ML20043D304
| ML20043D304 | |
| Person / Time | |
|---|---|
| Site: | Cook  |
| Issue date: | 05/01/2020 |
| From: | Robert Kuntz Plant Licensing Branch III |
| To: | Gebbie J Indiana Michigan Power Co |
| Kuntz R | |
| References | |
| EPID L-2019-LLA-0147 | |
| Download: ML20043D304 (20) | |
Text
May 1, 2020 Mr. Joel P. Gebbie Senior Vice President and Chief Nuclear Officer Indiana Michigan Power Company Nuclear Generation Group One Cook Place Bridgman, MI 49106
SUBJECT:
DONALD C. COOK NUCLEAR PLANT, UNIT NOS. 1 AND 2 - ISSUANCE OF AMENDMENT NOS. 351 AND 332 TO REVISE TECHNICAL SPECIFICATION 3.8.1 AC SOURCE - OPERATING (EPID L-2019-LLA-0147)
Dear Mr. Gebbie:
The U.S. Nuclear Regulatory Commission (the Commission) has issued the enclosed Amendment Nos. 351 and 332 to Renewed Facility Operating License Nos. DPR-58 and DPR-74, for the Donald C. Cook Nuclear Plant (CNP), Unit Nos. 1 and 2, respectively. The amendments consist of changes to the Technical Specifications in response to your application dated June 27, 2019.
The amendments revise the CNP, Unit Nos. 1 and 2, Technical Specification 3.8.1, AC Sources - Operating, by deleting surveillance requirement 3.8.1.20 which requires verification that diesel generator (DG) availability is not compromised when the DG is tested by connecting to its load test resistor banks.
A copy of our related safety evaluation is also enclosed. A Notice of Issuance will be included in the Commissions biweekly Federal Register notice.
Sincerely,
/RA/
Robert F. Kuntz, Senior Project Manager Plant Licensing Branch III Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-315 and 50-316
Enclosure:
- 1. Amendment No. 351 to DPR-58
- 2. Amendment No. 332 to DPR-74
- 3. Safety Evaluation cc: Listserv
INDIANA MICHIGAN POWER COMPANY DOCKET NO. 50-315 DONALD C. COOK NUCLEAR PLANT, UNIT NO. 1 AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment No. 351 License No. DPR-58
- 1.
The U.S. Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Indiana Michigan Power Company dated June 27, 2019, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commissions rules and regulations set forth in 10 CFR Chapter I; B.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C.
There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commissions regulations; D.
The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commissions regulations and all applicable requirements have been satisfied.
2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Renewed Facility Operating License No. DPR-58 is hereby amended to read as follows:
(2)
Technical Specifications The Technical Specifications contained in Appendix A, and the Environmental Protection Plan contained in Appendix B, as revised through Amendment No. 351, are hereby incorporated in this license. The licensee shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
3.
This license amendment is effective as of its date of issuance and shall be implemented within 90 days of the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION Nancy L. Salgado, Chief Plant Licensing Branch III Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
Attachment:
Changes to the Renewed Facility Operating License and Technical Specifications Date of Issuance: May 1, 2020 Scott P. Wall Digitally signed by Scott P.
Wall Date: 2020.05.01 15:12:36
-04'00'
ATTACHMENT TO LICENSE AMENDMENT NO. 351 DONALD C. COOK NUCLEAR PLANT, UNIT NO. 1 AMENDMENT TO RENEWED FACILITY OPERATING LICENSE DOCKET NO. 50-315 Renewed Facility Operating License No. DPR-58 Replace the following page of the Renewed Facility Operating License No. DPR-58 with the attached revised page. The revised page is identified by amendment number and contains marginal lines indicating the area of change INSERT REMOVE Technical Specifications Replace the following page of the Renewed Facility Operating License, Appendix A, Technical Specifications, with the attached revised page. The revised page is identified by amendment number and contains marginal lines indicating the area of change.
