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{{#Wiki_filter:Donald C. Cook Nuclear Plant Commitment Change Summary October 2020 to May 2022 UNITS 1 AND 2 ISSUANCE OF AMENDMENTS RELATED TO REACTOR PROTECTION SYSTEM UPGRADE Commitment No: 6020 | {{#Wiki_filter:Donald C. Cook Nuclear Plant Commitment Change Summary October 2020 to May 2022 | ||
UNITS 1 AND 2 ISSUANCE OF AMENDMENTS RELATED TO REACTOR PROTECTION SYSTEM UPGRADE | |||
Commitment No: 6020 Classification: Revision | |||
Source Document: N94001 (ADAMS Accession No. 9402140102) | |||
Existing Commitment Statement: | Existing Commitment Statement: | ||
The use of radio transmitters inside the Control Room is controlled by administrative procedures. Except for a cordless telephone for use in front of the control boards, use of radio transmitters in the Control Room is otherwise prohibited. | The use of radio transmitters inside the Control Room is controlled by administrative procedures. Except for a cordless telephone for use in front of the control boards, use of radio transmitters in the Control Room is otherwise prohibited. | ||
Revised Commitment Statement: | Revised Commitment Statement: | ||
The use of radio transmitters inside the Control Room is controlled by administrative procedures. Except for those devices specifically authorized by administrative procedures, use of radio transmitters in the Control Room is otherwise prohibited. | The use of radio transmitters inside the Control Room is controlled by administrative procedures. Except for those devices specifically authorized by administrative procedures, use of radio transmitters in the Control Room is otherwise prohibited. | ||
Change Description Summary: | Change Description Summary: | ||
This revision allows for the use of additional radio transmitters in the Control Rooms provided that use of these devices can be shown to result in radio frequency levels, at Reactor Protection System cabinets, remaining below the testing levels used to verify their normal operations for modification RFC-12-2985. The authorization of additional devices will be controlled by administrative procedures. | This revision allows for the use of additional radio transmitters in the Control Rooms provided that use of these devices can be shown to result in radio frequency levels, at Reactor Protection System cabinets, remaining below the testing levels used to verify their normal operations for modification RFC-12-2985. The authorization of additional devices will be controlled by administrative procedures. | ||
Donald C. Cook Nuclear Plant Commitment Change Summary October 2020 to May 2022 EMERGENCY | 1 Donald C. Cook Nuclear Plant Commitment Change Summary October 2020 to May 2022 | ||
EMERGENCY PREPAREDNESS INFORMATION REQUESTED BY NUCLEAR REGULATORY COMMISSION LETTER: REQUEST FOR ADDITIONAL INFORMATION PURSUANT TO 10 CFR 50.54(f) REGARDING FUKUSHIMA NEAR-TERM TASK FORCE | |||
Commitment No: 8544 Classification: Revision | |||
Source Document: AEP-NRC-2012-43 (ADAMS Accession No. ML12172A353) | |||
Existing Commitment Statements: | Existing Commitment Statements: | ||
Incorporate expectations set for the Emergency Response Organization (ERO) to automatically respond to or a designated staging area when made aware of an area-wide disaster (e.g., loss of grid, natural or man-made disaster, etc.) resulting in degraded communications capabilities into the TS-C-CS17 (E-Plan Overview) and NANTeL CP-C-ANRQ (Emergency Plan Annual Requalification) lesson plans. | Incorporate expectations set for the Emergency Response Organization (ERO) to automatically respond to or a designated staging area when made aware of an area-wide disaster (e.g., loss of grid, natural or man-made disaster, etc.) resulting in degraded communications capabilities into the TS-C-CS17 (E-Plan Overview) and NANTeL CP-C-ANRQ (Emergency Plan Annual Requalification) lesson plans. | ||
Revised Commitment Statement: | Revised Commitment Statement: | ||
