ML15057A297
| ML15057A297 | |
| Person / Time | |
|---|---|
| Site: | Fermi  |
| Issue date: | 03/16/2015 |
| From: | Jennivine Rankin Plant Licensing Branch III |
| To: | Plona J DTE Electric Company |
| Rankin J | |
| References | |
| TAC MF4002 | |
| Download: ML15057A297 (19) | |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 March 16, 2015 Mr. Joseph H. Plona Senior Vice President and Chief Nuclear Officer DTE Electric Company Fermi 2 - 210 NOC 6400 North Dixie Highway Newport, Ml 48166
SUBJECT:
FERMI 2 - ISSUANCE OF AMENDMENT REGARDING REQUEST TO REVISE TECHNICAL SPECIFICATION SURVEILLANCE REQUIREMENTS FOR DIRECT CURRENT BATIERIES (TAC NO. MF4002)
Dear Mr. Plona:
The U.S. Nuclear Regulatory Commission has issued the enclosed Amendment No: 199 to Facility Operating License No. NPF-43 for the Fermi 2 facility. The amendment consists of changes to the technical specifications (TSs) in response to your application dated April 23, 2014, as supplemented by letters dated June 19, and October 13, 2014.
The amendment revises the TS surveillance requirements (SRs) associated with TS 3.8.4, "Direct Current (DC) Sources - Operating," and TS 3.8.6 "Battery Cell Parameters."
Specifically, the amendment corrects non-conservative TS affecting SRs 3.8.4.2, 3.8.4.5, and 3.8.6.3, and addresses a Component Design Basis Inspection concern identified by the NRC related to battery testing frequency in SR 3.8.4.8.
A copy of our safety evaluation is also enclosed. The Notice of Issuance will be included in the Commission's biweekly Federal Register notice.
Sincerely, Jennivine K. Rankin, Project Manager Plant Licensing Branch 111-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-341
Enclosures:
- 1. Amendment No. 199 to NPF-43
- 2. Safety Evaluation cc w/encls: Distribution via ListServ
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 DTE ELECTRIC COMPANY DOCKET NO. 50-341 FERMI 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 199 License No. NPF-43
- 1. The U.S. Nuclear Regulatory Commission (the Commission) has found that:
A. The application for amendment by the DTE Electric Company (DTE, the licensee) dated April 23, 2014, as supplemented by letters dated June 19, and October 13, 2014, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's 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 Commission's 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 Commission's 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 Facility Operating License No. NPF-43 is hereby amended to read as follows:
Enclosure 1
Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No. 199, and the Environmental Protection Plan contained in Appendix B, are hereby incorporated into this license. DTE Electric Company 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 60 days.
Davi L Pe , hief Plan Li sing Branch 111-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
Attachment:
Changes to the Facility Operating License and Technical Specifications Date of Issuance: March 16, 2015
ATTACHMENT TO LICENSE AMENDMENT NO. 199 FACILITY OPERATING LICENSE NO. NPF-43 DOCKET NO. 50-341 Replace the following pages of the Facility Operating License and Appendix A Technical Specifications with the attached revised pages. The revised pages are identified by amendment number and contain marginal lines indicating the areas of change.
REMOVE INSERT Page 3 Page 3 Replace the following pages of the Appendix A Technical Specifications with the attached revised pages. The revised pages are identified by amendment number and contain marginal lines indicating the areas of change.
REMOVE INSERT 3.8-17 3.8-17 3.8-18 3.8-18 3.8-24 3.8-24
(4) DTE Electric Company, pursuant to the Act and 10 CFR Parts 30, 40 and 70, to receive, possess, and use at any time any byproduct, source and special nuclear material such as sealed neutron sources for reactor startup, sealed sources for reactor instrumentation and radiation monitoring equipment calibration, and as fission detectors in amounts as required; (5) DTE Electric Company, 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 calibration or associated with radioactive apparatus or components; and (6) DTE Electric Company, pursuant to the Act and 10 CFR Parts 30, 40 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 license shall be deemed to contain and is subject to the conditions specified in the Commission's regulations set forth in 10 CFR Chapter I 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 DTE Electric Company is authorized to operate the facility at reactor core power levels not in excess of 3486 megawatts thermal (100% power) in accordance with conditions specified herein and in Attachment 1 to this license. The items identified in Attachment 1 to this license shall be completed as specified. Attachment 1 is hereby incorporated into this license.
