ML060260074
| ML060260074 | |
| Person / Time | |
|---|---|
| Site: | Quad Cities  |
| Issue date: | 03/09/2006 |
| From: | Banerjee M Plant Licensing Branch III-2 |
| To: | Crane C Exelon Generation Co |
| Banerjee M, NRR/ADPT, 415-2277 | |
| Shared Package | |
| ML060260084 | List: |
| References | |
| TAC MC7312, TAC MC7313 | |
| Download: ML060260074 (12) | |
Text
March 9, 2006 Mr. Christopher M. Crane, President and Chief Nuclear Officer Exelon Generation Company, LLC 4300 Winfield Road Warrenville, IL 60555
SUBJECT:
QUAD CITIES NUCLEAR POWER STATION, UNITS 1 AND 2 - ISSUANCE OF AMENDMENTS RE: FEEDWATER SYSTEM AND MAIN TURBINE HIGH WATER LEVEL TRIP INSTRUMENTATION (TAC NOS. MC7312 AND MC7313 )
Dear Mr. Crane:
The Commission has issued the enclosed Amendment No. 330 to Facility Operating License No. DPR-29 and Amendment No. 225 to Facility Operating License No. DPR-30 for the Quad Cities Nuclear Power Station, Units 1 and 2, respectively. The amendments are in response to your application dated June 15, 2005.
The amendments revise Technical Specification (TS) 3.3.2.2, ?Feedwater System and Main Turbine High Water Level Trip Instrumentation, to reflect a design change in the instrumentation logic that trips the three feedwater pumps and main turbine.
A copy of the related Safety Evaluation is also enclosed. The Notice of Issuance will be included in the Commission's biweekly Federal Register notice.
Sincerely,
/RA/
Maitri Banerjee, Senior Project Manager Plant Licensing Branch III-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-254 and 50-265
Enclosures:
- 1. Amendment No. 330 to DPR-29
- 2. Amendment No. 225 to DPR-30
- 3. Safety Evaluation cc w/encls: See next page
March 9, 2006 Mr. Christopher M. Crane, President and Chief Nuclear Officer Exelon Generation Company, LLC 4300 Winfield Road Warrenville, IL 60555
SUBJECT:
QUAD CITIES NUCLEAR POWER STATION, UNITS 1 AND 2 - ISSUANCE OF AMENDMENTS RE: FEEDWATER SYSTEM AND MAIN TURBINE HIGH WATER LEVEL TRIP INSTRUMENTATION (TAC NOS. MC7312 AND MC7313 )
Dear Mr. Crane:
The Commission has issued the enclosed Amendment No. 330 to Facility Operating License No. DPR-29 and Amendment No. 225 to Facility Operating License No. DPR-30 for the Quad Cities Nuclear Power Station, Units 1 and 2, respectively. The amendments are in response to your application dated June 15, 2005.
The amendments revise Technical Specification (TS) 3.3.2.2, ?Feedwater System and Main Turbine High Water Level Trip Instrumentation, to reflect a design change in the instrumentation logic that trips the three feedwater pumps and main turbine.
A copy of the related Safety Evaluation is also enclosed. The Notice of Issuance will be included in the Commission's biweekly Federal Register notice.
Sincerely,
/RA/
Maitri Banerjee, Senior Project Manager Plant Licensing Branch III-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-254 and 50-265
Enclosures:
- 1. Amendment No. 330 to DPR-29
- 2. Amendment No. 225 to DPR-30
- 3. Safety Evaluation cc w/encls: See next page DISTRIBUTION:
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- ADM & Secy pending info received on 3/9/06 - Ready to date and number ADAMS Accession Number:ML060260074(Ltr.)
Package access.no.ML060260084 Tech.spec.pages ML060720069 OFFICE LP3-2/PM LP3-2/PE LP3-2/LA EICB/BC NAME MBanerjee:mw RKuntz PCoates (DClarke for)*
AHowe DATE 2/21/2006 2/12/2006 3/9/2006 2/21/2006 OFFICE ITST/BC SBWB/BC OGC (NLO)
LP3-2/BC(A)
NAME TBoyce GCranston MWoods MLandau DATE 2/24/2006 2/27/2006 3/3/2006 3/7/2006 OFFICIAL RECORD COPY
EXELON GENERATION COMPANY, LLC AND MIDAMERICAN ENERGY COMPANY DOCKET NO. 50-254 QUAD CITIES NUCLEAR POWER STATION, UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 330 License No. DPR-29 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Exelon Generation Company, LLC, et al.
(the licensee) dated June 15, 2005, 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 3.B. of Facility Operating License No. DPR-29 is hereby amended to read as follows:
B.
Technical Specifications The Technical Specifications contained in Appendix A as revised through Amendment No. 330, are hereby incorporated into the renewed facility operating license. The licensee shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective as of the date of its issuance and shall be implemented prior to start-up from the spring 2007 refueling outage for Unit 1.
