ML13168A076
| ML13168A076 | |
| Person / Time | |
|---|---|
| Site: | Catawba  |
| Issue date: | 07/16/2013 |
| From: | Jason Paige Plant Licensing Branch II |
| To: | Capps S Duke Energy Carolinas |
| Paige J NRR/DORL/LPL2-1 | |
| References | |
| TAC MF0620, TAC MF0621, TAC MF0626, TAC MF0627 | |
| Download: ML13168A076 (22) | |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 July 16, 2013 Mr. Steven D. Capps Vice President McGuire Nuclear Station Duke Energy Carolinas, LLC 12700 Hagers Ferry Road Huntersville, NC 28078 SUB,JECT:
CATAWBA NUCLEAR STATION, UNITS 1 AND 2 AND MCGUIRE NUCLEAR STATION, UNITS 1 AND 2 - ISSUANCE OF AMENDMENTS REGARDING CHANGES TO TECHNICAL SPECIFICATION (TS) 3.6.14, "DIVIDER BARRIER INTEGRITY" (TAC NOS. MF0620, MF0621, MF0626 AND MF0627)
Dear Mr. Capps:
The Nuclear Regulatory Commission has issued the enclosed Amendment No. 270 to Renewed Facility Operating License NPF-35 and Amendment No. 266 to Renewed Facility Operating License NPF-52 for the Catawba Nuclear Station, Units 1 and 2, respectively, and Amendment No. 270 to Renewed Facility Operating License NPF-9 and Amendment No. 250 to Renewed Facility Operating License NPF-17 for the McGuire Nuclear Station, Units 1 and 2, respectively. The amendments consist of changes to the TSs in response to your application dated December 5, 2011. The amendments revise the divider barrier seal test coupons' tensile strength in Technical Specification Surveillance Requirement 3.6.14.4 from "> 39.7 psi" to
"> 39.7Ibs."
A copy of the related Safety Evaluation is also enclosed. A Notice of Issuance will be included in the Commission's biweekly Federal Register notice.
...)Isol"o'""n-c-.~P£Manager Plant Licensing Branch 11-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-413,50-414,50-369, and 50-370
Enclosures:
- 1. Amendment No. 270 to NPF-35
- 2. Amendment No. 266 to NPF-52
- 3. Amendment No. 270 to NPF-9
- 4. Amendment No. 250 to NPF-17
- 5. Safety Evaluation cc w/encls: Distribution via Listserv
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 DUKE ENERGY CAROLINAS, LLC NORTH CAROLINA ELECTRIC MEMBERSHIP CORPORATION DOCKET NO. 50-413 CATAWBA NUCLEAR STATION, UNIT 1 AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment No. 270 Renewed License No. NPF-35
- 1.
The U. S. Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment to the Catawba Nuclear Station, Unit 1 (the facility) Renewed Facility Operating License No. NPF-35 filed by the Duke Energy Carolinas, LLC, acting for itself, and North Carolina Electric Membership Corporation (licensees), dated January 21 t 2013, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations as 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 set forth in 10 CFR Chapter I; 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
- 2.
Accordingly, the license is hereby amended by page changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Renewed Facility Operating License No. NPF-35 is hereby amended to read as follows:
(2)
Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 270
,which are attached hereto, are hereby incorporated into this renewed operating license. Duke Energy Carolinas, LLC, shall operate the facility in accordance with the Technical Specifications.
- 3.
This license amendment is effective as of its date of issuance and shall be implemented within 30 days of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION Robert J. Pascarelli, Chief Plant Licensing Branch 11-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
Attachment:
Changes to License No. NPF-35 and the Technical Specifications Date of Issuance: July 16, 2013
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555*0001 DUKE ENERGY CAROLINAS, LLC NORTH CAROLINA MUNICIPAL POWER AGENCY NO.1 PIEDMONT MUNICIPAL POWER AGENCY DOCKET NO. 50-414 CATAWBA NUCLEAR STATION, UNIT 2 AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment No. 266 Renewed License No. NPF-52
- 1.
