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Category:CORRESPONDENCE-LETTERS
MONTHYEARML20217N8911999-10-15015 October 1999 Forwards Rept of Changes,Tests & Experiments at Pilgrim Nuclear Power Station for Period of 970422-990621,IAW 10CFR50.59(b).List of Changes Effecting Fsar,Encl ML20217D3951999-10-13013 October 1999 Forwards Request for Addl Info Re Util 990806 Submittal on USI A-46, Implementation Methodology Used at Pilgrim Nuclear Power Station, Per GL 87-02 ML20217E1581999-10-0808 October 1999 Forwards Insp Rept 50-293/99-05 on 990726-0905.Three Violations Noted & Being Treated as Ncvs.Violations Include Failure to Assure That Design Bases Correctly Translated Into Specifications ML20217C3151999-10-0606 October 1999 Forwards Scenario Package for Pilgrim Nuclear Power Station Nrc/Fema Evaluated Exercise Scheduled for 991207.Without Encl ML20217D5591999-10-0505 October 1999 Documents Pilgrim Nuclear Power Station Five Yr Survey of Main Breakwater.Survey Has Determined That Pilgrim Main Breakwater Is Intact & Remains Adequately Constructed to Perform Designed Safety Function ML20217C8051999-10-0505 October 1999 Forwards Proprietary Results of Audiologic Evaluations for Jp Giar,License SOP-10061-3.Attachment Clearly Shows Requirements for Operator Hearing Ability Are Met. Proprietary Info Withheld,Per 10CFR2.790(a)(6) ML20212J8301999-09-30030 September 1999 Informs of Completion of mid-cycle PPR of Pilgrim Nuclear Power Station.Staff Conducts Reviews for All Operating NPPs to Integrate Performance Info & to Plan Insp Activities at Facility Over Next Six Months ML20216J9961999-09-29029 September 1999 Forwards Resume of Person Identified as Acting RPM in Licensee to NRC Re Notification That Person Named in License Condition 11 of 20-07626-02,is No Longer Employed at Pilgrim Station.Resume Withheld,Per 10CFR2.790 ML20212F7871999-09-24024 September 1999 Advises That Util 990121 Application for Amend Being Treated as Withdrawn.Proposed Changes Would Have Modified Facility UFSAR Pertaining to Values for post-accident Containment Pressure Credited in Pilgrim Net Positive Head Analyses ML20212H1381999-09-23023 September 1999 Submits Info in Support of Request Filed on 990730 to Grant one-time Exemption from 10CFR50,App E,Authorizing Biennial Full Participation Emergency Preparedness Exercise to Be Conducted in 2002 Instead of 2001 ML20212H1441999-09-23023 September 1999 Withdraws 990121 Request for License Change Re Emergency Core Cooling Sys Net Positive Suction Head,Due to Incorrect Datum Preparation ML20216F3451999-09-16016 September 1999 Forwards Summary Rept Providing Results of ISI Conducted at PNPS on-line & Refueling Outage (RFO 12) ML20212C2861999-09-16016 September 1999 Forwards SER Accepting Licensee 981123 Request for Relief RR-E1,RR-E5,RR-E6 Pursuant to 10CFR50.55a(a)(3)(i) & Request for Relief RR-E2,RR-E3 & RR-E4 Pursuant to 10CFR50.55a(a)(3)(ii) ML20216E7111999-09-0909 September 1999 Forwards License Renewal Application Including Form NRC-398 & Form NRC-396 for Jp Giar,License SOP-10061-3.Without Encls ML20216E5891999-09-0707 September 1999 Forwards Copy of Pilgrim Station Organization Structure. Encl Refelcts Changes in Upper Mgt Level Structure.Changes Were Effective 990901 ML20211M4501999-09-0303 September 1999 Informs That Pilgrim Nuclear Power Station Plans to Conduct Full Participation Emergency Preparedness Exercise with Commonwealth of Ma on 991207,IAW 10CFR50,App E,Section IV.F.2 ML20211M9161999-08-31031 August 1999 Submits Review & Correction of Info in Reactor Vessel Integrity Database (Rvid),Version 2,re Pilgrim Station ML20211J8391999-08-30030 August 1999 Forwards Rev 1 to Provisional Decommissioning Trust Agreement for Plant,Changing Portions of Agreement to Permit Up to Two Distributions & Clarify Formula for Distribution ML20211H5701999-08-27027 August 1999 Forwards Insp Rept 50-293/99-04 on 990610-0725.Two Violations Identified Being Treated as non-cited Violations ML20211C3381999-08-19019 August 1999 Provides semi-annual LTP Update,Including Schedule, Commitment Descriptions,Progress Since Last Update & Summary of Changes.Rev Bars Indicate Changes in Status Since Last Submittal ML20210U5761999-08-18018 August 1999 Responds to Opposing Merger of Bec Energy & Commonwealth Energy Sys in Commonwealth of Massachusetts. Informs That for Sale,Nrc Responsible for Only Ensuring That Entergy Technically & Financially Qualified to Operate NPP ML20210U6691999-08-18018 August 1999 Forwards from Massachusetts State Senator T Murray Opposing Merger Between Bec Energy & Commonwealth Energy Systems ML20210U7521999-08-18018 August 1999 Forwards