ML080290323
| ML080290323 | |
| Person / Time | |
|---|---|
| Site: | Fermi  |
| Issue date: | 03/17/2008 |
| From: | Milano P NRC/NRR/ADRO/DORL/LPLIII-1 |
| To: | Jennifer Davis Detroit Edison |
| Milano P, NRR/DORL/LPLIII-1, 415-1457 | |
| Shared Package | |
| ML080290283 | List: |
| References | |
| TAC MD4930 | |
| Download: ML080290323 (11) | |
Text
March 17, 2008 Mr. Jack M. Davis Senior Vice President and Chief Nuclear Officer Detroit Edison Company Fermi 2 - 210 NOC 6400 North Dixie Highway Newport, MI 48166
SUBJECT:
FERMI 2 - ISSUANCE OF AMENDMENT RE: TECHNICAL SPECIFICATION CHANGE TO EMERGENCY DIESEL GENERATOR SURVEILANCE REQUIREMENTS (TAC NO. MD4930)
Dear Mr. Davis:
The Commission has issued the enclosed Amendment No. 178 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 March 19, 2007, as supplemented by letter dated August 16, 2007.
The amendment revises TS surveillance requirements (SRs) related to emergency diesel generator (EDG) testing. Specifically, it modifies TS SRs 3.8.1.2, 3.8.1.7, 3.8.1.10, 3.8.1.11, 3.8.1.14, and 3.8.1.17 in TS 3.8.1, AC [Alternating Current] Sources - Operating by revising the minimum EDG output voltage acceptance criterion from 3740 to 3873 volts.
A copy of our safety evaluation is also enclosed. The Notice of Issuance will be included in the Commissions biweekly Federal Register notice.
Sincerely,
/RA/
Patrick D. Milano, Senior Project Manager Plant Licensing Branch III-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-341
Enclosures:
- 1. Amendment No. 178 to NPF-43
- 2. Safety Evaluation cc w/encls: See next page
Mr. Jack M. Davis Senior Vice President and Chief Nuclear Officer Detroit Edison Company Fermi 2 - 210 NOC 6400 North Dixie Highway Newport, MI 48166
SUBJECT:
FERMI 2 - ISSUANCE OF AMENDMENT RE: TECHNICAL SPECIFICATION CHANGE TO EMERGENCY DIESEL GENERATOR SURVEILANCE REQUIREMENTS (TAC NO. MD4930)
Dear Mr. Davis:
The Commission has issued the enclosed Amendment No. 178 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 March 19, 2007, as supplemented by letter dated August 16, 2007.
The amendment revises TS surveillance requirements (SRs) related to emergency diesel generator (EDG) testing. Specifically, it modifies TS SRs 3.8.1.2, 3.8.1.7, 3.8.1.10, 3.8.1.11, 3.8.1.14, and 3.8.1.17 in TS 3.8.1, AC [Alternating Current] Sources - Operating by revising the minimum EDG output voltage acceptance criterion from 3740 to 3873 volts.
A copy of our safety evaluation is also enclosed. The Notice of Issuance will be included in the Commissions biweekly Federal Register notice.
Sincerely,
/RA/
Patrick D. Milano, Senior Project Manager Plant Licensing Branch III-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-341
Enclosures:
- 1. Amendment No. 178 to NPF-43
- 2. Safety Evaluation cc w/encls: See next page DISTRIBUTION:
PUBLIC RidsOgcRp LPL3-1 R/F RidsAcrsAcnw&mMailCenter RidsNrrPMAMuniz GHill, OIS RidsNrrLATHarris RidsRgn3MailCenter RidsNrrDorlDpr RidsNrrDorlLpl3-1 RidsNrrDirsItsb AKlett, NRR GWilson, NRR TKobetz, NRR RidsNrrPMPMilano JPoole, NRR Package Accession Number: ML080290283 Amendment Accession Number: ML080290323 TS Accession Number: ML080790026 OFFICE NRR/LPL3-1/PM NRR/LPL3-1/PM NRR/LPL3-1/LA NRR/LPL3-1/LA DE/EEEB/BC DIRS/ITSB OGC NRR/LPL3-1/BC NAME JPoole PMilano BTully THarris GWilson TKobetz AHodgdon LJames DATE 02/06/08 03/06/08 02/11/08 03/ /08 02/13/08 02/21/08 03/03/08 03/ 18 /08 OFFICIAL RECORD COPY
DETROIT EDISON COMPANY DOCKET NO. 50-341 FERMI 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 178 License No. NPF-43
- 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by the Detroit Edison Company (the licensee) dated March 19, 2007, as supplemented by letter dated August 16, 2007, 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 Facility Operating License No. NPF-43 is hereby amended to read as follows:
Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No. 178, and the Environmental Protection Plan contained in Appendix B, are hereby incorporated in the 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 30 days.
