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| number = ML082310646 | | number = ML082310646 | ||
| issue date = 09/08/2008 | | issue date = 09/08/2008 | ||
| title = | | title = Submittal of Issuance of Amendments Regarding (TAC Nos. MD6961 and MD6962) | ||
| author name = Stang J | | author name = Stang J | ||
| author affiliation = NRC/NRR/ADRO/DORL/LPLII-1 | | author affiliation = NRC/NRR/ADRO/DORL/LPLII-1 | ||
| addressee name = Morris J | | addressee name = Morris J | ||
| addressee affiliation = Duke Energy Carolinas, LLC | | addressee affiliation = Duke Energy Carolinas, LLC | ||
| docket = 05000413, 05000414 | | docket = 05000413, 05000414 | ||
| license number = NPF-035, NPF-052 | | license number = NPF-035, NPF-052 | ||
| contact person = Stang J | | contact person = Stang J, NRR/DORL, 415-1345 | ||
| case reference number = TAC MD6961, TAC MD6962 | | case reference number = TAC MD6961, TAC MD6962 | ||
| document type = Letter | | document type = Letter | ||
Line 18: | Line 18: | ||
=Text= | =Text= | ||
{{#Wiki_filter:September 8, 2008 | {{#Wiki_filter:September 8, 2008 Mr. J. R. Morris Site Vice President Catawba Nuclear Station Duke Energy Carolinas, LLC 4800 Concord Road York, SC 29745 | ||
Mr. J. R. Morris Site Vice President Catawba Nuclear Station Duke Energy Carolinas, LLC 4800 Concord Road York, SC | |||
==SUBJECT:== | ==SUBJECT:== | ||
CATAWBA NUCLEAR STATION, UNITS 1 AND 2 - ISSUANCE OF AMENDMENTS REGARDING SPECIFIC ISOLATION TIME FOR ISOLATION VALVES (TAC NOS. MD6961 AND MD6962) | CATAWBA NUCLEAR STATION, UNITS 1 AND 2 - ISSUANCE OF AMENDMENTS REGARDING SPECIFIC ISOLATION TIME FOR ISOLATION VALVES (TAC NOS. MD6961 AND MD6962) | ||
==Dear Mr. Morris:== | ==Dear Mr. Morris:== | ||
The Nuclear Regulatory Commission has issued the enclosed Amendment No. 244 to Renewed Facility Operating | The Nuclear Regulatory Commission has issued the enclosed Amendment No. 244 to Renewed Facility Operating License NPF-35 and Amendment No. 238 to Renewed Facility Operating License NPF-52 for the Catawba Nuclear Station, Units 1 and 2, respectively. The amendments consist of changes to the Technical Specifications (TSs) in response to your application dated September 27, 2007. | ||
The amendments revise TS 3.7.2, Main Steam Isolation Valves, and TS 3.7.3, Main Feedwater Isolation Valves, Main Feedwater Control Valves, Associated Bypass Valves and Tempering Valves, by removing the specific isolation time for the isolation valves from the associated surveillance requirements. | |||
The amendments revise TS 3.7.2, | 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, | |||
A copy of the related Safety | /RA by LOlshan for/ | ||
Sincerely, | John Stang, Senior Project Manager Plant Licensing Branch II-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-413 and 50-414 | ||
John Stang, Senior Project Manager Plant Licensing Branch II-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation | |||
Docket Nos. 50-413 and 50-414 | |||
==Enclosures:== | ==Enclosures:== | ||
: 1. Amendment No. 244 to NPF-35 | : 1. Amendment No. 244 to NPF-35 | ||
: 2. Amendment No. 238 to NPF-52 | : 2. Amendment No. 238 to NPF-52 | ||
: 3. Safety Evaluation | : 3. Safety Evaluation cc w/encls: See next page | ||
September 8, 2008 Mr. J. R. Morris Vice President Catawba Nuclear Station Duke Power Company LLC 4800 Concord Road York, SC 29745 | |||
==SUBJECT:== | ==SUBJECT:== | ||
CATAWBA NUCLEAR STATION, UNITS 1 AND 2 - ISSUANCE OF AMENDMENTS REGARDING SPECIFIC ISOLATION TIME FOR ISOLATION VALVES (TAC NOS. MD6961 AND MD6962) | CATAWBA NUCLEAR STATION, UNITS 1 AND 2 - ISSUANCE OF AMENDMENTS REGARDING SPECIFIC ISOLATION TIME FOR ISOLATION VALVES (TAC NOS. MD6961 AND MD6962) | ||
==Dear Mr. Morris:== | ==Dear Mr. Morris:== | ||
The Nuclear Regulatory Commission has issued the enclosed Amendment No. 244 to Renewed Facility Operating | The Nuclear Regulatory Commission has issued the enclosed Amendment No. 244 to Renewed Facility Operating License NPF-35 and Amendment No. 238 to Renewed Facility Operating License NPF-52 for the Catawba Nuclear Station, Units 1 and 2, respectively. The amendments consist of changes to the Technical Specifications (TSs) in response to your application dated September 27, 2007. | ||
The amendments revise TS 3.7.2, Main Steam Isolation Valves, and TS 3.7.3, Main Feedwater Isolation Valves, Main Feedwater Control Valves, Associated Bypass Valves and Tempering Valves, by removing the specific isolation time for the isolation valves from the associated surveillance requirements. | |||
The amendments revise TS 3.7.2, | 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, | |||