FOR THE NUCLEAR REGULATORY COMMISSION
/RA/
Mindy S. Landau, Acting Chief Plant Licensing Branch III-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: March 9, 2006
EXELON GENERATION COMPANY, LLC AND MIDAMERICAN ENERGY COMPANY DOCKET NO. 50-265 QUAD CITIES NUCLEAR POWER STATION, UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 225 License No. DPR-30 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Exelon Generation Company, LLC, et al. (the licensee) dated June 15, 2005, 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 3.B. of Facility Operating License No. DPR-30 is hereby amended to read as follows:
B.
Technical Specifications The Technical Specifications contained in Appendix A as revised through Amendment No. 225, are hereby incorporated into the renewed facility operating license. The licensee shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective as of the date of its issuance and shall be implemented prior to start-up from the Spring 2006 refueling outage for Unit 2.
FOR THE NUCLEAR REGULATORY COMMISSION
/RA/
Mindy S. Landau, Acting Chief Plant Licensing Branch III-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: March 9, 2006
ATTACHMENT TO LICENSE AMENDMENT NOS. 330 AND 225 FACILITY OPERATING LICENSE NOS. DPR-29 AND DPR-30 DOCKET NOS. 50-254 AND 50-265 Replace the following pages of the Appendix A Technical Specifications with the attached pages. The revised pages are identified by number and contain marginal lines indicating the area of change.
Remove Insert 3.3.2.2-1 3.3.2.2-1 3.3.2.2-2 3.3.2.2-2 3.3.2.2-3
SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 330 TO FACILITY OPERATING LICENSE NO. DPR-29 AND AMENDMENT NO. 225 TO FACILITY OPERATING LICENSE NO. DPR-30 EXELON GENERATION COMPANY, LLC AND MIDAMERICAN ENERGY COMPANY QUAD CITIES NUCLEAR POWER STATION, UNITS 1 AND 2 DOCKET NOS. 50-254 AND 50-265
1.0 INTRODUCTION
By letter to the Nuclear Regulatory Commission (NRC, Commissioin) dated June 15, 2005 (Agencywide Documents Access and Management System (ADAMS) Accession Number ML051730461), Exelon Generation Company, LLC, et al. (the licensee) requested changes to the technical specifications (TSs) for Quad Cities Nuclear Power Station, Units 1 and 2 (Quad Cities). The proposed amendment would revise TS 3.3.2.2, ?Feedwater System and Main Turbine High Water Level Trip Instrumentation and the related bases.
2.0 REGULATORY EVALUATION
The NRC staff finds that the licensee in Section 5.2 of its submittal identified the applicable regulatory requirements. The regulatory requirements for which the NRC staff based its acceptance are the Commissions regulatory requirements for TS changes set forth in the Title 10 of the Code of Federal Regulations (10 CFR), Section 50.36, ?Technical Specifications, for this evaluation. Specifically, 10 CFR 50.36(c)(2) specifies the requirements for limiting conditions for operation (LCO), and 10 CFR 50.36(c)(3) specifies the surveillance requirements (SRs). In addition, the NRC staff considered guidance and information in NUREG-1433,
?Standard Technical Specifications General Electric Plants BWR/4, Revision 3, in its evaluation.
3.0 TECHNICAL EVALUATION
The NRC staff has reviewed the licensees regulatory and technical analyses in support of its proposed license amendment which are described in Section 4.0 of the licensees submittal.
The detailed evaluation below will support the conclusion 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 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.
3.1 TS 3.3.2.2 - Feedwater System and Main Turbine High Water Level Trip Instrumentation The proposed TS changes are based on NUREG-1433. NUREG-1433 assumed a two-out-of-three trip logic with provision to permit plant operation for 7 days with one channel inoperable.
Because of the limitations of the existing feedwater system and main turbine high water level trip instrumentation using a two-out-of-two trip logic, the licensee could not adopt the NUREG-1433 specification for TS 3.3.2.2 during improved TS conversion. To use the existing spare components, the licensee proposes a one-out-of-two-twice trip logic and the wording specified under the Condition and Required Action columns, which are suitably modified from the wording in NUREG-1433, where required. The following is the technical evaluation of each of the proposed changes to TS 3.3.2.2.
LCO 3.3.2.2 The proposed revision to LCO 3.3.2.2 would change the number of operable channels from two to four. This change reflects the design change of the instrumentation from two channels to four channels, with two independent trip systems arranged in a one-out-of-two-twice logic. The NRC staff finds this change acceptable.
