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| | number = ML15267A683 | | | number = ML15267A683 |
| | issue date = 10/05/2015 | | | issue date = 10/05/2015 |
| | title = Donald C. Cook Nuclear Plant, Units 1 and 2 - Second Request for Additional Information Regarding License Amendment Request to Revise Technical Specification 3.8.1 (TAC Nos. MF5436 and MF5437) | | | title = Second Request for Additional Information Regarding License Amendment Request to Revise Technical Specification 3.8.1 |
| | author name = Dietrich A W | | | author name = Dietrich A |
| | author affiliation = NRC/NRR/DORL/LPLIII-1 | | | author affiliation = NRC/NRR/DORL/LPLIII-1 |
| | addressee name = Weber L J | | | addressee name = Weber L |
| | addressee affiliation = Indiana Michigan Power Co | | | addressee affiliation = Indiana Michigan Power Co |
| | docket = 05000315, 05000316 | | | docket = 05000315, 05000316 |
| | license number = DPR-058, DPR-074 | | | license number = DPR-058, DPR-074 |
| | contact person = Dietrich A W | | | contact person = Dietrich A |
| | case reference number = TAC MF5436, TAC MF5437 | | | case reference number = TAC MF5436, TAC MF5437 |
| | document type = Letter, Request for Additional Information (RAI) | | | document type = Letter, Request for Additional Information (RAI) |
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| =Text= | | =Text= |
| {{#Wiki_filter:Mr. Lawrence J. Weber Senior Vice President and Chief Nuclear Officer UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 October 5, 2015 Indiana Michigan Power Company Nuclear Generation Group One Cook Place Bridgman, Ml 49106 | | {{#Wiki_filter:UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 October 5, 2015 Mr. Lawrence J. Weber Senior Vice President and Chief Nuclear Officer Indiana Michigan Power Company Nuclear Generation Group One Cook Place Bridgman, Ml 49106 |
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| ==SUBJECT:== | | ==SUBJECT:== |
| DONALD C. COOK NUCLEAR PLANT, UNITS i AND 2 -SECOND REQUEST FOR ADDITIONAL INFORMATION REGARDING LICENSE AMENDMENT REQUEST TO REVISE TECHNICAL SPECIFICATION 3.8.1 (TAC NOS. MF5436 AND MF5437) | | DONALD C. COOK NUCLEAR PLANT, UNITS i AND 2 - SECOND REQUEST FOR ADDITIONAL INFORMATION REGARDING LICENSE AMENDMENT REQUEST TO REVISE TECHNICAL SPECIFICATION 3.8.1 (TAC NOS. |
| | MF5436 AND MF5437) |
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| ==Dear Mr. Weber:== | | ==Dear Mr. Weber:== |
| By letter dated December 17, 2014 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML 14356A022), as supplemented by letter dated July 9, 2015 (ADAMS Accession No. ML 15195A434), Indiana Michigan Power Company (l&M, the licensee) requested an amendment to Renewed Facility Operating Licenses DPR-58 and DPR-74 for Donald C. Cook Nuclear Plant, Units 1 and 2. The proposed amendments would revise the Technical Specifications 3.8.1, "AC Sources -Operating," to allow testing of the onsite standby emergency diesel generators (DGs) during modes in which it is currently prohibited. | | |
| Specifically, the proposed changes would remove the mode restrictions in the notes of Surveillance Requirements 3.8.1.1 O (DG single largest load rejection test), 3.8.1.11 (DG full load rejection test), and 3.8.1.15 (DG endurance run). The U.S. Nuclear Regulatory Commission (NRC) staff has reviewed the subject submittal and supplement, and has determined that additional information is needed to complete the review, as described in the enclosed Second Request for Additional Information (RAI). The draft RAI was sent to l&M via electronic mail on September 23, 2015. The NRC staff clarified the draft RAI in a conference call conducted on October 1, 2015. Based on our discussion, we understand that a response to the RAI will be provided by October 30, 2015. | | By letter dated December 17, 2014 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML14356A022), as supplemented by letter dated July 9, 2015 (ADAMS Accession No. ML15195A434), Indiana Michigan Power Company (l&M, the licensee) requested an amendment to Renewed Facility Operating Licenses DPR-58 and DPR-74 for Donald C. Cook Nuclear Plant, Units 1 and 2. The proposed amendments would revise the Technical Specifications 3.8.1, "AC Sources - Operating," to allow testing of the onsite standby emergency diesel generators (DGs) during modes in which it is currently prohibited. |
| L. Weber Please feel free to contact me at (301) 415-2846 if you have any additional questions or concerns. | | Specifically, the proposed changes would remove the mode restrictions in the notes of Surveillance Requirements 3.8.1.1 O (DG single largest load rejection test), 3.8.1.11 (DG full load rejection test), and 3.8.1.15 (DG endurance run). |
