ML15106A947
| ML15106A947 | |
| Person / Time | |
|---|---|
| Site: | Quad Cities  |
| Issue date: | 04/24/2015 |
| From: | Mozafari B Plant Licensing Branch III |
| To: | Bryan Hanson Exelon Generation Co, Exelon Nuclear |
| Mozafari B, DORL/LPLIII-2, 415-2020 | |
| References | |
| TAC MF4589, TAC MF4590 | |
| Download: ML15106A947 (13) | |
Text
Mr. Bryan C. Hanson Senior Vice President UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 April 24, 2015 Exelon Generation Company, LLC President and Chief Nuclear Officer (CNO)
Exelon Nuclear 4300 Winfield Road Warrenville, IL 60555
SUBJECT:
QUAD CITIES NUCLEAR POWER STATION, UNITS 1 AND 2 - CORRECTION TO AMENDMENTS REGARDING BATTERY SURVEILLANCE REQUIREMENTS (TAC NOS. MF4589 AND MF4590)
Dear Mr. Hanson:
On March 30, 2015, the U.S. Nuclear Regulatory Commission (NRC) issued amendments to Renewed Facility Operating License Nos. DPR-29 and DPR-30 in response to the application by Exelon Generation Company, LLC (the licensee) dated June 10, 2013, (Agencywide Documents Access and Management System (ADAMS) Accession No. ML13161A315). The licensee provided supplemental information in letters dated October 24, 2013, March 5, 2014, December 4, 2014, and February 4, 2015 (ADAMS Accession Nos. ML13297A266, ML14064A527, ML14338A176, and ML15035A266, respectively). The amendments for Quad Cities Nuciear Power Station (QCNPS), Units 1 and 2, revised the technical specifications and surveillance requirements 3.8.4.2 and 3.8.4.5 to add new acceptance criteria for total battery connection resistance. The December 4, 2014. reference was inadvertently omitted from the cover letter, safety evaluation, and both license pages.
After issuance it came to our attention that the amendment numbers 256 and 251 were incorrect for Renewed Facility Operating License Nos. DPR-29 and DPR-30, respectively. In addition, editorial errors were made on page 4 of the license pages of Renewed Facility Operating License Nos. DPR-29 and DPR-30. The enclosed license pages 1 and 2 for both DPR-29 and DPR-30 and title of page 1 of Enclosure 3 provide the corrected amendment numbers of 255 and 250. Inadvertent typographical errors on license and amendment pages are specifically described below:
In Paragraph 2 of the amendment page for Unit 1, "3. B" was inadvertently changed to "2.C.(2)"
Paragraph "B" of the amendment for Unit 1 was inadvertently changed to "(2)."
Paragraph 3 for both amendments indicated an implementation date of within 30 days.
The licensee's amendment request was to implement within 90 days. The implementation period does not change the effective date of the amendment.
In Paragraph E, page 4 of both licenses, "50.90 and" was inadvertently changed to "50.59 ad." This was a typographical error.
Paragraph F of both licenses, two lines at the bottom of page 4 were inadvertently omitted.
Please replace the pages with the enclosed correct pages. If you have any questions, please call me at (301) 415-2020. Thank you for bringing this matter to our attention. We regret any inconvenience this may have caused.
Docket Nos. 50-254 and 50-265
Enclosures:
f Sincerely,
/l&;;f#
Brenda L. Mozafari, Senior Project Manager Plant Licensing 111-2 and Planning and Analysis Branch Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
- 1. Corrected pages for Amendment No. 255 to DPR-29
- 2. Corrected pages for Amendment No. 250 to DPR-30
- 3. Corrected page for Safety Evaluation cc w/encls: Distribution via Listserv
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 EXELON GENERATION COMPANY, LLC AND MIDAMERICAN ENERGY COMPANY DOCKET NO. 50-254 QUAD CITIES NUCLEAR POWER STATION, UNIT 1 AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment No. 255 Renewed License No. DPR-29
- 1.
The U.S. Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Exelon Generatoin Company, LLS (the licensee) dated June10, 2013, as supplemented by letters October 24, 2013, March 5, 2014, December 4, 2014, and February 4, 2015, 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 1 O 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 Renewed 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. 255, are hereby incorporated into this renewed 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 within 90 days of the date of issuance.
Attachment:
Changes to the Technical FOR THE NUCLEAR REGULA TORY COMMISSION Travis L. Tate, Chief Plant Licensing 111-2 and Planning and Analysis Branch Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Specifications and Renewed Facility Operating License Date of Issuance: March 30, 2015
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 EXELON GENERATION COMPANY, LLC AND MIDAMERICAN ENERGY COMPANY DOCKET NO. 50-265 QUAD CITIES NUCLEAR POWER STATION, UNIT 2 AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment No. 250 Renewed License No. DPR-30
- 1.
The U.S. Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by the Exelon Generation Company, LLC (the licensee) dated June 10, 2013, as supplemented by letters October 24, 2013, March 5, 2014, December 4, 2014, and February 4, 2015, 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 1 O 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 Renewed 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. 250, are hereby incorporated into this renewed 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 within 90 days of the date of issuance.