A copy of the related Safety | /RA by LOlshan for/ | ||
Sincerely, | John Stang, Senior Project Manager Plant Licensing Branch II-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-413 and 50-414 | ||
John Stang, Senior Project Manager Plant Licensing Branch II-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation | |||
Docket Nos. 50-413 and 50-414 | |||
==Enclosures:== | ==Enclosures:== | ||
: 1. Amendment No. 244 to NPF-35 | : 1. Amendment No. 244 to NPF-35 | ||
: 2. Amendment No. 238 to NPF-52 | : 2. Amendment No. 238 to NPF-52 | ||
: 3. Safety Evaluation | : 3. Safety Evaluation cc w/encls: See next page DISTRIBUTION: Public LPL2-1 R/F GHill (4 hard copies) | ||
RidsNrrDorlLpl2-1 (MCWong) RidsNrrDirsItsb (RElliott) | |||
cc w/encls: | RidsNrrPMJStang (hard copy) RidsRgn2MailCenter (SRose) | ||
RidsNrrLAMO=Brien (hard copy) RidsNrrDorlDpr RidsOgcRp RidsAcrsAcnwMailCenter Package No.: ML082310657 Letter: ML082310646 Tech Spec No.: ML082310672 OFFICE NRR/LPL2-1/PM NRR/LPL2-1/LA OGC NLO NRR/ITBS/BC NRR/LPL2-1/BC NAME JStang MOBrien EWilliamson RElliott MCWong DATE 08/20/08 08/29/08 08/27/08 09/02/08 09/03/08 OFFICIAL RECORD COPY | |||
DISTRIBUTION: Public | |||
RidsNrrDorlLpl2-1 (MCWong) | |||
RidsNrrLAMO=Brien (hard copy) | |||
Package No.: | |||
cc: | Catawba Nuclear Station, Units 1 & 2 Page 1 of 2 cc: | ||
Site Vice President Senior Resident Inspector Catawba Nuclear Station U.S. Nuclear Regulatory Commission Duke Power Company, LLC 4830 Concord Road 4800 Concord Road York, South Carolina 29745 York, SC 29745 Manager Associate General Counsel and Managing Division of Waste Management Attorney Bureau of Land and Waste Management Duke Energy Carolinas, LLC Dept. of Health and Environmental Control 526 South Church Street - EC07H 2600 Bull Street Charlotte, North Carolina 28202 Columbia, South Carolina 29201-1708 Regulatory Compliance Manager Duke Energy Corporation Nuclear Regulatory Issues 4800 Concord Road and Industry Affairs York, South Carolina 29745 Duke Energy Corporation 526 South Church Street North Carolina Municipal Power Mail Stop EC05P Agency Number 1 Charlotte, North Carolina 28202 1427 Meadowwood Boulevard P.O. Box 29513 Saluda River Electric Raleigh, North Carolina 27626 P.O. Box 929 Laurens, South Carolina 29360 County Manager of York County York County Courthouse Vice President York, South Carolina 29745 Customer Relations and Sales Westinghouse Electric Company Piedmont Municipal Power Agency 6000 Fairview Road 121 Village Drive 12th Floor Greer, South Carolina 29651 Charlotte, North Carolina 28210 Assistant Attorney General Owners Group (NCEMC) | |||
North Carolina Department of Justice Duke Energy Corporation P.O. Box 629 4800 Concord Road Raleigh, North Carolina 27602 York, South Carolina 29745 NCEM REP Program Manager Senior Counsel 4713 Mail Service Center Duke Energy Carolinas, LLC Raleigh, North Carolina 27699-4713 526 South Church Street - EC07H Charlotte, NC 28202 North Carolina Electric Membership Corp. | |||
P.O. Box 27306 Raleigh, North Carolina 27611 | |||
Division of Radiation Protection NC Dept. of Environment, Health, and Natural Resources 3825 Barrett Drive Raleigh, North Carolina | Catawba Nuclear Station, Units 1 & 2 Page 2 of 2 cc: | ||
Division of Radiation Protection NC Dept. of Environment, Health, and Natural Resources 3825 Barrett Drive Raleigh, North Carolina 27609-7721 Group Vice President, Nuclear Generation and Chief Nuclear Officer P.O. Box 1006-EC07H Charlotte, NC 28201-1006 | |||
Group Vice President, Nuclear Generation and Chief Nuclear Officer P.O. Box 1006-EC07H Charlotte, NC 28201-1006 | |||
DUKE ENERGY CAROLINAS, LLC NORTH CAROLINA ELECTRIC MEMBERSHIP CORPORATION SALUDA RIVER ELECTRIC COOPERATIVE, INC. | DUKE ENERGY CAROLINAS, LLC NORTH CAROLINA ELECTRIC MEMBERSHIP CORPORATION SALUDA RIVER ELECTRIC COOPERATIVE, INC. | ||
DOCKET NO. 50-413 CATAWBA NUCLEAR STATION, UNIT 1 AMENDMENT TO | DOCKET NO. 50-413 CATAWBA NUCLEAR STATION, UNIT 1 AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment No. 244 Renewed License No. NPF-35 | ||
: 1. The Nuclear Regulatory Commission (the Commission) has found that: | : 1. The Nuclear Regulatory Commission (the Commission) has found that: | ||
A. The application for amendment to the Catawba Nuclear Station, Unit 1 (the facility) Renewed Facility | 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, North Carolina Electric Membership Corporation and Saluda River Electric Cooperative, Inc. (licensees), dated September 27, 2007, 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. 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. 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. 244 , which are attached hereto, are hereby incorporated into this 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 60 days of issuance. | : 3. This license amendment is effective as of its date of issuance and shall be implemented within 60 days of issuance. | ||