| Docket Nos. 50-315 and 50-316 | | The U.S. Nuclear Regulatory Commission (NRC) staff has reviewed the subject submittal and supplement, and has determined that additional information is needed to complete the review, as described in the enclosed Second Request for Additional Information (RAI). The draft RAI was sent to l&M via electronic mail on September 23, 2015. The NRC staff clarified the draft RAI in a conference call conducted on October 1, 2015. Based on our discussion, we understand that a response to the RAI will be provided by October 30, 2015. |
| | |
| | L. Weber Please feel free to contact me at (301) 415-2846 if you have any additional questions or concerns. |
| | Sincerely, |
| | ~f)~ |
| | Allison W. Dietrich, Project Manager Plant Licensing Branch 111-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-315 and 50-316 |
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| ==Enclosure:== | | ==Enclosure:== |
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| Second Request for Additional Information cc: Distribution via Listserv Sincerely, Allison W. Dietrich, Project Manager Plant Licensing Branch 111-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation SECOND REQUEST FOR ADDITIONAL INFORMATION REGARDING LICENSE AMENDMENT REQUEST TO REVISE TECHNICAL SPECIFICATIONS SURVEILLANCE REQUIREMENTS 3.8.1.10. | | Second Request for Additional Information cc: Distribution via Listserv |
| 3.8.1.11 I AND 3.8.1.15 DONALD C. COOK NUCLEAR PLANT. UNITS 1 AND 2 DOCKET NOS. 50-315 AND 50-316 TAC NOS. MF5436 and MF5437 The U.S. Nuclear Regulatory Commission staff has determined that the following additional information is needed to complete the review of the Indiana Michigan Power Company license amendment request dated December 17, 2014 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML 14356A022), as supplemented by letter dated July 9, 2015 (ADAMS Accession No. ML 15195A434), for the Donald C. Cook Nuclear Plant (CNP), Units 1 and 2. EEEB-RAl-5 In response to EEEB-RAl-2c, the licensee addressed the emergency diesel generator (EOG) operation during a loss of offsite power (LOOP) with a loss-of-coolant accident (LOCA) while the EOG is operating in parallel with the offsite power. The licensee stated: When the EOG [emergency diesel generator] | | |
| is in test mode, the SI [safety injection] | | SECOND REQUEST FOR ADDITIONAL INFORMATION REGARDING LICENSE AMENDMENT REQUEST TO REVISE TECHNICAL SPECIFICATIONS SURVEILLANCE REQUIREMENTS 3.8.1.10. 3.8.1.11 AND 3.8.1.15I DONALD C. COOK NUCLEAR PLANT. UNITS 1 AND 2 DOCKET NOS. 50-315 AND 50-316 TAC NOS. MF5436 and MF5437 The U.S. Nuclear Regulatory Commission staff has determined that the following additional information is needed to complete the review of the Indiana Michigan Power Company license amendment request dated December 17, 2014 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML14356A022), as supplemented by letter dated July 9, 2015 (ADAMS Accession No. ML15195A434), for the Donald C. Cook Nuclear Plant (CNP), Units 1 and 2. |
| or load shed signal will automatically trip the 4 kV [kilovolts] | | EEEB-RAl-5 In response to EEEB-RAl-2c, the licensee addressed the emergency diesel generator (EOG) operation during a loss of offsite power (LOOP) with a loss-of-coolant accident (LOCA) while the EOG is operating in parallel with the offsite power. The licensee stated: |
| Output Breaker during EOG test mode (these signals are blocked after two seconds, and therefore SI signal is prevented from reopening the breaker if a load shed occurs first, trips the breaker, then the breaker closes to load the EOG and a SI signal is initiated some time later). a. Please discuss the events or signals that initiate the load shed signal. If an SI signal also initiates a load shed signal, please clarify the sentence in parentheses in the above statement. | | When the EOG [emergency diesel generator] is in test mode, the SI [safety injection] or load shed signal will automatically trip the 4 kV [kilovolts] Output Breaker during EOG test mode (these signals are blocked after two seconds, and therefore SI signal is prevented from reopening the breaker if a load shed occurs first, trips the breaker, then the breaker closes to load the EOG and a SI signal is initiated some time later). |
| Also, please explain the EOG operation during degraded grid voltage conditions while the EOG is being tested in parallel with the offsite power source in Mode 1 or 2. b. Please discuss the EOG operation, including timing of vital load loads sequencing, during a LOOP concurrent with LOCA scenario, while the EOG is being tested in parallel with the offsite power source in Mode 1 or 2. Also, please clarify whether manual action to reset the lockout relay is allowed during a LOOP concurrent with LOCA event in the CNP licensing design basis accident analysis. | | : a. Please discuss the events or signals that initiate the load shed signal. If an SI signal also initiates a load shed signal, please clarify the sentence in parentheses in the above statement. Also, please explain the EOG operation during degraded grid voltage conditions while the EOG is being tested in parallel with the offsite power source in Mode 1 or 2. |