FOR THE NUCLEAR REGULATORY COMMISSION
/RA/
Lois M. James, Chief Plant Licensing Branch III-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications and Facility Operating License Date of Issuance: March 17, 2008
ATTACHMENT TO LICENSE AMENDMENT NO. 178 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 License Page 3 License Page 3 3.8-3 3.8-3 3.8-4 3.8-4 3.8-5 3.8-5 3.8-6 3.8-6 3.8-7 3.8-7 3.8-9 3.8-9
3 (4)
DECo, 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 instrumen-tation and radiation monitoring equipment calibration, and as fission detectors in amounts as required; (5)
DECo, 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)
DECo, 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 DECo is authorized to operate the facility at reactor core power levels not in excess of 3430 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 178 and the Environmental Protection Plan contained in Appendix B, are hereby incorporated into this license. DECo shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
(3)
Antitrust Conditions DECo 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 Detroit Edison Company and Amendment No. 178
SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 178 FACILITY OPERATING LICENSE NO. NPF-43 DETROIT EDISON COMPANY FERMI 2 DOCKET NO. 50-341
1.0 INTRODUCTION
By application dated March 19, 2007 (Agencywide Documents Access and Management System (ADAMS), Accession No. ML070860204), as supplemented by letter dated August 16, 2007 (ML072390050), the Detroit Edison Company (DECo or the licensee) requested changes to the Technical Specifications (TSs) for Fermi 2. The supplement dated August 16, 2007, provided additional information that clarified the application, did not expand the scope of the application as originally noticed, and did not change the U.S. Nuclear Regulatory Commission (NRC) staffs original proposed no significant hazards consideration determination as published in the Federal Register on April 24, 2007 (72 FR 20379). The proposed changes would revise TS surveillance requirements (SRs) related to emergency diesel generator (EDG) testing. Specifically, the licensee proposed to modify TS SRs 3.8.1.2, 3.8.1.7, 3.8.1.10, 3.8.1.11, 3.8.1.14, and 3.8.1.17 in TS 3.8.1, AC [Alternating Current] Sources - Operating by revising the minimum EDG output voltage acceptance criterion from 3740 to 3873 volts (V).
2.0 REGULATORY EVALUATION
The following regulatory requirements and guidance are applicable to the proposed TS change and were used by the NRC staff during its evaluation:
Title 10 of the Code of Federal Regulations (10 CFR) Section 50.36, Technical specifications, provides the regulatory requirements for the content required in a licensees TSs. As stated in 10 CFR 50.36(d), the TSs will include SRs to assure that the limiting conditions for operation will be met.
The regulation at 10 CFR Part 50 Appendix B, Quality Assurance Criteria for Nuclear Power Plants and Fuel Reprocessing Plants, Criterion III, Design Control, and Criterion XI, Test Control, requires that (1) measures be provided for verifying or checking the adequacy of design through design reviews, the use of alternative or simplified calculation methods, or the performance of a suitable testing program and (2) a test program be established to ensure that systems and components perform satisfactorily and that the test program includes operational tests during nuclear power plant operation.
