RS-16-061, Braidwood, Units 1 and 2 - Transmittal of Exelon Nuclear Radiological Emergency Plan Revision

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Braidwood, Units 1 and 2 - Transmittal of Exelon Nuclear Radiological Emergency Plan Revision
ML16074A415
Person / Time
Site: Braidwood  Constellation icon.png
Issue date: 03/14/2016
From: Imburgia D M
Exelon Generation Co
To:
Document Control Desk, Office of Nuclear Material Safety and Safeguards, Office of Nuclear Reactor Regulation
Shared Package
ML16074A414 List:
References
RS-16-061
Download: ML16074A415 (10)
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Text

Exelon Confidential/Proprietary Information

-Withhold Under 10 CFR 2.390 Attachment 3 contains Exelon Confidential/Proprietary Information; upon separation this cover letter and Attachments 1 and 2 are decontrolled.

Exelon Generation 10 CFR 50.54(q)(5) 10 CFR 50.4 10 CFR 72.44(f) RS-16-061 March 14, 2016 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Braidwood Station, Units 1 and 2

Subject:

Renewed Facility Operating License Nos. NPF-72 and NPF-77 NRC Docket Nos. STN 50-456. STN 50-457, and 72-73 Exelon Nuclear Radiological Emergency Plan Revision In accordance with 10 CFR 50.4(b)(5), 11 Emergency Plan and related submissions, 11 Exelon Generation Company, LLC (EGC) is submitting an Emergency Plan Addendum revision for Braidwood Station (Braidwood) as listed in the table below. Document Revision Title EP-AA-1001, Addendum 3 1 Emergency Action Levels for Braidwood Station The change to the Emergency Plan Addendum was evaluated under the requirements of 1 O CFR 50.54(q) and was determined not to result in a reduction in the effectiveness of the Emergency Plan for Braidwood. This notification is being submitted within 30 days of implementation of the changes as required by 1 O CFR 50.4(b)(5).

The changes continue to meet the applicable planning standards established in 10 CFR 50.47(b) and 10 CFR 50, Appendix E. Furthermore, the Emergency Plan Addendum identified in Attachment 3 of this letter is proprietary and confidential and contains trade secrets and commercial or financial information.

EGC maintains this information on a confidential basis and protects it from disclosure to the general public or unauthorized individuals.

EGC requests that the Emergency Plan Addendum contained in Attachment 3 be withheld from public disclosure pursuant to 1 O CFR 2.390(a)(4), and has attached an affidavit for this purpose (Attachment 2). However, if the NRC intends to place any of this information in the Public Document Room or on the Agencywide Documents Access and Management System or produce it in response to a Freedom of Information Act (FOIA) request, EGC requests the opportunity to redact the materials consistent with established FOIA exemptions and precedent.

Exelon Confidential/Proprietary Information

-Withhold Under 10 CFR 2.390 Attachment 3 contains Exelon Confidential/Proprietary Information; upon separation this cover letter and Attachments 1 and 2 are decontrolled.

U.S. Nuclear Regulatory Commission Emergency Plan Addendum Revision March 14, 2016 Page2 In addition, as required by 10 CFR 50.54(q)(5), this submittal includes a summary analysis of the changes to the Emergency Plan Addendum (Attachment 1 ). This submittal also satisfies the reporting requirements associated with 1 O CFR 72.44(f), which stipulates that within six months after any change is made to the Emergency Plan, the licensee shall submit a report containing a description of the changes to the Director, Division of Spent Fuel Storage and Transportation.

A copy of the revised Emergency Plan Addendum and supporting change summary analysis are included in the attachments to this letter. There are no regulatory commitments in this submittal.

If you have any questions or require additional information, please contact Amy Hambly at (630) 657-2808.