INSERT REMOVE 3.8.1-17 3.8.1-17 3.8.1-18 3.8.1-18 3.8.2-3 3.8.2-3 Renewed License No. DPR-58 Amendment No:332, 334, 335, 336, 337, 338, 343, 344, 345, 346, 347, 348, 349, 350, 351 and radiation monitoring equipment calibration, and as fission detectors in amounts as required; (4)
Pursuant to the Act and 10 CFR Parts 30, 40 and 70, to receive, possess and use in amounts as required any byproduct, source or special nuclear material without restriction to chemical or physical form, for sample analysis or instrument and equipment calibration or associated with radioactive apparatus or components; and (5)
Pursuant to the Act and 10 CFR Parts 30 and 70, to possess, but not separate, such byproduct and special nuclear materials as may be produced by the operation of the facility.
C.
This renewed operating license shall be deemed to contain and is subject to the conditions specified in the following Commission regulations in 10 CFR Chapter I: Part 20, Section 30.34 of Part 30, Section 40.41 of Part 40, Sections 50.54 and 50.59 of Part 50, and Section 70.32 of Part 70; and is subject to all applicable provisions of the Act and to the rules, regulations, and orders of the Commission now or hereafter in effect; and is subject to the additional conditions specified or incorporated below:
(1)
Maximum Power Level The licensee is authorized to operate the facility at steady state reactor core power levels not to exceed 3304 megawatts thermal in accordance with the conditions specified herein.
(2)
Technical Specifications The Technical Specifications contained in Appendix A, and the Environmental Protection Plan contained in Appendix B, as revised through Amendment No. 351, are hereby incorporated in this license. The licensee shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
(3)
Less than Four Loop Operation The licensee shall not operate the reactor at power levels above P-7 (as defined in Table 3.3.1-1 of Specification 3.3.1 of Appendix A to this renewed operating license) with less than four reactor coolant loops in operation until (a) safety analyses for less than four loop operation have been submitted, and (b) approval for less than four loop operation at power levels above P-7 has been granted by the Commission by amendment of this license.
(4)
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 licensees 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,
AC Sources - Operating 3.8.1 Cook Nuclear Plant Unit 1 3.8.1-17 Amendment No. 287, 291, 334, 351 SURVEILLANCE REQUIREMENTS (continued)
SURVEILLANCE FREQUENCY SR 3.8.1.20 DELETED SR 3.8.1.21
NOTE-------------------------------
This Surveillance shall not normally be performed in MODE 1, 2, 3, or 4. However, portions of the Surveillance may be performed to reestablish OPERABILITY provided an assessment determines the safety of the unit is maintained or enhanced.
Credit may be taken for unplanned events that satisfy this SR.
Verify, with a DG operating in test mode and connected to its bus, an actual or simulated ESF actuation signal overrides the test mode by:
a.
Returning DG to ready-to-load operation; and b.
Verifying the emergency loads are serviced by offsite power.
In accordance with the Surveillance Frequency Control Program
AC Sources - Operating 3.8.1 Cook Nuclear Plant Unit 1 3.8.1-18 Amendment No. 291, 309, 334, 351 SURVEILLANCE REQUIREMENTS (continued)
SURVEILLANCE FREQUENCY SR 3.8.1.22
NOTE-------------------------------
All DG starts may be preceded by an engine prelube period.
Verify when started simultaneously from standby condition, each DG achieves, in 10 seconds, voltage 3910 V and frequency 59.4 Hz.
In accordance with the Surveillance Frequency Control Program SR 3.8.1.23
NOTES------------------------------
1.
When Unit 2 is in MODE 5 or 6, or moving irradiated fuel assemblies in the containment or auxiliary building, the following Unit 2 SRs are not required to be performed: SR 3.8.1.3, SR 3.8.1.10, SR 3.8.1.11, SR 3.8.1.12, SR 3.8.1.15, SR 3.8.1.16, SR 3.8.1.17, and SR 3.8.1.18.
2.
Unit 2 SR 3.8.1.9.a is only required to be met when the auxiliary source is supplying the required Unit 2 electrical power distribution subsystem.