The U. S. Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment to the Catawba Nuclear Station, Unit 2 (the facility) Renewed Facility Operating License No. NPF-52 filed by the Duke Energy Carolinas, LLC, acting for itself, North Carolina Municipal Power Agency No.1 and Piedmont Municipal Power Agency (licensees), dated January 21, 2013, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations as 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 set forth in 10 CFR Chapter I; 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 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
- 2.
Accordingly, the license is hereby amended by page changes to the Technical Specifications as indicated in the attachment to this license amendment, and Paragraph 2.C.(2) of Renewed Facility Operating License No. NPF-52 is hereby amended to read as follows:
(2)
Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 266,which are attached hereto, are hereby incorporated into this renewed operating license. Duke Energy Carolinas, LLC, shall operate the facility in accordance with the Technical Specifications.
- 3.
This license amendment is effective as of its date of issuance and shall be implemented within 30 days of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION Robert J. Pascarelli, Chief Plant Licensing Branch 11-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
Attachment:
Changes to License No. NPF-52 and the Technical Specifications Date of Issuance: July 16, 2013
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555"()001 DUKE ENERGY CAROLINAS, LLC DOCKET NO. 50-369 MCGUIRE NUCLEAR STATION, UNIT 1 AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment No. 270 Renewed License No. NPF-9
- 1.
The U.S. Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment to the McGuire Nuclear Station, Unit 1 (the facility), Renewed Facility Operating License No. NPF-9, filed by the Duke Energy Carolinas, LLC (licensee), dated January 21, 2013, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations as 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 set forth in 10 CFR Chapter I; 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
- 2.
Accordingly, the license is hereby amended by page changes to th~ Technical Specifications as indicated in the attachment to this license amendment, and Paragraph 2.C.(2) of Renewed Facility Operating License No. NPF-9 is hereby amended to read as follows:
(2)
Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 270,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 its date of issuance and shall be implemented within 30 days of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
~~
Robert J. Pascarelli, Chief Plant Licensing Branch 11-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
Attachment:
Changes to License No. NPF-9 and the Technical Specifications Date of Issuance: July 16, 2013
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 DUKE ENERGY CAROLINAS, LLC DOCKET NO. 50-370 MCGUIRE NUCLEAR STATION, UNIT 2 AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment No. 250 Renewed License No. NPF-17
- 1.
The U. S. Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment to the McGuire Nuclear Station, Unit 2 (the facility), Renewed Facility Operating License No. NPF-17, filed by the Duke Energy Carolinas, LLC (the licensee), dated January 21, 2013, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations as 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 set forth in 10 CFR Chapter I; 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
- 2.
Accordingly, the license is hereby amended by page changes to the Technical Specifications as indicated in the attachment to this license amendment, and Paragraph 2.C.(2) of Renewed Facility Operating License No. NPF-17 is hereby amended to read as follows:
(2)
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 its date of issuance and shall be implemented within 30 days of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION Robert J. Pascarelli, Chief Plant Licensing Branch 11-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
Attachment:
Changes to License No. NPF-17 and the Technical Specifications Date of Issuance:
July 16, 2013
ATTACHMENT TO LICENSE AMENDMENT NO. 270 RENEWED FACILITY OPERATING LICENSE NO. NPF-35 DOCKET NO. 50-413 AND LICENSE AMENDMENT NO. 266 RENEWED FACILITY OPERATING LICENSE NO. NPF-52 DOCKET NO. 50-414 Replace the following pages of the Renewed Facility Operating Licenses and the Appendix A Technical Specifications (TSs) with the attached revised pages. The revised pages are identified by amendment number and contain marginal lines indicating the areas of change.