General Design Criterion (GDC) 17, Electric power systems, of Appendix A, General Design Criteria for Nuclear Power Plants, to 10 CFR Part 50 states, 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 to 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.
GDC-18, Inspection and testing of electric power systems, states that electric power systems that are important to safety must be designed to permit appropriate periodic inspection and testing of important areas and features, such as insulation and connections to assess the continuity of the systems and the condition of their components.
NRC Regulatory Guide (RG) 1.9, Revision 2, December 1979, ASelection, Design, and Qualification of Diesel Generator Units Used as Standby (Onsite) Electric Power Systems at Nuclear Power Plants,@ describes a method acceptable to the NRC staff for complying with the Commission=s regulations with regard to design and testing of diesel generators.
Branch Technical Positions [Plant Support Branch] (PSB), of Appendix 8-A to the Standard Review Plan (NUREG-0800, Revision 2, July 1981) represent guidelines intended to supplement the acceptance criteria established in NRC regulations, guidelines presented in RGs, and recommendations presented in applicable Institute of Electronics and Electrical Engineers standards.
3.0 TECHNICAL EVALUATION
3.1 Description of the Fermi 2 Electrical Power System The standby AC power system for Fermi 2 consists of four EDG units separated into two independent divisions (two EDGs per division). Section 8.3.1 of the Fermi 2 Updated Final Safety Analysis Report (UFSAR) states that either divisional pair of EDG units is capable of supplying loads needed to safely shut down the reactor and maintaining the reactor in a safe shutdown condition after a design-basis accident. The EDG units are Colt Industries, Fairbanks-Morse, Model 38TD8-1/8, diesel generator units, each driving a 4160-V AC salient pole generator. For testing purposes, units are started manually, brought to speed, synchronized to the power plant system, and loaded.
The Fermi 2 design conforms to the RG positions, with a few exceptions, as described in Appendix A of the Fermi 2 UFSAR. RG 1.9, Revision 2, states, in part, that an EDG unit selected for use in an onsite electric power system should have the capability to start and accelerate a number of large motor loads in rapid succession and be able to sustain the loss of all or any part of such loads and maintain voltage within acceptable limits.
The Fermi 2 UFSAR states that the generators and excitation systems are designed so that, for the sequential starting of the motors, bus voltage shall not dip below an acceptable limit determined by test or systems analysis. Voltage recovery time is held to the minimum possible after starting the first motor. The starting of subsequent motors does not reduce the bus voltage below the limits set forth in RG 1.9. The Fermi 2 UFSAR states that the voltage dip of 72.5 percent when starting the residual heat removal (RHR) pumps is an exception to the
guidance of 75 percent in RG 1.9. The Fermi 2 UFSAR states that each EDG unit shall be at rated voltage within 10 seconds, and each unit shall be capable of maintaining the required minimum voltage and sequentially starting the RHR and core spray pump motors while maintaining a voltage as close as possible to RG 1.9 guidance.
3.2 Evaluation The licensee proposed to amend TS SRs 3.8.1.2, 3.8.1.7, 3.8.1.10, 3.8.1.11, 3.8.1.14, and 3.8.1.17 in TS 3.8.1, AAC Sources - Operating,@ by changing all occurrences of the minimum EDG output voltage acceptance criterion from 3740 to 3873 V. The licensee proposed this change for both Divisions of onsite standby EDGs. Where the SRs require a minimum EDG voltage, the TS SRs currently specify an output voltage of 3740 V. This voltage equates to approximately 90 percent of the nominal 4160 V output voltage of the EDG. The licensee stated that the 90 percent value was established to prevent the voltage to the terminals of motors and other equipment from dropping below the minimum required operating voltage, which is usually specified as 90 percent of the nameplate voltage rating of the equipment.