FOR THE NUCLEAR REGULATORY COMMISSION | FOR THE NUCLEAR REGULATORY COMMISSION | ||
/RA/ | |||
Melanie C. Wong, Chief Plant Licensing Branch II-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation | |||
==Attachment:== | ==Attachment:== | ||
Changes to License No. NPF-35 | |||
Changes to License No. NPF-35 and the Technical Specifications Date of Issuance: September 8, 2008 | |||
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. 238 Renewed License No. NPF-52 | |||
: 1. The Nuclear Regulatory Commission (the Commission) has found that: | : 1. The Nuclear Regulatory Commission (the Commission) has found that: | ||
A. The application for amendment to the Catawba Nuclear Station, Unit 2 (the facility) Renewed Facility | 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 September 27, 2007, 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. 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. 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. 238 , which are attached hereto, are hereby incorporated into this 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 60 days of issuance. | : 3. This license amendment is effective as of its date of issuance and shall be implemented within 60 days of issuance. | ||
FOR THE NUCLEAR REGULATORY COMMISSION | FOR THE NUCLEAR REGULATORY COMMISSION | ||
/RA/ | |||
Melanie C. Wong, Chief Plant Licensing Branch II-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation | |||
==Attachment:== | ==Attachment:== | ||
Changes to License No. NPF-52 and the Technical Specifications Date of Issuance: September 8, 2008 | |||
ATTACHMENT TO LICENSE AMENDMENT NO. 244 RENEWED FACILITY OPERATING LICENSE NO. NPF-35 DOCKET NO. 50-413 AND LICENSE AMENDMENT NO. 238 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 Insert License Pages License Pages NPF-35 page 4 NPF-35 page 4 NPF-52 page 4 NPF-52 page 4 TSs TSs 3.7.2-2 3.7.2-2 3.7.3-2 3.7.3-2 | |||
SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 244 TO RENEWED FACILITY OPERATING LICENSE NPF-35 AND AMENDMENT NO. 238 TO RENEWED FACILITY OPERATING LICENSE NPF-52 DUKE ENERGY CAROLINAS, LLC CATAWBA NUCLEAR STATION, UNITS 1 AND 2 DOCKET NOS. 50-413 AND 50-414 | |||
== | ==1.0 INTRODUCTION== | ||
By application dated September 27, 2007 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML072760125), Duke Energy Carolinas, LLC (Duke, the licensee), requested changes to the Technical Specifications (TSs) for the Catawba Nuclear Station, Units 1 and 2 (Catawba 1 and 2). | |||
The proposed amendments would revise TS 3.7.2, Main Steam Isolation Valves, and TS 3.7.3, Main Feedwater Isolation Valves, Main Feedwater Control Valves, Associated Bypass Valves and Tempering Valves, by removing the specific isolation time for the isolation valves from the associated Surveillance Requirements. The changes to TSs are consistent with U.S. Nuclear Regulatory Commission (NRC)-approved Industry/Technical Specification Task Force (TSTF) | |||
Traveler TSTF-491, Revision 2, ARemoval of Main Steam and Feedwater Valve Isolation Times from Technical Specifications.@ | |||
==2.0 REGULATORY EVALUATION== | |||
3.1 | Section 182a of the Atomic Energy Act (the AAct@) requires applicants for nuclear power plant operating licenses to include TSs as part of the license. The TSs ensure the operational capability of structures, systems and components that are required to protect the health and safety of the public. The Commission=s regulatory requirements related to the content of the TSs are contained in Title 10 of the Code of Federal Regulations (10 CFR), Part 50, Section 50.36. | ||
That regulation requires that the TSs include items in the following specific categories: (1) safety limits, limiting safety systems settings, and limiting control settings (50.36(c)(1)); (2) Limiting Conditions for Operation (50.36(c)(2)); (3) Surveillance Requirements (50.36(c)(3)); (4) design features (50.34(c)(4)); and (5) administrative controls (50.36(c)(5)). | |||
In general, there are two classes of changes to TSs: (1) changes needed to reflect modifications to the design basis (TSs are derived from the design basis), and (2) voluntary changes to take advantage of the evolution in policy and guidance as to the required content Enclosure | |||
and preferred format of TSs over time. This amendment deals with the second class of changes. | |||