Attachment:
Changes to the Technical FOR THE NUCLEAR REGULATORY COMMISSION
~o(J;6 Travis L. Tate, Chief Plant Licensing 111-2 and Planning and Analysis Branch Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Specifications and Renewed Facility Operating License Date of Issuance: March 30, 2015
ATTACHMENT TO LICENSE AMENDMENT NOS. 255 AND 250 RENEWED FACILITY OPERATING LICENSE NOS. DPR-29 AND DPR-30 DOCKET NOS. 50-254 AND 50-265 Replace the following pages of the Renewed Facility Operating License and Appendix A Technical Specifications with the attached pages. The revised pages are identified by amendment number and contain marginal lines indicating the area of change.
Remove License DRP-29 Page4 License DPR-30 Page4 TSs Page 3.8.4-4 Page 3.8.4-5 License DPR-29 Page 4 License DPR-30 Page 4 TSs Page 3.8.4-4 Page 3.8.4-5 B.
Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 255, are hereby incorporated into this renewed operating license. The licensee shall operate the facility in accordance with the Technical Specifications.
C.
The licensee shall maintain the commitments made in response to the March 14, 1983, NUREG-0737 Order, subject to the following provision:
The licensee may make changes to commitments made in response to the March 14, 1983, NUREG-0737 Order without prior approval of the Commission as long as the change would be permitted without NRC approval, pursuant to the requirements of 10 CFR 50.59. Consistent with this regulation, if the change results in an Unreviewed Safety Question, a license amendment shall be submitted to the NRC staff for review and approval prior to implementation of the change.
D.
Equalizer Valve Restriction Three of the four valves in the equalizer piping between the recirculation loops shall be closed at all times during reactor operation with one bypass valve open to allow for thermal expansion of water.
E.
The licensee shall fully implement and maintain in effect all provisions of the Commission-approved physical security, training and qualification, and safeguards contingency plans including amendments made pursuant to provisions of the Miscellaneous Amendments and Search Requirements revisions to 10 CFR 73.55 (51 FR 27817 and 27822), and the authority of 1 O CFR 50.90 and 1 O CFR 50.54(p). The combined sets of plans 1, which contain Safeguards Information protected under 10 CFR 73.21, is entitled: "Quad Cities Nuclear Power Station Security Plan, Training and Qualification Plan, and Safeguards Contingency Plan, Revision 2," submitted by letter dated May 17, 2006.
Exelon Generation Company shall fully implement and maintain in effect all provisions of the Commission-approved cyber security plan (CSP), including changes made pursuant to the authority of 10 CFR 50.90 and 10 CFR 50.54(p).
The Exelon Generation Company CSP was approved by License Amendment No. 249.
F.
The licensee shall implement and maintain in effect all provisions of the approved fire protection program as described in the Updated Final Safety Analysis Report for the facility and as approved in the Safety Evaluation Reports dated July 27, 1979, with supplements dated November 5, 1980, and 1 The Training and Qualification Plan and Safeguards Contingency Plan are Appendices to the Security Plan.
Renewed License No. DPR-29 Amendment No. 255 B.
Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 250, are hereby incorporated into this renewed operating license. The licensee shall operate the facility in accordance with the Technical Specifications.
C.
The licensee shall maintain the commitments made in response to the March 14, 1983, NUREG-0737 Order, subject to the following provision:
The licensee may make changes to commitments made in response to the March 14, 1983, NUREG-0737 Order without prior approval of the Commission as long as the change would be permitted without NRC approval, pursuant to the requirements of 10 CFR 50.59. Consistent with this regulation, if the change results in an Unreviewed Safety Question, a license amendment shall be submitted to the NRC staff for review and approval prior to implementation of the change.
D.
Equalizer Valve Restriction Three of the four valves in the equalizer piping between the recirculation loops shall be closed at all times during reactor operation with one bypass valve open to allow for thermal expansion of water.
E.
The licensee shall fully implement and maintain in effect all provisions of the Commission-approved physical security, training and qualification, and safeguards contingency plans including amendments made pursuant to provisions of the Miscellaneous Amendments and Search Requirements revisions to 10 CFR 73.55 (51 FR 27817 and 27822), and the authority of 10 CFR 50.90 and 10 CFR 50.54(p). The combined sets of plans1, which contain Safeguards Information protected under 10 CFR 73.21, is entitled: "Quad Cities Nuclear Power Station Security Plan, Training and Qualification Plan, and Safeguards Contingency Plan, Revision 2," submitted by letter dated May 17, 2006.
Exelon Generation Company shall fully implement and maintain in effect all provisions of the Commission-approved cyber security plan (CSP), including changes made pursuant to the authority of 10 CFR 50.90 and 10 CFR 50.54(p).
The Exelon Generation Company CSP was approved by License Amendment No. 244.
F.