For required Unit 2 AC sources, the SRs of Unit 2 Specification 3.8.1, except SR 3.8.1.9.b, SR 3.8.1.13, SR 3.8.1.14 (ESF actuation signal portion only), SR 3.8.1.19, SR 3.8.1.21, and SR 3.8.1.22, are applicable.
In accordance with applicable SRs
AC Sources - Shutdown 3.8.2 Cook Nuclear Plant Unit 1 3.8.2-3 Amendment No. 287, 304,351 Corrected by letter of 5/28/08 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.8.2.1
NOTE-------------------------------
The following SRs are not required to be performed:
SR 3.8.1.3, SR 3.8.1.10 through SR 3.8.1.12, SR 3.8.1.15 through SR 3.8.1.17, and SR 3.8.1.18.
For AC sources required to be OPERABLE, the SRs of Specification 3.8.1, "AC Sources -- Operating,"
except SR 3.8.1.9, SR 3.8.1.13, SR 3.8.1.14 (ESF actuation signal portion only), SR 3.8.1.19, SR 3.8.1.21, and SR 3.8.1.22, are applicable.
In accordance with applicable SRs SR 3.8.2.2 One of the following SRs is applicable when the electrical distribution subsystem is being supplied by backfeed from an offsite source via the main transformer and a unit auxiliary transformer:
a.
SR 3.8.1.9.a when the preferred offsite circuit is required to be OPERABLE by LCO 3.8.2.a, or b.
SR 3.8.1.9.b when the alternate offsite circuit is required to be OPERABLE by LCO 3.8.2.a.
In accordance with applicable SR
INDIANA MICHIGAN POWER COMPANY DOCKET NO. 50-316 DONALD C. COOK NUCLEAR PLANT, UNIT NO. 2 AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment No. 332 License No. DPR-74
- 1.
The U.S. Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Indiana Michigan Power Company dated June 27, 2019, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commissions rules and regulations set forth in 10 CFR Chapter I; B.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C.
There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commissions regulations; D.
The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commissions regulations and all applicable requirements have been satisfied.
2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Renewed Facility Operating License No. DPR-74 is hereby amended to read as follows:
(2)
Technical Specifications The Technical Specifications contained in Appendix A and the Environmental Protection Plan contained in Appendix B, as revised through Amendment No. 332, are hereby incorporated into this license. The licensee shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
3.
This license amendment is effective as of its date of issuance and shall be implemented within 90 days of the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION Nancy L. Salgado, Chief Plant Licensing Branch III Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
Attachment:
Changes to the Renewed Facility Operating License and Technical Specifications Date of Issuance: May 1, 2020 Scott P. Wall Digitally signed by Scott P.
Wall Date: 2020.05.01 15:14:37
-04'00'
ATTACHMENT TO LICENSE AMENDMENT NO. 332 DONALD C. COOK NUCLEAR PLANT, UNIT NO. 2 AMENDMENT TO RENEWED FACILITY OPERATING LICENSE DOCKET NO. 50-316 Renewed Facility Operating License No. DPR-74 Replace the following page of the Renewed Facility Operating License No. DPR-74 with the attached revised page. The revised page is identified by amendment number and contains marginal lines indicating the area of change.
INSERT REMOVE Technical Specifications Replace the following page of the Renewed Facility Operating License, Appendix A, Technical Specifications, with the attached revised page. The revised page is identified by amendment number and contains marginal lines indicating the area of change.
INSERT REMOVE 3.8.1-17 3.8.1-17 3.8.1-18 3.8.1-18 3.8.2-3 3.8.2-3 Renewed License No. DPR-74 Amendment No. 313, 314, 316, 317, 318, 319, 320, 325, 326, 327, 328, 329, 330, 331, 332 radiation monitoring equipment calibration, and as fission detectors in amounts as required; (4)
Pursuant to the Act and 10 CFR Parts 30, 40, and 70, to receive, possess and use in amounts as required any byproduct, source or special nuclear material without restriction to chemical or physical form, for sample analysis or instrument and equipment calibration or associated with radioactive apparatus or components; and (5)
Pursuant to the Act and 10 CFR Parts 30 and 70, to possess, but not separate, such byproduct and special nuclear materials as may be produced by the operation of the facility.