In determining the acceptability of revising the Standard Technical Specifications (STS) 3.7.2 and 3.7.3, the NRC staff used the accumulation of generically approved guidance in NUREG-1430, AStandard Technical Specifications, Revision 3 Babcock and Wilcox Plants,@ dated June 2004; NUREG-1431, Revision 3, AStandard Technical Specifications, Westinghouse Plants,@ | |||
dated June 2004; and NUREG-1432, AStandard Technical Specifications, Revision 3 Combustion Engineering Plants,@ dated June 2004. | |||
Licensees may revise the TSs to adopt current improved STS format and content provided that plant-specific review supports a finding of continued adequate safety because: (1) the change is editorial, administrative or provides clarification (i.e., no requirements are materially altered), (2) the change is more restrictive than the licensee=s current requirement, or (3) the change is less restrictive than the licensee=s current requirement, but nonetheless still affords adequate assurance of safety when judged against current regulatory standards. The detailed application of this general framework, and additional specialized guidance, are discussed in Section 3.0 in the context of specific proposed changes. | |||
==3.0 TECHNICAL EVALUATION== | |||
The NRC staff has reviewed the justification for the proposed TSTF as described in the licensees September 27, 2007, submittal for Catawba 1 and 2. The detailed evaluation below supports the conclusion for Catawba 1 and 2 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. | |||
3.1 Main Steam Isolation Valves (MSIVs) | |||
One MSIV is located in each main steam line outside of the containment. Closing the MSIVs isolates each steam generator from the others and isolates the turbine, steam bypass system and other auxiliary steam supplies from the steam generator. | |||
By isolating the steam flow from the secondary side of the steam generator the MSIVs prevent over cooling the reactor core following a high energy line break (HELB). By preventing core overcooling, the MSIVs protect the reactor core from being damaged. | |||
The licensee is proposing to relocate the required closure times for the MSIVs to the TSs Bases. | The licensee is proposing to relocate the required closure times for the MSIVs to the TSs Bases. | ||
The licensee has a TSs Bases Program as required by Section 5.5.14 of the TSs. Changes to the Bases are subject to the 10 CFR 50.59 process. The 10 CFR 50.59 criteria provide | The licensee has a TSs Bases Program as required by Section 5.5.14 of the TSs. Changes to the Bases are subject to the 10 CFR 50.59 process. The 10 CFR 50.59 criteria provide adequate assurance that prior NRC staff review and approval will be requested by the licensee for changes to the TSs Bases requirements with the potential to affect the safe operation of the plant. Furthermore, the MSIVs are subject to periodic testing and acceptance criteria in accordance with the Inservice Testing (IST) Program. Compliance with the IST Program is required by Section 5.5.8 of the Catawba 1 and 2 TSs and 10 CFR 50.55a. The IST Program includes specific reference value baseline operating times for valves that are not subject to arbitrary changes. | ||
adequate assurance that prior NRC staff review and approval will be requested by the licensee for changes to the TSs Bases requirements with the potential to affect the safe operation of the plant. Furthermore, the MSIVs are subject to periodic testing and acceptance criteria in accordance with the Inservice Testing (IST) Program. Compliance with the IST Program is required by Section 5.5.8 of the Catawba 1 and 2 TSs and 10 CFR 50.55a. The IST Program includes specific reference value baseline operating times for valves that are not subject to arbitrary changes | |||
Based on the requirements of 10 CFR 50.36, 10 CFR 50.59 and the IST Program, the NRC staff concludes that relocating the MFIVs, MFRVs and BVs closure times to the TSs bases is acceptable. | Section 50.36 requires the inclusion of the periodic testing of the MSIVs in the surveillance requirements not the actual closure time of the valves. The TSs will still maintain the periodic testing requirements for MSIVs in accordance with 10 CFR 50.36. | ||
Based on the requirements of 10 CFR 50.36, 10 CFR 50.59 and the IST Program, the NRC staff concludes that relocating the MSIV closure time to the TSs Bases is acceptable. | |||
3.2 Main Feedwater Isolation Valves (MFIVs), Main Feedwater Regulation/Control Valves (MFRVs) and Associated Bypass Valves (BVs) | |||