Respectfully, Dominic M. Imburgia Manager -Licensing Programs Exelon Generation Company, LLC Attachments:

1. 1 O CFR 50.54(q)(5)

Procedure Change Summary Analysis 2. Affidavit

3. EP-AA-1001, Addendum 3, Revision 1, Emergency Action Levels for Braidwood Station cc: Regional Administrator

-NRC Region Ill Director, NRC Division of Spent Fuel Storage and Transportation, ONMSS NRC Senior Resident Inspector

-Braidwood Station NRC Project Manager, NRR -Braidwood Station ATTACHMENT 1 10 CFR 50.54(q)(5)

Procedure Change Summary Analysis 1 O CFR 50.54{g){5)

Procedure Change Summary Analysis Procedure title Exelon Generation Company, LLC (EGC) is submitting the following Emergency Plan Addendum revision for Braidwood Station (Braidwood):

  • EP-AA-1001, Addendum 3, Revision 1, 11 Emergency Action Levels for Braidwood Station 11 This document contains Exelon Confidential/Proprietary Information and is requested to be withheld from public disclosure pursuant to 1 O CFR 2.390. Description of procedure EP-AA-1001, Addendum 3 describes the Emergency Action Levels (EALs) implemented at Braidwood for entering Emergency Classification Levels (ECLs). Description of change This revision to EP-AA-1001, Addendum 3 for Braidwood incorporates the following changes: 1. Implementation of NEI 99-01, Revision 6, 11 Development of Emergency Action Levels for Non-Passive Reactors, 11 which involved a complete rewrite/formatting of the document.
2. Establishes EAL thresholds for the NRC pre-approved EALs RG2 and RS2 and an additional threshold for RA2 based on Spent Fuel Pool (SFP) levels. 3. Revised EAL MU3 (ATWS) to provide clarity regarding a successful reactor shutdown.

A more detailed description of the changes is provided below. 1. The revised EAL schemes based on NEI 99-01, Revision 6 were submitted to the NRC in a License Amendment Request (LAR) dated May 30, 2014. The NRC approved the LAR as documented in a letter and supporting Safety Evaluation Report (SER) dated July 28, 2015. Training was satisfactorily completed for the Braidwood and supporting Corporate Emergency Response Organization (ERO) personnel on the revised EAL schemes during the fourth quarter of 2015. As a result, the NRG-approved EAL schemes based on the NEI 99-01, Revision 6 guidance were implemented and this revision to EP-AA-1001, Addendum 3 reflects the changes. 2. As part of the NRC approval of the new EAL Scheme, three new thresholds were approved generically without specific levels associated with them. The levels are based on enhanced SFP level devices placed in service in accordance with the information provided in Section 1.4, of NRC Order EA-12-051.

NEI 99-01, Revision 6 recommended that these EAL thresholds be implemented when the enhanced SFP level instrumentation is available for use. At Braidwood, the enhanced SFP level instruments were placed in service in accordance with a site-approved design change package. For the new EALs RG2 and RS2 a 11 site specific level 3 11 threshold value is used and for RA2 there is a third threshold that uses a Page 1 of 3 Attachment 1

11 site specific level 2" value. Based on the site-approved design change package the following thresholds were used for each of the site-specific values: A supporting site-approved calculation was used to document the logic and assumptions for establishing the EAL thresholds for SFP 11 site specific level 3 11 and "site specific level 2.11

  • For EAL thresholds RG2 and RS2, the value of 1.00 foot was calculated for 11 site specific level 3 11 value.
  • For EAL threshold RA2.3 the value of 10.50 feet was calculated for 11 site specific level 2 11 value. For EALs RG2 and RS2 the value of 1.00 foot as indicated on applicable instrumentation was chosen as being indicative of the immediate need to restore SPF level. For EAL threshold RA2.3 the value of 10.50 feet as indicated applicable instrumentation was chosen as being the SFP level that is adequate to provide substantial radiation shielding for a person standing on the SFP operating deck. The site-specific levels are determined in accordance with NRC Order EA-12-051 and NEI 12-02, 11 lndustry Guidance for Compliance with NRC Order EA-12-051, 'To Modify Licenses with Regard to Reliable Spent Fuel Pool lnstrumentation, 111 and applicable owner's group guidance, and have been modified to reflect site-specific constraints and limitations associated with the design and operation of the applicable instrumentation as required by the developer guidance in the NRG-endorsed NEI 99-01, Revision 6 guidance.