The licensee shall implement and maintain in effect all provisions of the approved fire protection program as described in the Updated Final Safety Analysis Report for the facility and as approved in the Safety Evaluation Reports dated July 27, 1979 with supplements dated 1 The Training and Qualification Plan and Safeguards Contingency Plan are Appendices to the Security Plan.
Renewed License No. DPR-30 Amendment No. 250
DC Sources-Operating 3.8.4 SURVEILLANCE REQUIREMENTS SR 3.8.4.l SR 3.8.4.2 SR 3.8.4.3 SR 3.8.4.4 SURVEILLANCE Verify battery terminal voltage on float charge is:
- a.
~ 260.4 VDC for each 250 VDC subsystem; and
- b.
~ 125.9 VDC for each 125 VDC subsystem.
Verify no visible corrosion at battery terminals and connectors.
Verify battery connection resistance is
~ l.5E-4 ohm for inter-cell connections and
~ l.5E-4 ohm for terminal connections.
Verify total battery connection resistance is:
- a.
~ 6.0E-3 ohm for each 250 VDC subsystem, and
- b.
~ 2.4E-3 ohm for each 125 VDC subsystem.
Verify battery cells, cell plates, and racks show no visual indication of physical damage or abnormal deterioration that could degrade battery performance.
Remove visible corrosion and verify battery eel l to eel l and terminal connections are coated with anti-corrosion material.
Quad Cities 1 and 2 3.8.4-4 FREQUENCY In accordance with the Surveillance Frequency Control Program In accordance with the Surveillance Frequency Control Program In accordance with the Surveillance Frequency Control Program In accordance with the Surveillance Frequency Control Program (continued)
Amendment No.'255,'25J I
DC Sources-Operating 3.8.4 SURVEILLANCE REQUIREMENTS SR 3.8.4.5 SR 3.8.4.6 SR 3.8.4.7 SURVEILLANCE Verify battery connection resistance is
~ 1.5E-4 ohm for inter-cell connections and
~ l.5E-4 ohm for terminal connections.
Verify total battery connection resistance is:
- a.
~ 6.0E-3 ohm for each 250 voe subsystem, and
- b.
~ 2.4E-3 ohm for each 125 VDC subsystem.
Verify each required battery charger supplies:
- a.
~ 250 amps at ~ 250 voe for ~ 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> for the 250 voe subsystems; and
- b.
~ 200 amps at ~ 125 voe for ~ 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> for the 125 voe subsystems.
- - - - - - - - - - - - - - - - - - - NOTE - - - - - - - - - - - - - - - - - - - -
The modified performance discharge test in SR 3.8.4.8 may be performed in lieu of the service test in SR 3.8.4.7 provided the modified performance discharge test completely envelopes the service test.
Verify battery capacity is adequate to supply, and maintain in OPERABLE status, the required emergency loads for the design duty cycle when subjected to a battery service test.
Quad Cities 1 and 2 3.8.4-5 FREQUENCY In accordance with the Surveillance Frequency Control Program In accordance with the Surveillance Frequency Control Program In accordance with the Surveillance Frequency Control Program (continued)
Amendment No. 255,2'.:D I
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 255 TO RENEWED FACILITY OPERATING LICENSE NO. DPR-29 AND AMENDMENT NO. 250 AND TO RENEWED FACILITY OPERATING LICENSE NO. DPR-30 EXELON GENERATION COMPANY. LLC AND MIDAMERICAN ENERGY COMPANY QUAD CITIES NUCLEAR POWER STATION. UNITS 1AND2 DOCKET NOS. 50-254 AND 50-265
1.0 INTRODUCTION
By application dated June 10, 2013, (Agencywide Documents Access and Management System (ADAMS) Accession No. ML13161A315), Exelon Generation Company, LLC (the licensee) requested an amendment to Renewed Facility Operating License Nos. DPR-29 and DPR-30 for Quad Cities Nuclear Power Station (QCNPS), Units 1 and 2, respectively. The proposed changes would revise QCNPS Technical Specification (TS) Surveillance Requirements (SRs) 3.8.4.2 and 3.8.4.5 by adding a requirement to verify the safety-related batteries' total battery connection resistances are within pre-established limits to ensure their intended design functions are met.
In response to the U.S. Nuclear Regulatory Commission (NRC, the Commission) staff's requests for additional information, the licensee provided supplemental information in letters dated October 24, 2013, March 5, 2014, December 4, 2014, and February 4, 2015 (ADAMS Accession Nos. ML13297A266, ML14064A527, ML14338A176, and ML15035A266, respectively).
2.0 REGULA TORY REQUIREMENTS The following NRC requirements and guidance documents are applicable to the NRC staff's review of the license amendment request (LAR).
Title 10 of the Code of Federal Regulations (10 CFR) Part 50, Appendix A, General Design Criterion (GDC) 17. "General Design Criteria for Nuclear Power Plants," requires, in part,
ML15106A947 OFFICE LPL3-2/PM LPL3-2/LA LPL3-2/BC LPL3-2/PM NAME BMozafari SRohrer TTate BMozafari DATE 04/23/2015 04/23/2015 04/24/2015 04/24/2015