The MFIVs and BVs or the MFRVs and BVs isolate the nonsafety-related portions from the safety-related portions of the system. In the event of a secondary side pipe rupture inside containment, these valves limit the quantity of high energy fluid that enters the containment through the break and provide a pressure boundary for the controlled addition of auxiliary feedwater to the intact loops. | |||
By isolating the feedwater flow from the affected steam generator, the MFIVs, MFRVs and BVs prevent over cooling the reactor core and over pressurizing the containment from feedwater pump runout. | |||
As with the MSIVs, the licensee is also proposing to relocate the required closure times for the MFIVs, MFRVs and BVS to the TSs Bases. The licensee has a TSs Bases Program as required by Section 5.5.14 of the TSs. The 10 CFR 50.59 criteria provide adequate assurance that prior NRC staff review and approval will be requested by the licensee for changes to the TSs Bases requirements with the potential to affect the safe operation of the plant. Furthermore, the MFIVs, MFRVs and BVs are subject to periodic testing and acceptance criteria in accordance with the IST Program. Compliance with the IST Program is required by Section 5.5.8 of the Catawba 1 and 2 TSs and 10 CFR 50.55. The IST Program includes specific reference value baseline operating times for valves that are not subject to arbitrary changes. | |||
Section 50.36 requires the periodic testing of the MFIVs, MFRVs and BVs in the surveillance requirements not the actual closure time of the valves. The TSs will still maintain the periodic testing requirements for the MFIVs, MFRVs and BVs in accordance with 10 CFR 50.36. | |||
Based on the requirements of 10 CFR 50.36, 10 CFR 50.59 and the IST Program, the NRC staff concludes that relocating the MFIVs, MFRVs and BVs closure times to the TSs bases is acceptable. | |||
==4.0 | ==4.0 CONCLUSION== | ||
The changes proposed by the licensee in the September 27, 2007, application would make the affected surveillances more consistent with the Engineered Safety Feature Actuation System (ESFAS) response time requirement in SR 3.3.2.10 | The changes proposed by the licensee in the September 27, 2007, application would make the affected surveillances more consistent with the Engineered Safety Feature Actuation System (ESFAS) response time requirement in SR 3.3.2.10 which states AVerify ESFAS REPONSE TIMES are within limits@. The NRC staff concludes that the proposed changes are consistent with the requirements as contained in 10 CFR 50.36. On this basis, the NRC staff concludes that the changes proposed to the TSs are acceptable. | ||
@. The NRC staff concludes that the proposed changes are consistent with the requirements as contained in 10 CFR 50.36. On this basis, the NRC staff concludes that the changes proposed to the TSs are acceptable. | |||
==5.0 | ==5.0 STATE CONSULTATION== | ||
In accordance with the Commission's regulations, the South Carolina State official was notified of the proposed issuance of the amendments. The State official had no comments. | In accordance with the Commission's regulations, the South Carolina State official was notified of the proposed issuance of the amendments. The State official had no comments. | ||
==6.0 | ==6.0 ENVIRONMENTAL CONSIDERATION== | ||
The amendments change a requirement with | 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 and change surveillance requirements. 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 (73 FR 10297). 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. | ||
==7.0 | ==7.0 CONCLUSION== | ||
The Commission has concluded, based on the considerations discussed above, that: | 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: | Principal Contributor: J. Stang Date: September 8, 2008}} |
Latest revision as of 14:51, 14 November 2019
ML082310646 | |
Person / Time | |
---|---|
Site: | Catawba ![]() |
Issue date: | 09/08/2008 |
From: | Stang J NRC/NRR/ADRO/DORL/LPLII-1 |
To: | Morris J Duke Energy Carolinas |
Stang J, NRR/DORL, 415-1345 | |
References | |
TAC MD6961, TAC MD6962 | |
Download: ML082310646 (16) | |
Text
September 8, 2008 Mr. J. R. Morris Site Vice President Catawba Nuclear Station Duke Energy Carolinas, LLC 4800 Concord Road York, SC 29745
SUBJECT:
CATAWBA NUCLEAR STATION, UNITS 1 AND 2 - ISSUANCE OF AMENDMENTS REGARDING SPECIFIC ISOLATION TIME FOR ISOLATION VALVES (TAC NOS. MD6961 AND MD6962)
Dear Mr. Morris:
The Nuclear Regulatory Commission has issued the enclosed Amendment No. 244 to Renewed Facility Operating License NPF-35 and Amendment No. 238 to Renewed Facility Operating License NPF-52 for the Catawba Nuclear Station, Units 1 and 2, respectively. The amendments consist of changes to the Technical Specifications (TSs) in response to your application dated September 27, 2007.
