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Category:CORRESPONDENCE-LETTERS
MONTHYEARML20138H3831999-10-25025 October 1999 Forwards Draft Model of Renewed License for Calvert Cliffs, Unit 2 to Illustrate How List of Minimum Requirements Could Be Incorporated Into License Condition ML20217M9991999-10-22022 October 1999 Forwards Response to NRC 990930 RAI Re Void Swelling Degradation Mechanism,Per License Renewal Application for Ccnpp,Units 1 & 2 ML20217M1721999-10-19019 October 1999 Forwards NRC Rept Number 17, Requal Tracking Rept Form Operator Licensing Tracking Sys.Rept Was Used by NRC to Schedule Requalification Exam for Operators & Record Requal Pass Dates ML20212M2631999-10-0404 October 1999 Informs That Staff Concluded That Licensee Responses to GL 97-06 Provides Reasonable Assurance That Condition of Util SG Internals in Compliance with Current Licensing Bases for Calvert Cliffs Nuclear Power Plant ML20216J8671999-10-0101 October 1999 Forwards Rev 52 to QA Policy for Calvert Cliffs Nuclear Power Plant. Rev Accurately Presents Changes Made Since Previous Submittal,Necessary to Reflect Info & Analyses Submitted to NRC or Prepared,Per to NRC Requirements ML20212J7811999-09-30030 September 1999 Requests That Licensee Address Potential Aging Mgt Issue Re Effects of Void Swelling of Rv Internals by Making Plant Specific Commitment to Implement Focused age-related Degradation Insp for Evidence of Void Swelling in Future ML20212J5611999-09-29029 September 1999 Informs That on 990916,NRC Completed mid-cycle Plant Performance Review of Calvert Cliffs.No Areas in Which Util Performance Warranted Addl Insp Beyond Core Insp Program Identified.Historical Listing of Plant Issues,Encl ML20216H7831999-09-28028 September 1999 Forwards Addl Info Re NRC SER for Ccnpp,Units 1 & 2,per License Renewal Application ML20212D5361999-09-20020 September 1999 Forwards Rev 1 to Calculation CA04048, Fuel Handling Accident During Reconstitution, as Agreed During 990909 Telcon ML20212C1861999-09-15015 September 1999 Requests That NRC Complete Review of TR CED-387-P,Rev 00-P, Abb Critical Heat Flux Correlations for PWR Fuel, by 000201.Util Expects to Use ABB-NV Correlation for Current non-mixing Vane Fuel in Reload Analyses in 2000 for Ccnpp ML20212A2001999-09-0808 September 1999 Forwards Insp Repts 50-317/99-06 & 50-318/99-06.Two Violations Being Treated as Noncited Violations ML20211N8971999-09-0707 September 1999 Responds to Ltr to D Rathbun of NRC Dtd 990720,in Which Recipient Refers to Ltr from Wc Batton Expressing Support on Renewal Application of Baltimore Gas & Electric Co for Calvert Cliffs Plants ML20211H9841999-08-31031 August 1999 Provides Comments Re Data Entered in Rvid for Ccnpp,Units 1 2,per GL 92-01,Rev 1,Suppl 1, Reactor Vessel Structural Integrity ML20211K3091999-08-27027 August 1999 Informs That During 990826 Telcon,L Briggs & B Bernie Made Arrangements for NRC to Inspect Licensed Operator Requalification Program at Calvert Cliffs Npp.Insp Planned for Wk of 991025 ML20211J1611999-08-17017 August 1999 Documents Bg&E Consultations with MD Dept of Natural Resources Re Potential Impacts to Chesapeake Bay Critical Area & Forest Interior Dwelling Bird Habitat,Per Ccnpp License Renewal.Telcons Ref Satisfy Consulting Requirement ML20210V1181999-08-17017 August 1999 Forwards Toxic Gases Calculations for Control Room Habitability,As Discussed During 990713 Telcon.Util Will Make Final Submittal for Toxic Gases After NRC Has Completed Review of ARCON96 ML20210T5061999-08-16016 August 1999 Forwards Rev 0 to Ccnpp COLR for Unit 2,Cycle 13, Per Plant TS 5.6.5 ML20210U2761999-08-13013 August 1999 Forwards Listed Info Re Guarantee of Payment of Deferred Premiums for Ccnpp,Units 1 & 2,IAW 10CFR140.21 Requirements ML20210S8131999-08-12012 August 1999 Forwards Summary of Various Open Licensing Actions for Bg&E That Were Completed During Unit 2 Refueling Outage Ending 990506 ML20210S8101999-08-12012 August 1999 Forwards Application Requesting Renewal of License for Mv Seckens,License SOP-10369-2.Without Encl ML20210S7901999-08-12012 August 1999 Forwards semi-annual Fitness for Duty Program Performance Data for Period of 990101-990630,IAW 10CFR36.71(d) ML20210Q1941999-08-11011 August 1999 Informs That Info Submitted in 981130 Application Re CEN-633-P,Rev 03-P,dtd Oct 1998,marked Proprietary,Will Be Withheld from Public Disclosure,Per 10CFR2.790(b)(5) & Section 103(b) of AEA of 1954,as Amended ML20210N5881999-08-0606 August 1999 Forwards ISI Rept for Ccnpp,Unit 2,fulfilling Intentions & Requirements Stated in Program Plan & Commitment to Comply with ASME Code Section XI ISI Requirements ML20210N1291999-08-0505 August 1999 Forwards NRC Response to W Batton Ltr Expressing Support of Renewal Application for Calvert Cliffs Plants as Requested in Ltr ML20210N5491999-08-0505 August 1999 Requests That License SOP-10371-2,for RW Scott,Be Renewed IAW 10CFR55.57.Individual Has Satisfactorily Discharged License Responsibilities Competently & Safely.Without Application ML20210N5471999-08-0505 August 1999 Requests That License SOP-10031-3,for DF Theders,Be Removed from Active Files for Ccnpp,Due to Individual Being Reassigned to Position No Longer Requiring License ML20210N9291999-08-0404 August 1999 Forwards Clarification to Initial Response to Biennial Rept on Status of Decommissioning Funding,As Required by 10CFR50.75(f)(1) ML20210J0741999-07-30030 July 1999 Expresses Appreciation for Participation in Y2K Training & Tabletop Exercise on 990714.Suggests Referral to NRC Y2K Web Site to View Issues & Lessons from Tabletop That Will Be Tracked by Nrc.Web Site Should Reflect Info within 2 Wks ML20211B5381999-07-30030 July 1999 Expresses Appreciation for Support in Y2K Training & Tabletop Exercise Held on 990714.Suggests Referral to NRC Y2K Web Site to View Issues & Lessons from Tabletop That Will Be Tracked by NRC ML20211C0951999-07-30030 July 1999 Expresses Appreciation for Participation in Y2K Training & Tabletop Exercise Held on 990714 ML20211C3251999-07-30030 July 1999 Expresses Appreciation for Participation in Y2K Training & Tabletop Exercise Held on 990714 ML20210E4941999-07-23023 July 1999 Informs That 1999 Emergency Response Plan Exercise Objectives Is Scheduled for Wk of 991025.Exercise Scenario Will Test Integrated Capability & Major Portion of Elements Existing within Emergency Response Plan ML20210D0911999-07-22022 July 1999 Responds to to Chairman Jackson Referring to Ltr from New 7th Democratic Civic Club,Inc.Forwards Staff Response to W Batton,President of New 7th Democratic Civic Club,Inc ML20210C5011999-07-21021 July 1999 Informs That SL Walters,License OP-10096-3 & CC Zapp,License Number SOP-2188-9,have Been Reassigned within Organization & No Longer Require NRC License,Per 10CFR50.74(a).Removal of Subject Licenses from Active Files for Ccnpp,Requested ML20210C2681999-07-20020 July 1999 Forwards Certified Copy of Listed Nuclear Liability Policy Endorsement,Per 10CFR140.15(e) ML20210A5021999-07-20020 July 1999 Responds to ,Expressing Support for Renewal of Operating Licenses for Calvert Cliffs Plant & to Concerns Re Lack of Specificity for License Renewal Regulations & Length of Time Set Aside for Public Comment ML20211N9101999-07-20020 July 1999 Forwards Correspondence Author Received from New 7th Democratic Club Civic,Inc Raising Some Serious Concerns About Renewal of Nuclear Reactor Licenses for Calvert Cliffs Power Plant ML20210C8461999-07-19019 July 1999 Informs That CF Farrow,License OP-10648-1,will No Longer Be Employed with Bg&E,As of 990709,per 10CFR50.74(a).Removal of Subject License from Active Files for Ccnpp,Requested ML20209J5171999-07-16016 July 1999 Forwards Comments from Accuracy Review of License Renewal Application SER ML20210B7651999-07-15015 July 1999 Forwards SER Denying Licensee Proposed TS Amend Dtd 981120, to Delete TS Requirements for Tendon Surveillance & Reporting Because TS Requirements Duplication of Requirements in 10CFR50.55a.Notice of Denial Encl ML20209G2081999-07-13013 July 1999 Forwards Insp Repts 50-317/99-05 & 50-318/99-05 on 990509- 0626.No Violations Noted ML20210A6311999-07-0606 July 1999 Discusses Closure of TACs MA0532 & MA0533 Re Response to Requests for Addl Info to GL 92-01,rev1,suppl 1, Reactor Vessel Structural Integrity, for Plant,Units 1 & 2 ML20209C1391999-07-0202 July 1999 Forwards Responses to Open & Confirmatory Items Based on Review of SER for Bg&E Application for Renewal of Operating Licenses for Calvert Cliffs.Bg&E Intends to Forward Comments Based on Accuracy Verification in Near Future ML20210D1531999-06-30030 June 1999 Informs of Receipt of from New 7th Democratic Civic Club,Inc Expressing Support for License Renewal. Requests Consideration in Addressing Concerns & Recommendations ML20209B5781999-06-29029 June 1999 Submits Response to GL 98-01, Y2K Readiness of Computer Sys at Nuclear Power Plants. GL 98-01 Requested Response on Status of Facility Y2K Readiness by 990701.Disclosure Encl ML20210D1741999-06-24024 June 1999 Expresses Opinions on Renewal of Nuclear Reactor Licenses Re Plant & Support Renewal Application of Bg&E.Requests That NRC Revise Procedures to Allow Sufficient Time for Public to Review,Evaluate & Respond to Info ML20211H8431999-06-23023 June 1999 Ack Participation of Calvert Cliffs Nuclear Engineering Dept in NRC Cooperative Research Project with Univ of Virginia. Copy of Relevant Portion of NRC Cooperative Agreement with Univ of Virginia Encl ML20196C6831999-06-21021 June 1999 Discusses Proposed Alternative Submitted by Bg&E for Calvert Cliffs NPP to Requirements of 10CFR50.55a(g)(4) in Regard to Compliance with Latest Approved Edition of ASME Code,Section XI for Third Ten Year Insp Interval Beginning on 990701 ML20196C4291999-06-21021 June 1999 Forwards Rev to ERDS Data Point Library for Ccnpp,Unit 2,per 10CFR50,App E,Section VI.3.a.Table Provides Brief Summary of Changes ML20195J8271999-06-16016 June 1999 Ack Receipt of to Jackson,Chairman of NRC Re Environ Impacts of Increased Patuxtent River Complex Flight Operations on Ccnpp.Clarification & Correction of Listed Statement Found on Page Two,Provided 1999-09-08
[Table view] Category:INCOMING CORRESPONDENCE
MONTHYEARML20217M9991999-10-22022 October 1999 Forwards Response to NRC 990930 RAI Re Void Swelling Degradation Mechanism,Per License Renewal Application for Ccnpp,Units 1 & 2 ML20216J8671999-10-0101 October 1999 Forwards Rev 52 to QA Policy for Calvert Cliffs Nuclear Power Plant. Rev Accurately Presents Changes Made Since Previous Submittal,Necessary to Reflect Info & Analyses Submitted to NRC or Prepared,Per to NRC Requirements ML20216H7831999-09-28028 September 1999 Forwards Addl Info Re NRC SER for Ccnpp,Units 1 & 2,per License Renewal Application ML20212D5361999-09-20020 September 1999 Forwards Rev 1 to Calculation CA04048, Fuel Handling Accident During Reconstitution, as Agreed During 990909 Telcon ML20212C1861999-09-15015 September 1999 Requests That NRC Complete Review of TR CED-387-P,Rev 00-P, Abb Critical Heat Flux Correlations for PWR Fuel, by 000201.Util Expects to Use ABB-NV Correlation for Current non-mixing Vane Fuel in Reload Analyses in 2000 for Ccnpp ML20211H9841999-08-31031 August 1999 Provides Comments Re Data Entered in Rvid for Ccnpp,Units 1 2,per GL 92-01,Rev 1,Suppl 1, Reactor Vessel Structural Integrity ML20210V1181999-08-17017 August 1999 Forwards Toxic Gases Calculations for Control Room Habitability,As Discussed During 990713 Telcon.Util Will Make Final Submittal for Toxic Gases After NRC Has Completed Review of ARCON96 ML20210T5061999-08-16016 August 1999 Forwards Rev 0 to Ccnpp COLR for Unit 2,Cycle 13, Per Plant TS 5.6.5 ML20210U2761999-08-13013 August 1999 Forwards Listed Info Re Guarantee of Payment of Deferred Premiums for Ccnpp,Units 1 & 2,IAW 10CFR140.21 Requirements ML20210S8101999-08-12012 August 1999 Forwards Application Requesting Renewal of License for Mv Seckens,License SOP-10369-2.Without Encl ML20210S8131999-08-12012 August 1999 Forwards Summary of Various Open Licensing Actions for Bg&E That Were Completed During Unit 2 Refueling Outage Ending 990506 ML20210S7901999-08-12012 August 1999 Forwards semi-annual Fitness for Duty Program Performance Data for Period of 990101-990630,IAW 10CFR36.71(d) ML20210N5881999-08-0606 August 1999 Forwards ISI Rept for Ccnpp,Unit 2,fulfilling Intentions & Requirements Stated in Program Plan & Commitment to Comply with ASME Code Section XI ISI Requirements ML20210N5491999-08-0505 August 1999 Requests That License SOP-10371-2,for RW Scott,Be Renewed IAW 10CFR55.57.Individual Has Satisfactorily Discharged License Responsibilities Competently & Safely.Without Application ML20210N5471999-08-0505 August 1999 Requests That License SOP-10031-3,for DF Theders,Be Removed from Active Files for Ccnpp,Due to Individual Being Reassigned to Position No Longer Requiring License ML20210N9291999-08-0404 August 1999 Forwards Clarification to Initial Response to Biennial Rept on Status of Decommissioning Funding,As Required by 10CFR50.75(f)(1) ML20210E4941999-07-23023 July 1999 Informs That 1999 Emergency Response Plan Exercise Objectives Is Scheduled for Wk of 991025.Exercise Scenario Will Test Integrated Capability & Major Portion of Elements Existing within Emergency Response Plan ML20210C5011999-07-21021 July 1999 Informs That SL Walters,License OP-10096-3 & CC Zapp,License Number SOP-2188-9,have Been Reassigned within Organization & No Longer Require NRC License,Per 10CFR50.74(a).Removal of Subject Licenses from Active Files for Ccnpp,Requested ML20210C2681999-07-20020 July 1999 Forwards Certified Copy of Listed Nuclear Liability Policy Endorsement,Per 10CFR140.15(e) ML20211N9101999-07-20020 July 1999 Forwards Correspondence Author Received from New 7th Democratic Club Civic,Inc Raising Some Serious Concerns About Renewal of Nuclear Reactor Licenses for Calvert Cliffs Power Plant ML20210C8461999-07-19019 July 1999 Informs That CF Farrow,License OP-10648-1,will No Longer Be Employed with Bg&E,As of 990709,per 10CFR50.74(a).Removal of Subject License from Active Files for Ccnpp,Requested ML20209J5171999-07-16016 July 1999 Forwards Comments from Accuracy Review of License Renewal Application SER ML20209C1391999-07-0202 July 1999 Forwards Responses to Open & Confirmatory Items Based on Review of SER for Bg&E Application for Renewal of Operating Licenses for Calvert Cliffs.Bg&E Intends to Forward Comments Based on Accuracy Verification in Near Future ML20210D1531999-06-30030 June 1999 Informs of Receipt of from New 7th Democratic Civic Club,Inc Expressing Support for License Renewal. Requests Consideration in Addressing Concerns & Recommendations ML20209B5781999-06-29029 June 1999 Submits Response to GL 98-01, Y2K Readiness of Computer Sys at Nuclear Power Plants. GL 98-01 Requested Response on Status of Facility Y2K Readiness by 990701.Disclosure Encl ML20210D1741999-06-24024 June 1999 Expresses Opinions on Renewal of Nuclear Reactor Licenses Re Plant & Support Renewal Application of Bg&E.Requests That NRC Revise Procedures to Allow Sufficient Time for Public to Review,Evaluate & Respond to Info ML20196C4291999-06-21021 June 1999 Forwards Rev to ERDS Data Point Library for Ccnpp,Unit 2,per 10CFR50,App E,Section VI.3.a.Table Provides Brief Summary of Changes ML20195J6591999-06-16016 June 1999 Submits Proposed Alternative to Requirements of 10CFR50.55a(g)(4) (Automatic Compliance with Latest Approved Edition of ASME Code Every 120 Months).Proposal Will Apply Third ten-year ISI Interval,Scheduled to Begin 990701 ML20207F0201999-06-0101 June 1999 Forwards Third Interval Inservice Insp Program Plan for Ccnpp,Units 1 & 2, for NRC Review.Plan Satisfies Commitment Contained in Licensee to NRC 05000317/LER-1999-002, Requests That Cover Page for LER 99-002,dtd 990525,be Corrected to Indicate Rept Is Submitted Per Requirements of 10CFR20.2201(b)1999-05-28028 May 1999 Requests That Cover Page for LER 99-002,dtd 990525,be Corrected to Indicate Rept Is Submitted Per Requirements of 10CFR20.2201(b) ML20195B2521999-05-25025 May 1999 Submits Response to RAI Re LAR for Tube Repair Using Leak Limiting Alloy 800 Sleeves for Ccnpp,Units 1 & 2.Test Repts Encl ML20195B3751999-05-25025 May 1999 Forwards ECCS Codes & Methods Rept, as Required by 10CFR50.46(a)(3)(ii) ML20195B2271999-05-24024 May 1999 Forwards Certified Copy of Nuclear Liability Policy NF-216, Endorsement 128 ML20206U3051999-05-19019 May 1999 Submits Written Rept as Required follow-up to Verbal Rept Given to NRC Regional Administrator on 990419 of SG Tube Insps Conducted,Cause of Tube Degradation & Corrective Measures Taken as Result of Insp Findings ML20206U8281999-05-18018 May 1999 Forwards Missing Pages C-30,C-31,C-114 & C-115 from 990319 Response to NRC RAI, Wind Tunnel Modeling of Calvert Cliffs NPP Cpp Project 94-1040. Complete Copy of 1985 Rept, Wind Flows & Dispersion Conditions of Calvert Cliffs, Encl ML20212G9751999-05-12012 May 1999 Forwards Draft write-up Re OI 16 for F Grubelich to Consider ML20206K6921999-05-10010 May 1999 Forwards Certified Copy of Listed Nuclear Liability Policy Endorsements,In Compliance with 10CFR140.15(e).Without Encl ML20206K1711999-05-0707 May 1999 Informs That on 990430 Util Filed Encl Articles of Share Exchange with Maryland Dept of Assessments & Taxation to Form Holding Company,Constellation Energy Group,Inc (Ceg). CEG Is Parent Company of Bg&E ML20206C7521999-04-29029 April 1999 Provides Rept of Number of Tubes Plugged in Calvert Cliffs Unit 2 SGs During Recently Completed Isi,As Required by Calvert Cliffs Unit 1,TS 5.6.9.a ML20206C7271999-04-28028 April 1999 Forwards Occupational Radiation Exposure Repts for 1998, as Required by Units 1 & 2 Tech Specs 5.6.1 & 6.1 of Isfsi. Repts Contain Tabulation of Number of Station,Util & Other Personnel Receiving Exposures Greater than 100 Mrem ML20212G9891999-04-28028 April 1999 Forwards Current Draft Response to Ci 3.3.2.2-1 to Be Used as Example for OI Vs License Condition Vs Commitment Situation ML20206C7211999-04-27027 April 1999 Forwards Addl Info Which Is Being Made Available in Encl Licensed Operators Fitness for Duty Questionnaire.Encl Specifics of Personal Info Are Withheld,Per 10CFR2.790 ML20212G9851999-04-26026 April 1999 Provides Proposed Response to OI 4.1.3-1 for B Elliott to Consider ML20206U6691999-04-26026 April 1999 Advises That Documents Re Operation of Calvert Cliffs Nuclear Power Plant Should Be Addressed to Listed Natl Marine Fisheries Svc Office ML20205F8851999-04-0202 April 1999 Provides First Annual Amend to Bg&E License Renewal Application for Ccnpp,Units 1 & 2,as Required by 10CFR54 ML20205J0691999-04-0202 April 1999 Forwards Response to NRC 990129 RAI Re GL 96-05, Periodic Verification of Design-Basis Capability of Safety-Related Movs ML20205G2971999-04-0101 April 1999 Requests That NRC Complete Review of Rev 0 to CENPD-396-P, Common Qualified Platform TR & Rev 0 to CE-CES-195-P, Software Program Manual for 'Common Q' Sys, by 990930 ML20205D7471999-03-30030 March 1999 Forwards Biennial Rept on Status of Decommissioning Funding, IAW 10CFR50.75(f)(1) ML20207G4391999-03-30030 March 1999 Responds to from Cl Miller,Requesting Assistance of FEMA in Addressing Concerns Received by NRC Involving Offsite Emergency Preparedness at Plant NPP ML20205C4091999-03-26026 March 1999 Submits Info Related to Scope,Risk Mgt & Summary of Risk for Performing Preventive Maintenance on P-13000-2 Unit Transformer Re License Amend 205 1999-09-28
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C u rusIs 11. C ut u Hahinmre Ons and Lieurie Cornpany Vice Preudent Cahert Clif fs Nuslear Power Plant Nucicar Energy 1650 Cah ett Chif 6 P,ukw ay i Lustiy. htaryland 20657 l 410 495-445$ I October 14,1997 U. S. Nuclear Regulatory C insion l
Washington, DC 20$55 ATTENTION: Document Control Desk SUILIECT: Calvert Clif1s Nuclear Power Plant Unit No- 1 & 2; Docket Nos. 50 317 & $0 318 Reactor Pressure Vessel Second Ten-Year Inservice 'nspection Relief Request to Use Performance Demonstration Imtlative Program as an Alternative to Code
}{tqukement
REFERENCES:
(a) latter from Mr. R. A. Capra (NRC) to Mr. G. C. Creel (PGE), dated January 11,19c0, Approval of Second Ten Year Inservice inspection Program Plan for Calvert Cliffs Units 1 and 2 (Unit i TAC 67094; Unit 2 TAC No. 67095)
(b) NRC Proposed Generic Communication; " Effectiveness of Ultrasonic Testing Systems in Inservice Inspection Programs," Federal Register I Notice, Volume 61 Number 2!2, December 31,1996 page 69117 (c) Letter from Mr. R. A. Capra (NRC) to Mr.1. Johnson (Comed), dated hiay 13,19P7, Evaluation of the First 10 Year Interval luspection Program Plan Request for Relief NR 29 Braidwood Station, Units 1 and 2 (TAC Nos. M97134 and M97135)
(e Meeting Summary by Mr. A. W. Dromerick (NRC), dated \
October 2,1997, Sunmary of August 27, 1997 Meeting Regarding Calvert Cliffs Nuclear Power Plant, Units Nos. I and 2 Reactor Pressure Vessel 10 Year Inservice inspection Project /
Pursuant to 10 CFR Part 50, Paragraph 50.55a(a)(3)(i), Baltimore Gas and Electric Company hereby proposes an alternative to the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code (Code) requirement concerning the Calvert Cliffs Nuclear Power Plant (CCNPP) reactor pressure vessel (RPV) Second Ten Year Inservice inspecti on (ISI). Calvert Cliffs Technical Specification 4.0.5 states in par *., " Inservice inspection of ASME Code Class 1,2, and 3 components
. . . shall be performed in accordance with Section XI of the ASME Boller and Pressure Vessel Code and applicable Addenda as required by 10 CFR 50, Section 50.55a(g) . . . ." Paragraph 50.55a(a)(3)(i) allows h ipo$ b b PDR-17 hl![Il$lhll! }l!'$lhll} l g '
Docum3nt Control Desk October 14,1997 Page 2 the use of alternatives to the requirements of Paragraph 50.55a(g), that provide an acceptable level of quality and safety, when authorized by the Director of the Ofuce of Nuclear Reactor Regulation.
The Second Ten Year ISI Program Plan for CCNPP, Units I and 2 meets the requirements of the 1983 Edition, Summer 1983 Addenda of Section XI of the ASME Code, as approved by Nuclear Regulatory Commission (NRC) letter dated January 11,1990 (Reference a). Table IWB 25001 in Section XI describes the method of examination for the components and parts of pressure retaining boundaries.
Article IWA 2232 of Section XI requires ultrasonic examination (UT) of vessel welds to be conducted in accordance with Article 4 of Section V. As an alternative, BGE proposes to use examination procedures, equipment, and personnel qualified by performance demonstration in accordance with the Performance Demonstration initiative (PDl) program.
The PD1 program was developed by the U.S. Nuclear Industry to manage implementation of the perfonnance demonstration criteria of Appendix Vill,Section XI of the ASME Code,1992 Edition, 1993 Addenda. Appendix Vill was developed to ensure the efTectiveness of the UT examinations within the nuclear industry by means of e rigorous, item specific, performance demonstration. The performance demonstration requires that equipment, procedures, and examlurs be tested on Dawed and notched materials and configurations similar to those found in actual plant conditions, llence, performance based UT techniques provide a higher degree of reliability for detection and characterization of flaw when compared to the conventional amplitude based UT techniques that is required by the current Code of record for CCNPP. The NRC staff has assessed the PDI program activities and found that the "PD1 has established and is in the process of executing a well planned and effective program . . . "(Reference b).
In addition, the NRC staff has recently approved the use ef PDI techniques at Commonwealth Edison Company's Braidwood Station for the first ISI interval to be implemented during the Units 1 and 21997 outages (Reference c).
On August 27,1997, we met with the NRC stafTto discuss our strategy for CCNPP Units I and 2 Second 10 Year RPV Inservice inspection (Reference d). During this meeting, we informed the staff of our plan to implement the PDI techniques by invoking Section XI, Paragraph IWA 2240, provision for alternative examinations. Instead, the stalt recommended that we submit a proposal in accordance with 10 CFR 50.55a(3) for their review and evaluation. At this meeting, we also infonned the staff of our intention to satisfy the 10 CFR 50.55a(g)(6)(ii)(A) " augmented," RPV inspection requirements, in addition to the Code Requirements during the Second 10 Year ISI.
COMPONENT FOR WHICH_RELLEF IS REOUESTED
+ Components that will be examined using PDI techniques only:
=> CCNPP Units I and 2 RPV Circumferential Welds (Weld Nos. 8-203,9 203,and 10 203)
=> CCNPP Units 1 and 2 RPV Longitudinal Welds (Weld Nos.1203A/B/C,2 203A/B/C, and 3 203Ml/C)
=> CCNPP Units I and 2 RPV Lower llead Welds (Weld Nos,4 204 and 1204 A)
D6cument Control Desk October 14,1997 Page 3 i
+ Components that will be examined using PD1 Techniques in Combination with AshtB Code Techniques:
o CCNPP Units 1 & 2 RPV Vessel to Flange Weld (Weld No. 7 203 This weld will be examined from the flange seal surface using AShiE Code techniques for detection of Daws parallel to the weld pinne Examination for transverse Daws will be conducted from the vessel inside surface using in u dmiques.)
o CCNPP Units 1 & 2 RPV Nozzle to-Shell Welds (Weld Nos.10 205A/I) and 4 205A/B/C/D PD) techniques will be applied from the vessel wall for detection of transverse reacctors. ar the detection of Daws that are parallel to the weld, examinations will be conducted from the nozzle bore using standard ASME Code techniques.)
CODE REOUlltEMENTS FOR WillCILRTLIEF IS llEQ1]ESIEI)
American Society of Mechanical Engineers Code,Section XI,1983 Edition, with the Summer 1983 Addenda, Subsection IWB, Table IWil 25004, Examination Cstegory B A Items 111.11. Bl.12,111.22, 111.30, and B D ltem 113.90 require volumetric examination. The requirements for volumetric examinations are stated in Article IWA 2232, which requires that examinations be conducted in accordance with Article 4 of Section V as amended by Section XI.
PROPOSED ALTERNATIVE Examination procedmes, equipment, and personnel qualified by performance demonstration will be utilized, in accordance with the PDI Program, in combination with Section V, Article 4 techniques.
Attachment (1) provides a comparison of the proposed PD1 technique for CCNPP and the standard Article 4,Section V and Regulatory Guide 1.150 procedures.
As a minimum, all Code requirements of the 1983 Edition through Summer 1983 Addenda of Section XI will be implemented, except where specific differences have been identi0ed in this submittal and Reference (a). ?n addition, as mentioned above, it is our intention to satisfy the 10 CFR 50.55a(g)(dii)(A)" augmented," RPV insp:ction requirements.
SUPPORTING INFORMATION llaltimore Gas and Electric Company has contracted with Southwest Research Institute (SwRI) to perfomi the Second Ten Year RPV examination using a combination of the PDI quali0ed techniques and ASME Section V Article 4 techniques. South', vest Research Institute's procedures were quali0ed in accordance with the PD1 program covering Supplements 4, " Qualification Requirements for the Clad / Base Metal Interface of Reactor Vessel,' and 6, "Quall0 cation Requirements for Reactor Vessel Welds Other than Clad /Dase Metal Interface," of Appendix Vill,Section XI ASME Code. Both double-and single sided approaches were qualined for Supplement 4 applicat!ons and for Supplement 6 applications up through 12 inch wall thicknesses. (Southwest R^ search Institute's PDI certification is on file at the Electric Power Research Institute Non-Destructive Examination Center in Charlotte, NC.)
Southwest Research Institute's PDI detection procedure utilizes two types of search units (55 degree, multibeam) when scanning can be accomplished from two sides of the weld, and three types of search units (45,55, and multibeam) when scanning can only be accomplished from one side of the weld. The
17ocument Control Desk
- October 14,1997 Page 4 multibeam search unit is used to examine the inner 25 percent thickness. The 45 and 55 degree shear.
wave search units are used to examine the outer 75 percent. A 0-degree search unit may also be used to detect laminar reDectors and determine component thickness. (NOTE: Baltimore Gas and Electric Company has instructed SwRI to scan from two sides of each weld whenever it is possible.) Scanning is performed: (1) perpendicular to the weld fer Daws orientated parallel to the weld; and (2) parallel to the weld for Daws orientated perpendicular (transverse) to the weld. Flaw discrimination inethods are independent of signal amplitude. Scanning sensitivities are determined based on the actual material noise.
Analysis and sizing of indications are performed by qualined Level 111 Data Analysts using SwRI procedures. Regardless whether the detection examinations are being performed per ASME Code or PDI procedures, SwRl's sizing procedures utilize tip-diffraction methods qua. lined in accordance with the PD1 guidelines.
SAFETY COMMrITEE REVIFM The proposed teller request has been reviewed by our Plant Operations and Safety Review Committee, and they have concluded that the proposed alternative provides an acceptable level of quality and safety.
SC11EllULE The Second Ten Year Calvert Cliffs Unit 1 RPV ISI is scheduled to take place during the spring 1998 refueling outage. We request that the NRC review and approve our proposed alternative by February 15,1998, to allow a timely preparation and implementation of the PDI procedures.
Should you have questions regarding this matter, we will be pleased to discuss them with you.
Very truly yours, f
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CilC/GT/bjd Attechment: (1) Comparison of Reactor Pressure Vessel Welds Examination Techniques cc: R. S, Fleishman, Esquire 11. J. Miller, NRC J. E. Silberg, Esquire Resident inspector, NRC Director, Project Directorate 1 1, NRC R.1. McLehn, DNR A. W. Dromerick, NRC J 11. Walter, PSC S. J. Todd, Sw R1
ATTACilMENT (1)
COMPARISON OF REACTOR PRESSURE VESSEL WELDS EXAMINATION TECIINIQUES Calvert Cliffs Nuclear Power Plant Units 1 and 2 October 14,1997
ATTACIIMENT m -
COMPARISON OF REACTOR PRESSURE VESSEL SIIELL WELD EXAMINATION TECtINIQUES 4 SnRI PDUAppendix VIII Qualified Procedser Description (Code Reference) .
Regulatory Guide I.150 Procedure :
Examination Angles Four transducers required to perfonn the detection Two types of search umts; a multibeam search unit scans 0*,45', and 60' plus a multibeam transducer and 55' search unit, are used to perform the double (Section V, T-441) for clad-to-base metal interface (Regulatory Guide sided detection examinations. i 1.150 requirement)is used. Three types of scarch units, multibeam; 45* and 55 s
. j
, are used for single sided detection examinations. The 7{
multibeam search units are used to examine the near surface, and the 45' and 55' search units are used to examine the remainder of the wall These examination angles were successfully qualified under the PDI protocol using the PDI g- cry uu test blocks.
Instrument Calibrations Section V requires that instrument screen height and SwRrs PDI-qualified procedure does not require that (Section V. T 431,Section XI, amplitude control linearity be evaluated at least every linearity checks be performed on site before and after IWA-2232) three months.Section XI requires that these linearity examinations because amplitude lineanty is not relied checks be performed before and after the upon for evaluation of flaws. SuRI does perform examinations performed during one outage. instrument linearity checks at least every 6 months as part of the maintenance and Loumucra certification Process.
System Calibrations Requires that the original system calibration be per- One calibration standard is used for the multibeam (Section V, T-435) formed on the Code basic calibration block. It allows search unit and another standard is used for the 45' the use of different types of reference blocks and and 55'scarr.h units. These standards contain a series electronic simulators to perform system calibration of side drilled holes and are used to establish a verifications. calibrated time base and initial sensithity. Periodic sweep calibration checks are made and sensitivity checks are made on the vessel wa!L I
A'ITACHMENT (1)
COMPARISON OF REACTOR PRESSURE VESSEL SHELL WEIE EXAMINATION TECHNIQUES Uf--- (Code Reference) R, Standard Secties
_ _y weide V,XI, 1.150 Precedere hRI N ( " VH1 W h Scanning Sensitivity Scanning is performed at the reference level Initial sensitivity is incicaxd. if m, until (Section V,T-425) sensitivity when electronic distance amplitude background noise from the riaterial in the correction (DAC) is used for automated examinations. examinaten area equals a level specified in the qualified procedure. This method of determining scanning sensitivity was successfully qualified under the PDI protocol using the PDI p vy.-- test blocks.
Recording level Section V requires recording and evaluation at 50% No amplitude thresholds are used. Data are recorded (Section V,T-44I) DAC. Regulatory Guide 1.150 requires recording and and evaluated independently of signal amplitude.
evaluation at 20% DAC for the inner 25% of material This evaluation method was successfully qualified thickness. under the PDI protocol using the PDI test blocks.
Scan Index, Pulse Repetition Sec'?ou V requires a minimum merement overlap of Scanning overlap is 10 % for the near surface Rate 10% of the dimension of the piezoelectric element multibeam search units and 40% for the other (Section V, T-425 and Section between scans.Section XI requires 50% overlap detection search units, as qualified under the PDI XI,IWA-2232) when not scanning in beam direction. Regulatory protocol using the PDI test blocks. Pulse repetition Guide 1.150 requires 25% minimum overlap for rate is set such that data are collected at 0.040-inch detection and 0.25' maximum increment for increments in the directen ofscan.
characterization.Section XI also requires a pulse repetition rate sufficient to provide at least 10 %
overlap of the minimum beam dimension.
F:aw Sizing and Evaluation Amplitude based sizing at 50 % DAC. Other Multibeam tip diffraction techniques are used for (Section V,T 441 and T-451) techniques and methods may be used. through-wall sizing. The length sizing is accom-plished using amplitude drop methods. Beam spicad calculations are not pu foi o.cd for these keniqws.
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