ML070960047
| ML070960047 | |
| Person / Time | |
|---|---|
| Site: | Perry  |
| Issue date: | 04/30/2007 |
| From: | Thomas Wengert NRC/NRR/ADRO/DORL/LPLIII-2 |
| To: | Pearce L FirstEnergy Nuclear Operating Co |
| Wengert, Thomas NRR/DORL 415-4037 | |
| Shared Package | |
| ML070960051 | List: |
| References | |
| TAC MC8997 | |
| Download: ML070960047 (12) | |
Text
April 30, 2007 Mr. L. W. Pearce Site Vice President FirstEnergy Nuclear Operating Company Mail Stop A-PY-A290 P.O. Box 97, 10 Center Road Perry, OH 44081
SUBJECT:
PERRY NUCLEAR POWER PLANT, UNIT NO. 1 - ISSUANCE OF AMENDMENT RE: EMERGENCY DIESEL GENERATOR SURVEILLANCE TESTING VOLTAGE AND FREQUENCY LIMITS (TAC NO. MC8997)
Dear Mr. Pearce:
The U.S. Nuclear Regulatory Commission (the Commission) has issued the enclosed Amendment No. 142 to Facility Operating License No. NPF-58 for the Perry Nuclear Power Plant, Unit No. 1. This amendment revises the technical specifications (TSs) in response to your application dated November 21, 2005, as supplemented by letter dated February 22, 2007.
This amendment revises the acceptance criteria of TS surveillance requirements associated with TS 3.8.1 to modify the emergency diesel generator start tests to provide minimum voltage and frequency limits and to clarify other pre-existing limits as steady state parameters.
A copy of the Safety Evaluation is also enclosed. The Notice of Issuance will be included in the Commissions next biweekly Federal Register notice.
Sincerely,
/RA/
Thomas J. Wengert, Project Manager Plant Licensing Branch III-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-440
Enclosures:
- 1. Amendment No. 142 to NPF-58
- 2. Safety Evaluation cc w/encls: See next page
April 30, 2007 Mr. L. W. Pearce Site Vice President FirstEnergy Nuclear Operating Company P.O. Box 97, A290 10 Center Road Perry, Ohio 44081
SUBJECT:
PERRY NUCLEAR POWER PLANT, UNIT NO. 1 - ISSUANCE OF AMENDMENT RE: EMERGENCY DIESEL GENERATOR SURVEILLANCE TESTING VOLTAGE AND FREQUENCY LIMITS (TAC NO. MC8997)
Dear Mr. Pearce:
The U.S. Nuclear Regulatory Commission (the Commission) has issued the enclosed Amendment No. 142 to Facility Operating License No. NPF-58 for the Perry Nuclear Power Plant, Unit No. 1. This amendment revises the technical specifications (TSs) in response to your application dated November 21, 2005, as supplemented by letter dated February 22, 2007.
This amendment revises the acceptance criteria of TS surveillance requirements associated with TS 3.8.1 to modify the emergency diesel generator start tests to provide minimum voltage and frequency limits and to clarify other pre-existing limits as steady state parameters.
A copy of the Safety Evaluation is also enclosed. The Notice of Issuance will be included in the Commissions next biweekly Federal Register notice.
Sincerely,
/RA/
Thomas J. Wengert, Project Manager Plant Licensing Branch III-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-440
Enclosures:
- 1. Amendment No. 142 to NPF-58
- 2. Safety Evaluation DISTRIBUTION:
PUBLIC LPL3-2 R/F RidsNrrPMTWengert RidsNrrDirsItsb RidsOgcRp RidsNrrLAEWhitt RidsRgn3MailCenter RidsNrrDorlLpl3-2 RidsNrrDorlDpr RidsNrrDeEeeb OChopra, NRR GHill (2)
RidsAcrsAcnwMailCenter TWertz, NRR Package Accession Number: ML070960051 Amendment Accession Number: ML070960047 TS Accession Number: ML071200503 NLO OFFICE LPL3-2/PM LPL3-2/LA DE/EEEB/BC DIRS/ITSB/BC OGC LPL3-2/BC NAME TWengert EWhitt GWilson TKobetz AHodgdon RGibbs DATE 4/30/07 4/30/07 04/25/07 04/25/07 4/27/07 4/30/07 OFFICIAL RECORD COPY
FIRSTENERGY NUCLEAR OPERATING COMPANY FIRSTENERGY NUCLEAR GENERATION CORP.