(2) Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A as revised through Amendment No. 199 and the Environmental Protection Plan contained in Appendix B, are hereby incorporated into this license. DTE Electric Company shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
(3) Antitrust Conditions DTE Electric Company shall abide by the agreements and interpretations between it and the Department of Justice relating to Article I, Paragraph 3 of the Electric Power Pool Agreement between DTE Electric Company and Amendment No. 199
DC Sources -Operating 3.8.4 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.8.4.1 Verify battery terminal voltage is 7 days
~ 125.7 Von float charge.
SR 3.8.4.2 Verify no visible corrosion at battery 92 days terminals and connectors.
-OR Verify each battery:
- a. Cell-to-cell and terminal connection resistance is ~ l.5E-4 ohm: and
- b. Total cell-to-cell and terminal connection resistance is~ 2.7E-3 ohm.
SR 3.8.4.3 Verify battery cells, cell plates. and 18 months racks show no visual indication of physical damage or abnormal deterioration that could degrade battery performance.
SR 3.8.4.4 Remove visible corrosion and verify battery 18 months cell to cell and terminal connections are coated with anti-corrosion material.
SR 3.8.4.5 Verify each battery: 18 months
- a. Cell-to-cell and terminal connection resistance is ~ l.5E-4 ohm; and
- b. Total cell-to-cell and terminal connection resistance is~ 2.7E-3 ohm.
SR 3.8.4.6 Verify each required battery charger 18 months supplies~ 100 amps at~ 124.7 V for
~ 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.
(continued)
FERMI
- UNIT 2 3.8-17 Amendment No. "If,,, ~. 199
DC Sources-Operating 3.8.4 SURVEILLANCE REQUIREMENTS (continued)
SURVEILLANCE FREQUENCY SR 3 . 8 . 4 . 7 - * - - * - - * - * * * -- * - - -
- NOTE ----* * -* * * -* ---* * * -
The performance discharge test in SR 3.8.4.8 may be performed in lieu of the service test in SR 3.8.4.7 once per 60 months.
Verify battery capacity is adequate to 18 months supply, and maintain in OPERABLE status, the actual or simulated emergency loads for the design duty cycle when subjected to a battery service test.
SR 3 . 8. 4. 8 - - - - - - - - - - - - -- - * - - - NOTE -------------* * ---* -
This Surveillance shall not be performed in MODE 1, 2, or 3. However, credit may be taken for unplanned events that satisfy this SR.
Verify battery capacity is ~ 80% of the 60 months manufacturer's rating when subjected to a performance discharge test. AND 12 months when battery shows degradation or has reached 85% of expected life with capacity < 100% of manufacturer's rating AND 24 months when battery has reached 85% of the expected life with capacity ~ 100% of manufacturer's rating FERMI - UNIT 2 3.8-18 Amendment No. +/-34, 199
Battery Cell Parameters 3.8.6 SURVEILLANCE REQUIREMENTS (continued)
SURVEILLANCE FREQUENCY SR 3.8.6.2 Verify battery cell parameters meet 92 days Table 3.8.6-1 Category B limits.
AND Once within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after battery discharge
< 105 v AND Once within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after battery overcharge
> 145 v SR 3.8.6.3 Verify average electrolyte temperature of 92 days representative cells is > 70°F.
FERMI - UNIT 2 3.8-24 Amendment No. Iii. +/-d-6, 199
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 199 TO FACILITY OPERATING LICENSE NO. NPF-43 DTE ELECTRIC COMPANY FERMI 2 DOCKET NO. 50-341
1.0 INTRODUCTION
By application dated April 23, 2014 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML14113A445), as supplemented by letters dated June 19, and October 13, 2014 (ADAMS Accession Nos. ML14170B201 and ML14286A098, respectively),
DTE Electric Company (the licensee), requested changes to the technical specifications (TSs) for Fermi 2.