Remove License Pages License Pages NPF-35, page 4 NPF-35, page 4 NPF-52, page 4 NPF-52, page 4 TS Pages TS Pages 3.6.14-3 3.6.14-3
(2)
Technical Specifications The TechnicaJ Soecificatlons contained In Appendix A, as revised through Amendment No. 270,which are attached hereto, are hereby incorporated into this renewed operating license. Duke Energy Carolinas, LLC shall operate the facility in accordance with the Technical Specifications.
(3)
Updated Final Safety Analysis Report The Updated Final Safety AnalYSis Report supplement submitted pursuant to 10 CFR 54.21(d}, as revised on December 16, 2002, describes certain future activities to be completed before the period of extended operation. Duke shall complete these activities no later than December 6, 2024, and shall notify the NRC in writing when implementation of these activities is complete and can be verified by NRC inspection.
The Updated Final Safety Analysis Report supplement as revised on December 16, 2002, described above. shall be included In the next scheduled update to the Updated Final Safety Analysis Report required by 10 CFR 50.71 (e}(4), following issuance of this renewed operating license. Until that update is complete, Duke may make changes to the programs described in such supplement without prior Commission approval, provided that Duke evaluates each such change pursuant to the criteria set forth in 10 CFR 50.59 and otherwise complies with the requirements in that section.
(4)
Antjtrust Conditions Duke Energy Carolinas. LLC shall comply with the antitrust conditions delineated in Appendix C to this renewed operating license.
(5)
Fire Protection Program (Section 9.5.1. SER, SSER #2. SSER #3. SSER #4.
SSER #5)*
Duke Energy Carolinas. LLC shall implement and maintain in effect all provisions of the approved fire protection program as described In the Updated Final Safety Analysis Report. as amended, for the facility and as approved in the SER through Supplement 5, subject to the following provision:
The licensee may make changes to the approved fire protection program without prior approval of the Commission only if those changes would not adversely affect the ability to achieve and maintain safe shutdown in the event of a fire.
- The parenthetical notation following the title of this renewed operating license condition denotes the section of the Safety Evaluation Report and/or its supplement wherein this renewed license condition is discussed.
Renewed License No. NPF*35 Amendment No. 270
-4 (2)
Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No* 26q,which are attached hereto, are hereby incorporated into this renewed operating license. Duke Energy Carolinas, LLC shall operate the facility in accordance with the Technical Specifications.
(3)
Updated Final Safety Analysis Report The Updated Final Safety Analysis Report supplement submitted pursuant to 10 CFR 54.21 (d), as revised on December 16,2002, describes certain future activities to be completed before the period of extended operation. Duke shall complete these activities no later than February 24,2026, and shall notify the NRC in writing when implementation of these activities is complete and can be verified by NRC inspection.
The Updated Final Safety Analysis Report supplement as revised on December 16. 2002, described above, shall be included in the next scheduled update to the Updated Final Safety Analysis Report required by 10 CFR 50.71 (e)(4). following issuance of this renewed operating license. Until that update is complete. Duke may make changes to the programs described in such supplement without prior Commission approval, provided that Duke evaluates each such change pursuant to the criteria set forth in 10 CFR 50.59 and otherwise complies with the reqUirements In that section.
(4)
Antitrust Conditions Duke Energy Carolinas, LLC shall comply with the antitrust conditions delineated in Appendix C to this renewed operating license.
(5)
Fire Protection Prog ram (Section 9.5.1. SER. SSER #2. SSER #3, SSER #4, SSER #5)*
Duke Energy Carolinas. LLC shall implement and maintain in effect all provisions of the approved fire protection program as described in the Updated Final Safety Analysis Report. as amended. for the facility and as approved In the SER through Supplement 5, subject to the following provision:
The licensee may make changes to the approved fire protection program without prior approval of the Commission only if those changes would not adversely affect the ability to achieve and maintain safe shutdown in the event of a fire.
- The parenthetical notation following the title of this renewed operating license condition denotes the section of the Safety Evaluation Report and/or Its supplements wherein this renewed license condition is discussed.