Incorporate expectations set for the Emergency Response Organization (ERO) to automatically respond to or a designated staging area when made aware of an area-wide disaster (e.g., loss of grid, natural or man-made disaster, etc.) resulting in degraded communications capabilities into the EP-I-OVRW, Emergency Plan Overview, lesson plans. | Incorporate expectations set for the Emergency Response Organization (ERO) to automatically respond to or a designated staging area when made aware of an area-wide disaster (e.g., loss of grid, natural or man-made disaster, etc.) resulting in degraded communications capabilities into the EP-I-OVRW, Emergency Plan Overview, lesson plans. | ||
Change Description Summary: | Change Description Summary: | ||
TS-C-CS17, E-Plan Overview, and NANTeL CP-C-ANRQ, Emergency Plan Annual Requalification have been merged into one Lesson Plan and renamed EP-I-OVRW, Emergency Plan Overview. | TS-C-CS17, E-Plan Overview, and NANTeL CP-C-ANRQ, Emergency Plan Annual Requalification have been merged into one Lesson Plan and renamed EP-I-OVRW, Emergency Plan Overview. | ||
Donald C. Cook Nuclear Plant Commitment Change Summary October 2020 to May 2022 FINAL SAFETY ANALYSIS REPORT, AMENDMENT 20, QUESTION 4.28 Commitment No: 859 | 2 Donald C. Cook Nuclear Plant Commitment Change Summary October 2020 to May 2022 | ||
FINAL SAFETY ANALYSIS REPORT, AMENDMENT 20, QUESTION 4.28 | |||
Commitment No: 859 Classification: Revision | |||
Source Document: Original Final Safety Analysis Report | |||
Existing Commitment Statement: | |||
The response to our request number 4.16.5 concluded that no inservice inspection was required on the primary coolant pump motor flywheel. We do not concur with this conclusion and believe that our views on the matter are suitably discussed within Safety Guide No. 14 dated October 27, 1971. Accordingly it is requested that a suitable inservice inspection program for the primary coolant pump motor flywheels be provided. We suggest that the essential elements of this inservice inspection program be incorporated into Section 4.2 of the Technical Specifications. | The response to our request number 4.16.5 concluded that no inservice inspection was required on the primary coolant pump motor flywheel. We do not concur with this conclusion and believe that our views on the matter are suitably discussed within Safety Guide No. 14 dated October 27, 1971. Accordingly it is requested that a suitable inservice inspection program for the primary coolant pump motor flywheels be provided. We suggest that the essential elements of this inservice inspection program be incorporated into Section 4.2 of the Technical Specifications. | ||
ANSWER: | ANSWER: | ||
The inservice inspection program for each reactor coolant pump flywheel will include the following: | The inservice inspection program for each reactor coolant pump flywheel will include the following: | ||
| Line 43: | Line 68: | ||
: c. Each flywheel will be inspected at intervals not exceeding 10 years. | : c. Each flywheel will be inspected at intervals not exceeding 10 years. | ||
: d. Examination procedure and acceptance criteria shall be in conformance with Section 4.5.1.2 of the Donald C. Cook Nuclear Plant FSAR. | : d. Examination procedure and acceptance criteria shall be in conformance with Section 4.5.1.2 of the Donald C. Cook Nuclear Plant FSAR. | ||
Revised Commitment Statement: | Revised Commitment Statement: | ||
The response to our request number 4.16.5 concluded that no inservice inspection was required on the primary coolant pump motor flywheel. We do not concur with this conclusion and believe that our views on the matter are suitably discussed within Safety Guide No. 14 dated October 27, 1971. Accordingly it is requested that a suitable inservice inspection program for the primary coolant pump motor flywheels be provided. We suggest that the essential elements of this inservice inspection program be incorporated into Section 4.2 of the Technical Specifications. | The response to our request number 4.16.5 concluded that no inservice inspection was required on the primary coolant pump motor flywheel. We do not concur with this conclusion and believe that our views on the matter are suitably discussed within Safety Guide No. 14 dated October 27, 1971. Accordingly it is requested that a suitable inservice inspection program for the primary coolant pump motor flywheels be provided. We suggest that the essential elements of this inservice inspection program be incorporated into Section 4.2 of the Technical Specifications. | ||