C.
This renewed operating license shall be deemed to contain and is subject to the conditions specified in the following Commission regulations in 10 CFR Chapter I: Part 20, Section 30.34 of Part 30, Section 40.41 of Part 40, Sections 50.54 and 50.59 of Part 50, and Section 70.32 of Part 70; and is subject to all applicable provisions of the Act and to the rules, regulations, and orders of the Commission now or hereafter in effect; and is subject to the additional conditions specified or incorporated below:
(1)
Maximum Power Level The licensee is authorized to operate the facility at steady state reactor core power levels not to exceed 3468 megawatts thermal in accordance with the conditions specified herein and in Attachment 1 to the renewed operating license. The preoperational tests, startup tests and other items identified in Attachment 1 to this renewed operating license shall be completed. Attachment 1 is an integral part of this renewed operating license.
(2)
Technical Specifications The Technical Specifications contained in Appendix A, and the Environmental Protection Plan contained in Appendix B, as revised through Amendment No. 332, are hereby incorporated into this license. The licensee shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
(3)
Additional Conditions (a) Deleted by Amendment No. 76 (b) Deleted by Amendment No. 2 (c) Leak Testing of Emergency Core Cooling System Valves Indiana Michigan Power Company shall prior to completion of the first inservice testing interval leak test each of the two valves in series in the
AC Sources - Operating 3.8.1 Cook Nuclear Plant Unit 2 3.8.1-17 Amendment No. 269, 273, 316, 332 SURVEILLANCE REQUIREMENTS (continued)
SURVEILLANCE FREQUENCY SR 3.8.1.20 DELETED SR 3.8.1.21
NOTE-------------------------------
This Surveillance shall not normally be performed in MODE 1, 2, 3, or 4. However, portions of the Surveillance may be performed to reestablish OPERABILITY provided an assessment determines the safety of the unit is maintained or enhanced.
Credit may be taken for unplanned events that satisfy this SR.
Verify, with a DG operating in test mode and connected to its bus, an actual or simulated ESF actuation signal overrides the test mode by:
a.
Returning DG to ready-to-load operation; and b.
Verifying the emergency loads are serviced by offsite power.
In accordance with the Surveillance Frequency Control Program
AC Sources - Operating 3.8.1 Cook Nuclear Plant Unit 2 3.8.1-18 Amendment No. 273, 291, 316, 332 SURVEILLANCE REQUIREMENTS (continued)
SURVEILLANCE FREQUENCY SR 3.8.1.22
NOTE-------------------------------
All DG starts may be preceded by an engine prelube period.
Verify when started simultaneously from standby condition, each DG achieves, in 10 seconds, voltage 3910 V and frequency 59.4 Hz.
In accordance with the Surveillance Frequency Control Program SR 3.8.1.23
NOTES------------------------------
1.
When Unit 1 is in MODE 5 or 6, or moving irradiated fuel assemblies in the containment or auxiliary building, the following Unit 1 SRs are not required to be performed: SR 3.8.1.3, SR 3.8.1.10, SR 3.8.1.11, SR 3.8.1.12, SR 3.8.1.15, SR 3.8.1.16, SR 3.8.1.17, and SR 3.8.1.18.
2.
Unit 1 SR 3.8.1.9.a is only required to be met when the auxiliary source is supplying the required Unit 1 electrical power distribution subsystem.
For required Unit 1 AC sources, the SRs of Unit 1 Specification 3.8.1, except SR 3.8.1.9.b, SR 3.8.1.13, SR 3.8.1.14 (ESF actuation signal portion only), SR 3.8.1.19, SR 3.8.1.21, and SR 3.8.1.22, are applicable.