Renewed License No. NPF....52 Amendment No. 266
Divider Barrier Integrity 3.6.14 SURVEILLANCE FREQUENCY SR 3.6.14.4 Remove two divider barrier seal test coupons and verify both test coupons' tensile strength is.?:: 39.7 Ibs.
In accordance with the Surveillance Frequency Control Program SR 3.6.14.5 Visually inspect.?:: 95% of the divider barrier seal length, and verify:
- a.
Seal and seal mounting bolts are properly installed; and
- b.
Seal material shows no evidence of deterioration In accordance with the Surveillance Frequency Control Program due to holes, ruptures, chemical attack, abrasion, radiation damage, or changes in physical appearance.
Catawba Units 1 and 2 3.6.14-3 Amendment Nos. 270 and 266
ATTACHMENT TO LICENSE AMENDMENT NO. 270 RENEWED FACILITY OPERATING LICENSE NO.
AND NPF-9 DOCKET NO. 50-369 LICENSE AMENDMENT NO. 250 RENEWED FACILITY OPERATING LICENSE NO. NPF-17 DOCKET NO. 50-370 Replace the following pages of the Renewed Facility Operating Licenses and the Appendix A Technical Specifications (TSs) with the attached revised pages. The revised pages are identified by amendment number and contain marginal lines indicating the areas of change.
Remove License Pages License Pages NPF-9, page 3 NPF-9, page 3 NPF-17, page 3 NPF-17, page 3 TS Pages TS Pages 3.6.14-2 3.6.14-2
-3 (4)
Pursuant to the Act and 10 CFR Parts 30, 40 and 70, to receive, possess and use in amounts as required any byproduct, source or special nuclear material without restriction to chemical or physical form, for sample analysis or instrument calibration or associated with radioactive apparatus or components; (5) Pursuant to the Act and 10 CFR Parts 30, 40 and 70. to possess, but not separate, such byproducts and special nuclear materials as may be produced by the operation of McGuire Nuclear Station. Units 1 and 2, and; (6)
Pursuant to the Act and 10 CFR Parts 30 and 40, to receive, possess and process for release or transfer such byproduct material as may be produced by the Duke Training and Technology Center.
C. This renewed operating license shall be deemed to contain and is subject to the conditions specified in the Commission's 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 or hereafter in effect; and is subject to the additional conditions specified or incorporated below:
(1) Maximum Power Level The licensee is authorized to operate the facility at a reactor core full steady state power level of 3469 megawatts thermal (100%).
(2) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 270, are hereby incorporated into this renewed operating license. The licensee shall operate the facility in accordance with the Technical Specifications.
(3) Updated Final Safety Analysis Report The Updated Final Safety Analysis Report supplement submitted pursuant to 10 CFR 54.21 (d). as revised on December 16.2002, describes certain future activities to be completed before the period of extended operation.
Duke shall complete these activities no later than June 12, 2021, and shall notify the NRC in writing when implementation of these activities is complete and can be verified by NRC inspection.
The Updated Final Safety Analysis Report supplement as revised on December 16,2002. described above, shall be included in the next scheduled update to the Updated Final Safety Analysis Report required by 10 CFR 50.71(e)(4), following issuance of this renewed operating license.
Until that update is complete, Duke may make changes to the programs described in such supplement without prior Commission approval, provided that Duke evaluates each such change pursuant to the criteria set forth in 10 CFR 50.59 and otherwise complies with the requirements in that section.
Renewed License No. NPF-9 Amendment No. 270
- 3 (4)
Pursuant to the Act and 10 CFR Parts 30, 40 and 70, to receive, possess and use in amounts as required any byproduct, source or special nuclear material without restriction to chemical or physical form, for sample analysis or instrument calibration or associated with radioactive apparatus or components; (5) Pursuant to the Act and 10 CFR Parts 30, 40 and 70, to possess, but not separate, such byproducts and special nuclear materials as may be produced by the operation of McGuire Nuclear Station, Units 1 and 2; and, (6) Pursuant to the Act and 10 CFR Parts 30 and 40, to receive, possess and process for release or transfer such byproduct material as may be produced by the Duke Training and Technology Center.
