ML071640310
| ML071640310 | |
| Person / Time | |
|---|---|
| Site: | Palisades  |
| Issue date: | 08/14/2007 |
| From: | Tate T L NRC/NRR/ADRO/DORL/LPLIII-1 |
| To: | Balduzzi M A Entergy Nuclear Operations |
| Sun, Robert NRR/DLR/RLRB 415-3421 | |
| References | |
| TAC MD3461 | |
| Download: ML071640310 (7) | |
Text
August 14, 2007Mr. Michael BalduzziSr. Vice President, Regional Operations NE Entergy Nuclear Operations, Inc.
440 Hamilton Avenue White Plains, NY 10601
SUBJECT:
PALISADES NUCLEAR PLANT - APPROVAL OF PROPOSED REACTORVESSEL SURVEILLANCE CAPSULE WITHDRAWAL SCHEDULE (TAC NO. MD3461)
Dear Mr. Balduzzi:
By letter dated September 19, 2006, (Agencywide Documents Access and Management System(ADAMS) Accession No. ML0626300710), and supplemented by letter dated, January 30, 2007, (ADAMS Accession No. ML070300405), Nuclear Management Company, LLC (NMC, the licensee, at the time of submittal), submitted a proposed change to reactor vessel material surveillance capsule withdrawal schedule pursuant to Title 10 of the Code of Federal Regulations (10 CFR),Part 50, Appendix H. The proposed schedule was developed to accommodate the 60-year licensing period for Palisades Nuclear Plant (PNP) using the guidance of American Society for Testing and Materials (ASTM) Standard Practice E-185-82, "Standard Practice for Conducting Surveillance Tests for Light-Water Cooled Nuclear Power Reactor Vessels." Entergy Nuclear Operations, Inc (ENO), has since become the current licensee, following a license transfer that occurred on April 11, 2007. Our review is contained in the enclosed safety evaluation. The Nuclear Regulatory Commission stafffound that the proposed surveillance capsule withdrawal schedule for PNP is in accordance with Appendix H to 10 CFR Part 50, and the recommendations of ASTM Standard Practice E-185-82. Sincerely,/RA/Travis L. Tate, Acting ChiefPlant Licensing Branch III-1 Division of Operating Reactor Licensing Office of Nuclear Reactor RegulationDocket No. 50-255
Enclosure:
Safety Evaluationcc w/encl: See next page
ML070300405), Nuclear Management Company, LLC (NMC, the licensee, at the time of submittal), submitted a proposed change to reactor vessel material surveillance capsule withdrawal schedule pursuant to Title 10 of the Code of Federal Regulations (10 CFR),Part 50, Appendix H. The proposed schedule was developed to accommodate the 60-year licensing period for Palisades Nuclear Plant (PNP) using the guidance of American Society for Testing and Materials (ASTM) Standard Practice E-185-82, "Standard Practice for Conducting Surveillance Tests for Light-Water Cooled Nuclear Power Reactor Vessels." Entergy Nuclear Operations, Inc (ENO), has since become the current licensee, following a license transfer that occurred on April 11, 2007. Our review is contained in the enclosed safety evaluation. The Nuclear Regulatory Commission stafffound that the proposed surveillance capsule withdrawal schedule for PNP is in accordance with Appendix H to 10 CFR Part 50, and the recommendations of ASTM Standard Practice E-185-82. Sincerely,/RA/Travis L. Tate, Acting ChiefPlant Licensing Branch III-1 Division of Operating Reactor Licensing Office of Nuclear Reactor RegulationDocket No. 50-255
Enclosure:
Safety Evaluationcc w/encl: See next pageDISTRIBUTION
- PUBLICLPL3-1 R/FRidsNrrPMMChawlaRidsNrrLATHarris RidsNrrDorlLpl3-1RidsOgcRpRidsAcrsAcnwMailCenterRidsNrrDorlDprMMitchell, NRR CLipa, RGN-IIIRidsRgn3MailCenterTBloomer, EDO, Rgn IIIADAMS Accession Number: ML071640310
- Safety Evaluation dated: March 6, 2007OFFICENRR/LPL3-1NRR/LPL3-1/PMNRR/LPL3-1/LADCI/CVIBOGCNRR/LPL3-1/(A)BCNAMERSunMChawlaTHarrisMMitchellJ.Bonanno NLOTTateDATE06/28/0708/ 14 /0708/ 14 /0703/06/0707/10/0708/ 14 /07 Palisades Plant cc:
Regional Administrator, Region IIIU.S. Nuclear Regulatory Commission Suite 210 2443 Warrenville Road Lisle, IL 60532-4351SupervisorCovert Township P. O. Box 35 Covert, MI 49043Office of the GovernorP. O. Box 30013 Lansing, MI 48909U.S. Nuclear Regulatory CommissionResident Inspector's Office Palisades Plant 27782 Blue Star Memorial Highway Covert, MI 49043Michigan Department of Environmental QualityWaste and Hazardous Materials Division Hazardous Waste and Radiological Protection Section Nuclear Facilities Unit Constitution Hall, Lower-Level North 525 West Allegan Street P.O. Box 30241 Lansing, MI 48909-7741Michigan Department of Attorney GeneralSpecial Litigation Division 525 West Ottawa St.
