Updated Final Safety Analysis Report update as required by 10 CFR 50.71(e).

D. This renewed license is subject to the following antitrust conditions:

(1) As used herein:

a. "Entity" means any financially responsible person, private or public corporation, municipality, county, cooperative, association, joint stock association or business trust, owning, operating or proposing to own or operate equipment or facilities within the state of Georgia (other than Chatham, Effingham, Fannin, Towns and Union Counties) for Insert AST here Insert AST (g) Alternative Source Term

1) Southern Nuclear Operating Company, Inc (SNC, the licensee) shall complete actions by April 30, 2010, as described in SNC's

letters dated October 18, 2007, and March 13, 2008, to complete

the design modifications to the HNP turbine building ventilation

exhaust systems. Specifically, the HNP Units 1 and 2 turbine

building exhaust fans shall be capable of being manually switched

over from normally operating power supplies, to a Class 1E circuit

that will be isolated by an appropriately rated safety related, environmentally and seismically qualified circuit breaker. For

further protection and isolation, the licensee shall also use fuses

that will be located in a seismically qualified manual transfer switch

housing. The aforementioned circuit breaker and fuses shall be

adequately coordinated with the upstream load center breaker over

the entire range. These devices shall be adequately rated to

prevent adverse effects of a fault to the rest of the distribution system.

2) SNC shall complete actions by May 31, 2010, as described in , page 4, of SNC's letter dated August 29, 2006, to

modify the logic for cable spreading room fan control to

automatically trip supply and exhaust fans on initiation of the

pressurization mode in the main control room.

3) SNC shall complete actions by May 31, 2010, as described in SNC's letter response to Request for Additional Information number

20 in SNC's letter dated December 11, 2007, to walk down the HNP

Unit Nos. 1 and 2 turbine building motor control centers credited in

the analyses to validate their seismic characteristics.

4) SNC shall implement modifications by May 31, 2010, as described in Enclosure 1, section 2.7.3.2, of the LAR and section 5.7 of SNC's

letter dated February 25, 2008, (NL 08-0175) to modify the design

for the air supply to the turbine building exhaust ventilation

dampers, such that operating air to the dampers will be supplied

from a non-interruptible instrument air source to eliminate single

failure point vulnerability to loss of system/instrument air.

5) SNC shall complete actions by May 31, 2010, as described in SNC's letter dated February 25, 2008 (NL-08-0175) to install and

implement the capability for Standby Liquid Control System hand

switch jumpers for HNP Units 1 and 2.

6) SNC shall complete actions by May 31, 2011, for HNP Unit 2, as described in SNC's letters dated February 25, 2008 (NL-08-0175)

and July 2, 2008 (NL-08-1022), to modify the following Main Steam

Isolation Valve alternate leakage treatment boundary valves, such

that they can be closed in the event of a loss of offsite power

without requiring local operation:

Insert AST (continued) 2N11-F004A, 2N11-F004B, 2N33-F003, 2N33-F004

7) SNC shall implement actions by May 31, 2010, as described in SNC's letter dated February 27, 2008, to assure that temperature

switches which monitor charcoal bed temperature meet the

environmental qualification requirements of 10 CFR 50.49.

Edwin I. Hatch Nuclear Plant Request to Implement an Alternative Source Term Response to Request for Additional Information Regarding the Addition of License Conditions to the Units 1 and 2 Operating Licenses Enclosure 4 Operating Licenses Clean Typed Pages

Renewed License No. DPR-57 Amendment No. program attribute not covered by the plant-specific surveillance material testing program. The plant-specific program, if needed, will include the following actions:

(a) Capsules will periodically be removed to determine the rate of embrittlement.

(b) Capsules will be removed at neutron fluence levels that provide relevant data for assessing the integrity of the Plant Hatch, Unit 1 reactor pressure vessel (in particular, for the determination of reactor pressure vessel pressure-temperature limits through the

period of extended operation).

(c) Capsules will contain material to monitor the impact of irradiation on the Plant Hatch Unit 1 reactor pressure vessel and will contain dosimetry to monitor neutron fluence.

Before the renewal term begins, the licensee will notify the NRC of its decision to implement the integrated surveillance program or a plant-specific program, and provide the appropriate revisions to the Updated

Final Safety Analysis Report Suppl ement summary descriptions of the vessel surveillance material testing program.