from Massachusetts State Senator T Murray Opossing Merger Between Bec Energy & Commonwealth Energy Systems ML20210U5151999-08-17017 August 1999 Forwards Notice of Withdrawal of Application for Approval of Indirect Transfer of FOL for Pilgrim in Response to .Approval No Longer Needed Since Beco Sold Interest in Pilgrim to EOI on 990713 ML20211B3841999-08-16016 August 1999 Forwards Response to NRC Second RAI Re Pressure Locking & Thermal Binding of SR power-operated Gate Valves ML20210U4831999-08-13013 August 1999 Forwards fitness-for-duty Program Performance Data Sheets for Period of 990101-0630,per 10CFR26.71(d) ML20210S0891999-08-0909 August 1999 Forwards Amend 11 to Indemnity Agreement B-48 Signed by Boston Edison Co & Entergy Nuclear Generation Co ML20210R6251999-08-0606 August 1999 Provides Supplementary Info on USI A-46 Implementation Methodology at Pilgrim Station,To Enable NRC to Perform Evaluation & Issuance of Plant Specific SER for Plant ML20210M9411999-08-0202 August 1999 Requests That NRC Treat Pending Actions Requested by Beco Prior to 990713,as Requests Made by Entergy.Ltr Requests That Minor Administrative Changes to License Amend 182 & Associated Ser, ,reflect 990713 Transfer ML20210H8761999-07-30030 July 1999 Requests That NRC Grant Exemption from Requirements of 10CFR50,App E,Section IV F,Which Would Authorize Rescheduling of 2001 Biennial Full Participation Emergency Preparedness Exercise for Pilgrim Station to 2002 ML20210H8661999-07-29029 July 1999 Provides Revised Response to GL 96-06 & Addresses NRC Insp Concern for Containment Penetration X-12.Info Submitted to Facilitate NRC Review & Closeout of Subject GL for Plant ML20216E2321999-07-26026 July 1999 Discusses GL 92-01,rev 1,suppl 1, Rv Structural Integrity. NRC Revised Info in Rvid & Releasing as Rvid Version 2 ML20216D4131999-07-22022 July 1999 Informs That J Conlon,License OP-11040-1,terminated Employment with Beco on 990703,per 10CFR50.74.Individual Will Not Participate in Util Licensed Operator Requalification Training Program ML20210E2231999-07-20020 July 1999 Discusses Arrangements Made by Dennis & M Santiago During 990615 Telephone Conversation for NRC to Inspect Licensed Operator Requalification Program at Pilgrim During Wk of 991004 ML20210C4151999-07-19019 July 1999 Informs That Util Intends to Submit Approx Eight Licensing Actions in FY00 & Eight in FY01,in Response to Administrative Ltr 99-02.Actions Are Not Expected to Generate Complex Reviews ML20210F3711999-07-14014 July 1999 Informs NRC That Effective 990713,listed Pilgrim Station Security Plans Have Been Transferred from Boston Edison to Entergy & Are Still in Effect ML20210A9441999-07-14014 July 1999 Responds to Re Changes to Pilgrim Nuclear Power Station Physical Security Plan Identified as Issue 2,rev 14, Addendum 1,respectively.No NRC Approval Is Required IAW 10CFR54(p) ML20209G2251999-07-0909 July 1999 Forwards Insp Rept 50-293/99-03 on 990419-0609.Five Severity Level IV Violations of NRC Requirements Identified & Being Treated as non-cited Violations,Consistent with App C. Several Individual Tagging Errors Occurred ML20209C4661999-07-0707 July 1999 Forwards SE Accepting Addendum on Proposed Change in Corporate Ownership Structure Involving Entergy Nuclear Generation Co ML20209C7761999-07-0606 July 1999 Submits Annual Summary Rept of Changes Made to QAP Description as Described in QA Manual,Vol Ii.Rept Covers Period of Jul 1998 Through June 1999.No Changes Made During Period ML20209C3851999-07-0606 July 1999 Forwards Redacted Draft of Decommissioning Trust Agreement Re Transfer of PNPS & NRC Operating License & Matls License from Boston Edison Co to Entergy Nuclear Generating Co ML20196J7251999-07-0101 July 1999 Informs of Completion of Licensing Action for GL 96-01, Testing of Safety-Related Logic Circuits, for Pilgrim Nuclear Power Station ML20209B9411999-06-30030 June 1999 Discusses Deferral of IGSCC Welds to RFO 13.Deferral of Welds to Refueling Outage 13 Does Not Impact Acceptable Level of Quality & Safety Per 10CFR50.55(a)(3)(i) Since Plant in Compliance W/Exam Percentage Requirements ML20209B9431999-06-30030 June 1999 Provides Formal Notification That Closing Date for Sale & Transfer of Pilgrim Station Scheduled to Occur on 990713. a Wang Will Be Verbally Notified of Time of Sale Closing ML20209B9791999-06-29029 June 1999 Forwards Rev 13A to Pilgrims COLR for Cycle 13,IAW TS 5.6.5 Requirements.Rev 13A Provides cycle-specific Limits for Operating Pilgrim During Remainder of Cycle 13 ML20196H2381999-06-29029 June 1999 Forwards SER Denying Licensee 980820 Request for Alternative Under PRR-13,rev 2 for Use