Updating the EAL threshold values based on an NRG-accepted methodology and the resulting approved design change and supporting calculation does not alter the meaning or intent of the basis of the EAL provided in the NRC's SER approving the EALs. 3. A change is being made to EAL MU3 (ATWS) to provide further clarification regarding a successful reactor shutdown in order to avoid confusion when making the assessment.

The following clarifying statement has been added in three places in the EAL. 11 *** as indicated by Reactor Power <5% ... 11 The addition of the phrase 11 as indicated by Reactor Power <5%," to EAL MU3, as the criteria to determine a successful reactor shutdown clarifies the indication to be used for this determination and will eliminate any potential confusion.

This ensures that consistency is applied within EAL MU3 for determining that the reactor is not shutdown and is also being used to determine a successful reactor shutdown.

This change is also in keeping with the escalation path for EAL MA3 and MS3 regarding the determination for reactor shutdown.

Description of how the change still complies with regulations This revision to the EP-AA-1001, Addendum 3 continues to satisfy the applicable Emergency Planning requirements established in 1 O CFR 50.47(b)(4) and the Program Element guidance specified in NUREG-0654, Section 11.D as noted below. 1. This revision to EP-AA-1001, Addendum 3 implements the EAL scheme changes reviewed and approved by the NRC as documented in its letter dated July 28, 2015. As Page 2 of 3 Attachment 1

such, the NRC has determined that this revision to the Emergency Plan Addendum is acceptable and the changes satisfy regulatory requirements and commitments.

2. Updating the threshold values for EALs RG2, RS2, and RA2 based on NRG-accepted methodology and site-approved design change documentation and supporting calculation does not alter the meaning or intent of the basis for the approved EALs. The applicable emergency planning regulations and commitments continue to be met. 3. Updating the threshold value for MU3 to provide further clarification regarding the assessment for determining a successful reactor shutdown does not alter the meaning or intent of the basis of the approved EAL. The applicable emergency planning regulations and commitments continue to be met. Description of why the change is not a reduction in effectiveness (RIE) 1. The change to the Braidwood EAL schemes reflects the NRC's approval of the LAR as documented in its letter and supporting SER dated July 28, 2015 (i.e., Braidwood Amendment No. 184 to Facility Operating License No. NPF-72 and Amendment No. 184 to Facility Operating License No. NPF-77). The applicable emergency planning regulations and commitments continue to be met. Therefore, this change does not result in a reduction in effectiveness of the Braidwood Emergency Plan. 2. The changes to EALs RG2, RS2, and RA2 reflect the changes as approved by the NRC as documented in its letter and supporting SER dated July 28, 2015. The approved EALs had indicated that a site-specific threshold value would be added upon installation of enhanced SFP level devices in accordance with NRC Order EA-12-051.

Braidwood has subsequently installed the enhanced SFP level devices and threshold values have been established in accordance with a site-approved design change and supporting calculation.

Updating the EAL threshold values based on an approved technical analysis does not alter the meaning or intent of the basis of the approved EALs. The applicable emergency planning regulations and commitments continue to be met. Therefore, this change does not result in a reduction in effectiveness of the Braidwood Emergency Plan. 3. The change to EAL MU3 (ATWS) is being made to provide additional clarification regarding the determination for assessing a successful reactor shutdown.

This clarification will ensure consistency is applied within EAL MU3 for determining when the reactor is not shutdown and when a successful reactor shutdown has been achieved.

