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Category:CORRESPONDENCE-LETTERS
MONTHYEARML20217B3331999-10-0707 October 1999 Responds to 990825 Telephone Call Re Presense of Polychlorinated Biphenyl Wastes at Plant,Unit 1 ML20212F4481999-09-17017 September 1999 Forwards NRC Form 536 Containing Currently Proposed Site Specific Operator Licensing Exam Schedule & Estimates of Number of Applicants for Generic Fundamentals Exams Through Cy 2003 ML20212F7051999-09-14014 September 1999 Forwards Rev 19 to Ipn,Units 1 & 2 Physical Security Plan. Plan Withheld,Per 10CFR2.790(d) & 73.21 ML20211N0681999-09-0202 September 1999 Informs That Commission Requested Publication of Notice of Consideration of Issuance of Amend to Fol,Proposed NSHC Determination & Opportunity for Hearing. Amend Changes Senior Reactor License Requirement for Operations Manager ML20211H6291999-08-26026 August 1999 Forwards NPDES Discharge Monitoring Rept for July 1999 for Indian Point,Units 1,2 & 3. Rept of Noncompliance Is Attached for Noncompliance Which Occurred at Unit 3 ML20211E1531999-08-18018 August 1999 Forwards Semi Annual fitness-for-duty Program Performance Data for 990101-990630,IAW 10CFR26.71(d) ML20211H6051999-08-18018 August 1999 Forwards Rev 8 to Security Force Training & Qualification Plan, for Indian Point 3 Nuclear Power Plant.Rev Facilitates Transition of Duty Weapons Carried by Security Force Members from Revolvers to Semiautomatic Pistols ML20211A9241999-08-11011 August 1999 Informs That IPS Currently Estimates,That Approx Two Licensing Actions Will Be Submitted to NRC During Remainder of 1999 NRC Fiscal Yr & Approx Ten Will Be Submitted During 2000 NRC Fiscal Yr ML20210M7251999-07-26026 July 1999 Forwards Projection of Ability to Pay Retrospective Premium Adjustment for Period of Aug 1999 to 000731, Which Demonstrates That Ceny Will Have Sufficient Cash Flow &/Or Cash Reserve Available Throughout Period to Pay Premium ML20210G8911999-07-20020 July 1999 Forwards Application for Amend to License DPR-5 for Proposed New TS 3.2.1.i,revising Senior Reactor License Requirement for Operations Manager ML20209B6611999-06-29029 June 1999 Returns Recently Submitted Renewal Applications,Nrc Form 398,for Three Reactor Operators,As They Are Not Completed Properly.List of Docket Numbers & Block Numbers That Contain Incorrect Info & Block Numbers Not Completed.Without Encls ML20196A6371999-06-15015 June 1999 Forwards Rev 19 to Physical Security Plan.Rev Withheld,Per 10CFR2.790(d) & 73.21 ML20207D1861999-05-27027 May 1999 Informs That Effective 990328,NRC Office of NRR Underwent Reorganization.Mt Masnik Section Chief for Indian Point Station,Unit 1.JL Minns Remains Primary Contact for All Routine Licensing & Administrative Matters.Chart Encl ML20205R1981999-04-15015 April 1999 Requests That Dept of Environ Conservation Modify SPDES Permit for IPS IAW Proposed Rev Attached & Described as Listed ML20205R2961999-04-15015 April 1999 Forwards Copy of Proposed Change to Indian Point SPDES Permit NY0004472.Proposed Change Requests Permission to Add Permitted Outfall to Plant as Well as Change Character of Existing Outfall.Without Encl ML20196K8111999-03-31031 March 1999 Forwards Decommissioning Funding Status Rept for Indian Point,Units 1 & 2 Through 981231 ML20205F9711999-03-25025 March 1999 Informs That Under Separate Cover,Licensee Transmitted to Ofc of Nuclear Regulatory Research Annual Rept of Results of Individual Monitoring at Indian Point,Units 1 & 2,for CY98 ML20204F7931999-03-17017 March 