The proposed changes include the following:
- Surveillance Requirements (SRs) 3.8.4.2 and 3.8.4.5 are revised to add the Total Allowable Aggregate Battery Measured Resistance Limit of 2. 7 E-3 ohm for each 130 Volt Direct Current (VDC) battery section as another acceptance criterion, in addition to the existing criterion for a single cell-to-cell and terminal connection resistance limit of 1.5 E-4 ohm.
- SR 3.8.6.3 is revised to require verification of average electrolyte temperature of representative cells is greater than 70 degrees Fahrenheit (°F).
- SR 3.8.4.8 is revised to require verification that battery capacity is ~ 80 percent of the manufacturer's rating when subjected to a performance discharge test at 60 months interval; AND at 12 months when the battery shows degradation, or has reached 85 percent of the expected life with capacity < 100 percent of manufacturer's rating; AND at 24 months when the battery has reached 85 percent of the expected life with capacity ~
100 percent of manufacturer's rating.
The supplemental letters dated June 19, and October 13, 2014, provided additional information that clarified the application, did not expand the scope of the application as originally noticed, and did not change the staff's original proposed no significant hazards consideration determination as published in the Federal Register on July 22, 2014 (79 FR 42542).
Enclosure 2
2.0 REGULATORY EVALUATION
The regulatory framework which the NRC staff applied in the review of the application includes:
Title 10 of the Code of Federal Regulations, Part 50 (10 CFR 50), Appendix A, "General Design Criteria for Nuclear Power Plants," General Design Criterion (GDC) 17, "Electric power systems," requires, in part, that nuclear power plants have onsite and offsite electric power systems to permit the functioning of structures, systems, and components that are important safety. The onsite system is required to have sufficient independence, redundancy, and testability to perform its safety function, assuming a single failure. The offsite power system is required to be supplied by two physically independent circuits that are designed and located so as to minimize, to the extent practical, the likelihood of their simultaneous failure under operating and postulated accident and environmental conditions. In addition, this criterion requires provisions to minimize the probability of losing electric power from the remaining electric power supplies as a result of loss of power from the unit, the offsite transmission network, or the onsite power supplies.
GDC 18, "Inspection and Testing of Electric Power Systems," requires that electric power systems that are important to safety must be designed to permit appropriate periodic inspection and testing.
10 CFR 50.36(c)(3), Technical Specifications," requires that TSs include SRs, which are requirements 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.
10 CFR 50.63, "Loss of all alternating current power," requires that each light-water cooled nuclear power plant licensed to operate must be able to withstand for a specified duration and recover from a station blackout (SBO).
3.0 TECHNICAL EVALUATION
3.1 Description of the DC Electrical Power System The DC power system consists of two independent Class 1E battery systems, one system per division. Each system supplies DC power at 260 VDC and 130 VDC. Each division is physically, electrically, and functionally independent of the other division in accordance with GDC 17.
Each divisional 260 VDC battery system is comprised of two 130 VDC battery sections, two adequately sized battery chargers (one per battery section), a spare battery charger and related equipment. The 130 VDC battery sections provide control power for each of the two load groups within a division and power for control of each division's two diesel generators and their associated switchgear. The 260 VDC sources furnish power for the DC motors and motor-operated valves necessary during shutdown conditions. Each charger uses a fused connection to charge and keep its respective battery on float voltage during normal operation.
3.2 Evaluation of Proposed Technical Specifications Changes 3.2.1 Proposed Changes to SR 3.8.4.2 and SR 3.8.4.5 The licensee proposed to revise SR 3.8.4.2 and SR 3.8.4.5 to add a criterion for the limit for battery resistance in addition to the existing criterion for the cell-to-cell and terminal connection resistance.
The current SR 3.8.4.2 states:
Verify no visible corrosion at battery terminals and connectors.
OR Verify each battery cell-to-cell and terminal connection resistance is s 1.5 E-4 ohm.
The revised SR 3.8.4.2 would state:
Verify no visible corrosion at battery terminals and connectors.
OR Verify each battery cell-to-cell and terminal connection resistance is s 1.5 E-4 ohm.
AND Verify total battery cell-to-cell and terminal connection resistance is s 2. 7 E-3 ohm.