of Code Case N-522 During Pressure Testing of Containment Penetration Piping ML20209A8761999-06-28028 June 1999 Forwards SER Authorizing Licensee 990317 Relief Request to Use ASME Code Case N-573 as Alternative to ASME Code Section XI Article IWA-4000 for Remainder of 10-year Interval Pursuant to 10CFR50.55a(a)(3)(i) ML20209A8701999-06-25025 June 1999 Responds to NRC Request for Info Re Y2K Readiness of Computer Sys at Nuclear Power Plants. Y2K Readiness Disclosure for Plant,Reporting Status of Facility Y2K Readiness Encl ML20210U5901999-06-25025 June 1999 Opposes Merger of Bec Energy & Commonwealth Energy Sys in Commonwealth of Massachusetts.Expresses Skepticism Re Claim by Companies That Consumers Will Benefit from Proposed Consolidation & four-year Freeze in Base Rates ML20209C3431999-06-22022 June 1999 Forwards Addendum 1,Rev 14 to Pilgrim Station Security Plan,Iaw 10CFR50.54(p)(2).Changes Proposed Have Been Implemented & Constitute Increase in Plant Defense Plan Commitments.Encl Withheld,Per 10CFR73.21 1999-09-09
[Table view] Category:INCOMING CORRESPONDENCE
MONTHYEARML20217N8911999-10-15015 October 1999 Forwards Rept of Changes,Tests & Experiments at Pilgrim Nuclear Power Station for Period of 970422-990621,IAW 10CFR50.59(b).List of Changes Effecting Fsar,Encl ML20217C3151999-10-0606 October 1999 Forwards Scenario Package for Pilgrim Nuclear Power Station Nrc/Fema Evaluated Exercise Scheduled for 991207.Without Encl ML20217C8051999-10-0505 October 1999 Forwards Proprietary Results of Audiologic Evaluations for Jp Giar,License SOP-10061-3.Attachment Clearly Shows Requirements for Operator Hearing Ability Are Met. Proprietary Info Withheld,Per 10CFR2.790(a)(6) ML20217D5591999-10-0505 October 1999 Documents Pilgrim Nuclear Power Station Five Yr Survey of Main Breakwater.Survey Has Determined That Pilgrim Main Breakwater Is Intact & Remains Adequately Constructed to Perform Designed Safety Function ML20216J9961999-09-29029 September 1999 Forwards Resume of Person Identified as Acting RPM in Licensee to NRC Re Notification That Person Named in License Condition 11 of 20-07626-02,is No Longer Employed at Pilgrim Station.Resume Withheld,Per 10CFR2.790 ML20212H1441999-09-23023 September 1999 Withdraws 990121 Request for License Change Re Emergency Core Cooling Sys Net Positive Suction Head,Due to Incorrect Datum Preparation ML20212H1381999-09-23023 September 1999 Submits Info in Support of Request Filed on 990730 to Grant one-time Exemption from 10CFR50,App E,Authorizing Biennial Full Participation Emergency Preparedness Exercise to Be Conducted in 2002 Instead of 2001 ML20216F3451999-09-16016 September 1999 Forwards Summary Rept Providing Results of ISI Conducted at PNPS on-line & Refueling Outage (RFO 12) ML20216E7111999-09-0909 September 1999 Forwards License Renewal Application Including Form NRC-398 & Form NRC-396 for Jp Giar,License SOP-10061-3.Without Encls ML20216E5891999-09-0707 September 1999 Forwards Copy of Pilgrim Station Organization Structure. Encl Refelcts Changes in Upper Mgt Level Structure.Changes Were Effective 990901 ML20211M4501999-09-0303 September 1999 Informs That Pilgrim Nuclear Power Station Plans to Conduct Full Participation Emergency Preparedness Exercise with Commonwealth of Ma on 991207,IAW 10CFR50,App E,Section IV.F.2 ML20211M9161999-08-31031 August 1999 Submits Review & Correction of Info in Reactor Vessel Integrity Database (Rvid),Version 2,re Pilgrim Station ML20211J8391999-08-30030 August 1999 Forwards Rev 1 to Provisional Decommissioning Trust Agreement for Plant,Changing Portions of Agreement to Permit Up to Two Distributions & Clarify Formula for Distribution ML20211C3381999-08-19019 August 1999 Provides semi-annual LTP Update,Including Schedule, Commitment Descriptions,Progress Since Last Update & Summary of Changes.Rev Bars Indicate Changes in Status Since Last Submittal ML20211B3841999-08-16016 August 1999 Forwards Response to NRC Second RAI Re Pressure Locking & Thermal Binding of SR power-operated Gate Valves ML20210U4831999-08-13013 August 1999 Forwards fitness-for-duty Program Performance Data Sheets for Period of 990101-0630,per 10CFR26.71(d) ML20210S0891999-08-0909 August 1999 Forwards Amend 11 to Indemnity Agreement B-48 Signed by Boston Edison Co & Entergy Nuclear Generation Co ML20210R6251999-08-0606 August 1999 Provides Supplementary Info on USI A-46 Implementation Methodology at Pilgrim Station,To Enable NRC to Perform Evaluation & Issuance of Plant Specific SER for Plant ML20210M9411999-08-0202 August 1999 Requests That NRC Treat Pending Actions Requested by Beco Prior to 990713,as Requests Made by Entergy.Ltr