1999 Forwards Table Outlining Nuclear Property Insurance Which Has Been Placed on Behalf of Consolidated Edison Co of Ny, Inc.Insurance Covers Indian Point,Units 1 & 2 ML20204J9971999-03-0909 March 1999 Forwards Insp Rept 50-003/98-19 on 981130-990222.No Violations Noted ML20203B9001999-02-0808 February 1999 First Partial Response to FOIA Request for Documents. Forwards Documents Listed in App a Already Available in PDR, Documents in App B Released in Entirety & Documents in App C Being Withheld in Part (Ref Exemption 6) ML20202J6171999-02-0505 February 1999 Forwards Transcript from 990120 Public Meeting Held in Peekskill,Ny Re Decommissioning ML20199H3731999-01-11011 January 1999 Informs That T Schmeiser,Con Ed Plant Manager for Plant Is Retiring,Effective 990111.AA Blind Will Assume Duties & Responsibilities of Plant Manager Until Replacement Named ML20198E9561998-12-21021 December 1998 Forwards Order Prohibiting Involvement in NRC Licensed Activities Re Deliberate Misconduct in Violation of Regulation When False Info Was Provided to Two NRC Licensees ML20198C2371998-12-15015 December 1998 Ltr Contract:Task Order 237, Review & Evaluation of Indian Point 3 Nuclear Power Plant Application for Conversion to Improved TS, Under Contract NRC-03-95-026 ML20198C4911998-12-11011 December 1998 Forwards Rev 18 to Physical Security Plan,Reflecting Organizational Changes & Incorporating Administrative Corrections & Clarifications.Encl Withheld ML20198C3251998-12-11011 December 1998 Responds to ,Responding to NRC Ltr Re Concerns Raised About Potential Chilling Effect from Temp Denial of Site Access to Employee Raising Safety Issues to Util Senior Mgt ML20155H2901998-11-0303 November 1998 Responds to to Lj Callan Expressing Concern About Continued Operation of Indian Point Nuclear Generating Station.Explanation Why NRC Do Not Think Revoking OLs for Indian Point Units 2 & 3 Justified,Provided ML20155F9181998-10-28028 October 1998 Forwards Changes to SPDES Permit,Removing Requirement to Monitor Svc Boiler Blowdown for Phosphates,Eliminate Redundant Sampling of Oil or Grease Entering Flow Tributary to Floor Drains,Per Ts,App B,Section 3.2 ML20155D2791998-10-23023 October 1998 Forwards Corrected Pages for Indian Point Annual Radiological Environ Operating Rept for 1997 ML20154Q1761998-10-21021 October 1998 Second Final Response to FOIA Request for Documents. Documents Listed in App C Being Withheld in Part (Ref FOIA Exemption 7) ML20154L8031998-10-16016 October 1998 Ack Receipt of & Payment in Amount of $55,000 in Electronic Funds for Civil Penalty Proposed by NRC in .Corrective Actions Will Be Examined During Future Insp ML20155H3021998-09-24024 September 1998 Urges NRC to Revoke Operating Licenses for Indian Point Nuclear Generating Station,Units 2 & 3 & Not Renew OL for Unit 1 ML20154A1391998-09-22022 September 1998 Informs That Effective 980724,AA Blind Assumed Position of Vice President,Nuclear Power & Ja Baumstark Assumed Position of Vice President,Nuclear Power Engineering,Effective 980813 ML20153F0661998-09-18018 September 1998 Provides Response to Violations Noted in Insp Rept 50-286/98-05 & Proposed Imposition of Civil Penalty Dtd 980819.Corrective Actions:Existing Drawings for Spare Switchgear Cubicles Have Been Revised ML20151W4871998-09-10010 September 1998 Informs That as Part of NRC Probabilistic Risk Assessment Implementation Plan,Commission Assigned Two Senior Reactor Analysts (Sras) to Each Regional Ofc.T Shedlosky & J Trapp Has Been Assigned as SRAs for Region