C. This renewed operating license shall be deemed to contain and is subject to the conditions specified in the Commission's 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 or hereafter in effect; and is subject to the additional conditions specified or incorporated below:
(1) Maximum Power Level The licensee is authorized to operate the facility at a reactor core full steady state power level of 3469 megawatts thermal (100%).
(2) 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)
Updated Final Safety Analysis Report The Updated Final Safety Analysis Report supplement submitted pursuant to 10 CFR 54.21(d), as revised on December 16, 2002, describes certain future activities to be completed before the period of extended operation.
Duke shall complete these activities no later than March 3, 2023. and shall notify the NRC in writing when implementation of these activities is complete and can be verified by NRC inspection.
The Updated Final Safety Analysis Report supplement as revised on December 16,2002, described above, shall be included in the next scheduled update to the Updated Final Safety Analysis Report required by 10 CFR 50.71 (e)(4), following issuance of this renewed operating license.
Until that update is complete, Duke may make changes to the programs described in such supplement without prior Commission approval, provided that Duke evaluates each such change pursuant to the criteria set forth in 10 CFR 50.59, and otherwise complies with the requirements in that section.
Renewed License No. NPF-17 Amendment No. 250
Divider Barrier Integrity 3.6.14 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.14.1 Verify, by visual inspection, all personnel access doors and equipment hatches between upper and lower containment compartments are closed.
Prior to entering MODE 4 from
. MODE 5 SR 3.6.14.2 Verify, by visual inspection, that the seals and sealing surfaces of each personnel access door and equipment hatch have:
Prior to final closure after each opening
- a.
No detrimental misalignments; AND
- b.
- c.
No cracks or defects in the sealing surfaces; and No apparent deterioration of the seal material.
NOTE-------
Only required for seals made of resilient materials In accordance with the Surveillance Frequency Control Program SR 3.6.14.3 Verify, by visual inspection, each personnel access door or equipment hatch that has been opened for personnel transit entry is closed.
After each opening SR 3.6.14.4 Remove two divider barrier seal test coupons and verify In accordance with both test coupons' tensile strength is ~ 39.7 Ibs.
the Surveillance Frequency Control I Program (continued)
McGuire Units 1 and 2 3.6.14-2 Amendment No. 270 and 250
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 270 TO RENEWED FACILITY OPERATING LICENSE NPF-35 AMENDMENT NO. 266 TO RENEWED FACILITY OPERATING LICENSE NPF-52 AMENDMENT NO. 270 TO RENEWED FACILITY OPERATING LICENSE NPF-9 AND AMENDMENT NO. 250 TO RENEWED FACILITY OPERATING LICENSE NPF-17 DUKE ENERGY CAROLINAS, LLC CATAWBA NUCLEAR STATION, UNITS 1 AND 2 MCGUIRE NUCLEAR STATION, UNITS 1 AND 2 DOCKET NOS. 50-413, 50-414, 50-369, AND 50-370
1.0 INTRODUCTION
By application dated January 21. 2013 (Agencywide Documents Access and Management System (ADAMS) Accession Nos. ML13032A033), Duke Energy Carolinas, LLC (Duke Energy.
the licensee), requested changes to the Technical Specifications (TSs) for Catawba Nuclear Station (Catawba), Units 1 and 2. and McGuire Nuclear Station (McGuire). Units 1 and 2.
The proposed amendments would revise one of the surveillance requirements (SRs) in TS 3.6.14. "Divider Barrier Integrity." Specifically, the amendments would modify the divider barrier seal test coupons' tensile strength in SR 3.6.14.4 from "~39.7 psi" to"~ 39.7Ibs." The licensee stated that the change would correct an error where the wrong units were used when Catawba and McGuire converted to Standard Technical Specifications (STS) in 1998 using NUREG-1431. Revision 1.
