AEP-NRC-2013-55, Response to a Request for Additional Information Regarding the Application for Amendment to Transition the Fire Protection Program to National Fire Protection Association Standard 805 TAC (ME6629 and ME6630).: Difference between revisions

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| issue date = 06/21/2013
| issue date = 06/21/2013
| title = Response to a Request for Additional Information Regarding the Application for Amendment to Transition the Fire Protection Program to National Fire Protection Association Standard 805 TAC (ME6629 and ME6630).
| title = Response to a Request for Additional Information Regarding the Application for Amendment to Transition the Fire Protection Program to National Fire Protection Association Standard 805 TAC (ME6629 and ME6630).
| author name = Gebbie J P
| author name = Gebbie J
| author affiliation = Indiana Michigan Power Co
| author affiliation = Indiana Michigan Power Co
| addressee name =  
| addressee name =  
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==References:==
==References:==
: 1. Letter from M. H. Carlson, Indiana Michigan Power Company (I&M), to U. S. Nuclear Regulatory Commission (NRC) Document Control Desk, "Donald C. Cook Nuclear Plant Units 1 and 2, Docket Nos. 50-315 and 50-316, Request for License Amendment to Adopt National Fire Protection Association (NFPA) 805 Performance-Based Standard for Fire Protection for Light Water Reactor Generating Plants (2001 Edition)," AEP-NRC-201 1-1, dated July 1,2011, ADAMS Accession No. ML11188A145.
: 1. Letter from M. H. Carlson, Indiana Michigan Power Company (I&M), to U. S. Nuclear Regulatory Commission (NRC) Document Control Desk, "Donald C. Cook Nuclear Plant Units 1 and 2, Docket Nos. 50-315 and 50-316, Request for License Amendment to Adopt National Fire Protection Association (NFPA) 805 Performance-Based Standard for Fire Protection for Light Water Reactor Generating Plants (2001 Edition)," AEP-NRC-201 1-1, dated July 1,2011, ADAMS Accession No. ML11188A145.
: 2. Letter from J. P. Gebbie, I&M, to NRC Document Control Desk, "Donald C. Cook Nuclear Plant Units 1 and 2, Docket Nos. 50-315 and 50-316, Supplement to Request for License Amendment to Adopt National Fire Protection Association (NFPA) 805 Performance-Based Standard for Fire Protection for Light Water Reactor Generating Plants (2001 Edition)," AEP-NRC-2011-62, dated September 2, 2011, ADAMS Accession No. ML 11 256A030.3. Letter from P. S. Tam, NRC, to L. J. Weber, I&M, "Donald C. Cook Nuclear Plant, Units 1 and 2 -Request for Additional Information on the Application for Amendment to Transition the Fire Protection Program to National Fire Protection Association Standard 805 (TAC Nos. ME6629 AND ME6630)," dated January 27, 2012, ADAMS Accession Nos.ML113560709, ML12003A186, and ML12017A251.
: 2. Letter from J. P. Gebbie, I&M, to NRC Document Control Desk, "Donald C. Cook Nuclear Plant Units 1 and 2, Docket Nos. 50-315 and 50-316, Supplement to Request for License Amendment to Adopt National Fire Protection Association (NFPA) 805 Performance-Based Standard for Fire Protection for Light Water Reactor Generating Plants (2001 Edition)," AEP-NRC-2011-62, dated September 2, 2011, ADAMS Accession No. ML11256A030.3. Letter from P. S. Tam, NRC, to L. J. Weber, I&M, "Donald C. Cook Nuclear Plant, Units 1 and 2 -Request for Additional Information on the Application for Amendment to Transition the Fire Protection Program to National Fire Protection Association Standard 805 (TAC Nos. ME6629 AND ME6630)," dated January 27, 2012, ADAMS Accession Nos.ML113560709, ML12003A186, and ML12017A251.
: 4. E-Mail from P. S. Tam, NRC, to H. L. Etheridge, J. R. Waters, M. K. Scarpello, I&M, et al.,"D.C. Cook -Draft RAI re. Transition to NFPA 805, Questions in Health Physics (TAC ME6629 and ME6630)," dated March 22, 2012, ADAMS Accession No. ML12082A043.
: 4. E-Mail from P. S. Tam, NRC, to H. L. Etheridge, J. R. Waters, M. K. Scarpello, I&M, et al.,"D.C. Cook -Draft RAI re. Transition to NFPA 805, Questions in Health Physics (TAC ME6629 and ME6630)," dated March 22, 2012, ADAMS Accession No. ML12082A043.
: 5. Letter from M. H. Carlson, I&M, to NRC Document Control Desk, "Donald C. Cook Nuclear Plant Units 1 and 2, Response to Request for Additional Information Regarding the Application for Amendment to Transition the Fire Protection Program to National Fire Protection Association Standard 805, (TAC Nos. ME6629 AND ME6630)," AEP-NRC-2012-29, dated April 27, 2012, ADAMS Accession No. ML12132A390.
: 5. Letter from M. H. Carlson, I&M, to NRC Document Control Desk, "Donald C. Cook Nuclear Plant Units 1 and 2, Response to Request for Additional Information Regarding the Application for Amendment to Transition the Fire Protection Program to National Fire Protection Association Standard 805, (TAC Nos. ME6629 AND ME6630)," AEP-NRC-2012-29, dated April 27, 2012, ADAMS Accession No. ML12132A390.