On August 22, 1986, the NRC approved License Amendment No. 4 to the Fermi 2 TS. The amendment, in part, revised the Division I 4160 V Emergency Bus Undervoltage (Degraded Voltage) minimum setting in TS 3.3.8.1 from 3628 to 3873 V to allow for Division I component operability. Because the EDG minimum output voltage requirement in the TS 3.8.1 SRs was not revised with Amendment No. 4, the current value of 3740 V is not conservative. Therefore, the licensee is proposing to amend the TS to revise the TS SRs to ensure that the minimum TS SR EDG output voltage acceptance criterion is consistent with the minimum voltage required for component operability in the licensees calculations.
Branch Technical Position PSB-1 of the Standard Review Plan, Revision 2, recommends, in part, that the second level of undervoltage (degraded voltage) protection should be based on an analysis of the voltage requirements of the Class 1E loads at all onsite system distribution levels.
Consequently, when powering the safety-related busses from EDGs, the minimum required EDG steady state voltage must be greater than or equal to the minimum established voltage for component reliability. The licensees license amendment request stated that the design calculations for the EDG loading document that at a minimum EDG output voltage of 3873 V for Division I and a minimum of 3628 V for Division II, sufficient terminal voltage is available to required emergency safeguards equipment to operate under worst-case accident conditions.
The licensee also stated that EDG SR records indicated that the 3873 V output voltage can be achieved within the 10-second interval required by the TS SRs. The licensee stated that the Division II EDGs would also be conservatively tested to the proposed EDG output voltage requirement of 3873 V for consistency between divisions.
The NRC staff was concerned that the proposed TS SR voltage value did not account for drift, measurement uncertainty, and margin. By letter dated August 16, 2007, the licensee committed to maintain administrative controls to ensure that the acceptance criteria for EDG surveillance voltage verification account for potential measurement uncertainty. The NRC staff finds this reasonable and therefore acceptable.
The NRC staff finds the proposed EDG minimum output voltage requirement for the TS 3.8.1 SRs, in addition to the licensees commitment to maintain administrative controls to ensure that the acceptance criteria for EDG surveillance voltage verification account for potential
measurement uncertainty, ensure that the calculated required voltage for equipment operability can be demonstrated through EDG testing. Therefore, the amendment request is acceptable and meets the regulations and requirements with regard to EDG testing.
The NRC staff has reviewed the licensee=s proposed TS changes and supporting documentation. Based on the evaluation discussed above, the NRC staff determined that the proposed amendment to TS 3.8.1 is acceptable because the testing demonstrates that the necessary quality of the EDGs is maintained, which ensures that facility operation will be within analysis limits, and the limiting conditions for EDG operations will be met.
3.3 Regulatory Commitment The licensee will maintain administrative controls to ensure that the acceptance criteria for EDG surveillance voltage verification account for potential measurement uncertainty.
4.0 STATE CONSULTATION
In accordance with the Commissions 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. The 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 (72 FR 20379). 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) such activities will be conducted in compliance with the Commissions 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: A. Klett, NRR Date: March 17, 2008
Fermi 2 cc:
David G. Pettinari Legal Department 688 WCB Detroit Edison Company 2000 2nd Avenue Detroit, MI 48226-1279 Michigan Department of Environmental Quality Waste and Hazardous Materials Division Radiological Protection and Medical Waste Section Nuclear Facilities Unit Constitution Hall, Lower-Level North 525 West Allegan Street P.O. Box 30241 Lansing, MI 48909-7741 U.S. Nuclear Regulatory Commission Resident Inspector's Office 6450 N Dixie Highway Newport, MI 48166 Mr. M. V. Yudasz, Jr., Director Monroe County Emergency Management Division 965 South Raisinville Road Monroe, MI 48161 Ronald W. Gaston Manager, Nuclear Licensing Detroit Edison Company Fermi 2 - 200 TAC 6400 North Dixie Highway Newport, MI 48166 Supervisor - Electric Operators Michigan Public Service Commission P.O. Box 30221 Lansing, MI 48909 Wayne County Emergency Management Division 10250 Middlebelt Road Detroit, MI 48242 Mr. Joseph H. Plona Vice President - Nuclear Generation Detroit Edison Company Fermi 2 - 210 NOC 6400 North Dixie Highway Newport, MI 48166