I ML20151W9511998-09-10010 September 1998 Informs That as Part of NRC PRA Implementation Plan, Commission Has Assigned Two Senior Reactor Analysts (Sras) to Regional Ofc.T Shedlosky & J Trapp Has Been Assigned SRAs Duties for Region I ML20155F4391998-08-26026 August 1998 Forwards Demand for Info,Being Issued to Enable NRC to Fully Understand Recipient Views on Facts & Circumstances Surrounding Allegedly False Info Provided to Two NRC-licensed Activities ML20238F5151998-08-26026 August 1998 First Partial Response to FOIA Request for Documents. Documents Listed in App a Being Released in Entirety. Documents Listed in App B Being Withheld in Part (Ref FOIA Exemption 6) IR 05000286/19980051998-08-19019 August 1998 Discusses Insp Rept 50-286/98-05 on 980528-0612 & Forwards NOV & Proposed Imposition of Civil Penalty in Amount of $55,000.Most Significant Violation Involved Failure, Following Design Mod in Oct 1997 ML20237B1001998-08-0505 August 1998 Responds to NRC Re Violations Noted in Insp Repts 50-247/97-13,50-247/97-15,50-247/98-02 & Investigation Rept 1-97-038,respectively.Corrective Actions:Acted Promptly to Assure Conforming to Testing Requirements ML20236X8511998-07-31031 July 1998 Forwards Rept Re Projection of Ability to Pay Retrospective Premium Adjustment for Period 980801-990731,per 10CFR140.21 ML20236V4211998-07-13013 July 1998 Forwards SER Approving Topical Repts WCAP-14333P & WCAP-14334NP (Proprietary & non-propiretary, PRA of RPS & ESFAS Test Times & Completion Times ML20236Q1431998-07-0808 July 1998 Responds to Administrative Ltr 98-03 Re Operating Reactor Licensing Action Estimates IR 05000247/19970131998-07-0606 July 1998 Discusses Insp Repts 50-247/97-13,50-247/97-15 & 50-247/98-02 & Forwards Notice of Violation & Proposed Imposition of Civil Penalty in Amount of $110,000 ML20238F5231998-06-29029 June 1998 FOIA Request for Documents Re NRC Office of Investigation Rept 1-97-038,meeting Minutes of Summary of Enforcement Conference on 980506 & Meeting Minutes or Summary of 980520 Predecisional Enforcement Conference ML20154Q1831998-06-29029 June 1998 FOIA Request for Documents Re NRC OI Rept 1-97-038,meeting Minutes of Summary of Enforcement Conference on 980506 & Meeting Minutes or Summary of 980520 Predecisional Enforcement Conference ML20236J9871998-06-24024 June 1998 First Final Response to FOIA Request for Documents.Documents Listed in App a Already Available in Pdr.Documents Listed in App B Being Released in Entirety ML20248F2891998-05-26026 May 1998 Ltr Contract:Task Order 8, Indian Point 2,A/E Follow-up Insp, Under Contract NRC-03-98-021 ML20248L9861998-05-21021 May 1998 Forwards Rev 7 to Security Force Training & Qualification Plan.Review to Verify Receipt of Revised Plan & Sign & Return Receipt Ack Form Provided ML20247M6951998-05-20020 May 1998 Forwards RAI Re GL 96-06, Assurance of Equipment Operability & Containment Integrity During Design-Basis Accident Conditions, for Plant,Unit 2 1999-09-02
[Table view] Category:INCOMING CORRESPONDENCE