| Enclosure c. Please provide the timeline of tripping and closing of the EOG breaker, and discuss the timing of vital load sequencing for the following scenarios, with the EOG initially in test mode and paralleled with the offsite source: (1) LOOP followed by LOCA (2) LOCA followed by LOOP EEEB-RAl-6 In response to EEEB-RAl-3, the licensee stated that the EOG protective relays for generator overcurrent, generator differential, and generator neutral overcurrent remain active in emergency conditions. | | : b. Please discuss the EOG operation, including timing of vital load loads sequencing, during a LOOP concurrent with LOCA scenario, while the EOG is being tested in parallel with the offsite power source in Mode 1 or 2. Also, please clarify whether manual action to reset the lockout relay is allowed during a LOOP concurrent with LOCA event in the CNP licensing design basis accident analysis. |
| : a. Please explain the conditions defined as "non-emergency" and "emergency." b. Please provide a single line diagram showing the connection of the protective relays. Also, please discuss the physical location of the protective relays, including the lockout relay, for the EOG. EEEB-RAl-7 In response to EEEB-RAl-4, the licensee stated: The maximum 3 phase fault contribution from the EOG is 4.1 kA [kilo amperes]. | | Enclosure |
| The maximum fault at the T Bus is less than 42kA including the EOG contribution. | | : c. Please provide the timeline of tripping and closing of the EOG breaker, and discuss the timing of vital load sequencing for the following scenarios, with the EOG initially in test mode and paralleled with the offsite source: |
| The symmetrical interrupting rating of the 4 kV switchgear and breakers is 46.9 kA adjusted for the 4.16 kV rating. The maximum fault current, 42 kA calculated with the EOG in parallel does not exceed the fault rating of switchgear and breakers. | | (1) LOOP followed by LOCA (2) LOCA followed by LOOP EEEB-RAl-6 In response to EEEB-RAl-3, the licensee stated that the EOG protective relays for generator overcurrent, generator differential, and generator neutral overcurrent remain active in non-emergency conditions. |
| The fault currents are conservatively estimated based on the low circuit impedances and maximum fault contribution from the system and the motors connected to the bus. a. Section 8.4 of the CNP Updated Final Safety Analysis Report states that one EOG supplies power to two 4.16 KV safety buses (e.g., T11A and T11 Bin Unit 1, Train B). Please clarify whether the EOG is connected to both 4.16 kV safety buses (e.g., T11 A and T11 B) during testing of the EOG paralleled with the offsite power source, and during emergency conditions. | | : a. Please explain the conditions defined as "non-emergency" and "emergency." |
| | : b. Please provide a single line diagram showing the connection of the protective relays. Also, please discuss the physical location of the protective relays, including the lockout relay, for the EOG. |
| | EEEB-RAl-7 In response to EEEB-RAl-4, the licensee stated: |
| | The maximum 3 phase fault contribution from the EOG is 4.1 kA [kilo amperes]. |
| | The maximum fault at the T Bus is less than 42kA including the EOG contribution. The symmetrical interrupting rating of the 4 kV switchgear and breakers is 46.9 kA adjusted for the 4.16 kV rating. The maximum fault current, 42 kA calculated with the EOG in parallel does not exceed the fault rating of switchgear and breakers. The fault currents are conservatively estimated based on the low circuit impedances and maximum fault contribution from the system and the motors connected to the bus. |
| | : a. Section 8.4 of the CNP Updated Final Safety Analysis Report states that one EOG supplies power to two 4.16 KV safety buses (e.g., T11A and T11 Bin Unit 1, Train B). Please clarify whether the EOG is connected to both 4.16 kV safety buses (e.g., T11 A and T11 B) during testing of the EOG paralleled with the offsite power source, and during emergency conditions. |
| : b. Please provide a summary of the short circuit calculations at the T Bus( es) that is( are) connected to the EOG with the EOG in parallel with offsite power. | | : b. Please provide a summary of the short circuit calculations at the T Bus( es) that is( are) connected to the EOG with the EOG in parallel with offsite power. |
| L. Weber Please feel free to contact me at (301) 415-2846 if you have any additional questions or concerns.