Sixth Floor, G. Mennen Williams Building Lansing, MI 48913Mr. Michael R. KanslerPresident & CEO/CNO Entergy Nuclear Operations, Inc.
440 Hamilton Avenue White Plains, NY 10601Mr. John T. HerronSr. Vice President Entergy Nuclear Operations, Inc.
440 Hamilton Avenue White Plains, NY 10601Sr. Vice President,Engineering and Technical Services Entergy Nuclear Operations, Inc.
1340 Echelon Parkway Jackson, MS 39213Mr. Bruce C. WilliamsVice President, Oversight Entergy Nuclear Operations, Inc.
1340 Echelon Parkway Jackson, MS 39213Mr. Christopher J. SchwarzSite Vice President Entergy Nuclear Operations, Inc.
Palisades Nuclear Plant 27780 Blue Star Memorial Highway Covert, MI 49043General Manager, Plant OperationsEntergy Nuclear Operations, Inc.
Palisades Nuclear Plant 27780 Blue Star Memorial Highway Covert, MI 49043Mr. Oscar LimpiasVice President, Engineering Entergy Nuclear Operations, Inc.
440 Hamilton Avenue White Plains, NY 10601Mr. John F. McCannDirector, Nuclear Safety & Licensing Entergy Nuclear Operations, Inc.
440 Hamilton Avenue White Plains, NY 10601Ms. Charlene D. FaisonManager, Licensing Entergy Nuclear Operations, Inc.
440 Hamilton Avenue White Plains, NY 10601Mr. Ernest J. HarknessDirector of Oversight Entergy Nuclear Operations, Inc.
440 Hamilton Avenue White Plains, NY 10601 Mr. William DennisAssistant General Counsel Entergy Nuclear Operations, Inc.
440 Hamilton Avenue White Plains, NY 10601Mr. Joseph DeRoyVice President, Operations Support Entergy Nuclear Operations, Inc.
1340 Echelon Parkway Jackson, MS 39213Laurie A. Lahti, Manager, LicensingRegulatory Affairs Entergy Nuclear Operations, Inc.
Palisades Nuclear Plant 27780 Blue Star Memorial Highway Covert, MI 49043 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATIONSURVEILLANCE CAPSULE WITHDRAWAL SCHEDULE PALISADES NUCLEAR PLANTNUCLEAR MANAGEMENT COMPANYDOCKET NO. 50-25
51.0INTRODUCTION
By letter dated September 19, 2006, (Agencywide Documents Access and ManagementSystem (ADAMS) Accession No. ML0626300710), and supplemented by letter dated, January 30, 2007, (ADAMS Accession No. ML070300405) pursuant to Title 10 of the Code ofFederal Regulations (10 CFR), Part 50, Appendix H, "Reactor Vessel Material SurveillanceProgram Requirements," Nuclear Management Company (NMC, the licensee, at the time of submittal), submitted a proposed reactor pressure vessel (RPV) material surveillance capsule withdrawal schedule for Nuclear Regulatory Commission (NRC) staff review and approval.
The proposed schedule was developed to accommodate the 60-year licensing period for Palisades Nuclear Plant (PNP) using the guidance of American Society for Testing and Materials (ASTM) Standard Practice E-185-82, "Standard Practice for Conducting Surveillance Tests for Light-Water Cooled Nuclear Power Reactor Vessels." Entergy Nuclear Operations, Inc (ENO), has since become the current licensee, following a license transfer that occurred on April 11, 2007. 2.0REGULATORY REQUIREMENTSThe surveillance program requirements in Appendix H to 10 CFR Part 50, were established tomonitor the radiation-induced changes in the mechanical and impact properties of the RPV materials. Appendix H to 10 CFR Part 50 requires licensees to monitor changes in the fracture toughness properties of ferritic materials in the RPV beltline region of light-water nuclear power reactors. Appendix H to 10 CFR Part 50 states that the design of the surveillance program and the withdrawal schedule must meet the requirements of the edition of ASTM E-185 that is current on the issue date of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code (ASME Code) to which the RPV was purchased.
