ML021700003
| ML021700003 | |
| Person / Time | |
|---|---|
| Site: | Clinton  |
| Issue date: | 07/17/2002 |
| From: | Hopkins J NRC/NRR/DLPM/LPD3 |
| To: | Skolds J Exelon Generation Co, Exelon Nuclear |
| References | |
| TAC MB0909 | |
| Download: ML021700003 (10) | |
Text
July 17, 2002 Mr. John L. Skolds, President and Chief Nuclear Officer Exelon Nuclear Exelon Generation Company, LLC 4300 Winfield Road Warrenville, Illinois 60555
SUBJECT:
CLINTON POWER STATION, UNIT 1 - ISSUANCE OF AMENDMENT (TAC NO. MB0909)
Dear Mr. Skolds:
The U.S. Nuclear Regulatory Commission (Commission) has issued the enclosed Amendment No. 153 to Facility Operating License No. NPF-62 for the Clinton Power Station, Unit 1. The amendment is in response to the application from AmerGen Energy Company, LLC, dated December 28, 2000, as supplemented May 31, 2002.
The amendment decreases the allowed outage time for an inoperable channel or channels of the anticipated transient without scram recirculation pump trip instrumentation.
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/
Jon B. Hopkins, Senior Project Manager, Section 2 Project Directorate III Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket No. 50-461
Enclosures:
- 1. Amendment No. 153 to NPF-62
- 2. Safety Evaluation cc w/encls: See next page
- No legal objection OFFICE PM:PD3-2 LA:PD3-2 BC:RORP OGC/NLO*
SC:PD3-2 NAME JHopkins THarris RDennig for WBeckner RWeisman AMendiola DATE 06/21/02 06/20/02 06/28/02 07/12/02 07/15/02
Clinton Power Station, Unit 1 cc:
Chief Operating Officer Exelon Generation Company, LLC 4300 Winfield Road Warrenville, Illinois 60555 Senior Vice President - Nuclear Services Exelon Generation Company, LLC 4300 Winfield Road Warrenville, Illinois 60555 Vice President - Mid-West Opns Support Exelon Generation Company, LLC 4300 Winfield Road Warrenville, Illinois 60555 Senior Vice President - Mid-West Regional Operating Group Exelon Generation Company, LLC 4300 Winfield Road Warrenville, Illinois 60555 Vice President - Licensing and Regulatory Affairs Exelon Generation Company, LLC 4300 Winfield Road Warrenville, Illinois 60555 Manager Licensing - Clinton and LaSalle Exelon Generation Company, LLC 4300 Winfield Road Warrenville, IL 60555 Director-Licensing Mid-West Regional Operating Group Exelon Generation Company, LLC 4300 Winfield Road Warrenville, Illinois 60555 Senior Counsel, Nuclear Mid-West Regional Operating Group Exelon Generation Company, LLC 4300 Winfield Road Warrenville, Illinois 60555 Document Control Desk-Licensing Exelon Generation Company, LLC 4300 Winfield Road Warrenville, Illinois 60555 Illinois Department of Nuclear Safety Office of Nuclear Facility Safety 1035 Outer Park Drive Springfield, IL 62704 Site Vice President - Clinton Power Station AmerGen Energy Company, LLC Clinton Power Station RR 3, Box 228 Clinton, IL 61727-9351 Clinton Power Station Plant Manager AmerGen Energy Company, LLC Clinton Power Station RR 3, Box 228 Clinton, IL 61727-9351 Regulatory Assurance Manager - Clinton AmerGen Energy Company, LLC Clinton Power Station RR 3, Box 228 Clinton, IL 61727-9351
Clinton Power Station, Unit 1 cc:
Resident Inspector U.S. Nuclear Regulatory Commission RR#3, Box 229A Clinton, IL 61727 R. T. Hill Licensing Services Manager General Electric Company 175 Curtner Avenue, M/C 481 San Jose, CA 95125 Regional Administrator, Region III U.S. Nuclear Regulatory Commission 801 Warrenville Road Lisle, IL 60532-4351 Chairman of DeWitt County c/o County Clerks Office DeWitt County Courthouse Clinton, IL 61727 J. W. Blattner Project Manager Sargent & Lundy Engineers 55 East Monroe Street Chicago, IL 60603
AMERGEN ENERGY COMPANY, LLC DOCKET NO. 50-461 CLINTON POWER STATION, UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 153 License No. NPF-62 1.