Revision as of 02:18, 22 June 2019

Response to a Request for Additional Information Regarding the Application for Amendment to Transition the Fire Protection Program to National Fire Protection Association Standard 805 TAC (ME6629 and ME6630).
ML13178A209
Person / Time
Site: Cook  American Electric Power icon.png
Issue date: 06/21/2013
From: Gebbie J
Indiana Michigan Power Co
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
AEP-NRC-2013-55
Download: ML13178A209 (27)


Text

INDIANA Indiana Michigan Power MICHIGAN Cook Nuclear Plant POWER 0 One Cook Place Bridgman, MI 49106 A unit of American Electric Power IndianaMichiganPower.com June 21, 2013 AEP-NRC-2013-55 10 CFR 50.90 Docket Nos.: 50-315 50-316 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D. C. 20555-0001 Donald C. Cook Nuclear Plant Units 1 and 2 Response to a Request for Additional Information Regarding the Application for Amendment to Transition the Fire Protection Program to National Fire Protection Association Standard 805 (TAC Nos. ME6629 and ME6630) and the Use of Compensatory Measures Associated With the Proposed Modifications.

This letter provides Indiana Michigan Power Company's (I&M's), licensee for Donald C. Cook Nuclear Plant (CNP) Units 1 and 2, response to Requests for Additional Information (RAI) by the U. S. Nuclear Regulatory Commission (NRC) regarding a proposed license amendment to transition CNP, Units 1 and 2, to a new fire protection program based on National Fire Protection Association Standard 805 (NFPA 805).By References 1 and 2, I&M proposed to amend CNP Units 1 and 2 Facility Operating Licenses DPR-58 and DPR-74 to adopt a new fire protection program based on NFPA 805, in accordance with 10 CFR 50.48(a) and (c). Reference 1, hereafter referred to as the Transition Report, provided information associated with the CNP transition to NFPA 805. By References 3, 4, 8, 9, 11, and 14, the NRC transmitted RAIs regarding the proposed amendment.

References 5, 6, 7, 12, 13, 15, 16, and 17 transmitted I&M's responses to the Reference 3, 4, 8, 9, 11, and 14 RAIs. By Reference 18, the NRC transmitted RAls regarding the Transition Report Attachment M ("Licensing Condition Changes"), of Reference

17. This letter provides I&M's response to Reference 18.On Page 5 of the Transition Report, the listing of approved Safety Evaluation Reports (SERs)includes an entry of February 1, 1990, for each CNP Unit. This SER date is also in the current license conditions for CNP Units 1 and 2. It has been identified that this SER date is incorrect.

The correct SER date is February 8, 1990. This condition has been entered into I&M's corrective action program and will be resolved upon issuance of the NRC's approval of the proposed License Amendment for transition to a new fire protection program based on NFPA 805.vLe U. S. Nuclear Regulatory Commission AEP-NRC-2013-55 Page 2 Enclosure 1 to this letter provides an affirmation statement.

Enclosure 2 identifies documents referenced in this letter and its enclosures.

Enclosures 3 and 4 provide revisions to Attachments M and S, respectively, of the Transition Report.Copies of this letter and its enclosures are being transmitted to the Michigan Public Service Commission and Michigan Department of Environmental Quality, in accordance with the requirements of 10 CFR 50.91. There are no new regulatory commitments associated with this response.

Should you have any questions, please contact Mr. Michael K. Scarpello, Regulatory Affairs Manager, at (269) 466-2649.Sincerely, Joel P. Gebbie Site Vice President JMT/rdw

Enclosures:

1. Affirmation
2. Identification of Documents Referenced in this Letter and its Enclosures
3. Revision 5 of Attachment M, "License Condition Changes," to the Transition Report Provided in Support of Response to Request for Additional Information Concerning NFPA 805 LAR Supplement Dated 5/1/13 4. Revision 6 of Attachment S, "Plant Modifications and Items to be Completed During Implementation," to the Transition Report, Provided in Support of Response to Request for Additional Information Concerning NFPA 805 LAR Supplement Dated 5/1/13 c: C. A. Casto, NRC Region III J. T. King, MPSC S. M. Krawec, AEP Ft. Wayne, w/o enclosures MDEQ -RMD/RPS NRC Resident Inspector T. J. Wengert, NRC Washington, DC Enclosure 1 to AEP-NRC-2013-55 AFFIRMATION I, Joel P. Gebbie, being duly sworn, state that I am Site Vice President of Indiana Michigan Power Company (I&M), that I am authorized to sign and file this request with the Nuclear Regulatory Commission on behalf of I&M, and that the statements made and the matters set forth herein pertaining to I&M are true and correct to the best of my knowledge, information, and belief.Indiana Michigan Power Company Joel P. Gebbie Site Vice President SWORN TO AND SUBSCRIBED BEFORE ME THISc2s DAY OF Q--&_e ,2013 Notary Pub My Commission Expires \T;a I .W'3 Enclosure 2 to AEP-NRC-2013-55 Identification of Documents Referenced in this Letter and Its Enclosures

References:

1. Letter from M. H. Carlson, Indiana Michigan Power Company (I&M), to U. S. Nuclear Regulatory Commission (NRC) Document Control Desk, "Donald C. Cook Nuclear Plant Units 1 and 2, Docket Nos. 50-315 and 50-316, Request for License Amendment to Adopt National Fire Protection Association (NFPA) 805 Performance-Based Standard for Fire Protection for Light Water Reactor Generating Plants (2001 Edition)," AEP-NRC-201 1-1, dated July 1,2011, ADAMS Accession No. ML11188A145.
2. Letter from J. P. Gebbie, I&M, to NRC Document Control Desk, "Donald C. Cook Nuclear Plant Units 1 and 2, Docket Nos. 50-315 and 50-316, Supplement to Request for License Amendment to Adopt National Fire Protection Association (NFPA) 805 Performance-Based Standard for Fire Protection for Light Water Reactor Generating Plants (2001 Edition)," AEP-NRC-2011-62, dated September 2, 2011, ADAMS Accession No. ML11256A030.3. Letter from P. S. Tam, NRC, to L. J. Weber, I&M, "Donald C. Cook Nuclear Plant, Units 1 and 2 -Request for Additional Information on the Application for Amendment to Transition the Fire Protection Program to National Fire Protection Association Standard 805 (TAC Nos. ME6629 AND ME6630)," dated January 27, 2012, ADAMS Accession Nos.ML113560709, ML12003A186, and ML12017A251.
4. E-Mail from P. S. Tam, NRC, to H. L. Etheridge, J. R. Waters, M. K. Scarpello, I&M, et al.,"D.C. Cook -Draft RAI re. Transition to NFPA 805, Questions in Health Physics (TAC ME6629 and ME6630)," dated March 22, 2012, ADAMS Accession No. ML12082A043.
5. Letter from M. H. Carlson, I&M, to NRC Document Control Desk, "Donald C. Cook Nuclear Plant Units 1 and 2, Response to Request for Additional Information Regarding the Application for Amendment to Transition the Fire Protection Program to National Fire Protection Association Standard 805, (TAC Nos. ME6629 AND ME6630)," AEP-NRC-2012-29, dated April 27, 2012, ADAMS Accession No. ML12132A390.
6. Letter from J. P Gebbie, I&M, to NRC Document Control Desk, "Response to Second Request for Additional Information Regarding the Application for Amendment to Transition the Fire Protection Program to National Fire Protection Association Standard 805 (TAC Nos. ME6629 AND ME6630)," AEP-NRC-2012-47, dated June 29, 2012, ADAMS Accession No. ML12195A013.
7. Letter from M. H. Carlson, I&M, to NRC Document Control Desk, "Donald C. Cook Nuclear Plant Units 1 and 2, Response to Request for Additional Information Regarding the Application for Amendment to Transition the Fire Protection Program to National Fire Protection Association Standard 805, (TAC Nos. ME6629 AND ME6630)," AEP-NRC-2012-58, dated August 9, 2012, ADAMS Accession No. ML12242A246.

Enclosure 2 to AEP-NRC-2013-55 Page 2 8. Letter from T. J. Wengert, NRC, to L. J. Weber, I&M, "Donald C. Cook Nuclear Plant, Units 1 and 2 -Request for Additional Information on the Application for Amendment to Transition the Fire Protection Program to National Fire Protection Association Standard 805 (TAC Nos. ME6629 and ME6630)," dated February 1, 2013, ADAMS Accession Nos.ML13014A549.

9. E-Mail from T. Wengert, NRC, to H. L. Etheridge, J. M. Tanko, M. K. Scarpello, I&M, et al.,"D.C. Cook -Draft RAI re. Transition to NFPA 805, UFSAR Description as a Result of Implementing NFPA 805 and (FAQ) 12-0062 Closure Memo, ADAMS Accession No. ML12082A043," dated March 20, 2013, (Identified as RAI-62 in this letter AEP-NRC-2013-17).
10. I&M NFPA 805 LAR Revisions Action Request 2012-12753, dated October 12, 2012.11. Letter from T. J. Wengert, NRC, to L. J. Weber, I&M, "Donald C. Cook Nuclear Plant, Units 1 and 2 -Request for Additional Information on the Application for Amendment to Transition the Fire Protection Program to National Fire Protection Association Standard 805 (TAC Nos.ME6629 and ME6630)," dated October 11, 2012, ADAMS Accession Nos. ML12276A300 and ML12285A179.
12. Letter from M. H. Carlson, I&M, to NRC Document Control Desk, "Donald C. Cook Nuclear Plant Units 1 and 2, Response to Second Round Request for Additional Information Regarding the Application for Amendment to Transition the Fire Protection Program to National Fire Protection Associations Standard 805 (TAC Nos. ME6629 and ME6630)," AEP-NRC-2012-92, dated October 15, 2012, ADAMS Accession No. ML12297A213.
13. Letter from M. H. Carlson, I&M, to NRC Document Control Desk, "Donald C. Cook Nuclear Plant Units 1 and 2, Response to Second-Round Request for Additional Information Item 54.b, and Submittal of Revised Tables Regarding the Application for Amendment to Transition to National Fire Protection Association Standard 805 (TAC Nos. ME6629 and ME6630)," AEP-NRC-2012-101, dated November 9, 2012, ADAMS Accession No.ML123261084.
14. Letter from T. J. Wengert, NRC, to L. J. Weber, I&M, "Donald C. Cook Nuclear Plant, Units 1 and 2 -Request for Additional Information on the Application for Amendment to Transition the Fire Protection Program to National Fire Protection Association Standard 805 (TAC Nos.ME6629 and ME6630)," dated December 13, 2012, ADAMS Accession No. ML12345A327.
15. Letter from Q. S. Lies, I&M, to NRC Document Control Desk, "Donald C. Cook Nuclear Plant Units 1 and 2, Response to Third Round Request for Additional Information Regarding the Application for Amendment to Transition the Fire Protection Program to National Fire Protection Association Standard 805 (TAC Nos. ME6629 and ME6630)," AEP-NRC-2013-1, dated January 14, 2013, ADAMS Accession No. ML13028A113.

Enclosure 2 to AEP-NRC-2013-55 Page 3 16. Letter from J. P. Gebbie, I&M, to NRC Document Control Desk, "Donald C. Cook Nuclear Plant, Units 1 and 2, Revised Response to a First Round Request for Additional Information Regarding the Application for Amendment to Transition the Fire Protection Program to National Fire Protection Association Standard 805 (TAC Nos. ME6629 and ME6630)," AEP-NRC-2013-09, dated February 1, 2013, ADAMS Accession No. ML13045A432.

