ML050620160
| ML050620160 | |
| Person / Time | |
|---|---|
| Site: | Quad Cities  |
| Issue date: | 03/15/2005 |
| From: | Rossbach L NRC/NRR/DLPM/LPD3 |
| To: | Crane C Exelon Generation Co |
| Rossbach L, 415-2863, NRR/DLPM | |
| Shared Package | |
| ML050760379 | List: |
| References | |
| TAC MC3413, TAC MC3414 | |
| Download: ML050620160 (13) | |
Text
March 15, 2005 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 (TAC NOS. MC3413 AND MC3414)
Dear Mr. Crane:
The U.S. Nuclear Regulatory Commission (Commission) has issued the enclosed Amendment No. 224 to Facility Operating License No. DPR-29 and Amendment No. 219 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 10, 2004, as supplemented by letters dated July 19 and July 21, 2004, and January 21, 2005.
The amendments revise the Quad Cities Nuclear Power Station Technical Specifications to change the allowable value and add Surveillance Requirements for the Main Steam Line Flow-High initiation of Group 1 Primary Containment Isolation System and Control Room Emergency Ventilation System isolation.
A copy of the Safety Evaluation is also enclosed. The Notice of Issuance will be included in the Commission's biweekly Federal Register notice.
Sincerely,
/RA/
Lawrence Rossbach, Project Manager, Section 2 Project Directorate III Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket Nos. 50-254 and 50-265
Enclosures:
- 1. Amendment No. 224 to DPR-29
- 2. Amendment No. 219 to DPR-30
- 3. Safety Evaluation cc w/encls: See next page
March 15, 2005 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 (TAC NOS. MC3413 AND MC3414)
Dear Mr. Crane:
The U.S. Nuclear Regulatory Commission (Commission) has issued the enclosed Amendment No. 224 to Facility Operating License No. DPR-29 and Amendment No. 219 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 10, 2004, as supplemented by letters dated July 19 and July 21, 2004, and January 21, 2005.
The amendments revise the Quad Cities Nuclear Power Station Technical Specifications to change the allowable value and add Surveillance Requirements for the Main Steam Line Flow-High initiation of Group 1 Primary Containment Isolation System and Control Room Emergency Ventilation System isolation.
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/
Lawrence Rossbach, Project Manager, Section 2 Project Directorate III Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket Nos. 50-254 and 50-265
Enclosure:
- 1. Amendment No. 224 to DPR-29
- 2. Amendment No. 219 to DPR-30
- 3. Safety Evaluation cc w/encl: See next page DISTRIBUTION:
PUBLIC OGC, O15B18 PD3-2 r/f ACRS, T2E26 WRuland GHill (4), T5C3 GSuh TBoyce, O-12H2 LRossbach MRing, RIII PCoates ADAMS Accession Number: ML050620160 (Amendments)
ADAMS Accession Number: ML050760194 (Technical Specifications)
ADAMS Accession Number: ML050760379 (Package)
OFFICE PM:LPD3-2 PM:LPD3-2 LA:LPD3-2 SC:EEIB-A SC:IROB-A SC:SRXB-A OGC SC:LPD3-2 NAME LRossbach WMacon PCoates EMarinos TBoyce FAkstulewicz BPoole GSuh DATE 3/15/05 3/15/05 3/16/05 03/04/05 03/07/05 3/14/05 03/10/05 3/15/05 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. 224 License No. DPR-29 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Exelon Generation Company, LLC (the licensee) dated June 10, 2004, as supplemented by letters dated July 19 and July 21, 2004, and January 21, 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 Appendices A and B, as revised through Amendment No. 224, are hereby incorporated in the 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 within 90 days of the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
/RA/
Gene Y. Suh, 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: March 15, 2005
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. 219 License No. DPR-30 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Exelon Generation Company, LLC (the licensee) dated June 10, 2004, as supplemented by letters dated July 19 and July 21, 2004, and January 21, 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 Appendices A and B, as revised through Amendment No. 219, are hereby incorporated in the 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 no later than 90 days after the start of the Unit 2 refueling outage currently scheduled for March 2006.