(8) Design Bases Accident Radiological Consequences Analyses Southern Nuclear is authorized to credit administering potassium iodide to reduce the 30 day post-accident thyroid radiological dose to the operators in the main control room until May 31, 2010. Should design basis changes be completed rendering the crediting of potassium iodide no longer necessary prior to May 31, 2010, Southern Nuclear will remove the crediting of potassium iodide from the design basis accident radiological consequences analyses (reference Unit 2 FSAR paragraph 15.3.3.4.2.2) in the next Updated Final Safety Analysis Report update as required by

10 CFR 50.71(e).

(9) Alternative Source Term (a) Southern Nuclear Operating Company, Inc (SNC, the licensee) shall complete actions by April 30, 2010, as described in SNC's letters dated October 18, 2007, and March 13, 2008, to complete the design modifications to the HNP turbine building ventilation exhaust systems. Specifically, the HNP Units 1 and 2 turbine building exhaust fans shall be capable of being manually switched over from normally operating power supplies, to a Class 1E circuit that will be isolated by an appropriately rated safety related, environmentally and seismically qualified circuit breaker. For further protection and isolation, the licensee shall also use fuses that will be located in a seismically qualified manual transfer switch housing. The aforementioned circuit breaker and fuses shall be adequately coordinated with the upstream load center Renewed License No. DPR-57 Amendment No. breaker over the entire range. These devices shall be adequately rated to prevent adverse effects of a fault to the rest of the distribution system.

(b) SNC shall complete actions by May 31, 2010, as described in Enclosure 1, page 4, of SNC's letter dated August 29, 2006, to modify the logic for cable spreading room fan control to automatically trip supply and exhaust fans on initiation of the pressurization mode in the main control room.

(c) SNC shall complete actions by May 31, 2010, as described in SNC's letter response to Request for Additional Information number 20 in SNC's letter dated December 11, 2007, to walk down the HNP Unit Nos. 1 and 2 turbine building motor control centers credited in the analyses to validate their seismic characteristics.

(d) SNC shall implement modifications by May 31, 2010, as described in Enclosure 1, section 2.7.3.2, of the LAR and section 5.7 of SNC's letter dated February 25, 2008 (NL 08-0175) to modify the design for the air supply to the turbine building exhaust ventilation dampers, such that operating air to the dampers will be supplied from a non-interruptible instrument air source to eliminate single failure point vulnerability to loss of system/instrument air.

(e) SNC shall complete actions by May 31, 2010, as described in SNC's letter dated February 25, 2008 (NL-08-0175) to install and implement the capability for Standby Liquid Control System hand switch jumpers for HNP Units 1 and 2.

(f) SNC shall complete actions by May 31, 2012 for HNP Unit 1, as described in SNC's letters dated February 25, 2008 (NL-08-0175) and July 2, 2008 (NL-08-1022), to modify the following Main Steam Isolation Valve alternate leakage treatment boundary valves, such that they can be closed in the event of a loss of offsite power without requiring local operation:

1N38-F101A, 1N38-F101B, 1N33-F012, 1N33-F013 (g) SNC shall implement actions by May 31, 2010, as described in SNC's letter dated February 27, 2008, to assure that temperature switches which monitor charcoal bed temperature meet the environmental qualification requirements of 10 CFR 50.49. Renewed License No. DPR-57 Amendment No. D. Southern Nuclear shall not market or broker power or energy from Edwin I. Hatch Nuclear Plant, Unit 1.

3. This renewed license is effective as of the date of issuance and shall expire at midnight, August 6, 2034.

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

Appendix A - Technical Specifications Appendix B - Environmental Protection Plan Date of Issuance: January 15, 2002 Renewed License No. NPF-5 Amendment No. Boiling Water Reactor Vessel Internals Project program or through a staff-approved plant-specific program. The plant-specific program, if needed, will be developed in a manner consistent with other aging management programs, will include consideration of the 10 program attributes utilized for other aging management programs, and will provide a technical justification for any program attribute not covered by the plant-specific surveillance material testing program. The plant-specific program, if needed, will include the following actions:

i. Capsules will periodically be removed to determine the rate of embrittlement.

ii. Capsules will be removed at neutron fluence levels that provide relevant data for assessing the integrity of the Plant Hatch Unit 2 reactor pressure vessel (in particular, for the determination of reactor pressure vessel pressure-temperature limits through the period of extended operation).

iii. Capsules will contain material to monitor the impact of irradiation on the Plant Hatch Unit 2 reactor pressure vessel and will contain dosimetry to monitor neutron fluence.