17. Letter from J. P. Gebbie, I&M, to NRC Document Control Desk, "Donald C. Cook Nuclear Plant, Units 1 and 2, Response to a Request for Additional Information (RAI 29.01, 61, and 62) Regarding the Application for Amendment to Transition the Fire Protection Program to National Fire Protection Association Standard 805 (TAC Nos. ME6629 and ME6630)," AEP-NRC-2013-17, dated May 1, 2013, ADAMS Accession No. ML13123A298.
18. E-Mail from T. J. Wengert, NRC, to H. L. Etheridge, I&M, "Donald C. Cook Nuclear Plant, Units 1 and 2 -Request for Additional Information on the Application for Amendment to Transition the Fire Protection Program to National Fire Protection Association Standard 805 (TAC Nos. ME6629 and ME6630)," dated June 14, 2013.

Enclosure 3 to AEP-NRC-2013-55 Revision 5 of Attachment M, "License Condition Changes," to the Transition Report Provided in Support of Response to Request for Additional Information Concerning NFPA 805 LAR Supplement Dated 5/1/13 Changes are indicated by revision bars in the right margin.

Indiana Michigan Power CNP NFPA 805 Transition Report -Attachment M Inin Mcia Poe N FA85Tasto eot-Atcmn M. License Condition Changes 5 Pages Revision 5 Page M-1 Revision 5 Page M-1 Indiana Michiqan Power CNP NFPA 805 Transition Report -Attachment M I&M proposes to replace the current CNP fire protection license conditions 2.C.(4) for Unit 1 and 2.C.(3)(o) for Unit 2 with the standard license condition in Regulatory Position C.3.1 of Regulatory Guide 1.205, Revision 1, as shown below. In support of this change, I&M has developed a Fire PRA which has been reviewed and been found acceptable by a Fire PRA WOG peer review conducted during October 12-16, 2009. Outstanding high level findings from the peer review are included in Attachment V of this TR. Any future changes to the Fire PRA will be subject to peer review in accordance with the guidance provided in NEI 07-12 and applicable ASME/ANS PRA standards.

Fire Protection Program Indiana Michigan Power Company shall implement and maintain in effect all provisions of the approved fire protection program that comply with 10 CFR 50.48(a) and 10 CFR 50.48(c), as specified in the licensee's amendment request dated July 1, 2011, as supplemented by letters dated September 2, 2011, April 27, 2012, June 29, 2012, August 9, 2012, October 15, 2012, November 9, 2012, January 14, 2013, February 1, 2013, May 1, 2013, and June 21, 2013, and as approved in the safety evaluation dated .Except where NRC approval for changes or deviations is required by 10 CFR 50.48(c), and provided no other regulation, technical specification, license condition or requirement would require prior NRC approval, the licensee may make changes to the fire protection program without prior approval of the Commission if those changes satisfy the provisions set forth in 10 CFR 50.48(a) and 10 CFR 50.48(c), the change does not require a change to a technical specification or a license condition, and the criteria listed below are satisfied.

Risk-Informed Changes that May Be Made Without Prior NRC Approval A risk assessment of the change must demonstrate that the acceptance criteria below are met.The risk assessment approach, methods, and data shall be acceptable to the NRC and shall be appropriate for the nature and scope of the change being evaluated; be based on the as-built, as-operated, and maintained plant; and reflect the operating experience at the plant. Acceptable methods to assess the risk of the change may include methods that have been used in the peer-reviewed Fire PRA (FPRA) model, methods that have been approved by NRC through a plant-specific license amendment or NRC approval of generic methods specifically for use in NFPA 805 risk assessments, or methods that have been demonstrated to bound the risk impact.(a) Prior NRC review and approval is not required for changes that clearly result in a decrease in risk. The proposed change must also be consistent with the defense-in-depth philosophy and must maintain sufficient safety margins. The change may be implemented following completion of the plant change evaluation.(b) Prior NRC review and approval is not required for individual changes that result in a risk increase less than lxil0 7/year (yr) for CDF and less than 1x10-8/yr for LERF. The proposed change must also be consistent with the defense-in-depth philosophy and must maintain sufficient safety margins. The change may be implemented following completion of the plant change evaluation.

Revision 5 Page M-2 Inrlionn it-hi nn PmAtor tKip Kii:PA qng Trnneifinn Pa rrf -Aftnt-hmanf InZI býiinPIIr

~ I IIAPl rn~i~ ~rr +~~mn .A~~~** h *MA .V~ I* ~ .IA*JLI'J ~J ~ ~ I V Other Changes that May Be Made Without Prior NRC Approval (1) Changes to NFPA 805, Chapter 3, Fundamental Fire Protection Program and Design Elements Prior NRC review and approval are not required for changes to the NFPA 805, Chapter 3, fundamental fire protection program elements and design requirements for which an engineering evaluation demonstrates that the alternative to the Chapter 3 element is functionally equivalent or adequate for the hazard. The licensee may use an engineering evaluation to demonstrate that a change to an NFPA 805, Chapter 3, element is functionally equivalent to the corresponding technical requirement.

A qualified fire protection engineer shall perform the engineering evaluation and conclude that the change has not affected the functionality of the component, system, procedure, or physical arrangement, using a relevant technical requirement or standard.The licensee may use an engineering evaluation to demonstrate that changes to certain NFPA 805, Chapter 3, elements are acceptable because the alternative is "adequate for the hazard." Prior NRC review and approval would not be required for alternatives to four specific sections of NFPA 805, Chapter 3, for which an engineering evaluation demonstrates that the alternative to the Chapter 3 element is adequate for the hazard. A qualified fire protection engineer shall perform the engineering evaluation and conclude that the change has not affected the functionality of the component, system, procedure, or physical arrangement, using a relevant technical requirement or standard.