FOR THE NUCLEAR REGULATORY COMMISSION
/RA/
Gene Y. Suh, 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: March 15, 2005
ATTACHMENT TO LICENSE AMENDMENT NOS. 224 AND 219 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 Pages Insert Pages 3.3.6.1-5 3.3.6.1-5 3.3.7.1-4 3.3.7.1-4
SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 224 TO FACILITY OPERATING LICENSE NO. DPR-29 AND AMENDMENT NO. 219 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 application dated June 10, 2004 (ML041740701), as supplemented by letters dated July 19 (ML042180210) and July 21, 2004 (ML042170075), and January 21, 2005 (ML050390330),
Exelon Generation Company, LLC (the licensee), requested changes to the Technical Specifications (TSs) for the Quad Cities Nuclear Power Station, Units 1 and 2 (QCNPS). The supplements dated July 19 and July 21, 2004, and January 21, 2005, provided additional information that clarified the application, did not expand the scope of the application as originally noticed, and did not change the staffs original proposed no significant hazards consideration determination as published in the Federal Register on August 31, 2004 (69 FR 53107).
The licensee is replacing the Main Steam Line (MSL) Flow-High differential pressure indicating switches, which initiate the isolation of the Group 1 Primary Containment Isolation System (PCIS) and the Control Room Emergency Ventilation (CREV) System isolation, with differential pressure transmitters, trip units, and interposing relays during the upcoming Unit 1 refueling outage in March 2005. Each differential pressure transmitter utilizes an analog trip unit (ATU) consisting of a master trip unit and an auxiliary relay. ATUs use a proven technology that is more reliable than the existing differential pressure indicating switches.
The proposed changes would revise the Surveillance Requirements (SRs) and the allowable value (AV) for the MSL Flow-High initiation of Group 1 PCIS and CREV System isolation.
Specifically, the proposed changes would revise the MSL Flow-High SRs to calibrate the ATUs every 92 days and revise the AV specified in TS Table 3.3.6.1-1, "Primary Containment Isolation Instrumentation," and Table 3.3.7.1-1, "Control Room Emergency Ventilation (CREV)
System Isolation Instrumentation," to reflect the changes in instrumentation. The proposed changes would add SR 3.3.6.1.3 for Function 1.d of Table 3.3.6.1-1 and SR 3.3.7.1.3 for Function 3 of Table 3.3.7.1-1. In addition, the proposed changes would revise the AV from
"< 254.3 psid" to "< 248.1 psid."
2.0 REGULATORY EVALUATION
The regulatory requirements for which the NRC staff based its acceptance are set forth in Title 10 of the Code of Federal Regulations (10 CFR), Part 50.36, "Technical Specifications." This regulation requires that the TSs will include items in the following categories: (1) Safety limits, limiting safety system settings, and limiting control settings, (2) Limiting conditions for operation, (3) Surveillance requirements, (4) Design features, and (5) Administrative controls. In particular, 10 CFR 50.36(c)(1)(ii)(A) specifies, among other things, that "where a limiting safety system setting is specified for a variable on which a safety limit has been placed, the setting must be so chosen that automatic protective action will correct the abnormal situation before a safety limit is exceeded." Accordingly, limits for instrument channels that initiate protective functions must be included in the TSs.
3.0 TECHNICAL EVALUATION
3.1 Background
The licensee provided background information for MSL Flow-High PCIS Instrumentation, including the following :
The primary containment isolation instrumentation automatically initiates closure of appropriate primary containment isolation valves (PCIVs). The isolation instrumentation includes the sensors, relays, and switches that are necessary to cause initiation of primary containment and reactor coolant pressure boundary isolation. Instrument channels include electronic equipment (e.g., trip units) that compares measured input signals with pre-established setpoints. When the setpoint is exceeded, the channel output relay actuates, which then outputs a primary containment isolation signal to the isolation logic. Monitoring a wide range of independent parameters provides functional diversity. MSL flow is one of several input parameters to the isolation logics.