Applicability The proposed revision to the Applicability section of TS 3.3.2.2 would add the note, Separate Condition entry is allowed for each channel. This change reflects wording in NUREG-1433 and represents the design modification. The proposed addition of a redundant trip channel to each trip system provides for the ability of the instrumentation to perform its intended function with multiple channels inoperable. Consequentially, the proposed change would allow for up to two trip channels to be inoperable (provided the two inoperable channels are in separate trip systems) while still maintaining the instrumentation capability. Therefore, the NRC staff finds this change acceptable.
Action A The proposed revision to Action A would (1) replace the existing Required Action A.1 statement, Restore Feedwater System and main turbine high water level trip capability, with a new statement, Place channel in Trip and add a Note, Not applicable if inoperable channel is the result of an inoperable feedwater pump breaker, and (2) changing the completion time from 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> to 7 days. With the modified design, the plant can operate for 7 days with one or more of the feedwater system and main turbine high water level trip channels inoperable because the current required action statement, which was applicable for the existing two-out-of-two trip logic, is not applicable for the proposed trip logic and conforms to NUREG-1433 which specifies a 7-day completion time for this condition. As stated in NUREG-1433 [t]he Completion Time of 7 days is based on the low probability of the event occurring coincident with a single failure in a remaining OPERABLE channel.
The added Note clarifies that the 7-day completion time is not applicable if the feedwater pump breaker is inoperable and conforms to NUREG-1433. The licensee stated its submittal that without this Note, placing the channel in trip may not adequately compensate for the inoperable breaker.
The NRC staff finds that the proposed changes to TS 3.3.2.2, Action A, conforms with NUREG-1433 and the new design, and is, therefore, acceptable.
Action B The proposed change would add a new Condition B, Feedwater System and main turbine high water level trip capability not maintained, a Required Action B.1, Restore trip capability, and an associated completion time of 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />. This complies with NUREG-1433 and the completion time statement in the current TS Condition A. Therefore, the NRC staff finds this change acceptable.
Action C The proposed revision would move the existing Condition B to Condition C, and would move the associated Required Actions B.1 to C.1 and B.2 to C.2, to reflect the addition of the new Condition B. This is an editorial change and, is therefore acceptable to the NRC staff.
Surveillance Requirements The Note in the SRs pertaining to the allowed inoperable time for surveillances before entering the associated conditions and required actions is changed from 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> to 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />. This proposed revision conforms with NUREG-1433 and General Electric Company Report,.
GENE-770-06-1-A, Bases for Changes to Surveillance Test Intervals and Allowed Out-of-Service Times for Selected Instrumentation Technical Specifications, and is therefore acceptable to the NRC staff.
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
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. 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, and there has been no public comment on such finding (70 FR 51381; August 30, 2005). Accordingly, the amendments meet 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) such activities will be conducted in compliance with the Commission's 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 Contributor: S. Mazumdar Date: March 9, 2006
Quad Cities Nuclear Power Station Units 1 and 2 cc:
Site Vice President - Quad Cities Nuclear Power Station Exelon Generation Company, LLC 22710 206th Avenue N.
Cordova, IL 61242-9740 Quad Cities Nuclear Power Station Plant Manager Exelon Generation Company, LLC 22710 206th Avenue N.
Cordova, IL 61242-9740 Regulatory Assurance Manager - Quad Cities Exelon Generation Company, LLC 22710 206th Avenue N.
Cordova, IL 61242-9740 Quad Cities Resident Inspectors Office U.S. Nuclear Regulatory Commission 22712 206th Avenue N.
Cordova, IL 61242 David C. Tubbs MidAmerican Energy Company One River Center Place 106 E. Second, P.O. Box 4350 Davenport, IA 52808-4350 Vice President - Law and Regulatory Affairs MidAmerican Energy Company One River Center Place 106 E. Second Street P.O. Box 4350 Davenport, IA 52808 Chairman Rock Island County Board of Supervisors 1504 3rd Avenue Rock Island County Office Bldg.
Rock Island, IL 61201 Regional Administrator U.S. NRC, Region III 801 Warrenville Road Lisle, IL 60532-4351 Illinois Emergency Management Agency Division of Disaster Assistance &
Preparedness 110 East Adams Street Springfield, IL 62701-1109 Document Control Desk - Licensing Exelon Generation Company, LLC 4300 Winfield Road Warrenville, IL 60555 Senior Vice President of Operations Exelon Generation Company, LLC 4300 Winfield Road Warrenville, IL 60555 Vice President - Licensing and Regulatory Affairs Exelon Generation Company, LLC 4300 Winfield Road Warrenville, IL 60555 Director - Licensing and Regulatory Affairs Exelon Generation Company, LLC 4300 Winfield Road Warrenville, IL 60555 Assistant General Counsel Exelon Generation Company, LLC 200 Exelon Way Kennett Square, PA 19348 Manager Licensing - Dresden, Quad Cities and Clinton Exelon Generation Company, LLC 4300 Winfield Road Warrenville, IL 60555