OHIO EDISON COMPANY DOCKET NO. 50-440 PERRY NUCLEAR POWER PLANT, UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 142 License No. NPF-58 1.
The U.S. Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for license filed by FirstEnergy Nuclear Operating Company, et al., (the licensee) dated November 21, 2005, as supplemented by letter dated February 22, 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-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. 142 are hereby incorporated into this license. FENOC 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 its issuance and shall be implemented within 120 days of the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
/RA/
Russell Gibbs, Chief Plant Licensing Branch III-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications and Facility Operating License Date of Issuance: April 30, 2007
ATTACHMENT TO LICENSE AMENDMENT NO. 142 FACILITY OPERATING LICENSE NO. NPF-58 DOCKET NO. 50-440 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 4 License Page 4 3.8-5 3.8-5 3.8-7 3.8-7 3.8-10 3.8-10 3.8-12 3.8-12 3.8-15 3.8-15 renewal. Such sale and leaseback transactions are subject to the representations and conditions set forth in the above mentioned application of January 23, 1987, as supplemented on March 3, 1987, as well as the letter of the Director of the Office of Nuclear Reactor Regulation dated March 16, 1987, consenting to such transactions. Specifically, a lessor and anyone else who may acquire an interest under these transactions are prohibited from exercising directly or indirectly any control over the licenses of PNPP Unit 1. For purposes of this condition the limitations of 10 CFR 50.81, as now in effect and as may be subsequently amended, are fully applicable to the lessor and any successor in interest to that lessor as long as the license for PNPP Unit 1 remains in effect; these financial transactions shall have no effect on the license for the Perry Nuclear facility throughout the term of the license.
(b)
Further, the licensees are also required to notify the NRC in writing prior to any change in: (I) the terms or conditions of any lease agreements executed as part of these transactions; (ii) the PNPP Operating Agreement; (iii) the existing property insurance coverage for PNPP Unit 1; and (iv) any action by a lessor or others that may have an adverse effect on the safe operation of the facility.
C.
This license shall be deemed to contain and is subject to the conditions specified in the Commissions 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 and hereafter in effect; and is subject to the additional conditions specified or incorporated below:
(1)
Maximum Power Level FENOC is authorized to operate the facility at reactor core power levels not in excess of 3758 megawatts thermal (100% power) 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. 142, are hereby incorporated into the license. FENOC shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
(3)
Antitrust Conditions
- a. FirstEnergy Nuclear Generation Corp. and Ohio Edison Company Amendment No. 142
SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 142 TO FACILITY OPERATING LICENSE NO. NPF-58 FIRSTENERGY NUCLEAR OPERATING COMPANY FIRSTENERGY NUCLEAR GENERATION CORP.
OHIO EDISON COMPANY PERRY NUCLEAR POWER PLANT, UNIT NO. 1 DOCKET NO. 50-440
1.0 INTRODUCTION
By letter to the Nuclear Regulatory Commission (NRC, the Commission) dated November 21, 2005, as supplemented by letter dated February 22, 2007, FirstEnergy Nuclear Operating Company, et al. (FENOC, the licensee) requested changes to the technical specifications (TSs) for the Perry Nuclear Power Plant (Perry), Unit No. 1. The proposed changes would revise the acceptance criteria of TS surveillance requirements (SRs) associated with TS 3.8.1, to modify the emergency diesel generator (EDG) start tests to provide minimum voltage and frequency limits and to clarify other limits as steady state parameters.
Specifically, the proposed changes would revise the following:
SR 3.8.1.2 would be revised to define the currently-listed voltage and frequency range as steady state.
SR 3.8.1.7, SR 3.8.1.12, SR 3.8.1.15, and SR 3.8.1.20 would be revised to require the EDG to achieve a voltage greater than or equal to 3900 volts (V) and a frequency greater than or equal to 58.8 Hertz (Hz) within 10 seconds of startup for Division 1 and Division 2, and a frequency greater than or equal to 58.8 Hz within 10 seconds of startup and a voltage greater than or equal to 3900 V within 13 seconds of startup for the Division 3 EDG. Each EDG (Division 1, 2 and 3) would be required to achieve steady state voltage of greater than or equal to 3900 V and less than or equal to 4400 V, and a frequency greater than or equal to 58.8 Hz and less than or equal to 61.2 Hz.
The licensee has cited the NRC staffs similar previously-approved change for Grand Gulf Nuclear Station, Unit 1 (Agencywide Documents Access and Management System (ADAMS)
Accession No. ML003729556) and Clinton Power Station, Unit No. 1 (ADAMS Accession No. ML020990599).