This change is also in keeping with the escalation path for EAL MA3 and MS3 regarding the determination of reactor shutdown.

Updating the EAL threshold to include the additional clarification in the assessment of determining a successful reactor shutdown does not alter the meaning or intent of the basis of the approved EAL. The applicable emergency planning regulations and commitments continue to be met. Therefore, this change does not result in a reduction in effectiveness of the Braidwood Emergency Plan. Page 3 of 3 Attachment 1

ATTACHMENT 2 Affidavit AFFIDAVIT OF DOMINIC M. IMBURGIA DOCKET NOS. STN 50-456, STN 50-457, and 72-73 I, Dominic M. Imburgia, Manager -Licensing Programs, Exelon Generation Company, LLC, do hereby affirm and state: 1. I am Manager, Licensing Programs for Exelon Generation Company, LLC (EGC), and I am authorized to execute this affidavit on behalf of EGC. 2. I am further authorized to review the documents sought to be withheld from public disclosure in connection with submittals to the Nuclear Regulatory Commission

("NRC"):

  • EP-AA-1001, Addendum 3, Revision 1, 11 Emergency Action Levels for Braidwood Station 11 3. I am also authorized to apply to the N RC for the withholding of the aforementioned documents from public disclosure under 1 O CFR 2.390(a)(4) and 9.17(a)(4) on the grounds that the documents contain privileged or confidential or proprietary commercial information.

The documents EGC seeks to withhold from public disclosure have been marked 11 Proprietary 11 and are summarized in the attachment to my Affidavit.

4. On behalf of EGC, I request that the documents marked by EGC as 11 Proprietary 11 and described in the attached list (Appendix
1) be withheld, in their entirety, by the NRC from public disclosure.
5. In making this application for withholding of proprietary and confidential information of which EGC is the owner, EGC relies on 10 CFR 2.390(a)(4) and 10 CFR 9.17(a)(4).

The proprietary documents contain privileged or confidential or proprietary commercial information.

6. The proprietary information described in Appendix 1 should be withheld from disclosure by the NRC pursuant to the policy reflected in 1 O CFR 2.390(a)(4), and for the following reasons to be considered pursuant to 1 O CFR 2.390(b)(4):

i.. The documents are each either a policy, procedure, process, technical requirements document, or other document that forms part of the Exelon Nuclear Management Model (ENMM). ii. The ENMM is a set of confidential policies and procedures that enable EGC to consistently achieve excellence in all key dimensions of its business.

It documents proven ways of achieving excellence and defines how EGC executes and manages performance and assesses results. EGC expended significant resources, in terms of time and money, to develop, implement, and update the ENMM. EGC derives economic benefit from the ENMM in terms of increased efficiency and improved results as well as revenue generated from EGC's sale or licensing of the ENMM. iii. The documents are now, and have been, held in confidence by EGC. EGC does not customarily make these documents available to the public. EGC has not authorized making the documents available through public sources. iv. EGC is providing the NRC with the documents and information in confidence.

Page 1 of 3 Attachment 2

v. Economic harm would come to EGC with the publication of the individual documents that form the ENMM, as it would reduce or eliminate the need for any third party to purchase or license the ENMM from EGC, and would reduce the competitive position of EGC based on the benefits that the ENMM provides to EGC in the management of its own nuclear plants. The ENMM is considered by EGC to be a very valuable part of our intellectual property and it would be very difficult, costly and time-consuming for another to duplicate it without access to these documents.
7. EGC requests that the document listed in Appendix 1 be withheld from public disclosure based on the reasons stated above in paragraph 6.i. through 6.v. I declare under penalty of perjury that the foregoing affidavit and statements therein are true and correct to the best of my knowledge, information, and belief. Dominic M. Imburgia Manager -Licensing Programs Exelon Generation Company, LLC Date: March 14, 2016 Page 2 of 3 Attachment 2

Appendix 1: Information that Should Be Withheld from Public Disclosure Date or Revision Description of Document Reason(s) to Withhold Entire document exempt from disclosure under 10 CFR 2.390(a)(4) and Revision 1 EP-AA-1001, Addendum 3 9.17(a)(4) based on paragraph 6 of the affidavit to which this Appendix 1 is attached.