The four specific sections of NFPA 805, Chapter 3, are as follows:."Fire Alarm and Detection Systems" (Section 3.8);* "Automatic and Manual Water-Based Fire Suppression Systems" (Section 3.9);* "Gaseous Fire Suppression Systems" (Section 3.10); and,* "Passive Fire Protection Features" (Section 3.11).This License Condition does not apply to any demonstration of equivalency under Section 1.7 of NFPA 805.(2) Fire Protection Program Changes that Have No More than Minimal Risk Impact Prior NRC review and approval are not required for changes to the licensee's fire protection program that have been demonstrated to have no more than a minimal risk impact. The licensee may use its screening process as approved in the NRC safety evaluation dated , to determine that certain fire protection program changes meet the minimal criterion.

The licensee shall ensure that fire protection defense-in-depth and safety margins are maintained when changes are made to the fire protection program.Revision 5 Page M-3 Indiana Michioan Power CNP NFPA 805 Transition ReDort -Attachment M Transition License Conditions (1) Before achieving full compliance with 10 CFR 50.48(c), as specified by (2) below, risk-informed changes to the licensee's fire protection program may not be made without prior NRC review and approval unless the change has been demonstrated to have no more than a minimal risk impact, as described in (2) above.(2) The licensee shall implement the modifications to its facility, as described in Enclosure 4, Attachment S, Table S-2, "Plant Modifications Committed," of I&M letter AEP-NRC-2013-55, dated June 21, 2013, to complete the transition to full compliance with 10 CFR 50.48(c) by [12 months following issuance of amendment/safety evaluation].

The licensee shall maintain appropriate compensatory measures in place until completion of these modifications.

(3) The licensee shall implement the items listed in Enclosure

4. Attachment S, Table S-3,"Implementation Items," of I&M letter AEP-NRC-2013-55, dated June 21, 2013, by [12 months following issuance of amendment/safety evaluation].

(4) The licensee shall complete an FPRA, focused scope peer review and resolve findings associated with the revised FPRA LERF values, prior to self-approval of changes that result in more than a minimal increase in risk.(5) The Licensee shall complete an FPRA focused scope peer review and resolve findings associated with FPRA modeling of the installation of the new Reactor Coolant Pump low-leakage safe shutdown seals, prior to self-approval of changes that result in more than a minimal increase in risk.(6) The licensee shall complete a focused scope peer review and resolve findings of the PRA upgrade related to reduced mission times for cutsets containing a test and maintenance event combined with a running failure, prior to self-approval of changes that result in more than a minimal increase in risk.The license conditions to be replaced are restated below.License condition 2.C(4) for Unit 1: Indiana Michigan Power Company shall implement and maintain, in effect, all provisions of the approved Fire Protection Program as described in the Final Safety Analysis Report for the facility and as approved in the SERs dated December 12, 1977, July 31, 1979, January 30, 1981, February 7, 1983, November 22, 1983, December 23, 1983, March 16, 1984, August 27, 1985, June 30, 1986, January 28, 1987, May 26, 1987, June 16, 1988, June 17, 1988, June 7, 1989, February 1, 1990, February 9, 1990, March 26, 1990, April 26, 1990, March 31, 1993, April 8, 1993, December 14, 1994, January Revision 5 Page M-4 Indiana Michiaan Power CNP NFPA 805 Transition Reoort -Attachment M 24, 1995, April 19, 1995, June 8, 1995, and March 11, 1996, subject to the following provision:

The licensee may make changes to the approved fire protection program without prior approval of the Commission only if those changes would not adversely affect the ability to achieve and maintain safe shutdown in the event of a fire.License condition 2.C(3)(o) for Unit 2: Indiana Michigan Power Company shall implement and maintain, in effect, all provisions of the approved Fire Protection Program as described in the Updated Final Safety Analysis Report for the facility and as approved in the SERs dated December 12, 1977, July 31, 1979, January 30, 1981, February 7, 1983, November 22, 1983, December 23, 1983, March 16, 1984, August 27, 1985, June 30, 1986, January 28, 1987, May 26, 1987, June 16, 1988, June 17, 1988, June 7, 1989, February 1, 1990, February 9, 1990, March 26, 1990, April 26, 1990, March 31, 1993, April 8, 1993, December 14, 1994, January 24, 1995, April 19, 1995, June 8, 1995, and March 11, 1996, subject to the following provision:

The licensee may make changes to the approved fire protection program without prior approval of the Commission only if these changes would not adversely affect the ability to achieve and maintain safe shutdown in the event of a fire.It is I&M's understanding that, implicit in the replacement of these license conditions, all prior fire protection program SERs and commitments will be superseded in their entirety by the revised license condition.

No other license conditions need to be replaced or revised.I&M implemented the following process for determining that these are the only license conditions required to be either revised or superseded to implement the new fire protection program which meets the requirements in 10 CFR 50.48(a) and 50.48(c): A review was conducted of the I&M Unit 1 Renewed License Number DPR-58, through Amendment No. 313 and Unit 2 Renewed License Number DPR-74, through Amendment No. 297, by the I&M licensing and NFPA 805 Transition Team. Outstanding LARs that have been submitted to the NRC but not yet approved were also reviewed for potential impact on the license conditions.