The current SR 3.8.4.5 states:
Verify each battery cell-to-cell and terminal connection resistance is s 1.5 E-4 ohm.
The revised SR 3.8.4.5 would state:
Verify each battery cell-to-cell and terminal connection resistance is s 1. 5 E-4 ohm AND Verify total battery cell-to-cell and terminal connection resistance is s 2. 7 E-3 ohm.
NRC Evaluation of Proposed Changes to SR 3.8.4.2 and SR 3.8.4.5 In 2013, the U.S. Nuclear Regulatory Commission (NRC) completed a Component Design Basis Inspection (CDBI) at Fermi 2. In its corresponding Inspection Report dated October 29, 2013 (ADAMS Accession No. ML133028260), the NRC identified a finding of very low safety significance and associated non-cited violation for the licensee's failure to submit a license amendment request (LAR) to revise the non-conservative TS issue, with SR 3.8.4.2 and SR 3.8.4.5, in a timely manner.
In the LAR dated April 23, 2014, the licensee stated the following:
In September 2009, an engineering self-assessment (Reference 6. 7) identified that the existing design calculations for station safety related batteries did not account for the battery cell-to-cell and terminal connection resistance.
Subsequent investigation under the Corrective Action Program identified a non-conservative TS issue with SR 3.8.4.2 and SR 3.8.4.5 that verify battery cell-to-cell and terminal connection resistance is s 1.5E-4 ohm.
The licensee also stated that in case that multiple connection resistances in the battery would simultaneously approach the 150 micro-ohm (µO) value, the aggregate of such elevated connection resistance could cause excessive voltage drops and result in insufficient battery terminal voltage to support safety related equipment's safety function. The licensee performed an Engineering Functional Analysis to verify that the cell-to-cell and terminal connection resistance values are low enough to demonstrate operability of the batteries. The analysis also evaluated the maximum allowable battery total connection resistance (2700 µO) that would still provide the minimum required voltage to support safety related DC equipment in performing their intended design functions. The licensee established administrative controls, which are still in effect, to limit the maximum battery total connection resistance to 2700 µO.
In the LAR dated April 23, 2014, the licensee proposed to change SR 3.8.4.2 and SR 3.8.4.5 by adding a total battery cell-to-cell and terminal connection resistance value of 2700 µO. The licensee stated the following:
The current Fermi 2 design basis calculation (Reference 6.2) provides the technical basis for the 2700 µO value by verifying the design functionality of all safety related equipment with the existing battery. In the process, the Design Calculation also confirms the adequacy of the battery capacity by calculating the number of positive plates required in each battery to support design functionality and comparing the calculated result with the actual installed number of plates in each battery.
To validate the licensee's proposed new total resistance value, the NRC staff issued a request for additional information (RAI) in an email dated September 3, 2014 (ADAMS Accession No. ML14251A071 ), requesting the licensee provide a summary of the resistance calculations which established the proposed TS battery connection resistance limits and supports safety related equipment in performing their intended safety function. The licensee responded to the RAI by letter dated October 13, 2014. In the response to RAl-5, the licensee stated the following:
The total connection resistance allowable value of 2700 µO is an input to the calculation that verifies the batteries support safety related equipment, with some margin, in performing their intended safety functions (Reference R 1).
The results of the calculation confirms that the safety related batteries, with the total connection resistance value of 2700 µO, continue to support operability of all safety related equipment, consistent with IEEE 485.
The NRC staff reviewed the licensee's response and the TS mark-up pages and verified that the new total resistance value of s 2. 7 E-3 ohm is included in SR 3.8.4.2 and SR 3.8.4.5. The NRC staff also reviewed the summary of the calculations and finds that the licensee has used the highest minimum required battery terminal voltage, for each device, in its calculation of the new total connection resistance, and as such it has shown that the new TS resistance value is adequate to support the safety-related equipment's safety functions.