ANSWER: | ANSWER: | ||
The inservice inspection program for each reactor coolant pump flywheel will include the following: | The inservice inspection program for each reactor coolant pump flywheel will include the following: | ||
| Line 50: | Line 77: | ||
: b. A surface examination of all surfaces exposed by removal of the flywheel cover with the flywheel keyed to the motor shaft. | : b. A surface examination of all surfaces exposed by removal of the flywheel cover with the flywheel keyed to the motor shaft. | ||
: c. Each flywheel will be inspected at the intervals specified in Technical Specification 5.5.5 (Reactor Coolant Pump Flywheel Inspection Program). | : c. Each flywheel will be inspected at the intervals specified in Technical Specification 5.5.5 (Reactor Coolant Pump Flywheel Inspection Program). | ||
Donald C. Cook Nuclear Plant Commitment Change Summary October 2020 to May 2022 Commitment No: 859 (continued) | 3 Donald C. Cook Nuclear Plant Commitment Change Summary October 2020 to May 2022 | ||
Commitment No: 859 (continued) | |||
: d. Examination procedure and acceptance criteria shall be in conformance with Section 4.5.1.2 of the Donald C. Cook Nuclear Plant FSAR. | : d. Examination procedure and acceptance criteria shall be in conformance with Section 4.5.1.2 of the Donald C. Cook Nuclear Plant FSAR. | ||
Change Description Summary: | Change Description Summary: | ||
The Nuclear Regulatory Commission approved License Amendments 350 and 331 for Unit 1 and Unit 2 which relax Reactor Coolant Pump (RCP) Flywheel Integrity Inspection frequency to 20 years. | The Nuclear Regulatory Commission approved License Amendments 350 and 331 for Unit 1 and Unit 2 which relax Reactor Coolant Pump (RCP) Flywheel Integrity Inspection frequency to 20 years. | ||
==Reference:== | ==Reference:== | ||
Letter from the Nuclear Regulatory Commission, to J. P. Gebbie, Indiana Michigan Power Company, Donald C. Cook Nuclear Plant, Unit Nos. 1 and 2 - Issuance of Amendment Nos. | Letter from the Nuclear Regulatory Commission, to J. P. Gebbie, Indiana Michigan Power Company, Donald C. Cook Nuclear Plant, Unit Nos. 1 and 2 - Issuance of Amendment Nos. | ||
350 and 331 to Revise Technical Specification 5.5.5, Reactor Coolant Pump Flywheel Inspection Program, in accordance with TSTF-421-A, Revision 0 (EPID L-1029-LLA-0185), | 350 and 331 to Revise Technical Specification 5.5.5, Reactor Coolant Pump Flywheel Inspection Program, in accordance with TSTF-421-A, Revision 0 (EPID L-1029-LLA-0185), | ||
ML19347B376, dated January 31, 2020. | ML19347B376, dated January 31, 2020. | ||
Donald C. Cook Nuclear Plant Commitment Change Summary October 2020 to May 2022 SUPPLEMENT TO SEISMIC PROBABILISTIC RISK ASSESSMENT IN RESPONSE TO NEAR TERM TASK FORCE RECOMMENDATION 2.1: SIESMIC Commitment No: 8657 | 4 Donald C. Cook Nuclear Plant Commitment Change Summary October 2020 to May 2022 | ||
SUPPLEMENT TO SEISMIC PROBABILISTIC RISK ASSESSMENT IN RESPONSE TO NEAR TERM TASK FORCE RECOMMENDATION 2.1: SIESMIC | |||
Commitment No: 8657 Classification: Schedule Change | |||
Source Document: AEP-NRC-2020-52 (ADAMS Accession No. ML20206K894) | |||
Existing Commitment Statement: | Existing Commitment Statement: | ||
Provide backup power to the containment distributed ignition system (DIS) in the event of loss of offsite power. | Provide backup power to the containment distributed ignition system (DIS) in the event of loss of offsite power. | ||
Due Date: 9/9/2022 Revised Commitment Statement: | |||
Due Date: 9/9/2022 | |||
Revised Commitment Statement: | |||
Provide backup power to the containment distributed ignition system (DIS) in the event of loss of offsite power. | Provide backup power to the containment distributed ignition system (DIS) in the event of loss of offsite power. | ||
Due Date: 12/15/2022 Change Description Summary: | |||
Due Date: 12/15/2022 | |||
Change Description Summary: | |||