Requests That Minor Administrative Changes to License Amend 182 & Associated Ser, ,reflect 990713 Transfer ML20210H8761999-07-30030 July 1999 Requests That NRC Grant Exemption from Requirements of 10CFR50,App E,Section IV F,Which Would Authorize Rescheduling of 2001 Biennial Full Participation Emergency Preparedness Exercise for Pilgrim Station to 2002 ML20210H8661999-07-29029 July 1999 Provides Revised Response to GL 96-06 & Addresses NRC Insp Concern for Containment Penetration X-12.Info Submitted to Facilitate NRC Review & Closeout of Subject GL for Plant ML20216D4131999-07-22022 July 1999 Informs That J Conlon,License OP-11040-1,terminated Employment with Beco on 990703,per 10CFR50.74.Individual Will Not Participate in Util Licensed Operator Requalification Training Program ML20210C4151999-07-19019 July 1999 Informs That Util Intends to Submit Approx Eight Licensing Actions in FY00 & Eight in FY01,in Response to Administrative Ltr 99-02.Actions Are Not Expected to Generate Complex Reviews ML20210F3711999-07-14014 July 1999 Informs NRC That Effective 990713,listed Pilgrim Station Security Plans Have Been Transferred from Boston Edison to Entergy & Are Still in Effect ML20209C3851999-07-0606 July 1999 Forwards Redacted Draft of Decommissioning Trust Agreement Re Transfer of PNPS & NRC Operating License & Matls License from Boston Edison Co to Entergy Nuclear Generating Co ML20209C7761999-07-0606 July 1999 Submits Annual Summary Rept of Changes Made to QAP Description as Described in QA Manual,Vol Ii.Rept Covers Period of Jul 1998 Through June 1999.No Changes Made During Period ML20209B9411999-06-30030 June 1999 Discusses Deferral of IGSCC Welds to RFO 13.Deferral of Welds to Refueling Outage 13 Does Not Impact Acceptable Level of Quality & Safety Per 10CFR50.55(a)(3)(i) Since Plant in Compliance W/Exam Percentage Requirements ML20209B9431999-06-30030 June 1999 Provides Formal Notification That Closing Date for Sale & Transfer of Pilgrim Station Scheduled to Occur on 990713. a Wang Will Be Verbally Notified of Time of Sale Closing ML20209B9791999-06-29029 June 1999 Forwards Rev 13A to Pilgrims COLR for Cycle 13,IAW TS 5.6.5 Requirements.Rev 13A Provides cycle-specific Limits for Operating Pilgrim During Remainder of Cycle 13 ML20209A8701999-06-25025 June 1999 Responds to NRC Request for Info Re Y2K Readiness of Computer Sys at Nuclear Power Plants. Y2K Readiness Disclosure for Plant,Reporting Status of Facility Y2K Readiness Encl ML20210U5901999-06-25025 June 1999 Opposes Merger of Bec Energy & Commonwealth Energy Sys in Commonwealth of Massachusetts.Expresses Skepticism Re Claim by Companies That Consumers Will Benefit from Proposed Consolidation & four-year Freeze in Base Rates ML20209C3431999-06-22022 June 1999 Forwards Addendum 1,Rev 14 to Pilgrim Station Security Plan,Iaw 10CFR50.54(p)(2).Changes Proposed Have Been Implemented & Constitute Increase in Plant Defense Plan Commitments.Encl Withheld,Per 10CFR73.21 ML20195G3721999-06-0707 June 1999 Informs That Proposed Indicators Failed QA Assessments for Digital Verification,Validation & Control of Software. Proposed Mod Can Be Completed on-line ML20195B5021999-05-27027 May 1999 Provides Suppl Info to 990203 Request of Beco That NRC Consent to Indirect Transfer of Control of Util Interest in License DPR-35.Request Described Proposed Merger of Bec Energy with Commonwealth Energy Sys ML20207D4681999-05-24024 May 1999 Provides Addl Info to That Included in Beco Ltr 98-123 Dtd 981001,addressing NRC Concerns Described in GL 96-06, Concerning Waterhammer in Reactor Bldg Closed Cooling Water Sys ML20195B9051999-05-20020 May 1999 Forwards Completed Renewal Applications for Listed Operators.Without Encls ML20206J4901999-05-0606 May 1999 Forwards Completed License Renewal Application,Including Forms NRC-398 & 396 for Sc Power,License OP-6328-3 ML20206P0711999-05-0606 May 1999 Forwards NRC Form 396, Certification of Medical Exam by Facility Licensee, for K Walz,License SOP-10886-1.Encl Withheld IAW 10CFR2.790(a)(6) ML20206D3621999-04-27027 April 1999 Informs NRC That Final Five Sys self-assessments Required to Fulfill Commitment Made in 980828 Response to Insp Rept 50-293/98-04 Were Completed on 990422.Completion Was Delayed by High Priority Refueling Outage 12 Preparatory Work ML20205R9871999-04-21021 April 1999 Forwards Affidavit of JW Yelverton of Entergy Nuclear Generation Co Supporting Request for Withholding Info from Rept on Audit of Financial Statements for Year Ended 971231. Pages 16 & 18 of Subj Rept Also Encl ML20207B0891999-04-20020 April 1999 Forwards e-mail Message from Constituent,J Riell Re Y2K