| |
| Docket Nos. 50-315 and 50-316
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| ==Enclosure:==
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| Second Request for Additional Information cc: Distribution via Listserv DISTRIBUTION:
| | ML15267A683 *via memorandum OFFICE DORL/LPL3-1 /PM DORL/LPL3-1/LA DE/EEEB/BC* DORL/LPL3-1 /BC DORL/LPL3-1/PM NAME ADietrich MHenderson JZimmerman DPelton ADietrich DATE 9/24/2015 9/25/2015 09/23/2015 10/5/2015 10/5/2015}} |
| PUBLIC RidsNrrDorllpl3-1 Resource RidsNrrPMDCCook Resource RidsAcrsAcnw MailCTR Resource VGoel, NRR ADAMS Accession No.: ML 15267A683 Sincerely, IRA/ Allison W. Dietrich, Project Manager Plant Licensing Branch 111-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation LPL3-1 R/F RidsNrrDeEeeb Resource RidsNrrLAMHenderson Resource AFoli, NRR *via memorandum OFFICE DORL/LPL3-1
| |
| /PM DORL/LPL3-1/LA DE/EEEB/BC* | |
| DORL/LPL3-1 | |
| /BC DORL/LPL3-1/PM NAME ADietrich MHenderson JZimmerman DPelton ADietrich DATE 9/24/2015 9/25/2015 09/23/2015 10/5/2015 10/5/2015 OFFICIAL RECORD COPY}} | |
Letter Sequence RAI |
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MONTHYEARAEP-NRC-2014-70, License Amendment Request Regarding Technical Specification Section 3.8.1, AC Sources - Operating, Surveillance Requirements 3.8.1.10, 3.8.1.11, and 3.8.1.152014-12-17017 December 2014
License Amendment Request Regarding Technical Specification Section 3.8.1, AC Sources - Operating, Surveillance Requirements 3.8.1.10, 3.8.1.11, and 3.8.1.15
Project stage: Request
ML15029A0072015-01-28028 January 2015
NRR E-mail Capture - LIC-109 Acceptance of D.C.Cook LAR to Modify Notes to TS 3.8.1 - MF5436 and MF5437
Project stage: Acceptance Review
ML15163A1672015-06-15015 June 2015
Request for Additional Information Regarding License Amendment Request to Revise Technical Specification 3.8.1
Project stage: RAI
AEP-NRC-2015-60, Response to a Request for Additional Information Regarding the License Amendment Request to Revise Technical Specification Section 3.8.1, AC Sources - Operating, Surveillance Requirements 3.8.1.10, 3.8.1.11, and 3.8.1.152015-07-0909 July 2015
Response to a Request for Additional Information Regarding the License Amendment Request to Revise Technical Specification Section 3.8.1, AC Sources - Operating, Surveillance Requirements 3.8.1.10, 3.8.1.11, and 3.8.1.15
Project stage: Response to RAI
ML15267A6832015-10-0505 October 2015
Second Request for Additional Information Regarding License Amendment Request to Revise Technical Specification 3.8.1
Project stage: RAI
2015-10-05
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Units 1 and 2 - Information Request for NRC Triennial Evaluation of Changes, Tests, and Experiments (50.59) Baseline Inspection 05000315/2020020 and 05000316/2020020
ML20232B4432020-03-25025 March 2020
Request for Supporting Information for the D.C. Cook SPRA Audit Review - Plant Response Model Questions
ML19267A1362019-09-24024 September 2019
NRC Information Request (September 23, 2019) - IP 71111.08 - DC Cook U2 - Documents Selected for Onsite Review (DRS-M.Holmberg)
ML19204A0962019-07-23023 July 2019
NRR E-mail Capture - D.C. Cook Nuclear Plant Unit Nos. 1 and 2 - Request for Additional Information Related to Unit 2 Leak Before Break Analysis and Deletion of Containment Humidity Monitors for Unit Nos. 1 and 2