The original system design was amended to support full remote operation from both unit control rooms. The updated DIS modification design requires installation within close proximity of existing plant equipment that could cause a plant trip. Operations management determined this scope of work cannot be performed online due to the potential trip hazard and requires rescheduling to the Spring and Fall 2022 Refueling Outages. | The original system design was amended to support full remote operation from both unit control rooms. The updated DIS modification design requires installation within close proximity of existing plant equipment that could cause a plant trip. Operations management determined this scope of work cannot be performed online due to the potential trip hazard and requires rescheduling to the Spring and Fall 2022 Refueling Outages. | ||
==Reference:== | ==Reference:== | ||
Letter from Q. S. Lies, Indianan Michigan Power Company, to the Nuclear Regulatory Commission, Commitment Schedule Change Related to Seismic PRA Distributed Ignition Backup Power Source, ML22061A195, dated March 2, 2022. | |||
5}} | 5}} | ||
Revision as of 15:50, 15 November 2024
Text
Donald C. Cook Nuclear Plant Commitment Change Summary October 2020 to May 2022
UNITS 1 AND 2 ISSUANCE OF AMENDMENTS RELATED TO REACTOR PROTECTION SYSTEM UPGRADE
Commitment No: 6020 Classification: Revision
Source Document: N94001 (ADAMS Accession No. 9402140102)
Existing Commitment Statement:
The use of radio transmitters inside the Control Room is controlled by administrative procedures. Except for a cordless telephone for use in front of the control boards, use of radio transmitters in the Control Room is otherwise prohibited.
Revised Commitment Statement:
The use of radio transmitters inside the Control Room is controlled by administrative procedures. Except for those devices specifically authorized by administrative procedures, use of radio transmitters in the Control Room is otherwise prohibited.
Change Description Summary:
This revision allows for the use of additional radio transmitters in the Control Rooms provided that use of these devices can be shown to result in radio frequency levels, at Reactor Protection System cabinets, remaining below the testing levels used to verify their normal operations for modification RFC-12-2985. The authorization of additional devices will be controlled by administrative procedures.
1 Donald C. Cook Nuclear Plant Commitment Change Summary October 2020 to May 2022
EMERGENCY PREPAREDNESS INFORMATION REQUESTED BY NUCLEAR REGULATORY COMMISSION LETTER: REQUEST FOR ADDITIONAL INFORMATION PURSUANT TO 10 CFR 50.54(f) REGARDING FUKUSHIMA NEAR-TERM TASK FORCE
Commitment No: 8544 Classification: Revision
Source Document: AEP-NRC-2012-43 (ADAMS Accession No. ML12172A353)
Existing Commitment Statements:
Incorporate expectations set for the Emergency Response Organization (ERO) to automatically respond to or a designated staging area when made aware of an area-wide disaster (e.g., loss of grid, natural or man-made disaster, etc.) resulting in degraded communications capabilities into the TS-C-CS17 (E-Plan Overview) and NANTeL CP-C-ANRQ (Emergency Plan Annual Requalification) lesson plans.
Revised Commitment Statement:
Incorporate expectations set for the Emergency Response Organization (ERO) to automatically respond to or a designated staging area when made aware of an area-wide disaster (e.g., loss of grid, natural or man-made disaster, etc.) resulting in degraded communications capabilities into the EP-I-OVRW, Emergency Plan Overview, lesson plans.
Change Description Summary:
TS-C-CS17, E-Plan Overview, and NANTeL CP-C-ANRQ, Emergency Plan Annual Requalification have been merged into one Lesson Plan and renamed EP-I-OVRW, Emergency Plan Overview.
2 Donald C. Cook Nuclear Plant Commitment Change Summary October 2020 to May 2022
FINAL SAFETY ANALYSIS REPORT, AMENDMENT 20, QUESTION 4.28
Commitment No: 859 Classification: Revision
Source Document: Original Final Safety Analysis Report
Existing Commitment Statement:
The response to our request number 4.16.5 concluded that no inservice inspection was required on the primary coolant pump motor flywheel. We do not concur with this conclusion and believe that our views on the matter are suitably discussed within Safety Guide No. 14 dated October 27, 1971. Accordingly it is requested that a suitable inservice inspection program for the primary coolant pump motor flywheels be provided. We suggest that the essential elements of this inservice inspection program be incorporated into Section 4.2 of the Technical Specifications.