Compliance of Nuclear Power Plant in Plymouth,Massachusetts. Copy of Article Entitled Nuke Plants May Not Be Y2K Ready Also Encl ML20206A2741999-04-16016 April 1999 Dockets Encl Ltr Which Was Sent to AL Vietti-Cook Re Condition of Approval of Transfer of License & License Condition for DPR-35.Encl Resolves Issues Between Attorney General of Commonwealth of Massachusetts & Applicants ML20205P9131999-04-16016 April 1999 Submits Applicant Consent to Listed Condition of Approval of Transfer of License & License Condition for License DPR-35 & Affirmatively Request That NRC Adopt Listed Language in Order ML20205P9271999-04-16016 April 1999 Withdraws Motion for Leave to Intervene & Petition for Summary Or,In Alternative,For Hearing.Requests That NRC Adopt Condition of Approval of Transfer of License & License Condition Agreed to Beco & Entergy Nuclear Generation Co ML20205Q9231999-04-15015 April 1999 Forwards Proprietary & non-proprietary Addl Info in Support of Request to Transfer of Plant FOL & Matls License to Entergy Nuclear Generation Co.Proprietary Info Withheld,Per 10CFR2.790 ML20205P9631999-04-15015 April 1999 Provides Attachments a & B in Support of Request for Transfer of Plant Operating License & NRC Matl License from Beco to Entergy Nuclear Generation Co as Submitted in Ref 1. Info Provided in Response to Request at 990413 Meeting ML20205H9281999-04-0707 April 1999 Requests Withdrawal of Uwua Locals 369 & 387 Unions Joint Intervention in Listed Matter ML20205F3731999-04-0202 April 1999 Submits Addl Info Provided in Support of Request for Transfer of Pilgrim Nuclear Power Station Operating License & Matls License.State of Ma Order Authorizing Divestiture & Copy of Financial Arrangement Encl ML20204H3771999-03-26026 March 1999 Informs That Local 387,Utility Workers Union of America,AFL- Cio Voted to Approve New Contract with Entergy Nuclear Generation Co & Voted to Accept Boston Edison Divestiture Agreement ML20205D4231999-03-24024 March 1999 Forwards Decommissioning Funding Rept for Pilgrim Nuclear Power Station,In Accordance with 10CFR50.75(f)(1) 1999-09-09
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h Boston Edison Pagom Nuclear Power Station Rocky Hilt Road Plymouth, Massachusetts 02360 E. T. Boulette, PhD Senor vu President - Nuclear May 3, 1995 BECo Ltr. #95- 059 U.S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, DC 20555 Docket No. 50-293 License No. DPR-35 Core Shroud Modification Request for Additional Information XM-19 Material (UNS S20100)
XM-19 material was selected for the Pilgrim shroud tie rods because of its strength, corrosion resistance in BWR environments, and material properties.
As purchased, this n'aterial is delivered in the solution heat treated condition. This involves heating the material to approximately 2000 F, whais the carbides (Cr23Ce) break down and the component atoms disperse into the matrix. This heating is followed by cooling a rate rapid enough to maintain the dispersion in the matrix. Forced air cooling of the tie rods was selected given the geometry and material properties of XM-19.
Based on information provided by General Electric Nuclear Energy for this specific alloy, air cooling k sufficiently rapid to avoid precipitation of carbides, as has been verified by a number of laboratory tests and experiments. For <xample, data published by EPRI's M.J. Povich and D. E. Broeker in the October 1979 issue of " Material Performance" (National Association of Corrosion Engineers; "The Stress Corrosion Cracking of Austenitic Stainless Steel Alloys in High Temperature Air Saturated Water") show that UNS S20100 is as resistant to corrosive atta ,k in the cold-worked and/or fumace-sensitized condition, as in the fully solution-heat-treated condition. Therefore, air cooling is sufficiently rapid to preserve the corrosioneesistant properties of the material.
In addition, each heat was tested for susceptibility to intergranular stress corrosion cracking in accordance with ASTM A-262, Practi,e E. The material was sensitized at 1250*F (+/-10 F) for one hour and air cooled. After a 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> boil in the prescribed solution, a bend test was performed and it was found to be satisfactory with no cracks. A copy of the material certification is attached for your review.
With respect to pessible deleterious effects of cold work due to machining operations, General Electric Nuclear Energy performed a microhardness survey on a representative section of M-19 barstock machined with 5-pitch stub acme threads and deliberately left in as-machined condition. Knopp was read with a 25 gram :oad.