2.0 REGULATORY EVALUATION
2.1 Regulatory Requirements In Section 50.36 of Title 10 of the Code of Federal Regulations (10 CFR), the NRC established its regulatory requirements related to the content of TSs. Pursuant to 10 CFR 50.36, TSs are required to include items in the following five specific categories: (1) safety limits, limiting safety system settings, and limiting control settings; (2) limiting conditions for operation (LCOs);
- 2 (3) SRs; (4) design features; and (5) administrative controls. The regulation does not specify the particular requirements to be included in a plant's TSs.
As discussed in 10 CFR 50.36(c)(2), LCOs are the lowest functional capability or performance level of equipment required for safe operation of the facility. When LCOs are not met, the licensee shall shut down the reactor or follow any remedial action permitted by the TSs until the LCO can be met.
As discussed in 10 CFR 50.36(c)(3), SRs are requirements relating to test, calibration, or inspection to assure that the necessary quality of systems and components is maintained, that facility operation will be within safety limits, and that the LCOs will be met.
2.2 Equipment Description The licensee's application dated January 21, 2013, provided the following description of the equipment associated with the proposed amendment:
The divider barrier consists of the operating deck and associated seals, personnel access doors, and equipment hatches that separate the upper and lower containment compartments. Divider barrier integrity is necessary to minimize bypassing of the ice condenser by the hot steam and air mixture released into the lower compartment during a DeSign Basis Accident (DBA).
This ensures that most of the gases pass through the ice bed, which condenses the steam and limits pressure and temperature during the accident transient.
Limiting the pressure and temperature reduces the release of fission product radioactivity from containment to the environment in the event of a DBA.
As discussed in Section 3.8.3.1.17 of the Catawba Updated Final Safety Analysis Report (UFSAR) and Section 3.8.3.1 of the McGuire UFSAR, pressure seals are provided at all locations where it is necessary to limit or eliminate bypass leakage during a loss-of-coolant accident (LOCA). The seals are required to remain functional to ensure that the maximum permissible bypass leakage area, between the upper and lower compartments, is not exceeded.
Test coupons located in the vicinity of the seals are used to determine the degree of degradation of the material due to normal operating conditions. The seals would be replaced if the test coupon results indicate a significant change in the material properties (e.g., tensile strength).
3.0 TECHNICAL EVALUATION
Catawba and McGuire LCO 3.6.14 require that divider barrier integrity shall be maintained in Modes 1, 2, 3, and 4. This LCO ensures that the divider barrier performs its safety function of ensuring that bypass leakage, in the event of a DBA, does not exceed the bypass leakage assumed in the accident analysis.
-3 Catawba and McGuire SR 3.6.14.4 currently reads:
Remove two divider barrier seal test coupons and verify both test coupons' tensile strength is ;::: 39.7 psi.
Conducting periodic physical property tests on divider barrier seal test coupons provides assurance that the seal material has not degraded in the containment environment, including the effects of irradiation with the reactor at power.
As discussed in Safety Evaluation (SE) Section 1.0, the proposed amendments would modify the divider barrier seal test coupons' tensile strength in SR 3.6.14.4 from ";::: 39.7 psi" to
";::: 39.7 Ibs." Prior to the STS conversion for Catawba and McGuire in 1998, the tensile strength units for SR 3.6.14.4 were in pounds (Ibs). However, the conversion inadvertently used the NUREG-1431, Revision 1, units of pounds per square inch (psi).
As discussed in the application dated January 21,2013, the Catawba and McGuire divider barrier seals are manufactured by the Presray Corporation. According to Presray's technical document for recommended rubber seal replacement schedule, the tests on the membrane type coupons shall be done in accordance with American Society for Testing and Materials (ASTM) standard D751, "Standard Test Methods for Coated Fabrics." The licensee stated that, according to this technical document, the minimum acceptable tensile strength for this membrane seal type is 39.7 Ibs based on hoop stress. The licensee further stated that the ASTM 0751 breaking strength test, Procedure B (Cut Strip Test Method), specifies the standard size for the test coupons to be one inch wide strips, therefore the allowable tensile strength is in units of Ibs instead of psi.