In regard to the DC system's availability during a design basis accident (OBA), the licensee stated in its April 23, 2014, LAR that it screened OBA scenarios and selected those that potentially give rise to limiting DC loadings. For each loading scenario the licensee performed the voltage drop/load flow calculations for the various bus/node voltages and battery discharge runs to determine the minimum required battery terminal voltage for each device. From these scenarios the licensee chose the highest minimum allowable battery voltage, to determine the bounding volt per cell value to be used in the sizing of the battery. In its September 3, 2014, email, the NRC staff issued an RAI requesting additional description of the loading scenario chosen in the computer modeling. In response to RAl-1, the licensee described the three scenarios used: concurrent loss of offsite power (LOOP) and a loss of coolant accident (LOCA),
concurrent LOOP and a LOCA with testing of the high pressure coolant injection or reactor core isolation cooling systems, and station blackout. The licensee also provided tables for each OBA scenario with data on the calculated minimum required battery terminal voltage, the bounding volt per cell value, and the most limiting voltage required at the component level and the corresponding voltage at the battery to meet the worst-case design basis loading requirements.
The NRC staff reviewed the licensee's response including the OBA scenario specific data and verified that the minimum required battery terminal voltage bounds the OBA most limiting voltage required at the component level. Based on this, the NRC staff finds that safety-related equipment required to operate during a OBA scenario will be provided with adequate voltage support.
Based on the above, the NRC staff concludes that the proposed changes ensure battery systems continue to meet the requirements as specified 10 CFR 50.63, and GDCs 17 and 18.
Additionally, the proposed changes meet the 10 CFR 50.36 requirements for surveillances by ensuring that the necessary quality of systems and components is maintained and that the limiting conditions for operation will be met. Therefore, the staff finds the proposed change to be acceptable.
3.2.2 Proposed Changes to SR 3.8.6.3 The current SR 3.8.6.3 states:
Verify average electrolyte temperature of representative cells is> 60 °F.
The revised SR 3.8.6.3 would state:
Verify average electrolyte temperature of representative cells is> 70 °F.
NRC Evaluation of Proposed Changes to SR 3.8.6.3 The licensee proposed to change SR 3.8.6.3 to increase the requirement of average electrolyte temperature of representative cells from> 60 degrees °F to> 70 °F. The licensee stated that if the electrolyte temperature were allowed to be as low as the existing TS limit of 60 degrees, adequate capacity could be challenged. Also the LAR would correct this potentially non-conservative TS issue and align the TS with the design basis calculations.
In its September 3, 2014, email, the NRC staff issued an RAI to validate the licensee's proposed new average electrolyte temperature value. In RAl-2, the staff requested the licensee provide a summary of the calculations to show that the safety related batteries at 70 °F continue to support operability of all safety related equipment. The licensee responded to the RAI by letter dated October 13, 2014. The licensee stated that the electrolyte temperature is an input to the design basis calculation, Fermi 2's calculation specifies maintaining a minimum temperature of 70 °F, and its result confirms that the safety-related batteries continue to support operability of all safety related equipment. The licensee also stated that electrolyte temperature of> 70 °F is well within the rated temperature of 77 °F, from the battery vendor qualification report, and it will improve the discharge performance and increase the battery capacity margin.
The NRC staff reviewed the licensee's response and the technical specifications mark-up page and verified that the new temperature value is included in SR 3.8.6.3. Based on its review of the LAR and the licensee's responses to the NRC staff's request for additional information, the NRC staff finds that increasing the average electrolyte temperature from > 60 °F to > 70 °F is consistent with Fermi 2's design basis calculation, and as such it will continue to support operability of all safety-related equipment.
Based on the above, the NRC staff concludes that the proposed changes ensure battery systems continue to meet the requirements as specified in 10 CFR 50.63, and GDCs 17 and 18.
Additionally, the proposed changes meet the 10 CFR 50.36 requirements for surveillances by ensuring that the necessary quality of systems and components is maintained and that the limiting conditions for operation will be met. Therefore, the staff finds the proposed changes to be acceptable.
3.2.3 Proposed Changes to SR 3.8.4.8 The licensee proposed to change the frequency of SR 3.8.4.8 from 18 months at 85 percent capacity to 12 months at 85 percent of expected life with capacity < 100 percent of manufacturer's rating and 24 months at 85 percent of expected life with capacity ~ 100 percent of manufacturer's rating.
The SR 3.8.4.8 states:
Verify battery capacity is ~ 80% of the manufacturer's rating when subjected to a performance discharge test.