Revision 5 Page M-5 Revision 5 Page M-5 Enclosure 4 to AEP-NRC-2013-55 Revision 6 of Attachment S, "Plant Modifications and Items to be Completed During Implementation," to the Transition Report Provided in Support of Response to Request for Additional Information Concerning NFPA 805 LAR Supplement Dated 5/1/13.Changes are indicated by revision bars in the right margin.

Indiana Michioan Power CNP NFPA 805 Transition Reoort -Attachment S S. Plant Modifications and Items to be Completed during Implementation 14 Pages Revision 6 Page S-i Revision 6 Page S-1 Indiamg Mirhinan Pnwpr r.NP NFPA ROS Trnmitinn Ppnnrt -Attarhmpnt S.......M.. ........ CN P N FP 805.. .. .. .. ... .. ..... .... .. R fn r ... ..............

Tables S-1 and S-2, Plant Modifications, include a description of the modifications along with the following information: " A problem statement,* Risk ranking of the modification,* An indication if the modification is currently included in the Fire PRA,* Compensatory Measure in place, and" A risk-informed characterization of the modification and compensatory measure.The following legend applies to the risk ranking indicated in Tables S-1 and S-2:* High = Modification would have an appreciable impact on reducing overall fire CDF.* Medium = Modification would have a measurable impact on reducing overall fire CDF.* Low = Modification would have either an insignificant or no impact on reducing overall fire CDF.Revision 6 Page S-2 Revision 6 Page S-2 Indiana Michiryan Power CNP NFPA 80l5 Trans~ition einort -Attachment S Attachment S -Table S-1 Plant Modifications Completed In Comp Risk Informed Item Rank Unit Problem Statement Proposed Modification FPRA Measure Characterization S-1.1 High 1, 2 Cable in conduit associated Provide 1-hour ERFBS with Y N Fire PRA credits this with the credited train of dc automatic suppression

& modification for electrical electrical power for Fire Area detection for cable of power redundancy AA39A and AA45A is concern in Fire Area AA39A Compensatory measure: unprotected and routed and AA45A None; modification through the area installed.

S-1.2 Low 1, 2 Actions identified in safe Revised safe shutdown N N Fire PRA does not credit shutdown procedure for procedures to reflect correct these actions transferring 600 volt Bus to actions. Compensatory measure: alternate source in Fire Areas None; Procedures AA14, AA23, AA39B and updated.AA45B were not accurately identified.

Revision 6 Page S-3 Revision 6 Page S-3 Indiana Michioan Power CNP NFPA 805 Transition ReDort -Attachment S Attachment S -Table S-2 Plant Modifications Committed Proposed In Comp Risk Informed Item Rank Unit Problem Statement Modification FPRA Measure Characterization S-2.1 Medium 1, 2 Short circuits can occur in Modify the following ten Y N Circuit failures which result in the the control circuit for (10) valves to resolve inability of operators to perform a motor operated valves 92-18 issue: recovery action are significant between control wiring 1(2)-FMO-212 contributors to both fire risk as well and power sources as internal events risk. The leading to spurious 1(2)-FMO-222 proposed modification will improve operation of the valve, the ability of plant operators to The same postulated 1(2)FMO232 manually align certain motor short circuit may bypass 1(2)-FMO-242 operated valves if required in order the torque/limit switches to maintain the plant in a safe and which, combined with the 1(2)-CM250 stable condition.

absence or bypass of thermal overload Compensatory measure for contacts, results in NFPA 805: Appropriate continuous energization Compensatory Measures will be of the valve motor and established when the NFPA 805 potential mechanical fire protection program is damage to the valve such approved by the NRC and that manual operation via remain in place until this handwheel would be modification is complete.inhibited.

This potential condition was described Compensatory measure for in Information Notice (IN) 10 CFR 50 Appendix R: None; IN 92-18 92-18 concerns were addressed by the current licensing basis, which credits the "double break" circuit design, as described in NRC SE dated November 22, 1983.Revision 6 Page S-4 Revision 6 Page S-4 lnrlinnn Mit-hirmn Pnimar iclVh#in.fn P /lAIP *IFPA R 1 iTrnn4.citinn annrf -,ntS Attachment S -Table S-2 Plant Modifications Committed Proposed In Comp Risk Informed Item Rank Unit Problem Statement Modification FPRA Measure Characterization S-2.2 High 1, 2 Electrical cabinet fire Modify the C0 2 system Y N This proposed modification will limit scenarios in fire areas from manual to the extent of damage predicted to AA40 and AA43 automatic actuation in occur for fire scenarios within the contribute significantly to the following fire areas: subject fire areas.fire CDF and LERF and warrant additional a) AA40 Compensatory measure for mitigation b) AA43 NFPA 805: Appropriate Compensatory Measures will be established when the NFPA 805 fire protection program is approved by the NRC and remain in place until this modification is complete.Compensatory measure for 10 CFR 50 Appendix R: None; fire areas AA40 and AA43 are deterministically compliant with 10 CFR 50 Appendix R.Revision 6 Page S-5 Revision 6 Page S-5 (TNP NFPA Rfl~ Tr~n~itinn P~nnrt -Attn,'hm,~nt