The NRC staff finds that the proposed change aligns the surveillance requirement with the manufacturer's recommendations and ASTM testing specifications. As such. the proposed change provides testing requirements that provide reasonable assurance that the necessary quality of the seals will be maintained. On this basis, the NRC staff concludes that the proposed amendments are consistent with the requirements in 10 CFR 50.36(c)(3), and, therefore. are acceptable.
4.0 STATE CONSULTATION
In accordance with the Commission's regulations, the North Carolina and South Carolina State officials were notified of the proposed issuance of the amendments. The State officials had no comments.
5.0 ENVIRONMENTAL CONSIDERATION
The amendments change a requirement with respect to the installation or use of facility components 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
- 4 significant hazards consideration, and there has been no public comment on such finding (78 FR 28251). 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) there is reasonable assurance that 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 Contributors:
J. Kim, NRR R. Ennis, NRR Date: July 16, 2013
July 16, 2013 Mr. Steven D. Capps Vice President McGuire Nuclear Station Duke Energy Carolinas, LLC 12700 Hagers Ferry Road Huntersville, NC 28078
SUBJECT:
CATAWBA NUCLEAR STATION, UNITS 1 AND 2 AND MCGUIRE NUCLEAR STATION, UNITS 1 AND 2 -ISSUANCE OF AMENDMENTS REGARDING CHANGES TO TECHNICAL SPECIFICATION (TS) 3.6.14, "DIVIDER BARRIER INTEGRITY" (TAC NOS. MF0620, MF0621, MF0626 AND MF0627)
Dear Mr. Capps:
The Nuclear Regulatory Commission has issued the enclosed Amendment No. 270 to Renewed Facility Operating License NPF-35 and Amendment No.266 to Renewed Facility Operating License NPF-52 for the Catawba Nuclear Station, Units 1 and 2, respectively, and Amendment No. 270 to Renewed Facility Operating License NPF-9 and Amendment No. 250 to Renewed Facility Operating License NPF-17 for the McGuire Nuclear Station, Units 1 and 2, respectively. The amendments consist of changes to the TSs in response to your application dated December 5, 2011. The amendments revise the divider barrier seal test coupons' tensile strength in Technical Specification Surveillance Requirement 3.6.14.4 from "> 39.7 psi" to
"> 39.7Ibs."
A copy of the related Safety Evaluation is also enclosed. A Notice of Issuance will be included in the Commission's biweekly Federal Register notice.
Sincerely, IRA!
Jason C. Paige, Project Manager Plant licenSing Branch 11-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-413,50-414, 50-369, and 50-370
Enclosures:
- 1. Amendment No. 270 to NPF-35
- 2. Amendment No. 266 to NPF-52
- 3. Amendment No. 270 to NPF-9
- 4. Amendment No. 250 to NPF-17
- 5. Safety Evaluation cc w/encls: Distribution via Listserv DISTRIBUTION:
PUBLIC LPL2-1 R/F RidsAcrsAcnw_MailCTR Resource RidsNrrDssStsb Resource RidsNrrDorlLpl2-1 Resource RidsNrrDorlDpr Resource RidsNrrLASFigueroa Resource RidsNrrDssScvb Resource RidsRgn2MailCenter Resource RidsOgcMailCenter Resource RidsNrrPMCatawba-Resource (hard copy)
ADAMS Accession No.: ML13168A076 OFFICE 1LPL2-11 PM LPL2-1/LA DSS/SCVB/BC DSS/STSBI BC OGC - NLO ILPL2-1/BC LPL2-1/PM NAME iJKim SFigueroa RDennig RElliott SUUal IRPascarelli JPaige DATE
- 06/21/13 06119113 06/24/13 06/25/13 07/01/13 107/16/13 07116113 OFFICIAL RECORD COpy