The February 22, 2007, supplement contained clarifying information and did not change the NRC staffs initial proposed finding of no significant hazards consideration.
2.0 REGULATORY EVALUATION
The regulatory requirements the NRC staff applied in its review of the application include:
General Design Criterion (GDC) 17, Electric power systems, of Appendix A, General Design Criteria for Nuclear Power Plants, to Title 10 of the Code of Federal Regulations (10 CFR),
Part 50 requires 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, requires 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.
3.0 TECHNICAL EVALUATION
The licensee proposed to revise the acceptance criteria of SR 3.8.1.7, SR 3.8.1.12, SR 3.8.15, and SR 3.8.1.20 consistent with the approved TS Task Force Traveler No. 163 (TSTF-163),
Revision 2. The acceptance criteria for the EDG start tests will be modified by specifying the minimum voltage and frequency to be achieved during startup, and assigning the currently listed voltage and frequency ranges as values to be achieved once steady state is reached.
Currently SRs 3.8.1.7, 3.8.1.12, 3.8.15, and 3.8.1.20 verify that when started from standby conditions, the Division 1 and 2 EDGs achieve a voltage $ 3900 V and # 4400 V and frequency
$ 58.8 Hz and # 61.2 Hz in # 10 seconds. In addition, these SRs require the Division 3 EDG to achieve frequency $ 58.8 Hz in # 10 seconds, and voltage $ 3900 V and # 4400 V, and frequency $ 58.8 Hz and # 61.2 Hz in # 13 seconds.
SR 3.8.1.2 currently verifies that each EDG starts from standby conditions and achieves voltage
$ 3900 V and # 4400 V and frequency $ 58.8 Hz and # 61.2 Hz. The licensee has proposed to revise SR 3.8.1.2 to define the currently listed voltages and frequency range as steady state, and to revise SRs 3.8.1.7, 3.8.1.12, 3.8.15 and 3.8.1.20 to require that Division 1 and Division 2 EDGs achieve a voltage $ 3900 V and a frequency $ 58.8 Hz in #10 seconds, and a frequency
$ 58.8 Hz in # 10 seconds, and voltage $ 3900 V in # 13 seconds for Division 3 EDG. After the startup period (10 or 13 seconds, as applicable) the EDG for each division must subsequently achieve a steady state voltage $ 3900 V and # 4400 V, and frequency $ 58.8 Hz and # 61.2 Hz, in accordance with the revised SRs.
The changes that the licensee has proposed appropriately specify the original voltage and frequency tolerance band as steady state values while, in the transient region within the time limit (10 or 13 seconds), they specify only minimum values. The licensee stated that when a test is performed that does not result in tying the EDG to the bus, a momentary voltage or frequency overshoot (and/or subsequent undershoot) can occur because no loads are being tied to the EDG. The loading tends to minimize the overshoot, whereas the unloaded overshoot might momentarily exceed the specified limits within the first 10 or 13 seconds of startup. This condition is not uncommon due to the nature of the EDG governor as it seeks to control EDG speed during fast starts when the EDG is unloaded. The voltage and frequency overshoot (or undershoot) does not affect the permissive for closure of the EDG output breaker, since the permissive is primarily dependent on minimum conditions being achieved regardless of any overshoot or subsequent momentary undershoot. By eliminating the time limit to reach steady state conditions, the governor can be set up to provide a more stable power source. In addition, the loss of offsite power (LOOP) test and, the LOOP in conjunction with the emergency core cooling system initiation signal test, required by TS SR 3.8.1.11 and SR 3.8.1.19 respectively, will continue to verify the capability of the EDGs to provide power at a voltage and frequency adequate to start and operate the safety loads.
Based on the above, the NRC staff believes that the voltage and frequency tolerance band currently specified in the subject surveillances are more appropriate for steady state limits than transient limits, and that the applicable TS SRs will continue to verify the capability of the EDGs to provide power at a voltage and frequency adequate to start and operate the safety loads.
The NRC staff and the industry have reviewed and resolved this issue on a generic basis:
TSTF-163, Revision 2, which applies to SR 3.8.1.7, SR 3.8.1.12, SR 3.8.1.15 and 3.8.1.20, (1) eliminates the maximum voltage and frequency limits from the start test, (2) rewords the SRs to clarify that each EDG is required to achieve steady state operation following the timed start; and (3) provides that the time to reach steady state operation is periodically monitored and the trend evaluated to identify degradation of governor and voltage regulator performance.