~Attachment S -Table S-2 Plant Modifications Committed Proposed In Comp Risk Informed Item Rank Unit Problem Statement Modification FPRA Measure Characterization S-2.3 High 1,2 Additional risk reduction Modify the Unit 1 and 2 Y N This proposed modification will modifications are Reactor Coolant Pump provide an FPRA risk reduction necessary to comply with seals with the low- within the acceptance guidelines of Regulatory Guide 1.174 leakage seal design Regulatory Guide 1.174 acceptance guidelines Compensatory measure for NFPA 805: Appropriate Compensatory Measures will be established when the NFPA 805 fire protection program is approved by the NRC and remain in place until this modification is complete.Compensatory measure for 10 CFR 50 Appendix R: None; fire areas AA56 and AA58 are deterministically compliant with 10 CFR 50 Appendix R.Revision 6 Page S-6 Revision 6 Page S-6 Indiana Michioan Power CNP NFPA 805 Transition ReDort -Attachment S Table S-3, identifies those implementation items (procedure changes, process updates, and training to affected plant personnel) that will be completed by I&M prior to the implementation of new NFPA 805 FP program. These items will be completed within twelve (12) months after NRC issuance of the NFPA 805 SE.Revision 6 Page S-7 Revision 6 Page S-7 lnrlinnn Mrhirynn PniAlor ('AIP AIFPd P09 Trnneitinn o nrf -AffnrhmontR Inc flic~hn~nPnI~nr AIPAWP Rfl Trnviinn ,~nd -Atf~hmntV5 Attachment S -Table S-3 Implementation Items Item Unit Description LAR Section I Source S-3.1 1,2 Initial General Employee Training (GET) will be verified and / or 4.1.2 and Attachment A updated to include the minimum fire protection program elements as discussed in Section K to NEI-04-02 (FAQ 06-0028).S-3.2 1, 2 The monitoring program required by NFPA 805 Section 2.6 will be 4.1.2, 4.6, and Attachment A developed in accordance with NFPA 805 FAQ 10-0059, and will include a process that reviews the FPP performance and trends in performance and implemented after the LAR approval as part of the FPP transition to NFPA 805.S-3.3 1, 2 Transient Combustible Free Zones will be established in high risk 4.5 and Attachments A and W Fire Areas AA40, AA43, AA48, AA50, AA51, and AA52.S-3.4 1, 2 Hot Work Restriction Zones will be established in high risk Fire 4.5 and Attachments A and W Areas AA40, AA43, AA48, AA50, AA51, and AA52.S-3.5 1, 2 Post-fire operating procedures will be updated to reflect new 4.2.1.3 and Attachment G NSCA strategies and training performed as necessary.

S-3.6 1,2 Technical and administrative procedures and documents that 4.3.2 and Attachment D relate to non-power modes of plant operating states will be revised as needed for implementation of NFPA 805.Revision 6 Page S-8 Indiana Michifryn Power CNP FPA 805~ Trans~ition Report -Attachment S Attachment S -Table S-3 Implementation Items Item Unit Description LAR Section I Source S-3.7 1, 2 Pre-fire plans and fire brigade training materials will be revised to 4.4.2 and Attachments A and E reflect changes required to meet the NFPA 805 radioactive release performance criteria.S-3.8 1, 2 A confirmatory demonstration (field verification walk-through) of 4.2.1.3 and Attachment G the feasibility for the credited NFPA 805 recovery actions will be performed.

This will include field verification of: (1) Transit times (i.e., travel times to/from recovery action manipulated plant equipment).

(2) Execution times (i.e., time required to physically perform the action, such as handwheel a valve open, open a breaker, etc.).(3) Communications for adequacy between the controlling location and recovery action locations for areas which involve actions.(4) Adequate lighting (either fixed or portable) for access/egress and local lights are provided for the component to be operated.S-3.9 1,2 CNP calculation Probabilistic Risk Assessment (PRA)-FIRE-4.2.1.3 and Attachment G 17663-012-LAR, "Post-Fire Human Reliability Analysis" and Technical Evaluation R1900-0026-001, "Recovery Action Transition for NFPA 805" will be reviewed and updated based on the results of the field walkdowns of the recovery actions (Item S-3.8) and procedure changes (Items S-3.5, S-3.11 and.S-3.14).

Revision 6 Page S-9 Revision 6 Page S-9 Indiana Michin.yin Power C NP NFPA 805~ Transition Rportnn -Attachment S~Attachment S -Table S-3 Implementation Items Item Unit Description LAR Section I Source S-3.10 1, 2 Technical documents and procedures that relate to new Fire 4.7.1, 4.7.2, 4.7.3, and Attachment W Protection (FP) design and licensing basis (e.g., Fire Protection Program Manual (FPPM), Technical Requirements Manual, Design Basis Document, maintenance and surveillance, configuration control, training and qualification guidelines, Quality Assurance Program Document (QAPD), etc.) will be revised as needed for implementation of NFPA 805.S-3.11 1, 2 A new restoration procedure (1/2-OHP-4025-R-XX series) will be Attachment W developed to address re-powering the hydrogen igniters following a fire in Fire Areas AA40, AA43, AA46, AA47, AA48, AA50, AA51 and AA52 S-3.12 1,2 The current transformer evaluation (Technical Evaluation 12.6) will 4.2.1.1/Attachment B be updated to address those CTs that currently have not screened out as sufficient CT data becomes available.

S-3.13 1, 2 Update the UFSAR following the guidance provided in Frequently 4.7.1/ Response to RAI-62 documented in Asked Question (FAQ) 12-0062 (ADAMS Accession No. I&M Letter dated May 1, 2013 ML121430035).

Revision 6 Page S-IC Revision 6 Page S-10 Inrlinnn Mirhirynn PnimarJV~l~l##nl A ~ PAI~r VAI/P AI/FPA Rnl; Trnniczitinn aPnnrf -Athqrhmgnt R Attachment S -Table S-3 Implementation Items Item Unit Description LAR Section / Source S-3.14 1, 2 Applicable operating procedures will be revised to include the Response to RAI-61 documented in I&M treatment of Fire PRA Actions added to the 'base fire PRA model' Letter dated May 1, 2013 that mitigate 'fire induced failures -but are not associated with the NSCA success path. This includes isolation of containment purge line isolation valves, and procedure changes for Turbine Driven Auxiliary Feed Water (TDAFW) pump battery charger re-alignment to address uncertainty considerations.