The current frequency states:
60 months AND 18 months when battery shows degradation or has reached 85% of expected life The revised frequency would state:
60 months AND 12 months when battery shows degradation or has reached 85% of expected life with capacity < 100% of manufacturer's rating AND 24 months when battery has reached 85% of expected life with capacity ~ 100%
of manufacturer's rating NRC Evaluation of Proposed Changes to SR 3.8.4.8 In CDBI Inspection Report 05000341/2013008, dated October 29, 2013, the NRC identified a finding of very low safety significance and an associated non-cited violation (NCV 05000341/2013008-04) for TS requirements that do not adhere to the IEEE 450-1972, "IEEE Recommended Practice for Maintenance, Testing, and Replacement of Large Stationary Type Power Plant and Substation Lead Storage Batteries," requirement for test frequency.
The licensee stated that based on the design margin assumed in the calculation for the batteries, several years remain before any battery reaches its 85 percent of expected life. By email dated September 3, 2014, the NRC requested additional information on the battery capacity margin. By letter dated October 13, 2014, the licensee responded to RAl-3 and provided a table with the battery capacity margin data based on the most recent TS surveillance test, and the expected life of the four lead acid 20-year rated batteries. The NRC staff also requested the licensee to provide additional information regarding the aging factor applied to the battery. By letter dated October 13, 2014, the licensee provided a revised table that included sizing, an applied aging factor, excess capacity, and design margin data for each of the batteries.
The NRC staff reviewed the licensee's response and the TS mark-up page and verified that the new frequency is included in SR 3.8.4.8, and it is in alignment with the frequency specified in
the standard TS and IEEE 450. The NRC staff also reviewed the data based on the surveillance test and the design margin and finds that SR 3.8.4.8 performed at the new TS frequency will continue to determine overall battery degradation due to age and usage.
Therefore, the NRC staff finds the new TS frequency to be acceptable.
Based on the above, the NRC staff concludes that the proposed changes ensure battery systems continue to meet the requirements as specified 10 CFR 50.63, and GDCs 17 and 18.
Additionally, the proposed changes meet the 10 CFR 50.36 requirements for surveillances by ensuring that the necessary quality of systems and components is maintained and that the limiting conditions for operation will be met. Therefore, the staff finds the proposed changes to be acceptable.
3.3 Conclusion The NRC staff evaluated the licensee's request to modify SRs 3.8.4.2, 3.8.4.5, 3.8.4.8, and 3.8.6.3. Based on the above evaluation, the NRC staff finds that the proposed changes to the Fermi 2's TSs provide reasonable assurance of the continued availability of the required electrical power to shut down the reactor and to maintain the reactor in a safe condition after an anticipated operational occurrence or a postulated design-basis accident. Furthermore, the NRC staff concludes that the proposed TS changes are in accordance with 10 CFR 50.36 and 10 CFR 50.63, and meet the intent of GDCs 17 and 18. Therefore, the NRC staff finds the proposed changes to be acceptable.
4.0 STATE CONSULTATION
In accordance with the Commission's regulations, the Michigan State official was notified of the proposed issuance of the amendment. The State official had no comments.
5.0 ENVIRONMENTAL CONSIDERATION
The amendment changes a requirement with respect to the installation or use of a facility component located within the restricted area as defined in 10 CFR Part 20 or changes the surveillance requirements. The NRC staff has determined that the amendment involves 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 amendment involves no significant hazards consideration and there has been no public comment on such finding (79 FR 42542). Accordingly, the amendment 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 amendment.
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 Commission's regulations, and (3) the issuance of the
amendment will not be inimical to the common defense and security or to the health and safety of the public.
Principal Contributor: S. Basturescu Date: March 16, 2015
ML15057A297 OFFICE LPL3-1/PM LPL3-1/PM LPL3-1/LA EEEB NAME KGreen JRankin MHenderson JZimmerman DATE 03/09/2015 03/09/2015 03/09/2015 03/09/2015 OFFICE DSS/STSB OGC LPL3-1/BC LPL3-1/PM NAME RElliott
- BHarris DPelton JRankin (TBeltz for)
DATE 03/11/2015 03/13/2015 03/16/2015 03/16/2015