The U.S. Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by AmerGen Energy Company, LLC (the licensee), dated December 28, 2000, as supplemented May 31, 2002, 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-62 is hereby amended to read as follows:
(2)
Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A and the Environmental Protection Plan contained in Appendix B, as revised through Amendment No. 153 are hereby incorporated into this license. AmerGen Energy Company, LLC 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 of the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
/RA/
Anthony J. Mendiola, Chief, Section 2 Project Directorate III Division of Licensing Project Management Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: July 17, 2002
ATTACHMENT TO LICENSE AMENDMENT NO. 153 FACILITY OPERATING LICENSE NO. NPF-62 DOCKET NO. 50-461 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 Pages Insert Pages 3.3-28 3.3-28 3.3-29 3.3-29 3.3-30 3.3-30
SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 153 TO FACILITY OPERATING LICENSE NO. NPF-62 AMERGEN ENERGY COMPANY, LLC CLINTON POWER STATION, UNIT 1 DOCKET NO. 50-461
1.0 INTRODUCTION
By letter dated December 28, 2000, AmerGen Energy Company, LLC (AmerGen or the licensee), proposed an amendment to the Clinton Power Station (CPS) Technical Specifications (TSs). The change would decrease the allowed outage time for an inoperable channel or channels of the anticipated transient without scram (ATWS) recirculation pump trip instrumentation.
Additional information submitted by letter dated May 31, 2002, made a minor change to the requested TS for clarification, and did not change the scope of the request as noticed or affect the determination of no significant hazards consideration proposed by the Nuclear Regulatory Commission (NRC) staff in the Federal Register.
2.0 BACKGROUND
By letter dated December 14, 1999, the licensee informed the NRC that incorrect design information was provided to the NRC concerning the ATWS reactor recirculation pump trip (RPT) for CPS in a 1990 license amendment request, which was approved by the NRC staff by license Amendment No. 64. The incorrect information supported changes to the TSs to increase the allowed outage time for the ATWS-RPT.
Specifically, the incorrect information was that the ATWS-RPT trip system logic consisted of two fully redundant systems such that a trip in either system was capable of tripping both recirculation pumps, whereas the actual system configuration is such that each trip system trips only its respective recirculation pump.
3.0 EVALUATION As a result of the ATWS-RPT design at CPS, the licensee is proposing to delete a note applicable to TS 3.3.4.2 surveillance requirements and the current TS 3.3.4.2 Condition A. The note associated with TS 3.3.4.2 surveillance requirements states the following.
When a channel is placed in an inoperable status solely for performance of required surveillances, entry into associated Conditions and Required Actions may be delayed for up to 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> provided the associated Function maintains ATWS-RPT trip capability.
As the licensee states in their submittal, the CPS ATWS-RPT design does not provide for maintaining the trip function capability when a channel is removed from service for testing.
Therefore, this note is not applicable for CPS and should be deleted. Additionally, the licensee states that the 6 hour6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> delay allowed by the note is not needed for CPS, since required testing can be accomplished without it. The NRC staff finds that the note associated with TS 3.3.4.2 surveillance requirements should be deleted because it is not appropriate for the ATWS-RPT design at CPS.
Current Condition A allows 14 days to restore or place in a tripped condition an inoperable channel of the ATWS-RPT instrumentation when one or more channels are inoperable. Like the note referred to above, this TS condition is based on an ATWS-RPT design where an inoperable channel will not cause the trip function capability to be lost. This is not the design at CPS. Therefore, deletion of this condition from the CPS TS is appropriate.
The TS conditions remaining will allow 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> to restore ATWS-RPT trip capability when one trip function capability is not maintained in one trip system. Because of the low likelihood of a significant transient, a failure to scram, and the failure of the remaining trip function capability in the affected trip system occurring simultaneously, the 72 hour8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> restoration time for one trip function capability not maintained in one trip system is appropriate for ensuring continued safe operation of the plant, and is acceptable to the NRC staff.
The allowed outage time will be one hour for the condition where more than one trip function capability is not maintained, regardless of whether the additional lost trip function capability is within the same trip system or the other trip system. The one hour time for more than one trip function capability not maintained is based on the logic redundancy and diversity of the CPS ATWS-RPT design. The NRC staff finds the one hour time to be acceptable for CPS for the condition where more than one trip function capability is not maintained and is conservative for the installed configuration.
The NRC staff has reviewed the revised TS including the TS Bases for the CPS ATWS-RPT system, and based on the above, finds the change acceptable.
4.0 STATE CONSULTATION
In accordance with the Commissions regulations, the Illinois State official was notified of the proposed issuance of the amendment. The State official had no comments.
5.0 ENVIRONMENTAL CONSIDERATION
This amendment changes a requirement with respect to installation or use of a facility component located within the restricted area as defined in 10 CFR Part 20 or changes a surveillance requirement. 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 (66 FR 9378). 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 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 the amendment will not be inimical to the common defense and security or to the health and safety of the public.
Principal Contributor: J. Hopkins Date: July 17, 2002