The amendments revise TS 3.7.2, Main Steam Isolation Valves, and TS 3.7.3, Main Feedwater Isolation Valves, Main Feedwater Control Valves, Associated Bypass Valves and Tempering Valves, by removing the specific isolation time for the isolation valves from the associated surveillance requirements.
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,
/RA by LOlshan for/
John Stang, Senior Project Manager Plant Licensing Branch II-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-413 and 50-414
Enclosures:
- 1. Amendment No. 244 to NPF-35
- 2. Amendment No. 238 to NPF-52
- 3. Safety Evaluation cc w/encls: See next page
September 8, 2008 Mr. J. R. Morris Vice President Catawba Nuclear Station Duke Power Company LLC 4800 Concord Road York, SC 29745
SUBJECT:
CATAWBA NUCLEAR STATION, UNITS 1 AND 2 - ISSUANCE OF AMENDMENTS REGARDING SPECIFIC ISOLATION TIME FOR ISOLATION VALVES (TAC NOS. MD6961 AND MD6962)
Dear Mr. Morris:
The Nuclear Regulatory Commission has issued the enclosed Amendment No. 244 to Renewed Facility Operating License NPF-35 and Amendment No. 238 to Renewed Facility Operating License NPF-52 for the Catawba Nuclear Station, Units 1 and 2, respectively. The amendments consist of changes to the Technical Specifications (TSs) in response to your application dated September 27, 2007.
The amendments revise TS 3.7.2, Main Steam Isolation Valves, and TS 3.7.3, Main Feedwater Isolation Valves, Main Feedwater Control Valves, Associated Bypass Valves and Tempering Valves, by removing the specific isolation time for the isolation valves from the associated surveillance requirements.
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,
/RA by LOlshan for/
John Stang, Senior Project Manager Plant Licensing Branch II-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-413 and 50-414
Enclosures:
- 1. Amendment No. 244 to NPF-35
- 2. Amendment No. 238 to NPF-52
- 3. Safety Evaluation cc w/encls: See next page DISTRIBUTION: Public LPL2-1 R/F GHill (4 hard copies)
RidsNrrDorlLpl2-1 (MCWong) RidsNrrDirsItsb (RElliott)
RidsNrrPMJStang (hard copy) RidsRgn2MailCenter (SRose)
RidsNrrLAMO=Brien (hard copy) RidsNrrDorlDpr RidsOgcRp RidsAcrsAcnwMailCenter Package No.: ML082310657 Letter: ML082310646 Tech Spec No.: ML082310672 OFFICE NRR/LPL2-1/PM NRR/LPL2-1/LA OGC NLO NRR/ITBS/BC NRR/LPL2-1/BC NAME JStang MOBrien EWilliamson RElliott MCWong DATE 08/20/08 08/29/08 08/27/08 09/02/08 09/03/08 OFFICIAL RECORD COPY
Catawba Nuclear Station, Units 1 & 2 Page 1 of 2 cc:
Site Vice President Senior Resident Inspector Catawba Nuclear Station U.S. Nuclear Regulatory Commission Duke Power Company, LLC 4830 Concord Road 4800 Concord Road York, South Carolina 29745 York, SC 29745 Manager Associate General Counsel and Managing Division of Waste Management Attorney Bureau of Land and Waste Management Duke Energy Carolinas, LLC Dept. of Health and Environmental Control 526 South Church Street - EC07H 2600 Bull Street Charlotte, North Carolina 28202 Columbia, South Carolina 29201-1708 Regulatory Compliance Manager Duke Energy Corporation Nuclear Regulatory Issues 4800 Concord Road and Industry Affairs York, South Carolina 29745 Duke Energy Corporation 526 South Church Street North Carolina Municipal Power Mail Stop EC05P Agency Number 1 Charlotte, North Carolina 28202 1427 Meadowwood Boulevard P.O. Box 29513 Saluda River Electric Raleigh, North Carolina 27626 P.O. Box 929 Laurens, South Carolina 29360 County Manager of York County York County Courthouse Vice President York, South Carolina 29745 Customer Relations and Sales Westinghouse Electric Company Piedmont Municipal Power Agency 6000 Fairview Road 121 Village Drive 12th Floor Greer, South Carolina 29651 Charlotte, North Carolina 28210 Assistant Attorney General Owners Group (NCEMC)
North Carolina Department of Justice Duke Energy Corporation P.O. Box 629 4800 Concord Road Raleigh, North Carolina 27602 York, South Carolina 29745 NCEM REP Program Manager Senior Counsel 4713 Mail Service Center Duke Energy Carolinas, LLC Raleigh, North Carolina 27699-4713 526 South Church Street - EC07H Charlotte, NC 28202 North Carolina Electric Membership Corp.