9505110077 950'503 PDR ADOCK 050rM293 0,0 P FDR ,
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'i 0.6 3r* 357 c36 ,
1.2 ' 3t 325 c32*
1.8 ' 31. 290 c27 2.4 299 274 c24 l 3.0 297 272 c24 l 3.6 284 259 c22 !
4.2 289 264 c23 !
4.8 256 231 b96 ;
. 5.4 266 241 b97.5 6.0 256 231 b96 6.6 254 229 b95.5 .
deep 257 ;
249 f 248 248 (251) 226 b95 !
253 i V 250 6 l
Although there is a measurable gradient in hardness, from the surface, it is very slight. The' microscopic appearance of the surface and adjacent grains do not show any of the smeared metal or other distress that we.s seen in the Type 316 material from previous studies.
l In conclusion, the tie rod threads in alloy XM-19 material do not require solution annealing to restore !
material properties. The metal is perfectly acceptable without such a treatment. ;
I b . Y. -th E. T. Boulette, PhD :
ETB/ RAH /nas/ Rap 95/Shrdmate Attachment cc: Mr. R. Eaton, Project Manager 5 Division of Reactor Projects - 1/11 i Mail Stop: 14D1 ;
U. S. Nuclear Regulatory Commission 1 White Flint North 11555 Rockville Pike !
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U.S. Nuclear Regulatory Commission Region I 475 Allendale Road King of Prussia, PA 19406 Senior Resident inspector Pilgrim Nuclear Power Station
DUBOSE NATIONAL ENERGY SERVICES, INC.
900 INDUSTRIAL DRIVE // CLINTON, NC 28328
- Certificate of Conformance/ Compliance /CMTR Customer: -
GE NUCLEAR ENERGY Date 12/01/94 Serial No. 39463 D G.E. TECH CENTER Our DC No. 101734 302 HANSEN ACCESS ROAD This material meets the requirements KING OF PRUSSIA PA 19406 of your PO number 528-94T710T
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Description Heat # /
Item Pieces Specification Grade Heat Code 1 4 3 1/2" DIA X 17' R/L ROUND BAR, ANNEALED A9164 ASTM A479-88A XM19 CRUCIBLE HHT LTI SHIPPING LENGTH TOTAL: 70' 6 5/8"
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ne .e = 4Q o.u n:... .
n y f .? .1C*' =V a
- k
.?
~~'
~
. =.3 A. The :.bove refercnced sample was submitted to cherical content ev:.luation by Spectroscopic .:nd Inert Gas Fusion An:1ysis and it uas found to be in conformance to ASTM A-479, Type XI:-19 and Custencr'c Carbor. requirement. The results are sc fol'.a/c:
ELEME!!T REOUIRED
~
TRACE O4572 Certon 0.040 caxi= uni .. 21
!!angcnese 4.00 - 6.00 4.2C Phosphorus 0. 040 maxi:num 0.C30 Sulfur 0.030 niaxirrum 0.002 Silicon 1.00 maximum 0.00 Nickel 11.50 - 13.50 11.55 Chromium 20.50 - 23.50 20.15 Molybdenum 1.50 - 3.00 1.57 Vancdium 0.10 - 0.30 C.11 Mitrogen 0.20 - 0.40 C.;C Colurbium 0.10 - 0.30 0.17 ArnoJ6 L. 21oroff AERCURY CONTAMINATION - During the testing and
( inspection, the product did not come m direct contactMity Accer .n- -e . n;ger with mercury or any of its compounds nor with any mercury containing devices employing a single boundary '
cI contahnt *
, ,, J A AUYwoa 2to SIGNATURE I I SUBJECT TO TERMS AND CONDITIONS PRINTED ON REVERSE SIDE OF TMS FORM.
customer COPY-DUPUCATE /6 2 NLd"/f/4CH 2
mj #215:24sassa @@'// 40G/# 0 N O. '17840 (90/[r Ormavece TERZSJ NET . 30 CAYO GE NUCLEAR ENERGY Po* 528-94T710T LABORATORY SHIPPING ADDRESS P.O. Box 249 Dubiln, Pennsylvania 18917 120 MtLL STREET, 0U8ktN. PA 18 17 DUBOSE NATIONAL ENERGY SERVICES, INC. L.T.I. Lab Report #B-94921 P.O. 45873-69 Page 2 of 2
- AMENDED CERTIFICATION (11/3/94)
- 3. A Tensile test was performed on the submitted Test Specimen and it was found to be in conformance to ASTM A-479-88a, Type XM-19, Annealed per the following results:
REQUIRED TRACE 44572 Tensile Strength 100,000 PSI 110,276 PSI Yield Strength (.2%) 55,000 PSI 57,644 PSI Elongation (In 2") 35.0% 44.9%
Reduction of Area . 55.0% 69.6%
C. A Hardness test was performed on the submitted Test Specimen and it was found to be in conformance to ASTM A-479-88a, Type XM-19, Annealed per the following results:
pu G en S% gJ" BICO
~2.5 A 5G oM h., t 'fikW
( REQUIRED- LESS THAN RC 30 9^ OtdCDP- 4.'I l CA PEVIEW l TRACE f4572: RB 90.0 F C d
. NimL ' '
OATe 4 D. An Intergranular Corrosion Susceptibility test was performed on the submitted Test Specimen (Trace-44572) in accordance with ASTM A-262, Practice E *using L.T.I. Procedure MAS-CORR, Rev. O dated 9/16/92. After a 24-hour boil in the prescribed solution, a bend test was performed and it was found to be satisfactory with no cracks.
