ML15216A240

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NRR E-mail Capture - D.C. Cook Nuclear Plant, Units 1 and 2 - Draft Request for Additional Information TSTF-490 and AST
ML15216A240
Person / Time
Site: Cook  American Electric Power icon.png
Issue date: 07/30/2015
From: Dietrich A
Plant Licensing Branch III
To: Kish H
American Electric Power
References
TAC MF5184, TAC MF5185
Download: ML15216A240 (4)


Text

NRR-PMDAPEm Resource From: Dietrich, Allison Sent: Thursday, July 30, 2015 9:27 AM To: 'hlkish@aep.com' Cc: 'dmburgoyne@aep.com'; Terry L Curtiss (tlcurtiss@aep.com); Edmonds, Shavon; Ray, Sheila

Subject:

D.C. Cook Nuclear Plant, Units 1 and 2 - Draft Request for Additional Information Re:

TSTF-490 and AST (TAC Nos. MF5184 and MF5185)

Attachments: EEEB RAI regarding Alternate Source Term MF5184 MF5185.docx By letter dated November 14, 2014 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML14324A209), as supplemented by letter dated February 12, 2015 (ADAMS Accession No. ML15050A247), Indiana Michigan Power Company (I&M) submitted a license amendment request for the Donald C. Cook Nuclear Plant, Units 1 and 2. The proposed amendment consists of adoption of Technical Specifications Task Force (TSTF)-490, Revision 0, and implementation of a full scope alternate source term radiological analysis methodology.

The U.S. Nuclear Regulatory Commission (NRC) staff in the Electrical Engineering Branch of the Office of Nuclear Reactor Regulation is currently reviewing your submittal, as supplemented. The staff has determined that additional information is needed in order to complete the review. A draft request for additional information (RAI) is attached.

You may accept this draft RAI as a formal request for additional information and respond to the questions by September 1, 2015. Alternatively, you may seek further clarification and discuss the content of the RAIs with the NRC staff in a conference call, including any change to the proposed response date.

Please let me know if you have any questions or concerns.

Sincerely, Allison W. Dietrich, Project Manager Plant Licensing Branch III-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation 301-415-2846 1

Hearing Identifier: NRR_PMDA Email Number: 2270 Mail Envelope Properties (Allison.Dietrich@nrc.gov20150730092600)

Subject:

D.C. Cook Nuclear Plant, Units 1 and 2 - Draft Request for Additional Information Re: TSTF-490 and AST (TAC Nos. MF5184 and MF5185)

Sent Date: 7/30/2015 9:26:41 AM Received Date: 7/30/2015 9:26:00 AM From: Dietrich, Allison Created By: Allison.Dietrich@nrc.gov Recipients:

"'dmburgoyne@aep.com'" <dmburgoyne@aep.com>

Tracking Status: None "Terry L Curtiss (tlcurtiss@aep.com)" <tlcurtiss@aep.com>

Tracking Status: None "Edmonds, Shavon" <Shavon.Edmonds@nrc.gov>

Tracking Status: None "Ray, Sheila" <Sheila.Ray@nrc.gov>

Tracking Status: None

"'hlkish@aep.com'" <hlkish@aep.com>

Tracking Status: None Post Office:

Files Size Date & Time MESSAGE 1443 7/30/2015 9:26:00 AM EEEB RAI regarding Alternate Source Term MF5184 MF5185.docx 23994 Options Priority: Standard Return Notification: No Reply Requested: No Sensitivity: Normal Expiration Date:

Recipients Received:

REQUEST FOR ADDITIONAL INFORMATION REGARDING ADOPTION OFTSTF-490, REVISION 0 ANDIMPLEMENTATION OF FULL-SCOPE ALTERNATE SOURCE TERM DONALD C. COOK NUCLEAR PLANT, UNITS 1 AND 2 DOCKET NOS. 50-315 AND 50-316 TAC NOS. MF5184 AND MF5185 RAI-EEEB-1 Provide a list and description of components being added to your 10 CFR 50.49 program due to this LAR. Confirm that these components are qualified for the environmental conditions they are expected to be exposed to.

RAI-EEEB-2 In the LAR submittal, Section 4.3 of the Regulatory Guide 1.183 Compliance Matrix under Basis of Compliance states that the CNP environmental qualification (EQ) analyses will continue to be based on Technical Information Document - 14844, Calculation of Distance Factors for Power and Test Reactor Sites in the EQ program. Provide a summary of any changes to the EQ analyses that will demonstrate that the EQequipment will continue to meet its intended safety function.

RAI-EEEB-3 In the LAR submittal, Section 5.1.2 of the Regulatory Guide 1.183 Compliance Matrix under Basis of Compliance states that Assumptions regarding the occurrence and timing of a loss of offsite power are made with the objective of maximizing the impact on dose. State how the assumptions used for the LOOP analysis will affect the current EQ analysis.

RAI-EEEB-4 List any loads being added to the CNP emergency diesel generators (EDGs) to support this LAR.

If any loads are being added, please describe how the loads will affect the capability and capacity of the EDGs (e.g., describe the impact of the proposed change on the EDG ratings). In addition, describe changes (if any) that have been made to the CNPEDG loading sequence to support this LAR.

RAI-EEEB-5 Are any non-safety related systems and components credited in the alternate source term analyses?

If so, a) Describe how this system will be electrically separated from the safety-related system (i.e.,

provide a detailed discussion on how a fault on the non-Class 1Eelectrical circuit will not propagate to the Class 1E electrical circuit).

b) Describe the independence (e.g., electrical and physical separation) and redundancy of these systems.

c) Describe how these systems meet the single failure criterion.

d) Describe how the operators will be notified in the event that these systems and components would become inoperable (e.g., control room annunciators).

e) Describe any impacts on seismic qualifications of these systems andcomponents.