P.O. Box 27306 Raleigh, North Carolina 27611
Catawba Nuclear Station, Units 1 & 2 Page 2 of 2 cc:
Division of Radiation Protection NC Dept. of Environment, Health, and Natural Resources 3825 Barrett Drive Raleigh, North Carolina 27609-7721 Group Vice President, Nuclear Generation and Chief Nuclear Officer P.O. Box 1006-EC07H Charlotte, NC 28201-1006
DUKE ENERGY CAROLINAS, LLC NORTH CAROLINA ELECTRIC MEMBERSHIP CORPORATION SALUDA RIVER ELECTRIC COOPERATIVE, INC.
DOCKET NO. 50-413 CATAWBA NUCLEAR STATION, UNIT 1 AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment No. 244 Renewed License No. NPF-35
- 1. The 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, North Carolina Electric Membership Corporation and Saluda River Electric Cooperative, Inc. (licensees), dated September 27, 2007, 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. 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. 244 , which are attached hereto, are hereby incorporated into this 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 60 days of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
/RA/
Melanie C. Wong, Chief Plant Licensing Branch II-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: September 8, 2008
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. 238 Renewed License No. NPF-52
- 1. The 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 September 27, 2007, 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. 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. 238 , which are attached hereto, are hereby incorporated into this 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 60 days of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
/RA/
Melanie C. Wong, Chief Plant Licensing Branch II-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: September 8, 2008
ATTACHMENT TO LICENSE AMENDMENT NO. 244 RENEWED FACILITY OPERATING LICENSE NO. NPF-35 DOCKET NO. 50-413 AND LICENSE AMENDMENT NO. 238 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 Insert License Pages License Pages NPF-35 page 4 NPF-35 page 4 NPF-52 page 4 NPF-52 page 4 TSs TSs 3.7.2-2 3.7.2-2 3.7.3-2 3.7.3-2
SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 244 TO RENEWED FACILITY OPERATING LICENSE NPF-35 AND AMENDMENT NO. 238 TO RENEWED FACILITY OPERATING LICENSE NPF-52 DUKE ENERGY CAROLINAS, LLC CATAWBA NUCLEAR STATION, UNITS 1 AND 2 DOCKET NOS. 50-413 AND 50-414
1.0 INTRODUCTION
By application dated September 27, 2007 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML072760125), Duke Energy Carolinas, LLC (Duke, the licensee), requested changes to the Technical Specifications (TSs) for the Catawba Nuclear Station, Units 1 and 2 (Catawba 1 and 2).
The proposed amendments would revise TS 3.7.2, Main Steam Isolation Valves, and TS 3.7.3, Main Feedwater Isolation Valves, Main Feedwater Control Valves, Associated Bypass Valves and Tempering Valves, by removing the specific isolation time for the isolation valves from the associated Surveillance Requirements. The changes to TSs are consistent with U.S. Nuclear Regulatory Commission (NRC)-approved Industry/Technical Specification Task Force (TSTF)
Traveler TSTF-491, Revision 2, ARemoval of Main Steam and Feedwater Valve Isolation Times from Technical Specifications.@
2.0 REGULATORY EVALUATION
Section 182a of the Atomic Energy Act (the AAct@) requires applicants for nuclear power plant operating licenses to include TSs as part of the license. The TSs ensure the operational capability of structures, systems and components that are required to protect the health and safety of the public. The Commission=s regulatory requirements related to the content of the TSs are contained in Title 10 of the Code of Federal Regulations (10 CFR), Part 50, Section 50.36.
That regulation requires that the TSs include items in the following specific categories: (1) safety limits, limiting safety systems settings, and limiting control settings (50.36(c)(1)); (2) Limiting Conditions for Operation (50.36(c)(2)); (3) Surveillance Requirements (50.36(c)(3)); (4) design features (50.34(c)(4)); and (5) administrative controls (50.36(c)(5)).
In general, there are two classes of changes to TSs: (1) changes needed to reflect modifications to the design basis (TSs are derived from the design basis), and (2) voluntary changes to take advantage of the evolution in policy and guidance as to the required content Enclosure
and preferred format of TSs over time. This amendment deals with the second class of changes.
In determining the acceptability of revising the Standard Technical Specifications (STS) 3.7.2 and 3.7.3, the NRC staff used the accumulation of generically approved guidance in NUREG-1430, AStandard Technical Specifications, Revision 3 Babcock and Wilcox Plants,@ dated June 2004; NUREG-1431, Revision 3, AStandard Technical Specifications, Westinghouse Plants,@
dated June 2004; and NUREG-1432, AStandard Technical Specifications, Revision 3 Combustion Engineering Plants,@ dated June 2004.