MONTHYEARML20212F4481999-09-17017 September 1999 Forwards NRC Form 536 Containing Currently Proposed Site Specific Operator Licensing Exam Schedule & Estimates of Number of Applicants for Generic Fundamentals Exams Through Cy 2003 ML20212F7051999-09-14014 September 1999 Forwards Rev 19 to Ipn,Units 1 & 2 Physical Security Plan. Plan Withheld,Per 10CFR2.790(d) & 73.21 ML20211H6051999-08-18018 August 1999 Forwards Rev 8 to Security Force Training & Qualification Plan, for Indian Point 3 Nuclear Power Plant.Rev Facilitates Transition of Duty Weapons Carried by Security Force Members from Revolvers to Semiautomatic Pistols ML20211E1531999-08-18018 August 1999 Forwards Semi Annual fitness-for-duty Program Performance Data for 990101-990630,IAW 10CFR26.71(d) ML20211A9241999-08-11011 August 1999 Informs That IPS Currently Estimates,That Approx Two Licensing Actions Will Be Submitted to NRC During Remainder of 1999 NRC Fiscal Yr & Approx Ten Will Be Submitted During 2000 NRC Fiscal Yr ML20210M7251999-07-26026 July 1999 Forwards Projection of Ability to Pay Retrospective Premium Adjustment for Period of Aug 1999 to 000731, Which Demonstrates That Ceny Will Have Sufficient Cash Flow &/Or Cash Reserve Available Throughout Period to Pay Premium ML20210G8911999-07-20020 July 1999 Forwards Application for Amend to License DPR-5 for Proposed New TS 3.2.1.i,revising Senior Reactor License Requirement for Operations Manager ML20196A6371999-06-15015 June 1999 Forwards Rev 19 to Physical Security Plan.Rev Withheld,Per 10CFR2.790(d) & 73.21 ML20205R2961999-04-15015 April 1999 Forwards Copy of Proposed Change to Indian Point SPDES Permit NY0004472.Proposed Change Requests Permission to Add Permitted Outfall to Plant as Well as Change Character of Existing Outfall.Without Encl ML20196K8111999-03-31031 March 1999 Forwards Decommissioning Funding Status Rept for Indian Point,Units 1 & 2 Through 981231 ML20205F9711999-03-25025 March 1999 Informs That Under Separate Cover,Licensee Transmitted to Ofc of Nuclear Regulatory Research Annual Rept of Results of Individual Monitoring at Indian Point,Units 1 & 2,for CY98 ML20204F7931999-03-17017 March 1999 Forwards Table Outlining Nuclear Property Insurance Which Has Been Placed on Behalf of Consolidated Edison Co of Ny, Inc.Insurance Covers Indian Point,Units 1 & 2 ML20199H3731999-01-11011 January 1999 Informs That T Schmeiser,Con Ed Plant Manager for Plant Is Retiring,Effective 990111.AA Blind Will Assume Duties & Responsibilities of Plant Manager Until Replacement Named ML20198C4911998-12-11011 December 1998 Forwards Rev 18 to Physical Security Plan,Reflecting Organizational Changes & Incorporating Administrative Corrections & Clarifications.Encl Withheld ML20155F9181998-10-28028 October 1998 Forwards Changes to SPDES Permit,Removing Requirement to Monitor Svc Boiler Blowdown for Phosphates,Eliminate Redundant Sampling of Oil or Grease Entering Flow Tributary to Floor Drains,Per Ts,App B,Section 3.2 ML20155D2791998-10-23023 October 1998 Forwards Corrected Pages for Indian Point Annual Radiological Environ Operating Rept for 1997 ML20155H3021998-09-24024 September 1998 Urges NRC to Revoke Operating Licenses for Indian Point Nuclear Generating Station,Units 2 & 3 & Not Renew OL for Unit 1 ML20154A1391998-09-22022 September 1998 Informs That Effective 980724,AA Blind Assumed Position of Vice President,Nuclear Power & Ja Baumstark Assumed Position of Vice President,Nuclear Power Engineering,Effective 980813 ML20153F0661998-09-18018 September 1998 Provides Response to Violations Noted in Insp Rept 50-286/98-05 & Proposed Imposition of Civil Penalty Dtd 980819.Corrective Actions:Existing Drawings for Spare Switchgear Cubicles Have Been Revised ML20237B1001998-08-0505 August 1998 Responds to NRC Re Violations Noted in Insp Repts 50-247/97-13,50-247/97-15,50-247/98-02 & Investigation Rept 1-97-038,respectively.Corrective Actions:Acted Promptly to Assure Conforming to Testing Requirements ML20236X8511998-07-31031 July 1998 Forwards Rept Re Projection of Ability to Pay Retrospective Premium Adjustment for Period 980801-990731,per 10CFR140.21 ML20236Q1431998-07-0808 July 1998 Responds to Administrative Ltr 98-03 Re Operating Reactor Licensing Action Estimates ML20238F5231998-06-29029 June 1998 FOIA Request for Documents Re NRC Office of Investigation Rept 1-97-038,meeting Minutes of Summary of Enforcement Conference on 980506 & Meeting Minutes or Summary of 980520 Predecisional Enforcement Conference ML20154Q1831998-06-29029 June 1998 FOIA Request for Documents Re NRC OI Rept 1-97-038,meeting Minutes of Summary of Enforcement Conference on 980506 & Meeting Minutes or Summary of 980520 Predecisional Enforcement Conference ML20248L9861998-05-21021 May 1998 Forwards Rev 7 to Security Force Training & Qualification Plan.Review to Verify Receipt of Revised Plan & Sign & Return Receipt Ack Form Provided ML20217F8501998-03-20020 March 1998 Forwards Table Which Outlines Nuclear Property Insurance That Has Been Placed on Behalf of Util,Per 10CFR50.54(w)(3) ML20199L9531998-01-26026 January 1998 Forwards Addl Info on Rev 6 to Security Force Training & Qualification Plan,Per 980113 Telcon Request of G Smith.Encl Withheld ML20199F7541998-01-21021 January 1998 Forwards Rev 17 to Physical Security Plan,Per Requirements of 10CFR50.54(p).Rev 17 Contains Summary of Changes, Detailing Changes Incorporated.Encl Withheld ML20198N1151998-01-20020 January 1998 Submits Status of Response to NRC Request for Addl Info, for Licenses TR-3 & R-93.Request for Commitment to Complete Decommissioning Activities by 2007 Has Been Persued Up Through Nasa Mgt ML20202F8281997-11-26026 November 1997 Reports Mod to Indian Point SPDES Permit as Required in Ts. Copy of New York State Dept of Environ Conservation Ltr That Modifies Permit Is Encl ML20198P7901997-10-31031 October 1997 Forwards Rev 6 to Physical Security Plan,Per 10CFR50.4(b)(4) to Meet Requirements of 10CFR50.54(p).Rev 16 Contains Summary of Changes, Detailing Changes Incorporated. Encl Withheld ML20198P3181997-10-30030 October 1997 Forwards Corrected Pages to Annual Radiological Environ Operating Rept for 1996 ML20211H7771997-10-0202 October 1997 Forwards Responses to RAIs 650.1 Through 650.8 Re Generic Issues & Generic Communications on Valve Testing & Valve Qualification.Westinghouse Status for Subject Issues Will Be Confirm W Pending Rev to Ssar & WCAP-13559 ML20211B4241997-09-19019 September 1997 Requests Withdrawal of Revs 16 & 18 to Physical Security Plan.Rev 16 re-submitted Per Provisions of 10CFR50.54(p)(2) & Deals W/Specific Operational Criteria of New Sys.Plan Withheld ML20211A9411997-09-18018 September 1997 Responds to NRC Re Violations Noted in Insp Rept 50-286/97-80.Corrective Actions:Revised Administrative Procedure AP-3 to Establish Responsibility for Engineering Review & Revised EOP ES-1.3 ML20149J2491997-07-16016 July 1997 Forwards Environ Ts/Nonroutine Event Rept for Units 1 & 2. Appropriate Ny State Agency Notified ML20148S5731997-06-26026 June 1997 Forwards Response to NRC Re Violations Noted in Insp Repts 50-247/96-80;96-07;96-08;97-03 & Imposition of Civil Penalties on 961027-970405.Corrective Actions:Unique Tag Numbers for Louvers Were Generated ML20148J1431997-06-0404 June 1997 Forwards Rev 15A to Ipn Units 1 & 2 Physical Security Plan, Per 10CFR50.54(p)(2).Plan Withheld ML20137M8371997-04-0101 April 1997 Provides Supplemental Response to RAI Re TS Change Request 96-01 on Conversion to Framatome Cogema Fuel.Tech Specs, Encl ML20137A8301997-03-13013 March 1997 Forwards Response to NRC Ltr Re Violations Noted in Insp Rept 50-286/96-80 on 961213.Corrective Actions:Expert Panel Has Agreed to Include Turbine Bldg & Power Conversion Equipment Bldg in Scope of IP3 Maint Rule Program JPN-97-008, Forwards Comments on Draft NUREG-1560, IPE Program: Persprctives on Reactor Safety & Plant Performance1997-03-0404 March 1997 Forwards Comments on Draft NUREG-1560, IPE Program: Persprctives on Reactor Safety & Plant Performance ML1004713451997-02-26026 February 1997 Forwards Proprietary & non-proprietary Versions of W Rept Entitled, Conditional Extension of Rod Misalignment TS for Indian Point 3. Authorization Ltr & Affidavit,Encl. Proprietary Encl Withheld Per 10CFR2.790 ML20135C7121997-02-21021 February 1997 Forwards Table That Outlines Nuclear Property Insurance on Behalf of Util Covering Units 1 & 2 ML1004713471997-02-18018 February 1997 Authorizes Utilization of Encl Affidavit by Util Re WCAP-14669,Rev 1, Conditional Extension of Rod Misalignment TS for Indian Point 3. Rept Should Be Withheld Per 10CFR2.790(b)(4) ML20134N6481996-12-24024 December 1996 Provides Further Details Re Corporate Reorganization of Consolidated Edison Co of Ny for Indian Point Units 1 & 2 ML20132C8071996-12-12012 December 1996 Forwards Check for $100 for Payment of NRC Invoice 7I0053 for Indemnity Fee on License DPR-5 for One Year Period 961204-971203.W/o Check ML20129D9611996-10-11011 October 1996 Forwards Controlled Copy of Plant Physical Security Plan,Rev 18,re Access Control Upgrade Which Adopts Biometric Hand Geometry.W/O Encl ML20117P6151996-09-11011 September 1996 Forwards Rev 9 to Security Training & Qualification Plan.W/O Encl ML20117E3891996-08-21021 August 1996 Forwards Four Copies of IP3 Security Contingency Plan,Rev 4. W/O Encl JPN-96-035, Informs NRC That Boraflex Not Used as Neutron Absorber in Either Util or Plant Spent Fuel Pool Storage Racks,Per GL 96-041996-08-0606 August 1996 Informs NRC That Boraflex Not Used as Neutron Absorber in Either Util or Plant Spent Fuel Pool Storage Racks,Per GL 96-04 1999-09-17
[Table view] Category:RESEARCH INSTITUTION/LABORATORY TO NRC
MONTHYEARML20245B5201987-05-28028 May 1987 Comments on Licensee Proposed Techniques for Augmented Inservice Insp Program of Lower Shell Longitudinal Weld at 345 Degrees of Reactor Vessel.Techniques Acceptable.Work Assignment 87-1 Re Flaw Indication Evaluation Encl ML20106A5601984-08-29029 August 1984 Summarizes 840815-17 Meetings & Lab Demonstrations Re Review & Evaluation of Reactor Vessel UT Indication ML20069N7551982-10-20020 October 1982 Forwards Review of Indian Point Probabilistic Safety Study ML20105B4071982-08-25025 August 1982 Forwards Draft, Ltr Rept on Review of Evaluation of Indian Point Probabilistic Safety Study ML19354C4661981-03-18018 March 1981 Ack Receipt of Documents Re Reactor Pressure Vessel Thermal Shock Event at Facility.Basis Should Be Given for Assuming That flaw,1-inch Deep,Is Conservative ML19345D4541980-11-0707 November 1980 Submits Completed Calculations Supporting NRC Review of Station Fuel Storage Rack Submittal ML1003407191980-09-26026 September 1980 Forwards Interim Technical Evaluation Rept, Fracture Toughness of Steam Generator & Reactor Coolant Pump Supports. ML19275J2101980-04-30030 April 1980 Forwards Containment Leakage Rate Testing,Indian Point Unit 2, Technical Evaluation Rept ML19261C2201979-02-23023 February 1979 Responds to 790129 Request to Review Pressure Vessel Fluence Calculations.Finds That Despite Some Uncertainties, Calculated Values Are in Good Agreement W/Empirical Fluence ML19269B9501978-12-28028 December 1978 Proposed Fire Protection Presented in SER Has Been Reviewed & Found Acceptable.Exceptions Re Valve Supervision,Hose Coupling Gaskets,Hose Stations,Smoke Removal & Turbine Bldg Must Be Evaluated by NRC ML20084B3541972-06-19019 June 1972 Trip Rept of Visit to Westinghouse Nuclear Fuel Div Re Design,Qa & Fabrication of Fuel Rod Clusters & Associated Guide Thimbles Supplied by Westinghouse to Facility 1987-05-28
[Table view] |
Text
- . . . . . _ _ . _
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Sandia National Laboratories Albuquerque, New Mexico 87185 August 29, 1984 1
e Mr. Louis Frank USliRC
- Materials Engineering Branch
- Washington, DC 20555
Dear Mr. Frank:
1.
Subject:
Review and Evaluation of the Indian Point 2 Reactor Vessel UT. Indication
? -
.On August 15,16, and 17, 1984 meetings and laboratory demonstrations
, .on'the basic calibration block used at Indian Point 2 and a full-thickness mockup block were attended at Westinghouse, Pittsburgh.
The data presented by Westinghouse in-these demonstrations were intended to show that the flaw indication in the Indian Point 2 vessel at 236 inch elevation and 345 1/2 degree azimuth was approximately 0.3 inches deep. The 0.3 inch depth evaluation was based on the ultrasonic examinations performed with the pitch-catch and delta technique.
- The first demonstration performed by Westinghouse was a full scale calibration with beam spread measurements of the 60 degree angle beam examination on the flat basic calibration. block. After this n '
calibration, a scan of 5 OD notches was performed on the' full-thickness mockup' block which simulated the actual vessel curvature and cladding surface. This demonstration was to.show that the
, correct beam angle of the examination was.56 degrees instead of the nominal 60 degrees and that the 56 degree angle was experimentally verified on'the curved mockup block. Although a larger signal, by as much as 30.dB, was obtained from the same size notch in the mockup as in the basic-calibration block, the calculated beam angles for the 1/2 maximum, maximum, and.1/2 maximum amplitudes were 54.64, 56.02, and 58.39 degrees for the basic calibration block and 54.61, 55.76, and 58.81 degrees for the mockup. Therefore, it is concluded that an angle of 56 degrees is appropriate for calculating path lengths and 50% DAC points according to ASME code requirements. The beam spread contributes to oversizing the flaw indication by the 50%
. DAC method.
The increased signal is thought to be partly due to the converging lens effect of the ID curvature of the mockup on the broad immersion
-beam. Figure 1 illustrates the difference in the refracted beam
. widths due to a flat and curved surface. The measured beam widths given above, however, are in very good agreement which indicates that some-other reason for the 30 dB increase in signal is responsible, Y
fyhbIhhh f h<p262(o2. go-1MT > g40YLJ A
. y Mr. Louis Frank August 29,1984 i
A 45 degree demonstration was not conducted but the same conclusions in all respects can be made. From the 45 degree calibration sheets for the vessel UT examination, a 43.7 degree angle for transducer TR22 and a 43.8 degree angle for TRh4 were caluclated from the notch indication of the basic calibration block. Therefore, since the pitch-catch and delta techniques used these transducers, an angle of 43.7 seems appropriate in all metal path and flaw depth calculations.
Th 'second demonstration performed by Westinghouse showed use of the delta technique to collect time interval data for artificial reflectors (slots) which were machined in the OD portion of the mockup. Two sI'~ o ts in the center of the mockup were 0.385 inches deep and 0.985 inches deep. The response and time interval measurements from these slots are to be compared with values
, measured for the actual Indian Point 2 vessel crack indication.
During this demonstration, time interval measurements were measured
~
and jotted down for appropriate ' peaks of the diffracted waves as the slots were scanned. Figure 2 shows where this data falls with respect to theoretical values calculated by time-of-flight information of the S-wave and diffracted L-wave for the geometry of the vessel which is illustrated in Figure 3. The shortest time interval recorded in the demonstration for the 0.385 inch slot was 129.9 microseconds and for the 0.985 inch slot it was 118.9
' microseconds. For these time intervals and from a calculation of the slot depth using the 9 inch block thickness, values of 0.24 inches 1.
and 1.02 inches are calculated for the slot depths.
The time interval can be measured to within 0.1 microsecond so that e depth information can be potentially determined to within 0.01 inch.
Knowing the exact geometry of beam angle, vessel thickness, and determining the water path delay accurately, may be the greatest sources of error. The demonstration was set up in a hurry and some
, of these factors may haved influenced the time interval measurements of the slots. The main purpose of the demonstration was.to experimentally show NRC and consultants that the tip diffracted L-wave was present and could be used to make depth measurements of the crack indication in the vessel. Even so, the determined slot depths l- lar this technique for the demonstration were in good agreement with i
actual values as shown in Figure 2. i 1.
I Assuming that an ideal geometry is known for the vessel indication, '
l the crack depth for the observed shortest time interval measurement I
of 130.0 microseconds is 0.14 inches for a 43.7 degree S-wave and l
- 0.26 inches for a 45 degree S-wave. Therefore, the 0.3 inch depth !
l evaluation by Westinghouse is valid.
h The third demonstration performed by Westinghouse showed the l amplitude shadowing responses of the slots in the pitch-catch mode
\
l l
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i Mr. Louis Frank August 29,1984 of operation which i$ also illustrated in Figure 3. This demonctration verified that a significant reduction of the received signal was observed (100% to 15%) as the beam traversed the 0.985 depth clot and only a slight reduction was observed as the 0.385 depth' slot was scanned. However, shadowing of the signal during the vessel examination was inconclusive since similar amplitude reductions-were observed in locations away from the crack indication and exact positions of the pitch-catch transducers with respect to the crack indication could not be determined from the video tape '
dat'a. - For this demonstration, the 2S time interval measurement was ,
. 188.9 microseconds which is in good agreement with the theoretical values of 188.2 for a 9.0 inch thickness and a 43.7 degree angle beam. The theoretical value for a 45 degree angle beam is 191.8
' microseconds. , ,
Sincerely, c J. H. Gieske Nondestructive Testing Technology Division 7552 9
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TRANSDUCER 4
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BEAM t BEAM WIDTHF OR WIDTH CURVED FOR FLAP SURFACE, SURFACE Figure 1. Refractive Beam Widths as a Function of a Flat Surface or a curved Surface.
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EXPERIMENTALLY OBSERVED 4
TIP & BASE DIFFRACTED L-WAVES-
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+ OBSERVED TIME INTERVAL FOR -
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THE INDICATION IN'THE VESSEL._
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- THEORETICAL CURVE Q '6 FOR A 45 DEGREE S WAVE l -
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TIME INTERVAL CMICROSECONDS) i FIGURE 2. CRACK THROUGH WALL DEPTH VERSUS TIME INTERVAL RESULTING I ~
FROM A TIP DIFFRACTED L-WAVE AT 0 DEGREES FOR INCIDENT -
- S-WAVES AT 45 AND 43.7 DEGREES.
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1 TRANSDUCER CONFIGURATION
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PITCH DELTA CATCH 4
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S-WAVES Figure 3. Geometry of the Delta and Pitch -Catch Techniques.