Later editions of ASTM E-185 may be used including those editions through 1982 (i.e., ASTM E-185-82). NUREG-1801, Generic Aging Lessons Learned Report provides additional guidance for the surveillance program for the 60-year extended period of operation.
3.0 TECHNICAL EVALUATION
3.1 Evaluation
Criteria of ASTM E-185-82PNP is using the requirements of ASTM E-185-82 as its basis for meeting the RPV surveillancecapsule withdrawal requirements of Appendix H to 10 CFR Part 50. Table 1 of ASTM E-185-82 requires that either a minimum of three, four, or five surveillance capsules be removed from each of the vessels, as based on the projected nilductility reference temperature shift (RT NDT)of the limiting material at the clad-vessel interface location of the RPV at the end-of-licensed plant life (EOL). ASTM E-185-82 establishes the following criteria for determining the minimum number of capsules that are to be removed in accordance with a withdrawal schedule and the number of capsules that are to be tested:For plants with projected RT NDT less than 100 F (56 C), three capsules are required tobe removed from the RPV and the first two capsules are required to be tested (for dosimetry, tensile-ductility, Charpy-V impact toughness, and alloying chemistry).For plants with projected RT NDT between 100 F (56 C) and 200 F (111 C), foursurveillance capsules are to be removed from the RPV and the first three capsules are required to be tested.
For plants with projected RT NDT above 200 F (111 C), five surveillance capsules arerequired to be removed from the RPV and the first four capsules are required to be tested.For any of these withdrawal schedules, ASTM E-185-82 specifies that the final surveillancecapsule should be withdrawn after accumulating a neutron fluence (E > 1.0 MeV) of between one and two times the peak, EOL RPV fluence.PNP has a limiting RT NDT value greater than 200 F. Therefore, because the RT NDT value isgreater than 200 F, ASTM E 185-82 recommends that, at a minimum, five capsules to bewithdrawn. PNP has removed and tested four capsules and has proposed a change in a withdrawal schedule for the fifth capsule. 3.2Changes Proposed to the Withdrawal Schedule for PNPIn accordance with ASTM E-185-82, Table 1, the recommended withdrawal schedule for the fifthcapsule, W-80, is such that the surveillance capsule fluence is not less than once or greater than twice the peak EOL vessel fluence. EOL for PNP is equivalent to 42.37 Effective Full Power Years (EFPYs) of operation based on the renewed license. The following table summarizes PNP capsules which have already been removed and theproposed withdrawal of remaining capsules. The fifth capsule is proposed to be removed and tested between the 40 th and 60 th year of plant operation. Capsules W-280 and W-260 bothremain available for subsequent removal and testing, if needed.The projected peak vessel fluence at 60 years (42.37 EFPY) is estimated to be 2.998X10 19neutrons per square centimeter (n/cm 2). The licensee projects a capsule fluence of 3.06X10 19(n/cm 2) at 31.96 EFPY. Thus, capsule W-80 will capture the 60 th year peak vessel fluence at31.96 EFPY. Capsules W-280 and W-260 are reserved and will be withdrawn and tested in the future, if necessary. WithdrawalSequence Capsule(Unit shown as subscript)Removal TimeCapsule FluenceX 10 19 (n/cm 2)FirstA-240 2.26 EFPY4.01SecondW-2905.21 EFPY0.926ThirdW-1109.95 EFPY1.66FourthW-10016.93 EFPY2.1FifthW-80~ 31.96 EFPY ~ 3.06W-280Reserved for future use W-260Reserved for future useT-150Reserved for future use
4.0 CONCLUSION
Based on the NRC staff's review of the NMC submittal, the revised surveillance capsulewithdrawal schedule for the PNP RPV satisfies the requirements of ASTM E-185-82. Therefore, the NRC staff concludes that the licensee's modified surveillance capsule withdrawal schedule for PNP, as provided in the September 19, 2006, submittal and supplemental letter dated January 30, 2007, is acceptable for implementation and satisfies the requirements of Appendix H to 10 CFR Part 50 for the 60-year extended license period.Principal Contributors: Neil K. Ray Date: