ML15314A069

Corrected Values in Final Integrated Plan for Mitigation Strategies for Beyond-Design-Basis External Events and Spent Fuel Pool Level Indication Status Report

ML15314A069
Person / Time
Site:	Cook
Issue date:	11/06/2015
From:	Lies Q Indiana Michigan Power Co
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
AEP-NRC--2015-107, EA-12-049, EA-12-051
Download: ML15314A069 (4)

Text

z INDIA NA Indiana Michigan Power MICHIGAN Cook Nuclear Plant PO*J*EROne Cook Place A

unt o

Amricn Elctrc PwerBridgman, Ml 49108 A

unt ofmerian Eectrc PoerIndianaMichiganPower.com AEP-N RC--201 5-107 10 CFR 50.4 Docket Nos.:

50-315 50-316 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Donald C. Cook Nuclear Plant Units 1 and 2 Corrected Values in Final Integrated Plan for Mitigation Strategies for Beyond-Design-Basis External Events and Spent Fuel Pool Level Indication Status Report

Reference:

1. Letter from E. J. Leeds and M. R. Johnson, U. S. Nuclear Regulatory Commission (NRC), to All Power Reactor Licensees and Holders of Construction Permits in Active or Deferred Status, "Issuance of Order to Modify Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events,"

dated March 12, 2012, Agencywide Documents Access and Management System (ADAMS) Accession No. ML12054A736.

2. Letter from E. J. Leeds and M. R. Johnson, NRC, to All Power Reactor Licensees and Holders of Construction Permits in Active or Deferred Status, "issuance of Order to Modify Licenses with Regard to Reliable Spent Fuel Pool Instrumentation," dated March 12, 2012, ADAMS Accession No. ML12054A682.

3. Letter from J. P Gebbie, l&M, to the NRC, "Donald C. Cook Nuclear Plant Units 1 and 2, Revision 1 of Final Integrated Plan Regarding March 12, 2012, U. S. Nuclear Regulatory Commission Order Regarding Mitigation Strategies for Beyond-Design-Basis External Events (Order Number EA-1 2-049),"

AEP-NRC-2015-83, dated October 1, 2015.

4. Letter from J. P. Gebbie, I&M, to the NRC, "Donald C. Cook Nuclear Plant Units 1 and 2, Six Month Status Report in Response to March 12, 2012, Commission Order Modifying Licenses with Regard to Reliable Spent Fuel Pool Instrumentation, (Order Number EA-12-051)," AEP-NRC-2014-16, dated February 27, 2014, ADAMS Accession No. ML14063A041.

U. S. Nuclear Regulatory Commission AEP-NRC-201 5-107 Page 2 In response to events at the Fukushima Dai-ichi-Nuclear Power Plant, the U. S. Nuclear Regulatory Commission (NRC) issued Order EA-12-049 (Reference 1) and Order EA-12-051 (Reference 2) to all power reactor licensees, including Indiana Michigan Power Company (I&M),

the licensee for the Donald C. Cook Nuclear Plant (CNP) Unit 1 and Unit 2.

I&M has determined that three numerical values provided in the correspondence submitted in response

• to these orders should be corrected. These corrections are presented below.

Order EA-12-049 of Reference 3 provided a revised Final Implementation Plan (FIP) describing CNP provisions for complying with Order EA-12-049 at CNP. Two numerical values stated in the FIP are corrected as described below.

The text in Section 2.11.1, on Page 47 of the FIP stated that the Diverse and Flexible Mitigation Capability (FLEX) Storage Building (FSB) is located about 600 feet northeast of the plant Protected Area (PA) boundary. However, the FSB is actually located about 1925 feet northeast of the plant PA boundary. Although the distance between the FSB and the PA is greater than originally stated, the FSB is well within the Owner Controlled Area, and the distance value was provided as general background information that was not input to any quantitative assessment.

Therefore, the adequacy of the FLEX equipment storage provisions is not affected by this change.

The text in Section 2.14.2, on Page 55 of the FIP provided a discussion of the potential effects of cold weather on the Turbine Driven Auxiliary Feedwater (TDAFW) pump. In that discussion, it was stated that the expected initial temperature in the TDAFW pump room would be approximately 104 degrees Fahrenheit (0F). However, this is an expected upper value used in addressing potential high temperature concerns. A more appropriate value for addressing low temperature concerns would be 72 0F, since the actual room temperatures typically remain above this value in winter months. The initial TDAFW pump room temperature was not used in any quantitative assessment of the effect of cold weather on the TDAFW pumps.

The qualitative assessment provided in Section 2.14.2 remains accurate and the conclusion that low outside temperatures would not have an adverse effect on the TDAFW pumps or supporting equipment remains valid.

Order EA-12-051 of Reference 4 provided responses to an NRC Request for Additional Information.

(RAI) regarding provisions for complying with Order EA-12-051 at CNP.

The response to PAI #9 on Page 8 stated that the Unit 1 channel of Spent Fuel Pool level Indication would receive power from a different 480 volts alternating current (VAC) bus than the Unit 2 channel.

However, the Unit 1 and Unit 2 channels actually receive power from 600 VAC buses in Unit 1 and Unit 2, respectively. Since the Unit 1 and Unit 2 channels receive power from different 600 VAC buses, the conclusion that the channels are provided with electrical separation remains valid.

U. S. Nuclear Regulatory Commission AEP-NRC-201 5-107 Page 3 The enclosure to-this letter provides an affirmation regarding the information contained herein.

This letter contains no new or revised regulatory commitments. Should you have any questions, please contact Mr. Michael K. Scarpello, Regulatory Affairs Manager, at (269) 466 2649.

Sincerely,

-Q. 4hae Lies Engineering Vice President JRW/ams Enclosure c:

R. J. Ancona, MPSC J. P. Boska, NRC Washington, DC A. W. Dietrich, NRC Washington, DC MDEQ -RMD/RPS NRC Resident Inspector C. D. Pederson, NRC Region Ill A. J. Williamson, AEP Ft. Wayne, w/o enclosure to AEP-NRC-2015-107 AFFIRMATION I, Q. Shane Lies, being duly sworn, state that I am Engineering Vice President of Indiana Michigan Power Company (I&M), that I am authorized to sign and file this document with the U. S. 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

/

Q. Shane Lies Engineering Vice President SWORN TO AND SUBSCRIBED BEFORE ME THIS_.

DAY OF Jr2*L

, 2015 Notary Public My Commission Expires LCD - [-o

/ 7-NoayANNE M. PALMA My c oUttef

'MIgo AOltln7Ilssi~n p-

.un.e

z INDIA NA Indiana Michigan Power MICHIGAN Cook Nuclear Plant PO*J*EROne Cook Place A

unt o

Amricn Elctrc PwerBridgman, Ml 49108 A

unt ofmerian Eectrc PoerIndianaMichiganPower.com AEP-N RC--201 5-107 10 CFR 50.4 Docket Nos.:

50-315 50-316 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Donald C. Cook Nuclear Plant Units 1 and 2 Corrected Values in Final Integrated Plan for Mitigation Strategies for Beyond-Design-Basis External Events and Spent Fuel Pool Level Indication Status Report

Reference:

1. Letter from E. J. Leeds and M. R. Johnson, U. S. Nuclear Regulatory Commission (NRC), to All Power Reactor Licensees and Holders of Construction Permits in Active or Deferred Status, "Issuance of Order to Modify Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events,"

dated March 12, 2012, Agencywide Documents Access and Management System (ADAMS) Accession No. ML12054A736.

2. Letter from E. J. Leeds and M. R. Johnson, NRC, to All Power Reactor Licensees and Holders of Construction Permits in Active or Deferred Status, "issuance of Order to Modify Licenses with Regard to Reliable Spent Fuel Pool Instrumentation," dated March 12, 2012, ADAMS Accession No. ML12054A682.

3. Letter from J. P Gebbie, l&M, to the NRC, "Donald C. Cook Nuclear Plant Units 1 and 2, Revision 1 of Final Integrated Plan Regarding March 12, 2012, U. S. Nuclear Regulatory Commission Order Regarding Mitigation Strategies for Beyond-Design-Basis External Events (Order Number EA-1 2-049),"

AEP-NRC-2015-83, dated October 1, 2015.

4. Letter from J. P. Gebbie, I&M, to the NRC, "Donald C. Cook Nuclear Plant Units 1 and 2, Six Month Status Report in Response to March 12, 2012, Commission Order Modifying Licenses with Regard to Reliable Spent Fuel Pool Instrumentation, (Order Number EA-12-051)," AEP-NRC-2014-16, dated February 27, 2014, ADAMS Accession No. ML14063A041.