Before the renewal term begins, the licensee will notify the NRC of its decision to implement the integrated surveillance program or a plant-specific program, and provide the appropriate revisions to the Updated Final Safety

Analysis Report Supplement summary de scriptions of the vessel surveillance material testing program.

(f) Design Bases Accident Radiological Consequences Analyses Southern Nuclear is authorized to credit administering potassium iodide to reduce the 30 day post-accident thyroid radiological dose to the operators in the main control room until May 31, 2010. Should design basis changes be completed rendering the crediting of potassium iodide no longer necessary prior to May 31, 2010, Southern Nuclear will remove the crediting of potassium iodide from the design basis accident radiological consequences analyses (reference Unit 2 FSAR paragraph 15.3.3.4.2.2) in the next Updated Final Safety Analysis Report update as required by

10 CFR 50.71(e).

(g) Alternative Source Term

1) Southern Nuclear Operating Company, Inc (SNC, the licensee) shall complete actions by April 30, 2010, as described in SNC's letters dated October 18, 2007, and March 13, 2008, to complete the design modifications to the HNP turbine building ventilation exhaust systems. Specifically, the HNP Units 1 and 2 turbine building exhaust fans shall be capable of being manually switched Renewed License No. NPF-5 Amendment No. over from normally operating power supplies, to a Class 1E circuit that will be isolated by an appropriately rated safety related, environmentally and seismically qualified circuit breaker. For further protection and isolation, the licensee shall also use fuses that will be located in a seismically qualified manual transfer switch housing. The aforementioned circuit breaker and fuses shall be adequately coordinated with the upstream load center breaker over the entire range. These devices shall be adequately rated to prevent adverse effects of a fault to the rest of the distribution system.

2) SNC shall complete actions by May 31, 2010, as described in Enclosure 1, page 4, of SNC's letter dated August 29, 2006, to modify the logic for cable spreading room fan control to automatically trip supply and exhaust fans on initiation of the pressurization mode in the main control room.

3) SNC shall complete actions by May 31, 2010, as described in SNC's letter response to Request for Additional Information number 20 in SNC's letter dated December 11, 2007, to walk down the HNP Unit Nos. 1 and 2 turbine building motor control centers credited in the analyses to validate their seismic characteristics.

4) SNC shall implement modifications by May 31, 2010, as described in Enclosure 1, section 2.7.3.2, of the LAR and section 5.7 of SNC's letter dated February 25, 2008, (NL 08-0175) to modify the design for the air supply to the turbine building exhaust ventilation dampers, such that operating air to the dampers will be supplied from a non-interruptible instrument air source to eliminate single failure point vulnerability to loss of system/instrument air.

5) SNC shall complete actions by May 31, 2010, as described in SNC's letter dated February 25, 2008 (NL-08-0175) to install and implement the capability for Standby Liquid Control System hand switch jumpers for HNP Units 1 and 2.

6) SNC shall complete actions by May 31, 2011, for HNP Unit 2, as described in SNC's letters dated February 25, 2008 (NL-08-0175) and July 2, 2008 (NL-08-1022), to modi fy the following Main Steam Isolation Valve alternate leakage treatment boundary valves, such that they can be closed in the event of a loss of offsite power without requiring local operation:

2N11-F004A, 2N11-F004B, 2N33-F003, 2N33-F004 Renewed License No. NPF-5 Amendment No. 7) SNC shall implement actions by May 31, 2010, as described in SNC's letter dated February 27, 2008, to assure that temperature switches which monitor charcoal bed temperature meet the environmental qualification requirements of 10 CFR 50.49.

D. This renewed license is subject to the following antitrust conditions:

(1) As used herein:

(a) "Entity" means any financially responsible person, private or public corporation, municipality, county, cooperative, association, joint stock association or business trust, owning, operating or proposing to own or operate equipment or facilities within the state of Georgia (other than Chatham, Effingham, Fannin, Towns and Union Counties) for the generation, transmission, or distribution of electricity, provided that, except for municipalities, counties, or rural electric cooperatives, "entity" is restricted to those which are or will be public utilities under the laws of the State of Georgia or under the laws of the United States, and are or will be providing retail electric service under a contract or rate schedule on file with and subject to the regulation of the Public Service Commission of the State of Georgia or any regulatory agency of the United States, and provided further, that as to municipalities, counties, or rural electric cooperatives, "entity" is restricted to those which provide electricity to the public at retail within the State of Georgia (other than Chatham, Effingham, Fannin, Towns and Union Counties) or to responsible and legally qualified organizations of such municipalities, counties, and/or cooperatives in

the State of Georgia (other than Chatham, Effingham, Fannin, Towns and Union Counties) to the extent they may bind their members.