Licensees may revise the TSs to adopt current improved STS format and content provided that plant-specific review supports a finding of continued adequate safety because: (1) the change is editorial, administrative or provides clarification (i.e., no requirements are materially altered), (2) the change is more restrictive than the licensee=s current requirement, or (3) the change is less restrictive than the licensee=s current requirement, but nonetheless still affords adequate assurance of safety when judged against current regulatory standards. The detailed application of this general framework, and additional specialized guidance, are discussed in Section 3.0 in the context of specific proposed changes.
3.0 TECHNICAL EVALUATION
The NRC staff has reviewed the justification for the proposed TSTF as described in the licensees September 27, 2007, submittal for Catawba 1 and 2. The detailed evaluation below supports the conclusion for Catawba 1 and 2 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.
3.1 Main Steam Isolation Valves (MSIVs)
One MSIV is located in each main steam line outside of the containment. Closing the MSIVs isolates each steam generator from the others and isolates the turbine, steam bypass system and other auxiliary steam supplies from the steam generator.
By isolating the steam flow from the secondary side of the steam generator the MSIVs prevent over cooling the reactor core following a high energy line break (HELB). By preventing core overcooling, the MSIVs protect the reactor core from being damaged.
The licensee is proposing to relocate the required closure times for the MSIVs to the TSs Bases.
The licensee has a TSs Bases Program as required by Section 5.5.14 of the TSs. Changes to the Bases are subject to the 10 CFR 50.59 process. The 10 CFR 50.59 criteria provide adequate assurance that prior NRC staff review and approval will be requested by the licensee for changes to the TSs Bases requirements with the potential to affect the safe operation of the plant. Furthermore, the MSIVs are subject to periodic testing and acceptance criteria in accordance with the Inservice Testing (IST) Program. Compliance with the IST Program is required by Section 5.5.8 of the Catawba 1 and 2 TSs and 10 CFR 50.55a. The IST Program includes specific reference value baseline operating times for valves that are not subject to arbitrary changes.
Section 50.36 requires the inclusion of the periodic testing of the MSIVs in the surveillance requirements not the actual closure time of the valves. The TSs will still maintain the periodic testing requirements for MSIVs in accordance with 10 CFR 50.36.
Based on the requirements of 10 CFR 50.36, 10 CFR 50.59 and the IST Program, the NRC staff concludes that relocating the MSIV closure time to the TSs Bases is acceptable.
3.2 Main Feedwater Isolation Valves (MFIVs), Main Feedwater Regulation/Control Valves (MFRVs) and Associated Bypass Valves (BVs)
The MFIVs and BVs or the MFRVs and BVs isolate the nonsafety-related portions from the safety-related portions of the system. In the event of a secondary side pipe rupture inside containment, these valves limit the quantity of high energy fluid that enters the containment through the break and provide a pressure boundary for the controlled addition of auxiliary feedwater to the intact loops.
By isolating the feedwater flow from the affected steam generator, the MFIVs, MFRVs and BVs prevent over cooling the reactor core and over pressurizing the containment from feedwater pump runout.
As with the MSIVs, the licensee is also proposing to relocate the required closure times for the MFIVs, MFRVs and BVS to the TSs Bases. The licensee has a TSs Bases Program as required by Section 5.5.14 of the TSs. The 10 CFR 50.59 criteria provide adequate assurance that prior NRC staff review and approval will be requested by the licensee for changes to the TSs Bases requirements with the potential to affect the safe operation of the plant. Furthermore, the MFIVs, MFRVs and BVs are subject to periodic testing and acceptance criteria in accordance with the IST Program. Compliance with the IST Program is required by Section 5.5.8 of the Catawba 1 and 2 TSs and 10 CFR 50.55. The IST Program includes specific reference value baseline operating times for valves that are not subject to arbitrary changes.
Section 50.36 requires the periodic testing of the MFIVs, MFRVs and BVs in the surveillance requirements not the actual closure time of the valves. The TSs will still maintain the periodic testing requirements for the MFIVs, MFRVs and BVs in accordance with 10 CFR 50.36.
Based on the requirements of 10 CFR 50.36, 10 CFR 50.59 and the IST Program, the NRC staff concludes that relocating the MFIVs, MFRVs and BVs closure times to the TSs bases is acceptable.
4.0 CONCLUSION
The changes proposed by the licensee in the September 27, 2007, application would make the affected surveillances more consistent with the Engineered Safety Feature Actuation System (ESFAS) response time requirement in SR 3.3.2.10 which states AVerify ESFAS REPONSE TIMES are within limits@. The NRC staff concludes that the proposed changes are consistent with the requirements as contained in 10 CFR 50.36. On this basis, the NRC staff concludes that the changes proposed to the TSs are acceptable.
5.0 STATE CONSULTATION
In accordance with the Commission's regulations, the South Carolina State official was notified of the proposed issuance of the amendments. The State official had no comments.
6.0 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 and change surveillance requirements. 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 (73 FR 10297). 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.
7.0 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: J. Stang Date: September 8, 2008