This includes procedure changes associated with the NSCA (item S-3.5), field verification walk-throughs (item S-3.8), hydrogen igniters (item S-3.11) and temporary ventilation (item S-3.17).S-3.15 1,2 Revise procedure PMP-2270-WBG-001, "Welding, Burning and Response to RAI-09.01 documented in I&M Grinding Activities," and procedure 12-FPP-2270-066-011, "Fire Letter dated October 15, 2012, and Watch Activities," and conduct training on discontinuing the use of Attachment A.(1) video cameras for fire watch and (2) use of a single fire watch for multiple hot work activities.

S-3.16 1, 2 Revise Procedure PMP-2270-CCM-001, "Control of Combustible Response to RAI-10.01 documented in I&M Materials," and conduct training on the requirements of NFPA 805 Letter dated October 15, 2012, and Section 3.3.1.2(1).

Attachment A.S-3.17 1,2 Revise Technical Evaluation R1900-0026-001, Revision 1, Response to RAI-18.01 documented in I&M"Recovery Action Transition in Support of NFPA 805," and Letter dated October 15, 2012, and applicable procedures, to establish temporary MCR ventilation for Attachment A.Recovery Actions associated with VFDRs for AA3-004, AA3-009, AA36/42.42-026, AA57A-001 and AA57B-001.

The Implementation Item will also require that training be conducted.

Revision 6 Page S- I I Indi.a.na Mi,.hicn..

n Power CNP NFPA 805 Transition Penort -Atta hment S Attachment S -Table S-3 Implementation Items Item Unit Description LAR Section I Source S-3.18 1,2 Verify MOV circuit changes (Table S-2, Item S-2.1) have been Response to RAI-44 documented in I&M accomplished as credited in Attachment W and verify the Letter dated October 15, 2012.associated valves are not credited in other areas where spurious operation could occur.S-3.19 1,2 Update the associated Fire PRA task and revise the Fire PRA Response to RAI-44 documented in I&M ignition frequency and/or fire modeling to include re-evaluation of Letter dated October 15, 2012.procedural actions/controls associated with control of automatic CO 2 actuation in certain areas (Table S-2, item S-2.2), Transient Combustible Fee Zones (Table S-3, Item S-3.3), establishing certain areas as Hot Work Restriction Zones (Table S-3, Item S-3.4).S-3.20 1,2 Upon completion of all Fire PRA credited implementation items in Response to RAI-44 documented in I&M Transition report Tables S-2 and S-3, verify the validity of the Letter dated October 15, 2012.change-in-risk provided in Attachment W. This includes procedure Response to RAI-61 documented in I&M changes affecting the fire PRA (item S-3.14), electrical circuit modifications (item S-3.18), fire ignition and suppression (item S- Letter dated May 1, 2013.3.19) and PRA methods (item S-3.21).If this verification determines that the risk metrics have changed such that the RG 1.205 acceptance guidelines are not met, additional analytical efforts, and/or procedure changes, and/or plant modifications will be implemented to assure the RG 1.205 acceptance criteria are met.S-3.21 1, 2 C")nduct a Fc.used Scope Peer Review of the PRA upgrade item This implementation item has been deleted rel.aed to, Reduccd Mission Times for cUtSetS containing a Test and included as a License Condition in and Maintenance event combined with a running failr Attachment M Revision 6 Page S-12 Revision 6 Page S-12 Inrliana Mirhirian Pnwpr.................

........NP NFPA 805 Transition Report -Attachment S Attachment S -Table S-3 Implementation Items Item Unit Description LAR Section I Source S-3.22 1, 2 Revise program documents and procedures, and conduct Response to RAI-60 documented in I&M associated training, as necessary to implement specific Letter dated October 15, 2012.requirements from NFPA 805 Section 2.7.3 as described in Transition Report Section 4.7.3.Revision 6 Page S-13 Revision 6 Page S-13 Indiana Michiaan Power CNP NFPA 805 Transition Reoort -Attachment S S-3.23 1, 2 Revise Technical Evaluation 12.5 and update the following Revised response to RAI-15(b) documented documentation to reflect the revised response to RAI-15(b)documented in I&M Letter dated January 14, 2013: in I&M Letter dated February 1,2013.1. Revise Unit 1 and Unit 2 250 Volt DC calculations 1-E-N-ELCP-250-001, "Unit 1 250VDC System Coordination Study," and 2-E-N-ELCP-250-001, "Unit 2 25OVDC System Coordination Study." These will be non-technical revisions to provide clarity regarding the CNP Licensing Basis and Design Requirements (specifically, the SSCA and NEI 00-01).2. Revise 600 Volt AC calculation 1-E-N-PROT-BKR-007,"Unit 1 600V Switchgear Breaker 11A6, 11A7, 11B3, 11C3, 11C9, 11C18, 11D9 and OB2-1 Settings." This will be a non-technical revision to provide clarity regarding the NFPA 805 requirements in the case of a potentially overloaded cable.3. Create new Unit 1 and Unit 2 120 Volt AC calculations.

A representative sample of cable data from buses identified in Technical Evaluation 12.5 was evaluated for adequate cable protection and coordination.

Results of the survey revealed that all cables were acceptable with significant margin to preclude cable damage and secondary fires.The new calculations will document the assembled data for each 120 Volt AC cable and protective device and be complete by March 28, 2013.4. Update Technical Evaluation 12.5. This update will provide justification for resolution of conditions currently identified as deficiencies with 250 Volt DC, 600 Volt AC and 120 Volt AC calculations.

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