ML19211C3032019-07-0303 July 2019
NRR E-mail Capture - D.C. Cook Nuclear Plant Unit Nos. 1 & 2 - Request for Additional Information Related to LAR to Address NSAL-15-1
ML19084A0002019-03-20020 March 2019
NRR E-mail Capture - Resubmitted: Draft Request for Additional Information DC Cook Unit 1 - Leak-Before-Break LAR
ML19072A1432019-03-12012 March 2019
NRR E-mail Capture - Resubmitted: Draft Request for Additional Information DC Cook Unit 1 - Leak-Before-Break LAR
ML19011A3512019-01-11011 January 2019
NRR E-mail Capture - Request for Additional Information DC Cook Unit 1 Leak Before Break Amendment
ML18313A0802018-11-0808 November 2018
NRR E-mail Capture - D.C. Cook Units 1 and 2 - RAI for RPV Threads in Flange Alternative
ML18263A1542018-09-14014 September 2018
NRR E-mail Capture - D.C. Cook Unit No. 1 - RAI for Leak-Before-Break LAR
ML18204A3722018-07-19019 July 2018
NRR E-mail Capture - D.C. Cook Unit No. 1 - RAI for Leak-Before-Break LAR
ML18143B6292018-05-29029 May 2018
Dtf. RAI
ML18142B5312018-05-29029 May 2018
Request for Additional Information Concerning 2017 Decommissioning Funding Status Report
ML18060A0212018-02-28028 February 2018
Enclosurequest for Additional Information (Request for Additional Information Regarding Indiana Michigan Power Company'S Decommissioning Funding Update for Donald C Cook Nuclear Plant Units 1 and 2 ISFSI)
ML18043A0092018-02-0909 February 2018
NRR E-mail Capture - DC Cook, Unit 2 - Request for Additional Information Regarding Reactor Vessel Internals Again Management Program
ML17304A0102017-11-0101 November 2017
Unit Nos.1 and 2 - Request for Additional Information Regarding Generic Letter 2016-01, Monitoring of Neutron-Absorbing Materials in Spent Fuel Pools (CAC Nos. MF9444 and MF9445; EPID L-2016-LRC-0001)
ML17249A7492017-08-28028 August 2017
E-Mail Sent August 28, 2017, Request for Information for Donald C. Cook Nuclear Power Plant, Unit 1 (Part B); Inspection Report 05000315/2017004 (Msh)
ML17108A7772017-04-18018 April 2017
17 Donald C. Cook Nuclear Power Plant, Unit 1 - Notification of NRC Baseline Inspection and Request for Information (05000315/2017003; 05000316/2017003) (Msh)
ML17068A0652017-03-0808 March 2017
Ltr 03/08/17 Donald C. Cook Nuclear Power Plant, Unit 2 - Information Request for an NRC Post-Approval Site Inspection for License Renewal 05000316/2017009 (Bxj)
ML17027A0192017-01-26026 January 2017
NRR E-mail Capture - D.C. Cook Units 1 and 2 - RAI Regarding LAR to Revise TS 5.5.14 (MF8483 and MF8484)
ML16211A0152016-08-0101 August 2016
Follow-Up Request for Additional Information Regarding License Amendment Request to Relocate Surveillance Frequencies to Licensee Control
IR 05000315/20160042016-07-11011 July 2016
Donald C. Cook Nuclear Power Plant, Unit 2 - Notification of NRC Inspection and Request for Information; Inspection Report 05000315/2016004; 05000316/2016004
ML16193A6542016-07-11011 July 2016
Notification of NRC Inspection and Request for Information; Inspection Report 05000315/2016004; 05000316/2016004
ML16154A1822016-06-0909 June 2016
Request for Additional Information Regarding License Amendment Request to Relocate Surveillance Frequencies to Licensee Control (CAC Nos. MF7114 and MF7115)
ML16127A0792016-05-11011 May 2016
Request for Additional Information Regarding License Amendment Request to Relocate Surveillance Frequencies to Licensee Control