Redundant sensor input signals from each parameter are provided for initiation of the isolation signal...
...The MSL flow signals are initiated from 16 differential pressure switches that are connected to the four MSLs (the switches sense differential pressure across a flow restrictor). The differential pressure switches are arranged such that, although physically separated, any of the four switches in a MSL would be able to detect the high flow condition. Four channels of MSL Flow-High Function for each MSL (two channels per trip system) are available in a one-out-of-two twice logic arrangement in each steam line, and are required to be operable so that no single instrument failure will preclude detecting a break in any individual MSL.
The CREV System is designed to provide a radiologically controlled environment to ensure the habitability of the control room for the safety of control room operators under all plant conditions. The instrumentation and controls for the CREV system automatically isolate the control room emergency zone to minimize the consequences of radioactive material in the control room environment. In the event of a MSL Flow-High signal, the control room is automatically isolated. The MSL Flow-High Function uses 16 channels, four for each MSL. One channel from each MSL provides input to one of the four trip strings. Two trip strings make up each trip system and both trip systems must trip to isolate the control room. The channels include electronic equipment (e.g., trip units) that compares measured input signals with pre-established setpoints. When the setpoint is exceeded, the channel output relay actuates, which then outputs a CREV System isolation signal to the initiation logic...
...High MSL flow could indicate a break in the MSL and will automatically initiate the isolation of the control room emergency zone, since this could be a precursor to a potential radiation release and subsequent radiation exposure to control room personnel. Therefore, the AV was chosen to be the same as that for the Primary Containment Isolation MSL Flow-High (i.e., Limiting Condition for Operation (LCO) 3.3.6.1, "Primary Containment Isolation Instrumentation").
3.1 Changes to Allowable Value The licensee provided the following evaluation for revising the AV from "< 254.3 psid" to
"< 248.1 psid" for the MSL Flow-High function:
The proposed change also revises the AV for the MSL Flow-High function in TS Sections 3.3.6.1 and 3.3.7.1. The revised TS AV is "< 248.1 psid." The Analytical Limit (AL) remains unchanged at 140% flow, or 292.45 psid. These proposed TS setpoint changes are based on NRC-approved Topical Reports and/or calculation methodologies. Reference 7 [NES-EIC-20.04, "Analysis of Instrument Channel Setpoint Error and Instrument Loop Accuracy"] describes the EGC setpoint methodology used for determining the revised AV. The NRC reviewed this methodology in Reference 8 [Letter from R. M. Krich (Commonwealth Edison Company) to U.S. NRC, "Request for Technical Specifications Changes for Dresden Nuclear Power Station, Units 1 and 2, LaSalle County Station, Units 1 and 2, and Quad Cities Nuclear Power Station, Units 1 and 2, to Implement Improved Statndard Technical Specifications," dated March 3, 2000], and approved its use in the Safety Evaluation in Reference 9 [Letter from U. S.
NRC to O.D. Kingsley (Exelon Generation Company), "Issuance of Amendments," dated March 30, 2001].
Installation of the upgraded equipment requires the revision of the AV for the MSL Flow-High Function in TS Sections 3.3.6.1 and 3.3.7.1. The setpoint methodology determines the uncertainties of instruments, instrument loops, and instrument setpoints and applies these uncertainties to the determination of instrument loop accuracies, allowable values, and calculated setpoints. This methodology is consistent with Instrument Society of America (ISA)
RP67.04-2000, Part 2, Method 3 to establish the setpoint AVs. The NRC staff has determined that AVs computed in accordance with ISA Method 3 do not provide adequate assurance that the safety analysis limits will not be exceeded. The NRC staff, therefore, did not evaluate the licensee's proposed revision of the AV.