In accordance with applicable SRs
AC Sources - Shutdown 3.8.2 Cook Nuclear Plant Unit 2 3.8.2-3 Amendment No. 269, 287, 332 Corrected by letter of 5/28/08 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.8.2.1
NOTE------------------------------
The following SRs are not required to be performed:
SR 3.8.1.3, SR 3.8.1.10 through SR 3.8.1.12, SR 3.8.1.15 through SR 3.8.1.17, and SR 3.8.1.18.
For AC sources required to be OPERABLE, the SRs of Specification 3.8.1, "AC Sources -- Operating,"
except SR 3.8.1.9, SR 3.8.1.13, SR 3.8.1.14 (ESF actuation signal portion only), SR 3.8.1.19, SR 3.8.1.21, and SR 3.8.1.22, are applicable.
In accordance with applicable SRs SR 3.8.2.2 One of the following SRs is applicable when the electrical distribution subsystem is being supplied by backfeed from an offsite source via the main transformer and a unit auxiliary transformer:
a.
SR 3.8.1.9.a when the preferred offsite circuit is required to be OPERABLE by LCO 3.8.2.a, or b.
SR 3.8.1.9.b when the alternate offsite circuit is required to be OPERABLE by LCO 3.8.2.a.
In accordance with applicable SR
SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NOS. 351 AND 332 TO RENEWED FACILITY OPERATING LICENSE NOS. DPR-58 AND DPR-74 INDIANA MICHIGAN POWER COMPANY DONALD C. COOK NUCLEAR PLANT, UNIT NOS. 1 AND 2 DOCKET NOS. 50-315 AND 50-316
1.0 INTRODUCTION
By application dated June 27, 2019 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML19184A070), Indiana Michigan Power Company (the licensee) submitted license amendment requests (LARs) for the Donald C. Cook Nuclear Plant (CNP),
Unit Nos. 1 and 2. The license amendments would revise the CNP, Unit Nos. 1 and 2, technical specification (TS) 3.8.1, AC Sources - Operating, by deleting surveillance requirement (SR) 3.8.1.20 which requires verification that diesel generator (DG) availability is not compromised when the DG is tested by connecting to its load test resistor banks. The license amendments also proposed the conforming editorial changes to delete reference to SR 3.8.1.20 in SRs 3.8.1.23 and 3.8.2.1.
2.0 REGULATORY EVALUATION
2.1 System Design and Operation The LAR described the DGs and the associated load test resitory banks. The CNP, Unit Nos. 1 and 2, onsite electrical systems include safety-related, independent emergency DGs (two for each unit) which are available to supply electrical power to engineered safety features (ESF) if both the normal power source (the main generator via the unit auxiliary transformers (UATs))
and the preferred offsite power source (the grid via the reserve auxiliary transformers (RATs))
are unavailable. The emergency DGs are rated 4 kilovolt (kV), 3500 kilowatt (kW). The output of each DG is connected to three breakers. One of these breakers can be connected to a load test resistor bank described below. The other two breakers can be connected in parallel to 4 kV unit-train specific buses, e.g., CNP, Unit No. 1, Train B buses (T11A and T11B buses). These "T" buses supply power to 4 kV/600 V transformers that power the ESF loads.
During normal plant operation, the T buses are powered from the main generator via the UAT.
Upon a trip of the main generator, power to the "T" busses would be automatically transferred from the UAT to the RAT. Upon loss of RAT power to a T bus, the associated DG will start automatically. When the DG voltage and speed approach rated values, the breaker to the associated T bus will automatically close to re-energize the bus. The DG would then supply power to the appropriate 600 V ESF components. If a DG fails to start, the remaining DG in that unit is capable of supplying the unit's required ESF loads.