Page 3 of 3 Attachment 2

Exelon Confidential/Proprietary Information

-Withhold Under 10 CFR 2.390 Attachment 3 contains Exelon Confidential/Proprietary Information; upon separation this cover letter and Attachments 1 and 2 are decontrolled.

Exelon Generation 10 CFR 50.54(q)(5) 10 CFR 50.4 10 CFR 72.44(f) RS-16-061 March 14, 2016 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Braidwood Station, Units 1 and 2

Subject:

Renewed Facility Operating License Nos. NPF-72 and NPF-77 NRC Docket Nos. STN 50-456. STN 50-457, and 72-73 Exelon Nuclear Radiological Emergency Plan Revision In accordance with 10 CFR 50.4(b)(5), 11 Emergency Plan and related submissions, 11 Exelon Generation Company, LLC (EGC) is submitting an Emergency Plan Addendum revision for Braidwood Station (Braidwood) as listed in the table below. Document Revision Title EP-AA-1001, Addendum 3 1 Emergency Action Levels for Braidwood Station The change to the Emergency Plan Addendum was evaluated under the requirements of 1 O CFR 50.54(q) and was determined not to result in a reduction in the effectiveness of the Emergency Plan for Braidwood. This notification is being submitted within 30 days of implementation of the changes as required by 1 O CFR 50.4(b)(5).

The changes continue to meet the applicable planning standards established in 10 CFR 50.47(b) and 10 CFR 50, Appendix E. Furthermore, the Emergency Plan Addendum identified in Attachment 3 of this letter is proprietary and confidential and contains trade secrets and commercial or financial information.

EGC maintains this information on a confidential basis and protects it from disclosure to the general public or unauthorized individuals.

EGC requests that the Emergency Plan Addendum contained in Attachment 3 be withheld from public disclosure pursuant to 1 O CFR 2.390(a)(4), and has attached an affidavit for this purpose (Attachment 2). However, if the NRC intends to place any of this information in the Public Document Room or on the Agencywide Documents Access and Management System or produce it in response to a Freedom of Information Act (FOIA) request, EGC requests the opportunity to redact the materials consistent with established FOIA exemptions and precedent.

Exelon Confidential/Proprietary Information

-Withhold Under 10 CFR 2.390 Attachment 3 contains Exelon Confidential/Proprietary Information; upon separation this cover letter and Attachments 1 and 2 are decontrolled.

U.S. Nuclear Regulatory Commission Emergency Plan Addendum Revision March 14, 2016 Page2 In addition, as required by 10 CFR 50.54(q)(5), this submittal includes a summary analysis of the changes to the Emergency Plan Addendum (Attachment 1 ). This submittal also satisfies the reporting requirements associated with 1 O CFR 72.44(f), which stipulates that within six months after any change is made to the Emergency Plan, the licensee shall submit a report containing a description of the changes to the Director, Division of Spent Fuel Storage and Transportation.

A copy of the revised Emergency Plan Addendum and supporting change summary analysis are included in the attachments to this letter. There are no regulatory commitments in this submittal.

If you have any questions or require additional information, please contact Amy Hambly at (630) 657-2808.

Respectfully, Dominic M. Imburgia Manager -Licensing Programs Exelon Generation Company, LLC Attachments:

1. 1 O CFR 50.54(q)(5)

Procedure Change Summary Analysis 2. Affidavit

3. EP-AA-1001, Addendum 3, Revision 1, Emergency Action Levels for Braidwood Station cc: Regional Administrator

-NRC Region Ill Director, NRC Division of Spent Fuel Storage and Transportation, ONMSS NRC Senior Resident Inspector

-Braidwood Station NRC Project Manager, NRR -Braidwood Station ATTACHMENT 1 10 CFR 50.54(q)(5)

Procedure Change Summary Analysis 1 O CFR 50.54{g){5)

Procedure Change Summary Analysis Procedure title Exelon Generation Company, LLC (EGC) is submitting the following Emergency Plan Addendum revision for Braidwood Station (Braidwood):

  • EP-AA-1001, Addendum 3, Revision 1, 11 Emergency Action Levels for Braidwood Station 11 This document contains Exelon Confidential/Proprietary Information and is requested to be withheld from public disclosure pursuant to 1 O CFR 2.390. Description of procedure EP-AA-1001, Addendum 3 describes the Emergency Action Levels (EALs) implemented at Braidwood for entering Emergency Classification Levels (ECLs). Description of change This revision to EP-AA-1001, Addendum 3 for Braidwood incorporates the following changes: 1. Implementation of NEI 99-01, Revision 6, 11 Development of Emergency Action Levels for Non-Passive Reactors, 11 which involved a complete rewrite/formatting of the document.
2. Establishes EAL thresholds for the NRC pre-approved EALs RG2 and RS2 and an additional threshold for RA2 based on Spent Fuel Pool (SFP) levels. 3. Revised EAL MU3 (ATWS) to provide clarity regarding a successful reactor shutdown.

A more detailed description of the changes is provided below. 1. The revised EAL schemes based on NEI 99-01, Revision 6 were submitted to the NRC in a License Amendment Request (LAR) dated May 30, 2014. The NRC approved the LAR as documented in a letter and supporting Safety Evaluation Report (SER) dated July 28, 2015. Training was satisfactorily completed for the Braidwood and supporting Corporate Emergency Response Organization (ERO) personnel on the revised EAL schemes during the fourth quarter of 2015. As a result, the NRG-approved EAL schemes based on the NEI 99-01, Revision 6 guidance were implemented and this revision to EP-AA-1001, Addendum 3 reflects the changes. 2. As part of the NRC approval of the new EAL Scheme, three new thresholds were approved generically without specific levels associated with them. The levels are based on enhanced SFP level devices placed in service in accordance with the information provided in Section 1.4, of NRC Order EA-12-051.

NEI 99-01, Revision 6 recommended that these EAL thresholds be implemented when the enhanced SFP level instrumentation is available for use. At Braidwood, the enhanced SFP level instruments were placed in service in accordance with a site-approved design change package. For the new EALs RG2 and RS2 a 11 site specific level 3 11 threshold value is used and for RA2 there is a third threshold that uses a Page 1 of 3 Attachment 1

11 site specific level 2" value. Based on the site-approved design change package the following thresholds were used for each of the site-specific values: A supporting site-approved calculation was used to document the logic and assumptions for establishing the EAL thresholds for SFP 11 site specific level 3 11 and "site specific level 2.11

  • For EAL thresholds RG2 and RS2, the value of 1.00 foot was calculated for 11 site specific level 3 11 value.
  • For EAL threshold RA2.3 the value of 10.50 feet was calculated for 11 site specific level 2 11 value. For EALs RG2 and RS2 the value of 1.00 foot as indicated on applicable instrumentation was chosen as being indicative of the immediate need to restore SPF level. For EAL threshold RA2.3 the value of 10.50 feet as indicated applicable instrumentation was chosen as being the SFP level that is adequate to provide substantial radiation shielding for a person standing on the SFP operating deck. The site-specific levels are determined in accordance with NRC Order EA-12-051 and NEI 12-02, 11 lndustry Guidance for Compliance with NRC Order EA-12-051, 'To Modify Licenses with Regard to Reliable Spent Fuel Pool lnstrumentation, 111 and applicable owner's group guidance, and have been modified to reflect site-specific constraints and limitations associated with the design and operation of the applicable instrumentation as required by the developer guidance in the NRG-endorsed NEI 99-01, Revision 6 guidance.

Updating the EAL threshold values based on an NRG-accepted methodology and the resulting approved design change and supporting calculation does not alter the meaning or intent of the basis of the EAL provided in the NRC's SER approving the EALs. 3. A change is being made to EAL MU3 (ATWS) to provide further clarification regarding a successful reactor shutdown in order to avoid confusion when making the assessment.

The following clarifying statement has been added in three places in the EAL. 11 *** as indicated by Reactor Power <5% ... 11 The addition of the phrase 11 as indicated by Reactor Power <5%," to EAL MU3, as the criteria to determine a successful reactor shutdown clarifies the indication to be used for this determination and will eliminate any potential confusion.

This ensures that consistency is applied within EAL MU3 for determining that the reactor is not shutdown and is also being used to determine a successful reactor shutdown.

This change is also in keeping with the escalation path for EAL MA3 and MS3 regarding the determination for reactor shutdown.

Description of how the change still complies with regulations This revision to the EP-AA-1001, Addendum 3 continues to satisfy the applicable Emergency Planning requirements established in 1 O CFR 50.47(b)(4) and the Program Element guidance specified in NUREG-0654, Section 11.D as noted below. 1. This revision to EP-AA-1001, Addendum 3 implements the EAL scheme changes reviewed and approved by the NRC as documented in its letter dated July 28, 2015. As Page 2 of 3 Attachment 1

such, the NRC has determined that this revision to the Emergency Plan Addendum is acceptable and the changes satisfy regulatory requirements and commitments.

2. Updating the threshold values for EALs RG2, RS2, and RA2 based on NRG-accepted methodology and site-approved design change documentation and supporting calculation does not alter the meaning or intent of the basis for the approved EALs. The applicable emergency planning regulations and commitments continue to be met. 3. Updating the threshold value for MU3 to provide further clarification regarding the assessment for determining a successful reactor shutdown does not alter the meaning or intent of the basis of the approved EAL. The applicable emergency planning regulations and commitments continue to be met. Description of why the change is not a reduction in effectiveness (RIE) 1. The change to the Braidwood EAL schemes reflects the NRC's approval of the LAR as documented in its letter and supporting SER dated July 28, 2015 (i.e., Braidwood Amendment No. 184 to Facility Operating License No. NPF-72 and Amendment No. 184 to Facility Operating License No. NPF-77). The applicable emergency planning regulations and commitments continue to be met. Therefore, this change does not result in a reduction in effectiveness of the Braidwood Emergency Plan. 2. The changes to EALs RG2, RS2, and RA2 reflect the changes as approved by the NRC as documented in its letter and supporting SER dated July 28, 2015. The approved EALs had indicated that a site-specific threshold value would be added upon installation of enhanced SFP level devices in accordance with NRC Order EA-12-051.

Braidwood has subsequently installed the enhanced SFP level devices and threshold values have been established in accordance with a site-approved design change and supporting calculation.

Updating the EAL threshold values based on an approved technical analysis does not alter the meaning or intent of the basis of the approved EALs. The applicable emergency planning regulations and commitments continue to be met. Therefore, this change does not result in a reduction in effectiveness of the Braidwood Emergency Plan. 3. The change to EAL MU3 (ATWS) is being made to provide additional clarification regarding the determination for assessing a successful reactor shutdown.

This clarification will ensure consistency is applied within EAL MU3 for determining when the reactor is not shutdown and when a successful reactor shutdown has been achieved.

This change is also in keeping with the escalation path for EAL MA3 and MS3 regarding the determination of reactor shutdown.

Updating the EAL threshold to include the additional clarification in the assessment of determining a successful reactor shutdown does not alter the meaning or intent of the basis of the approved EAL. The applicable emergency planning regulations and commitments continue to be met. Therefore, this change does not result in a reduction in effectiveness of the Braidwood Emergency Plan. Page 3 of 3 Attachment 1

ATTACHMENT 2 Affidavit AFFIDAVIT OF DOMINIC M. IMBURGIA DOCKET NOS. STN 50-456, STN 50-457, and 72-73 I, Dominic M. Imburgia, Manager -Licensing Programs, Exelon Generation Company, LLC, do hereby affirm and state: 1. I am Manager, Licensing Programs for Exelon Generation Company, LLC (EGC), and I am authorized to execute this affidavit on behalf of EGC. 2. I am further authorized to review the documents sought to be withheld from public disclosure in connection with submittals to the Nuclear Regulatory Commission

("NRC"):

  • EP-AA-1001, Addendum 3, Revision 1, 11 Emergency Action Levels for Braidwood Station 11 3. I am also authorized to apply to the N RC for the withholding of the aforementioned documents from public disclosure under 1 O CFR 2.390(a)(4) and 9.17(a)(4) on the grounds that the documents contain privileged or confidential or proprietary commercial information.

The documents EGC seeks to withhold from public disclosure have been marked 11 Proprietary 11 and are summarized in the attachment to my Affidavit.

4. On behalf of EGC, I request that the documents marked by EGC as 11 Proprietary 11 and described in the attached list (Appendix
1) be withheld, in their entirety, by the NRC from public disclosure.
5. In making this application for withholding of proprietary and confidential information of which EGC is the owner, EGC relies on 10 CFR 2.390(a)(4) and 10 CFR 9.17(a)(4).

The proprietary documents contain privileged or confidential or proprietary commercial information.

6. The proprietary information described in Appendix 1 should be withheld from disclosure by the NRC pursuant to the policy reflected in 1 O CFR 2.390(a)(4), and for the following reasons to be considered pursuant to 1 O CFR 2.390(b)(4):

i.. The documents are each either a policy, procedure, process, technical requirements document, or other document that forms part of the Exelon Nuclear Management Model (ENMM). ii. The ENMM is a set of confidential policies and procedures that enable EGC to consistently achieve excellence in all key dimensions of its business.

It documents proven ways of achieving excellence and defines how EGC executes and manages performance and assesses results. EGC expended significant resources, in terms of time and money, to develop, implement, and update the ENMM. EGC derives economic benefit from the ENMM in terms of increased efficiency and improved results as well as revenue generated from EGC's sale or licensing of the ENMM. iii. The documents are now, and have been, held in confidence by EGC. EGC does not customarily make these documents available to the public. EGC has not authorized making the documents available through public sources. iv. EGC is providing the NRC with the documents and information in confidence.

Page 1 of 3 Attachment 2

v. Economic harm would come to EGC with the publication of the individual documents that form the ENMM, as it would reduce or eliminate the need for any third party to purchase or license the ENMM from EGC, and would reduce the competitive position of EGC based on the benefits that the ENMM provides to EGC in the management of its own nuclear plants. The ENMM is considered by EGC to be a very valuable part of our intellectual property and it would be very difficult, costly and time-consuming for another to duplicate it without access to these documents.
7. EGC requests that the document listed in Appendix 1 be withheld from public disclosure based on the reasons stated above in paragraph 6.i. through 6.v. I declare under penalty of perjury that the foregoing affidavit and statements therein are true and correct to the best of my knowledge, information, and belief. Dominic M. Imburgia Manager -Licensing Programs Exelon Generation Company, LLC Date: March 14, 2016 Page 2 of 3 Attachment 2

Appendix 1: Information that Should Be Withheld from Public Disclosure Date or Revision Description of Document Reason(s) to Withhold Entire document exempt from disclosure under 10 CFR 2.390(a)(4) and Revision 1 EP-AA-1001, Addendum 3 9.17(a)(4) based on paragraph 6 of the affidavit to which this Appendix 1 is attached.

Page 3 of 3 Attachment 2

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