ML16025A0552016-01-22022 January 2016
Ltr. 01/22/16 Donald C. Cook Nuclear Power Plant, Units 1 and 2 - Request for Information for an NRC Pilot Design Bases Inspection on the Implementation of the Environmental Qualification Program Inspection Report 05000315/2016008; 05000316
ML15267A6832015-10-0505 October 2015
Second Request for Additional Information Regarding License Amendment Request to Revise Technical Specification 3.8.1
ML15231A5542015-08-18018 August 2015
Ltr. 08/18/15 Donald C. Cook Nuclear Power Plant, Units 1 and 2 - Request for Information for an NRC Triennial Pilot Baseline Component Design Bases Inspection (Inspection Report 05000315/2015008; 05000316/2015008) (Axd)
ML15225A5772015-08-13013 August 2015
Information Request to Support Upcoming Problem Identification and Resolution Inspection at D.C. Cook, Units 1 and 2
ML15163A1672015-06-15015 June 2015
Request for Additional Information Regarding License Amendment Request to Revise Technical Specification 3.8.1
ML15149A3832015-05-28028 May 2015
Information Request to Support NRC Annual Baseline Emergency Action Level and Emergency Plan Changes Inspection (Mxg)
ML15119A3392015-05-0505 May 2015
Follow-up Request for Additional Information Concerning the Reactor Vessel Internals Aging Management Program Submittal
ML15055A5702015-02-24024 February 2015
Cyber Security RFI Temporary Instruction 2201/004
ML15022A1532015-01-21021 January 2015
Dccook ISI Request for Information
2024-06-26
[Table view] |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 October 5, 2015 Mr. Lawrence J. Weber Senior Vice President and Chief Nuclear Officer Indiana Michigan Power Company Nuclear Generation Group One Cook Place Bridgman, Ml 49106
SUBJECT:
DONALD C. COOK NUCLEAR PLANT, UNITS i AND 2 - SECOND REQUEST FOR ADDITIONAL INFORMATION REGARDING LICENSE AMENDMENT REQUEST TO REVISE TECHNICAL SPECIFICATION 3.8.1 (TAC NOS.
MF5436 AND MF5437)
Dear Mr. Weber:
By letter dated December 17, 2014 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML14356A022), as supplemented by letter dated July 9, 2015 (ADAMS Accession No. ML15195A434), Indiana Michigan Power Company (l&M, the licensee) requested an amendment to Renewed Facility Operating Licenses DPR-58 and DPR-74 for Donald C. Cook Nuclear Plant, Units 1 and 2. The proposed amendments would revise the Technical Specifications 3.8.1, "AC Sources - Operating," to allow testing of the onsite standby emergency diesel generators (DGs) during modes in which it is currently prohibited.
Specifically, the proposed changes would remove the mode restrictions in the notes of Surveillance Requirements 3.8.1.1 O (DG single largest load rejection test), 3.8.1.11 (DG full load rejection test), and 3.8.1.15 (DG endurance run).
The U.S. Nuclear Regulatory Commission (NRC) staff has reviewed the subject submittal and supplement, and has determined that additional information is needed to complete the review, as described in the enclosed Second Request for Additional Information (RAI). The draft RAI was sent to l&M via electronic mail on September 23, 2015. The NRC staff clarified the draft RAI in a conference call conducted on October 1, 2015. Based on our discussion, we understand that a response to the RAI will be provided by October 30, 2015.