(b) "Power Company" means Georgia Power Company, any successor, assignee of this license, or assignee of all or substantially all of Georgia Power Company's assets, and any affiliate or subsidiary of Georgia Power Company to the extent it engages in the ownership of any bulk power supply generation or transmission resource in the State of Georgia (but specifically not including (1) flood rights and other land rights acquired in the State of Georgia incidental to hydroelectric generation facilities located in another state and (2) facilities located west of the thread of the stream on that part of the Chattahoochee River serving as the boundary between the states of Georgia and Alabama).

(2) Power Company recognizes that it is often in the public interest for those engaging in bulk power supply and purchases to interconnect, coordinate for reliability and economy, and engage in bulk power supply transactions in order to increase interconnected system reliability and reduce the costs of electric power. Such arrangements must provide for Power Company's costs (including a reasonable return) in connection therewith and allow other participating entities full access to the benefits available from interconnected Renewed License No. NPF-5 Amendment No. bulk power supply operations and must provide net benefits to Power Company. In entering into such arrangements neither Power Company nor any other participant should be required to violate the principles of sound engineering practice or forego a reasonably contemporaneous alternative arrangement with another, developed in good faith in arms length negotiations (but not including arrangements between Power Company and its affiliates or subsidiaries which impair entities' rights hereunder more than they would be impaired were such arrangements made in good faith between Power Company a non-affiliate or non-subsidiary) which affords it greater benefits. Any such arrangement must provide for adequate notice and joint planning procedures consistent with sound engineering practice, and must relieve Power Company from obligations undertaken by it in the event such procedures are not followed by any participating entity.

Power Company recognizes that each entity may acquire some or all of its bulk power supply from sources other than Power Company.

In the implementation of the obligations stated in the succeeding paragraphs, Power Company and entities shall act in accordance with the foregoing principles, and these principles are conditions to each of Power Company's obligations herein undertaken.

(3) Power Company shall interconnect with any entity which provides, or which has undertaken firm contractual obligations to provide, some or all of its bulk power supply from source other than Power Company on terms to be included in an interconnection agreement which shall provide for appropriate allocation of the costs of interconnection facilities; provided, however, that if an entity undertakes to negotiate such a firm contractual obligation, the Power Company shall, in good faith, negotiate with such entity concerning any proposed interconnection. Such interconnection agreement shall provide, without undue preference or discrimination, for the following, among other things, insofar as consistent with the operating necessities of Power Company's and any participating entity's systems:

(a) maintenance and coordination of reserves, including, where appropriate, the purchase and sale thereof, (b) emergency support,

(c) maintenance support, (d) economy energy exchanges,

(e) purchase and sale of firm and non-firm capacity and energy, (f) economic dispatch of power resources within the State of Georgia, provided, however, that in no event shall such arrangements impose a higher percentage of reserve requirements on the participating entity than that maintained by Power Company for similar resources. Renewed License No. NPF-5 Amendment No.

(4) Power Company shall sell full requirements power to any entity. Power Company shall sell partial requirements power to any entity. Such sales shall be made pursuant to rates on file with the Federal Power Commission, or any successor regulatory agency, and subject to reasonable

terms and conditions.

(5) (a) Power Company shall transmit ("transmission service") bulk power over its system to any entity or entities with which it is interconnected, pursuant to rate schedules on file with the Federal Power Commission which will fully compensate Power Company for the use of its system, to the extent that such arrangements can be accommodated from a functional engineering standpoint and to the extent that Power Company has surplus line capacity or reasonably available funds to finance new construction for this purpose. To the

extent the entity or entities are able, they shall reciprocally provide transmission service to Power Company. Transmission service will

be provided under this subparagraph for the delivery of power to an entity for its or its members' consumption and retail distribution or for casual resale to another entity for (1) its consumption or (2) its retail distribution. Nothing contained herein shall require the Power Company to transmit bulk power so as to have the effect of making the Tennessee Valley Authority ("TVA") or its distributors, directly or indirectly, a source of power supply outside the area determined by the TVA Board of Directors by resolution of May 16, 1966 to be the area for which the TVA or its distributors were the primary source of power supply on July 1, 1957, the date specified in the Revenue

Bond Act of 1959, 16 USC 831 n-4.