NOTE: The above material was sensitized at 12500 F. (+/- 10 0 F.)
for one hour and air cooled. {
The provisions of 10CFR21, 10CFR50, Appendix B and ANSI N45.2 apply to this order.
1 All testing performed in accordance with L.T.I. QA Program, Rev. 9 l dated 1/29/93 as audited and approved by DuBose National Energy Services, Inc.
ERCURY CONTAMINATION During the testing and
( ispection, ttw product did not come m direct contact Arnold L. Boroff
^ with mercury or any of its compounds nor with any g ,
ty As ur ce Man car mercury containing devices employing a single boundary . .
cf containment. '
.4 ( j SUBJECT To TERMS ANo CONDITIONS PRINTEo oN REVERSE SIDE of THIS FORM.
CUSTOMER COPY - DUPUCATE /g2 m- /P //f- d O
.HT.8llll%::::
Lgca/, c/ %/ymaoc, No. 127,4o g TER'.22: NET - 30 OAYS GE NUCLEAR ENERGY PO# 528-94T710T LABORATORY SHIPPING ADDRESS P.O. Box 249 Dublin Pennsylvania 18917 120 ulLL STREET, DUBLIN. PA 1s911 DUBOSE NATIONAL ENERGY SERVICES, INC. L.T.I. Lab Report #B-94921 P.O. 05873-69 Page 2 of 2
- AMENDED CERTIFICATION (11/3/94)
B. A Tensile test was performed on the submitted Test Specimen and it was found to be in conformance to ASTM A-479-88a, Type XM-19, Annealed per the following results:
REQUIRED TRACE 44572 Tensile Strength 100,000 PSI 110,276 PSI Yield Strength (.2%) 55,000 PSI 57,644 PSI Elongation (In 2") -
35.0% 44.9%
Reduction of Area 55.0% 69.6%
C. A Hardness test was performed on the submitted Test Specimen r.nd it was found to be in conformance to ASTM A-479-88a, Type XM-19, Annealed por the following results:
(
REQUIRED: LESS THAu RC 30 OdOS2 O t r Emy/ i TRACE #4572: RB 90.0 F fNnW. ' '
r;A7g f D. An Intergranular Corrosion Susceptibility test was performed on the submitted Test Specimen (Trace #4572) in accordance with ASTM A-262, Practice E *using L.T.I. Procedure MAS-CORR, Rev. O dated 9/16/92. After a 24-hour boil in the prescribed solution, a bend test was performed and it was found to be satisfactory with no cracks. .
NOTE: The above material was sensitized at 12500 F. (+/- 10 0 F.)
for one hour and air cooled.
The provisions cf 10CFR21, 10CFR50, Appendix B and ANSI N45.2 apply to this order.
All testing performed in accordance with L.T.I. QA Program, Rev. 9 dated 1/29/93 as audited and approved by DuBose National Energy Services, Inc.
(
1 AERCURY CONTAMINATION During the testing and inspection, the product did not come m direct contact Arnold L. Boroff unth mercury or any of its compounds nor with any Qu ity As ur ce Man r mercury containing devices ernp!aying a single boundary ci contamment, . j ,
,gj(j ;
$UBJECT To TERMS AND (.ONDITior S PRINTEC ON M VERSE SIDE of THl$ FORM.
CUSTOMER COPY - DUPLICATE /62. #e' /f Uf D
FIEiiE25ssi! N4 ca/g
[ $/ renam, No.12904 8 7777 TERMS: NET. 30 DAYS
.a LABORATORY TESTING INC. '
P.O. Box 249 Dublin, Pennsylvania 18917 SHIPPING ADDRESS EOLD TO 120 wu. sinter. oueuN er ,as,1 SHIP TO DuBosEllational Encrgy Services, Inc. Toolilig Specialists P.O. Box 499 East Fayette Street Clinton, NC 20323 Latrobe, PA 15650 Attentions , Ruth Barbar-Rich Ref: GE PO #520-94T71CT CUST. P.O. LAB REPORT HO. SHIPMENT INVOICE DATE Sd73-69 U-94921 Complete 11/30/94 DESCRIPTION Page 1 of 1 4 pcs. 3-1/2" Dia. x 17'/18' long Bars, (70' ASME Section III, Subsection NG-2540, I 6-5/0") 1309 Edition, No Addenda, ASTfi A-479-8Sa, Type XM-19, Ucat (A9164, Trace 44572A through 44572D (Ultrasonict.11y Inspected)
Referenco: Vendor PO #5672-69 '
Cu?C E Customer PC #528-94T710T c.t. FE ! 5W 1
e p. ;.: C OSY
/NY /
\
Llg1.-----~~DATE ~ i t
The above material was 1001 Ultrasonically inspected in ccccrdance with L.T.I. Procedure UT-NG2584, Rev. O dated 2/24/92 and (4) pieces representing (70' 6-5/8") were found te be acceptable to those requirements.