The LAR stated that there are two, 4 kV, nonsafety-related load test resistor banks located on the Auxiliary Building roof. These resistor banks were included in the original CNP, Unit Nos. 1 and 2, design to serve as an electrical load during DG testing. Each resistor bank is rated for 1750 kW which is approximately one-half of the rating of a single DG. The resistor banks are shared between Unit 1 and Unit 2. One resistor bank serves the Train A DGs of both units, while the other resistor bank serves the Train B DGs of both units. Safety-related breakers connect the DG output to the nonsafety-related load test resistor bank. An emergency signal (loss of offsite power or safety injection) would trip the associated resistor bank breaker. The resistor banks were used in the past for initial DG qualification, for monthly DG load testing, and for DG governor and voltage regulator tuning. The resistor banks were used for monthly DG 50 percent load testing until the applicable SR was changed in 1996 to require monthly, full load testing. The resistor banks are no longer operational and are no longer needed or used for DG testing, or DG governor and voltage regulator tuning.
2.2 Description of Proposed Changes The LAR stated that SR 3.8.1.20 is a site-specific SR that was transitioned from the previous NUREG-1452-based CNP, Unit Nos. 1 and 2, TS into the current NUREG-1431-based CNP TS during the conversion to the Improved Standard Technical Specification (ISTS). This SR recognized the presence and use of DG load test resistor banks, which few other plants have.
The purpose of this SR was to ensure that DG availability under accident conditions will not be compromised as the result of connection to the DG load test resistor bank; and to ensure that the DG will automatically reset to ready-to-load condition if an actuation signal is received during operation in the test mode.
The LAR stated that the licensee plans to remove the load test resistor banks because these are no longer needed for DG testing or governor and voltage regulator tuning; and the load banks are no longer operational. Their current location on the Auxiliary Building roof could be utilized for other nonsafety-related equipment. Therefore, all references to the load test resistor banks are proposed to be removed from the TS. Specifically, the LAR proposed to delete SR 3.8.1.20 which relates to testing the DG using the load test resistor bank. The LAR also proposed to delete reference to SR 3.8.1.20 in SRs 3.8.1.23 and 3.8.2.1.
2.3 Applicable Regulatory Requirements and Guidance Title 10 of the Code of Federal Regulations (10 CFR) 50.36, Technical specifications, establishes the requirements related to the content of the TS. Pursuant to 10 CFR 50.36(c), TS are required to include items in five specific categories related to station operation: (1) Safety limits, limiting safety system settings, and limiting control settings, (2) Limited conditions of operation, (3) SRs, (4) Design features; and (5) Administrative controls. The proposed changes in the LAR relate to the SR category.
The regulations at 10 CFR 50.36(c)(3), Surveillance requirements, requires surveillance relating to test, calibration, or inspection to assure that the necessary quality of systems and components is maintained, that facility operation will be within safety limits, and that the limiting conditions for operation will be met.
NUREG-1431, Standard Technical Specifications - Westinghouse Plants, Revision 4.0, contains the ISTS for Westinghouse plants. The changes reflected in Revision 4 result from the experience gained from the various plant operations using the ISTS and extensive public technical meetings and discussions among the NRC staff and various nuclear power plant licensees and the Nuclear Steam Supply System Owners Groups. The ISTS were developed based on the criteria in the Final Commission Policy Statement on Technical Specifications Improvements for Nuclear Power Reactors, dated July 22, 1993 (58 FR 39132), which was subsequently codified by changes to 10 CFR 50.36.
3.0 TECHNICAL EVALUATION
3.1 Deletion of SR 3.8.1.20 Various SRs are performed on DGs to determine operability at various frequencies. SR 3.8.1.20 requires verifying that an actual or simulated ESF signal overrides the test mode and returns the DG to ready-to-load operation, and verifying that the emergency loads are serviced by offsite power when operating a DG in test mode while connected to its load test resistor bank.
According to the LAR, the load testing of the DG is performed by paralleling the DG to a T bus when powered by the grid/offsite power (SRs 3.8.1.3; 3.8.1.10; 3.8.1.11, 3.8.1.15, 3.8.1.16), or by connecting the DG to its 600 V ESF loads via a T bus when not connected to grid/offsite power (SRs 3.8.1.12, 3.8.1.13, 3.8.1.17, 3.8.1.19). These SRs support load testing the DG which SR 3.8.1.20 also supports.