U. S. Nuclear Regulatory Commission AEP-NRC-201 5-107 Page 2 In response to events at the Fukushima Dai-ichi-Nuclear Power Plant, the U. S. Nuclear Regulatory Commission (NRC) issued Order EA-12-049 (Reference 1) and Order EA-12-051 (Reference 2) to all power reactor licensees, including Indiana Michigan Power Company (I&M),

the licensee for the Donald C. Cook Nuclear Plant (CNP) Unit 1 and Unit 2.

I&M has determined that three numerical values provided in the correspondence submitted in response

• to these orders should be corrected. These corrections are presented below.

Order EA-12-049 of Reference 3 provided a revised Final Implementation Plan (FIP) describing CNP provisions for complying with Order EA-12-049 at CNP. Two numerical values stated in the FIP are corrected as described below.

The text in Section 2.11.1, on Page 47 of the FIP stated that the Diverse and Flexible Mitigation Capability (FLEX) Storage Building (FSB) is located about 600 feet northeast of the plant Protected Area (PA) boundary. However, the FSB is actually located about 1925 feet northeast of the plant PA boundary. Although the distance between the FSB and the PA is greater than originally stated, the FSB is well within the Owner Controlled Area, and the distance value was provided as general background information that was not input to any quantitative assessment.

Therefore, the adequacy of the FLEX equipment storage provisions is not affected by this change.

The text in Section 2.14.2, on Page 55 of the FIP provided a discussion of the potential effects of cold weather on the Turbine Driven Auxiliary Feedwater (TDAFW) pump. In that discussion, it was stated that the expected initial temperature in the TDAFW pump room would be approximately 104 degrees Fahrenheit (0F). However, this is an expected upper value used in addressing potential high temperature concerns. A more appropriate value for addressing low temperature concerns would be 72 0F, since the actual room temperatures typically remain above this value in winter months. The initial TDAFW pump room temperature was not used in any quantitative assessment of the effect of cold weather on the TDAFW pumps.

The qualitative assessment provided in Section 2.14.2 remains accurate and the conclusion that low outside temperatures would not have an adverse effect on the TDAFW pumps or supporting equipment remains valid.

Order EA-12-051 of Reference 4 provided responses to an NRC Request for Additional Information.

(RAI) regarding provisions for complying with Order EA-12-051 at CNP.

The response to PAI #9 on Page 8 stated that the Unit 1 channel of Spent Fuel Pool level Indication would receive power from a different 480 volts alternating current (VAC) bus than the Unit 2 channel.

However, the Unit 1 and Unit 2 channels actually receive power from 600 VAC buses in Unit 1 and Unit 2, respectively. Since the Unit 1 and Unit 2 channels receive power from different 600 VAC buses, the conclusion that the channels are provided with electrical separation remains valid.

U. S. Nuclear Regulatory Commission AEP-NRC-201 5-107 Page 3 The enclosure to-this letter provides an affirmation regarding the information contained herein.

This letter contains no new or revised regulatory commitments. Should you have any questions, please contact Mr. Michael K. Scarpello, Regulatory Affairs Manager, at (269) 466 2649.

Sincerely,

-Q. 4hae Lies Engineering Vice President JRW/ams Enclosure c:

R. J. Ancona, MPSC J. P. Boska, NRC Washington, DC A. W. Dietrich, NRC Washington, DC MDEQ -RMD/RPS NRC Resident Inspector C. D. Pederson, NRC Region Ill A. J. Williamson, AEP Ft. Wayne, w/o enclosure to AEP-NRC-2015-107 AFFIRMATION I, Q. Shane Lies, being duly sworn, state that I am Engineering Vice President of Indiana Michigan Power Company (I&M), that I am authorized to sign and file this document with the U. S. 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

/

Q. Shane Lies Engineering Vice President SWORN TO AND SUBSCRIBED BEFORE ME THIS_.

DAY OF Jr2*L

, 2015 Notary Public My Commission Expires LCD - [-o

/ 7-NoayANNE M. PALMA My c oUttef

'MIgo AOltln7Ilssi~n p-

.un.e