Testing performed by Russell Spor, SNT-TC-1A, Level II.
The provisions of 10CFR21,10CFR50, Appendix B and ANSI N45.2 apply to this order.
All testing performed in accordance with L.T.I. QA Program, Fev. 10 dated 10/17/94 as audited and approved by DuBose National Energy Services, Inc.
MERCURY CONTAMINAT10N . During the testing and Arnold L. Horoff
(' inspection, the product did not come in direct contact Quality Assurance Manager with mercury or any of its compounds nor with any mercury containing devices employing a single boundary of containment.
h,.
d] AuTma;2tc SsG A @E SUBJECT TO TERMS AND CONDITION: PRINTED ON REVERSE SICE OF Teils FORM.
CUSTOMER COPY DUPLICATE /61_ se w- /fNf N 7
LABORATORY TESTING, INC.
GE NUCMAR ENERGY 120 MILL STREET, DUBLIN, PA 18917 F0# 528-94T710T ULTRASONIC INSPECTION CUS10MER: DuBose Nat. Energy CUSTOMER P.O.: 5873-69 LAB No.: U 94921 DATE RECElVED: 11/29/94 QTY RECEIVED: 4 pcs.(70'6-5/8") ACC.: 70'6-5/8" REJ.: APPROVED TEST PROCEDURE: APPLICABLE SPECS.:
UT NG2584, Rev. O dated 2/24/92
- ASME Section 111, Subsection NG 2540,1989 Edition, No Addenda n.DuBOS.E,.o e -. :. -
DESCRIPTION OF MATERIAL / STAGE OF MATERIAL AT TIME OF TEST : cA' FApTOr-Y 31/2" Dia. x 17'/18' long Bars, ASTM A-479-88a, Type XM-19, }
Heat #A9164, Trace #4572A through #4572D rf/gO M_:
t.
'n .%_L., / / C6_=
. ~ -5 t
TEST DIR.: Longitudinal EQUIP. MFG: Sonic MODEL No.: Mark 11 SERIAL No.: 11023E
~ ~
, TRANS MFG.: Technisonic MODEL No.: ILD-0206-GP l
SERIAL No.: E-8808 SIZE: .750" FREQUENCY: 2.25 MHz ;
CABLE LENGTH: CAllBRATION STD #: Production Piece DESCRIPTION: N/A CAllBRATION STD FINISH: PRODUCTION FINISH: IMMERSION N/A <250 RMS CONTACT X (TAC-tlc 76)
SCANNING SPEED: COUPLANT: REFERENCE LEVEL :
40 SIPS {
Water 80% F.S.H.
AREA GATED: DEFECT ALARM LEVEL: RECORDING EQUIP (if used):
- See Below 30% of Reference General Scanning RS6-SP
{
ADDITIONAL INFORMATION (if necessary):
- 1st Gate Back Reflection and 2nd Gate from center of bar to just before 1st back reflection. '
ULTRASONIC INSPECTOR d ,2 ,// Q DATE OF INSPECTION: 11/30/94 Russell Spor, SNT TC 1 A. Level 11 PAGE 1 OF 1
/22 Mw- if u?- 0 / 7 l
-* . T_T ouston S.C.,: a6689
.Lleat Treating Co.
HHT OTTICE:4201 Robertson Sc P.O. Bas 30070 PLANT:4111 Robenson Sc Houstan.TX 77249 PLANT:1301 Hays St Phone: G13) 691-4544 Housion.TX 77009 FAXs: 0 13)691 1923 or nucLzAn ruraar CERTIFICATION OF PROCESS Po# 528-94T710T (458290) $'$raday27-OCT-199410:05 h 86689 NATIONAL SPEC ALLOYS INC 1320 UPLAND HOUSTON TX 77043 Cusiomer P.O.e; Other Canoen sa #: 61sterial and Condaion:
29649 ?
W.&iP~1.n&22Wh*!ddilltin ii;stN!s"*Bh&MT7 %i+!&h::fCGktf%@51psiW51bGr.hyw%'i'&n??L%9%22'3C;3%42 4 HT9A9164 BARS 4 1/2"OD X 17'R/L g, .gg Cl,. ' : ilE'N
/
' ' DNidj
~TN:T!AL WE CERTUY THAT THE ABOVE DESCRIDED PARTS WERE PROCESSED IN ACCORDANCE WITH SPECIFICATIONS AS FOLLOWS:
HHT-HT-001 XM-19 HHT QC MANUAL DATED 05/31/91 PROCESS TEMPERATURE QUENCH DATE HRS /AT HEAT HRS / TOTAL SOL ANN 1093C / 2000F AIR 10-26-94 01.00 07.00 v
TEST REPORTS FROM /
NATIONAL SPECIALTY ALLOYS Custome3rrd,,,c, Neh j @ p.
P O. # 5"Te n - 6 f _
Part i Desc. '" IIA rW[ 7D T.8aa /1 S"C3
~
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