(b) Power Company shall transmit over its system from any entity or entities with which it is interconnected, pursuant to rate schedules on file with the Federal Power Commission which will fully compensate Power Company for the use of its system, bulk power which results from any such entity having exce ss capacity available from self-owned generating resources in the State of Georgia, to the extent such excess necessarily results from economic unit sizing or from failure to forecast load accurately or from such generating resources becoming operational earlier than the planned in-service date, to the extent that such arrangements can be accommodated from a functional engineering standpoint, and to the extent Power Company has surplus line capacity available.

(6) Upon request, Power Company shall provide service to any entity purchasing partial requirements service, full requ irements service or transmission service from Power Company at a delivery voltage appropriate for loads served by such entity, commensurate with Power Company's available transmission facilities. Sales of such service shall be made pursuant to rates on file with the Federal Power Commission or any successor regulatory agency, and subject to reasonable terms and conditions. Renewed License No. NPF-5 Amendment No. (7) Upon reasonable notice, Power Company shall grant any entity the opportunity to purchase an appropriate share in the ownership of, or, at the option of the entity, to purchase an appropriate share of unit power from each of the following nuclear generating units at Power Company's costs, to the extent the same are constructed and operated: Hatch 2, Vogtle 1, Vogtle 2, and any other nuclear generating unit constructed by Power Company in the State of Georgia which, in the application filed with USAEC or its successor agency, is scheduled for commercial operation prior to January 1, 1989.

An entity's request for a share must have regard for the economic size of such nuclear unit(s), for the entity's load size, growth and characteristics, and for demands upon Power Company's system from other entities and Power Company's retail customers, all in accordance with sound engineering practice. Executory agreements to accomplish the foregoing shall contain provisions reasonably specified by Power Company requiring the entity to consummate and pay for such purchase by an early date or dates certain.

For purposes of this provision, "unit power" shall mean capacity and associated energy from a specified generating unit.

(8) Southern Nuclear shall not market or broker power or energy from Edwin I. Hatch Nuclear Plant, Unit 2. Georgia Power Company shall continue to be responsible for compliance with the obligations imposed on it in its antitrust license conditions. Georgia Power Company is responsible and accountable for the actions of Southern Nuclear, to the extent that Southern Nuclear's actions may, in any way, contravene the existing antitrust license conditions.

(9) To effect the foregoing conditions, the following steps shall be taken:

(a) Power Company shall file with the appropriate regulatory authorities and thereafter maintain in force as needed an appropriate transmission tariff available to any entity;

(b) Power Company shall file with the appropriate regulatory authorities and thereafter maintain in force as needed an appropriate partial requirements tariff available to any entity; Power Company shall have its liability limited to the partial requirements service actually contracted for and the entity shall be made responsible for the security of the bulk power supply resources acquired by the entity from sources other than the Power Company; (c) Power Company shall amend the general terms and conditions of its current Federal Power Commission tariff and thereafter maintain in force as needed provisions to enable any entity to receive bulk power at transmission voltage at appropriate rates; Renewed License No. NPF-5 Amendment No. (d) Power Company shall not have the unilateral right to defeat the intended access by each entity to al ternative sources of bulk power supply provided by the conditions to this license; but Power Company shall retain the right to seek regulatory approval of changes in its tariffs to the end that it be adequately compensated for services it provides, specifically including, but not limited to, the provisions of Section 205 of the Federal Power Act; (e) Power Company shall use its best efforts to amend any outstanding contract to which it is a party that contains provisions which are inconsistent with the conditions of this license;

(f) Power Company affirms that no consents are or will become necessary from Power Company's parent, affiliates or subsidiaries to enable Power Company to carry out its obligations hereunder or to enable the entities to enjoy their rights hereunder;

(g) All provisions of these conditions shall be subject to and implemented in accordance with the laws of the United States and of the State of Georgia, as applicable, and with rules, regulations, and orders of agencies of both, as applicable.

3. This renewed license is effective as of the date of issuance and shall expire at midnight, June 13, 2038.

FOR THE U.S. NUCLEAR REGULATORY COMMISSION

Samuel J. Collins, Director Office of Nuclear Reactor Regulation

Attachments: Appendix A - Technical Specifications Appendix B - Environmental Protection Plan

Date of Issuance: January 15, 2002