L. Weber Please feel free to contact me at (301) 415-2846 if you have any additional questions or concerns.
Sincerely,
~f)~
Allison W. Dietrich, Project Manager Plant Licensing Branch 111-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-315 and 50-316
Enclosure:
Second Request for Additional Information cc: Distribution via Listserv
SECOND REQUEST FOR ADDITIONAL INFORMATION REGARDING LICENSE AMENDMENT REQUEST TO REVISE TECHNICAL SPECIFICATIONS SURVEILLANCE REQUIREMENTS 3.8.1.10. 3.8.1.11 AND 3.8.1.15I DONALD C. COOK NUCLEAR PLANT. UNITS 1 AND 2 DOCKET NOS. 50-315 AND 50-316 TAC NOS. MF5436 and MF5437 The U.S. Nuclear Regulatory Commission staff has determined that the following additional information is needed to complete the review of the Indiana Michigan Power Company license amendment request dated December 17, 2014 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML14356A022), as supplemented by letter dated July 9, 2015 (ADAMS Accession No. ML15195A434), for the Donald C. Cook Nuclear Plant (CNP), Units 1 and 2.
EEEB-RAl-5 In response to EEEB-RAl-2c, the licensee addressed the emergency diesel generator (EOG) operation during a loss of offsite power (LOOP) with a loss-of-coolant accident (LOCA) while the EOG is operating in parallel with the offsite power. The licensee stated:
When the EOG [emergency diesel generator] is in test mode, the SI [safety injection] or load shed signal will automatically trip the 4 kV [kilovolts] Output Breaker during EOG test mode (these signals are blocked after two seconds, and therefore SI signal is prevented from reopening the breaker if a load shed occurs first, trips the breaker, then the breaker closes to load the EOG and a SI signal is initiated some time later).
- a. Please discuss the events or signals that initiate the load shed signal. If an SI signal also initiates a load shed signal, please clarify the sentence in parentheses in the above statement. Also, please explain the EOG operation during degraded grid voltage conditions while the EOG is being tested in parallel with the offsite power source in Mode 1 or 2.
- b. Please discuss the EOG operation, including timing of vital load loads sequencing, during a LOOP concurrent with LOCA scenario, while the EOG is being tested in parallel with the offsite power source in Mode 1 or 2. Also, please clarify whether manual action to reset the lockout relay is allowed during a LOOP concurrent with LOCA event in the CNP licensing design basis accident analysis.
Enclosure
- c. Please provide the timeline of tripping and closing of the EOG breaker, and discuss the timing of vital load sequencing for the following scenarios, with the EOG initially in test mode and paralleled with the offsite source:
(1) LOOP followed by LOCA (2) LOCA followed by LOOP EEEB-RAl-6 In response to EEEB-RAl-3, the licensee stated that the EOG protective relays for generator overcurrent, generator differential, and generator neutral overcurrent remain active in non-emergency conditions.
- a. Please explain the conditions defined as "non-emergency" and "emergency."
- b. Please provide a single line diagram showing the connection of the protective relays. Also, please discuss the physical location of the protective relays, including the lockout relay, for the EOG.
EEEB-RAl-7 In response to EEEB-RAl-4, the licensee stated:
The maximum 3 phase fault contribution from the EOG is 4.1 kA [kilo amperes].
The maximum fault at the T Bus is less than 42kA including the EOG contribution. The symmetrical interrupting rating of the 4 kV switchgear and breakers is 46.9 kA adjusted for the 4.16 kV rating. The maximum fault current, 42 kA calculated with the EOG in parallel does not exceed the fault rating of switchgear and breakers. The fault currents are conservatively estimated based on the low circuit impedances and maximum fault contribution from the system and the motors connected to the bus.
- a. Section 8.4 of the CNP Updated Final Safety Analysis Report states that one EOG supplies power to two 4.16 KV safety buses (e.g., T11A and T11 Bin Unit 1, Train B). Please clarify whether the EOG is connected to both 4.16 kV safety buses (e.g., T11 A and T11 B) during testing of the EOG paralleled with the offsite power source, and during emergency conditions.
- b. Please provide a summary of the short circuit calculations at the T Bus( es) that is( are) connected to the EOG with the EOG in parallel with offsite power.
ML15267A683 *via memorandum OFFICE DORL/LPL3-1 /PM DORL/LPL3-1/LA DE/EEEB/BC* DORL/LPL3-1 /BC DORL/LPL3-1/PM NAME ADietrich MHenderson JZimmerman DPelton ADietrich DATE 9/24/2015 9/25/2015 09/23/2015 10/5/2015 10/5/2015