However, the NRC staff determined that an entirely different approach, based on the performance of an instrument channel rather than directly on the measured trip setting, can provide the required assurance. This alternative "performance-based" approach sets limits on acceptable nominal setpoints and on the observed deviation in the measured setpoint from the end of one test to the beginning of the next.
In its supplemental letter dated January 21, 2005, the licensee proposed to modify its change to the AV with a performance-based approach by adding a note (c) to TS Tables 3.3.6.1-1 and 3.3.7.1-1 regarding as-left trip setpoints for the specified instruments. The note states that the applicable Function "is OPERABLE with an actual Trip Setpoint value found outside its calibration tolerance band provided the Trip Setpoint value is conservative with respect to its associated Allowable Value and the channel is re-adjusted to within the established setting tolerance band of the Nominal Trip Setpoint." The methodology establishes a setting tolerance for all TS setpoints. The setting tolerance is the uncertainty of the calibration procedure allowances used by the technician in the calibration process and is a tighter band around the trip setpoint than the AV range. Plant programs ensure that instrument channels and calibrated setpoints will not be left outside the specific setting tolerance. This practice resets the as-left trip setpoint within the calculated setting tolerance and near the trip setpoint value. On this basis, the revised AV of "< 248.1 psid" plus the addition of note (c) to the TSs proposed by the licensee provides reasonable assurance that the limiting safety system setting will provide the automatic protective action (i.e., closure of appropriate PCIVs) and, therefore, is acceptable to the NRC staff.
Compliance with 10 CFR 50.36 requires applications for TSs to include a summary statement of the bases or reasons for the TSs. In its supplemental letter dated January 21, 2005, which, as noted above, proposed adding note (c) to TS Tables 3.3.6.1-1 and 3.3.7.1-1, the licensee did not provide a summary statement of the bases for note (c). Consistent with its Bases Control Program, the licensee shall update their TS Bases accordingly.
3.2 Addition of Surveillance Requirements for Trip Unit Calibration Every 92 Days The licensee proposed to add a SR for the trip unit calibration requirement in Function 1.d of Table 3.3.6.1-1 and in Function 3 of Table 3.3.7.1-1 to accommodate the design change. The proposed SRs for calibration are consistent with NRC-approved testing recommendations for TS actuation instrumentation. In the early 1980s, General Electric (GE) and the Boiling Water Reactor Owners Group started a program to evaluate testing requirements. The program resulted in a series of GE topical reports that provide the bases for a quarterly test interval. The proposed 92-day surveillance for the MSL Flow-High trip units is consistent with GE topical report NEDC-31677P-A, "Technical Specification Improvement Analysis for BWR Isolation Actuation Instrumentation," which was approved by the NRC in a safety evaluation dated June 18, 1990. In addition, GE topical report NEDC-30851P-A, "Technical Specification Improvement Analyses for BWR Reactor Protection System," approved by the NRC on July 15, 1987, specifically discusses the calibration intervals for trip units and concludes that a "3 month calibration interval for analog trip units can be supported by current information." The proposed test interval is also consistent with other Quad Cities TS trip functions that currently employ trip unit devices. Therefore, the proposed SRs 3.3.6.1.3 and 3.3.7.1.3 are acceptable for calibrating the MSL Flow-High trip units every 92 days.
The staff has concluded, based on the considerations discussed above, that the licensees proposed changes are in accordance with 10 CFR 50.36 and are therefore acceptable.
4.0 STATE CONSULTATION
In accordance with the Commission's 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 a requirement 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 (69 FR 53107). 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. Rhow, NRR/DE/EEIB Date: March 15, 2005
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 - Nuclear Services Exelon Generation Company, LLC 4300 Winfield Road Warrenville, IL 60555 Vice President of Operations - Mid-West Boiling Water Reactor 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 Associate General Counsel Exelon Generation Company, LLC 4300 Winfield Road Warrenville, IL 60555 Manager Licensing - Dresden, Quad Cities and Clinton Exelon Generation Company, LLC 4300 Winfield Road Warrenville, IL 60555