Performance of SR 3.8.1.21 provides verification that an actual or simulated ESF signal overrides the test modem returning the DG to ready-to-load operation, and then verifying that the emergency loads are serviced by offsite power when connected to its bus.
The LAR stated that DG governor and voltage regulator tuning, which previously used a load test resistor bank, is currently conducted by applying selected plant ESF loads to the DG via a T bus and 600 V bus when isolated from other power supplies. On December 12, 2019, a public meeting was held between the U.S. Nuclear Regulatory Commission (NRC) staff and the licensee via a teleconference (summary of meeting available in ADAMS Accession No. ML19350A055). During the meeting, the licensee clarified that existing plant procedures, which do not require a load resistor bank, are in place to accomplish the governor and voltage regulator tuning.
The NRC staff finds that the requirements of SR 3.8.1.20 (proposed to be deleted) are being met by SRs 3.8.1.12, 3.8.1.13, 3.8.1.17, 3.8.1.19, and by SR 3.8.1.21. The staff also finds that NUREG-1431, Standard Technical Specifications - Westinghouse Plants, does not contain an SR requiring testing of the DG by connecting it to a load test resistor bank. As such, deletion of SR 3.8.1.20 is consistent with NUREG-1431. Therefore, the staff finds the deletion of SR 3.8.1.20 acceptable.
3.2 Changes to SRs 3.8.1.23 and 3.8.2.1 The license amendment requested deletion of the reference to SR 3.8.1.20 in SR 3.8.1.23 and 3.8.2.1. The deletion of SR 3.8.1.20 from SRs 3.8.1.23 and 3.8.2.1 does not change the purpose of SR 3.8.1.23 or 3.8.2.1. The staff finds that these changes are conforming editorial changes to support the deletion of SR 3.8.1.20 and, are therefore, acceptable.
3.3 Technical Evaluation Conclusion
Based on the technical evaluation above, the NRC staff finds the proposed changes regarding deletion of SR 3.8.1.20 from TS Sections 3.8.1 and 3.8.2 is acceptable. The staff also concludes that, with implementation of the proposed changes, the licensee would continue to meet the SR requirements relating to the safety-related DGs and meet the intent of 10 CFR 50.36(c)(3).
4.0 STATE CONSULTATION
In accordance with the Commissions regulations, the State of Michigan official was notified of the proposed issuance of the amendments on February 11, 2020. The State official had no comments.
5.0 ENVIRONMENTAL CONSIDERATION
The amendments change the requirements with respect to installation or use of a facility component located within the restricted area as defined in 10 CFR Part 20 and changes a surveillance requirement. The NRC staff has determined that the amendments involve no significant increase in the amounts, and no significant change in the types, of any effluents that may be released offsite, and that there is no significant increase in individual or cumulative occupational radiation exposure. The Commission has previously issued a proposed finding that the amendments involve no significant hazards consideration in the Federal Register on August 13, 2019 (84 FR 40097), and there has been no public comment on such finding.
Accordingly, the amendments meets the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(9). Pursuant to 10 CFR 51.22(b), no environmental impact statement or environmental assessment need be prepared in connection with the issuance of the amendments.
6.0 CONCLUSION
The Commission has concluded, based on the considerations discussed above, that: (1) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner, (2) there is reasonable assurance that such activities will be conducted in compliance with the Commissions regulations, and (3) the issuance of the amendments will not be inimical to the common defense and security or to the health and safety of the public.
Principal Contributors: Vijay Goel, NRR Date of issuance: May 1, 2020
- via e-mail OFFICE NRR/DORL/LPL3/PM NRR/DORL/LPL3/LA NRR/DEX/EEOB/BC NRR/DSS/STSB/BC NAME RKuntz SRohrer BTitus*
VCusumano*
DATE 02/13/2020 02/13/2020 01/29/2020 03/20/2020 OFFICE OGC NRR/DORL/LPL3/BC NRR/DORL/LPL3/PM NAME STerk NLO NSalgado (SWall for)
RKuntz DATE 03/09/2020 05/01/2020 05/01/2020