While the amendment to SR 3.8.1.2 is not explicitly included as one of the changes endorsed in TSTF-163, Revision 2, the NRC staff considers this amendment to be consistent with the principles underlying TSTF-163, Revision 2.
In consideration of the foregoing, the NRC staff considers the amendments described herein as consistent with TSTF-163, Revision 2, as so described above. Pursuant to this, the NRC staff finds that the provisions of the SRs, as amended, will continue to ensure that proper steady state voltage and frequency are attained consistent with the proper EDG governor and voltage regulator performance. On this basis in conjunction with that outlined above, the NRC staff finds the proposed amendments acceptable. These types of changes have already been incorporated into the improved standard TS.
4.0 STATE CONSULTATION
In accordance with the Commissions regulations, the Ohio State official was notified of the proposed issuance of the amendment. The State official had no comments.
5.0 ENVIRONMENTAL CONSIDERATION
This amendment changes 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 effluent 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 this amendment involves no significant hazards consideration and there has been no public comment on such finding (71 FR 2591; January 17, 2006).
Accordingly, this 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 this amendment.
6.0 CONCLUSION
The NRC staff 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 this amendment will not be inimical to the common defense and security or to the health and safety of the public.
Principal Contributor: O. Chopra, NRR Date: April 30, 2007
Perry Nuclear Power Plant, Unit 1 cc:
David W. Jenkins, Attorney FirstEnergy Corporation Mail Stop A-GO-18 76 South Main Street Akron, OH 44308 Resident Inspector's Office U.S. Nuclear Regulatory Commission P.O. Box 331 Perry, OH 44081-0331 Regional Administrator, Region III U.S. Nuclear Regulatory Commission 2443 Warrenville Road, Suite 210 Lisle, IL 60532-4531 Sue Hiatt OCRE Interim Representative 8275 Munson Mentor, OH 44060 Manager, Site Regulatory Compliance FirstEnergy Nuclear Operating Company Perry Nuclear Power Plant Mail Stop A-PY-A210 P.O. Box 97, 10 Center Road Perry, OH 44081-0097 Mayor, Village of North Perry North Perry Village Hall 4449 Lockwood Road North Perry Village, OH 44081 Donna Owens, Director Ohio Department of Commerce Division of Industrial Compliance Bureau of Operations & Maintenance 6606 Tussing Road P.O. Box 4009 Reynoldsburg, OH 43068-9009 Carol OClaire, Chief, Radiological Branch Ohio Emergency Management Agency 2855 West Dublin Granville Road Columbus, OH 43235-7150 Mayor, Village of Perry P.O. Box 100 Perry, OH 44081-0100 Dennis Clum Radiological Assistance Section Supervisor Bureau of Radiation Protection Ohio Department of Health P.O. Box 118 Columbus, OH 43266-0118 Zack A. Clayton DERR Ohio Environmental Protection Agency ATTN: Mr. Zack A. Clayton P.O. Box 1049 Columbus, OH 43266-0149 Chairman Perry Township Board of Trustees 3750 Center Road, Box 65 Perry, OH 44081 Daniel Z. Fisher Transportation Department Public Utilities Commission 180 East Broad Street Columbus, OH 43215-3793 James H. Lash Senior Vice President of Operations and Chief Operating Officer FirstEnergy Nuclear Operating Company Mail Stop A-GO-14 76 South Main Street Akron, OH 44308 Director, Fleet Regulatory Affairs FirstEnergy Nuclear Operating Company Mail Stop A-GO-2 76 South Main Street Akron, OH 44308 Joseph J. Hagan President and Chief Nuclear Officer FirstEnergy Nuclear Operating Company Mail Stop A-GO-19 76 South Main Street Akron, OH 44308
Perry Nuclear Power Plant, Unit 1 cc:
Danny L. Pace Senior Vice President, Fleet Engineering FirstEnergy Nuclear Operating Company Mail Stop A-GO-14 76 South Main Street Akron, OH 44308 Jeannie M. Rinckel Vice President, Fleet Oversight FirstEnergy Nuclear Operating Company Mail Stop A-GO-14 76 South Main Street Akron, OH 44308 Manager, Fleet Licensing FirstEnergy Nuclear Operating Company Mail Stop A-GO-2 76 South Main Street Akron, OH 44308 Richard Anderson Vice President, Nuclear Support FirstEnergy Nuclear Operating Company Mail Stop A-GO-14 76 South Main Street Akron, OH 44308