ANSWER:
The inservice inspection program for each reactor coolant pump flywheel will include the following:
- a. An in-place ultrasonic examination of the flywheel keyways and all surfaces exposed by removal of the flywheel cover.
- b. A surface examination of all surfaces exposed by removal of the flywheel cover with the flywheel keyed to the motor shaft.
- c. Each flywheel will be inspected at intervals not exceeding 10 years.
- d. Examination procedure and acceptance criteria shall be in conformance with Section 4.5.1.2 of the Donald C. Cook Nuclear Plant FSAR.
Revised Commitment Statement:
The response to our request number 4.16.5 concluded that no inservice inspection was required on the primary coolant pump motor flywheel. We do not concur with this conclusion and believe that our views on the matter are suitably discussed within Safety Guide No. 14 dated October 27, 1971. Accordingly it is requested that a suitable inservice inspection program for the primary coolant pump motor flywheels be provided. We suggest that the essential elements of this inservice inspection program be incorporated into Section 4.2 of the Technical Specifications.
ANSWER:
The inservice inspection program for each reactor coolant pump flywheel will include the following:
- a. An in-place ultrasonic examination of the flywheel keyways and all surfaces exposed by removal of the flywheel cover.
- b. A surface examination of all surfaces exposed by removal of the flywheel cover with the flywheel keyed to the motor shaft.
- c. Each flywheel will be inspected at the intervals specified in Technical Specification 5.5.5 (Reactor Coolant Pump Flywheel Inspection Program).
3 Donald C. Cook Nuclear Plant Commitment Change Summary October 2020 to May 2022
Commitment No: 859 (continued)
- d. Examination procedure and acceptance criteria shall be in conformance with Section 4.5.1.2 of the Donald C. Cook Nuclear Plant FSAR.
Change Description Summary:
The Nuclear Regulatory Commission approved License Amendments 350 and 331 for Unit 1 and Unit 2 which relax Reactor Coolant Pump (RCP) Flywheel Integrity Inspection frequency to 20 years.
Reference:
Letter from the Nuclear Regulatory Commission, to J. P. Gebbie, Indiana Michigan Power Company, Donald C. Cook Nuclear Plant, Unit Nos. 1 and 2 - Issuance of Amendment Nos.
350 and 331 to Revise Technical Specification 5.5.5, Reactor Coolant Pump Flywheel Inspection Program, in accordance with TSTF-421-A, Revision 0 (EPID L-1029-LLA-0185),
ML19347B376, dated January 31, 2020.
4 Donald C. Cook Nuclear Plant Commitment Change Summary October 2020 to May 2022
SUPPLEMENT TO SEISMIC PROBABILISTIC RISK ASSESSMENT IN RESPONSE TO NEAR TERM TASK FORCE RECOMMENDATION 2.1: SIESMIC
Commitment No: 8657 Classification: Schedule Change
Source Document: AEP-NRC-2020-52 (ADAMS Accession No. ML20206K894)
Existing Commitment Statement:
Provide backup power to the containment distributed ignition system (DIS) in the event of loss of offsite power.
Due Date: 9/9/2022
Revised Commitment Statement:
Provide backup power to the containment distributed ignition system (DIS) in the event of loss of offsite power.
Due Date: 12/15/2022
Change Description Summary:
The original system design was amended to support full remote operation from both unit control rooms. The updated DIS modification design requires installation within close proximity of existing plant equipment that could cause a plant trip. Operations management determined this scope of work cannot be performed online due to the potential trip hazard and requires rescheduling to the Spring and Fall 2022 Refueling Outages.
Reference:
Letter from Q. S. Lies, Indianan Michigan Power Company, to the Nuclear Regulatory Commission, Commitment Schedule Change Related to Seismic PRA Distributed Ignition Backup Power Source, ML22061A195, dated March 2, 2022.
5