Similar Documents at Surry |
---|
Category:CORRESPONDENCE-LETTERS
MONTHYEARML18152B3571999-10-22022 October 1999 Requests Relief from Temporary Repair of Through Wall Leak Discovered on 30 Inch Component Cooling Heat Exchanger Discharge Pipe Associated with Service Water Sys Common to Surry Units 1 & 2 ML18152B3581999-10-14014 October 1999 Submits Response to Violations Noted in Insp Repts 50-280/98-201 & 50-281/98-201.Corrective Actions:Visual Insps Were Completed on Accessible Coatings Inside Containment for Both Units 1 & 2 ML18152B3541999-10-12012 October 1999 Requests Use of Code Case N-532 & N-619,per Provisions of 10CFR50.55a(a)(3).Detailed Info Supporting Request,Encl. Attachment 2 Includes Technical White Paper That Provides Further Technical Info ML18152B3401999-09-27027 September 1999 Requests That Ma Walker Be Removed from List of Individuals Scheduled to Take Exam IAW Guidance Provided in NUREG-1021, Operator Licensing Exam Stds for Power Reactors ML18152B3391999-09-27027 September 1999 Forwards Revised Relief Request IWE-3,which Now Includes Addl Visual Exam Requirement After post-repair or Mod Pressure Testing Is Completed,Per Telcon with NRC ML18152B3381999-09-21021 September 1999 Forwards in Triplicate,Applications for Renewal of License for Bf Jurewicz & JW Heide.Without Encls ML18152B3331999-09-17017 September 1999 Forwards Revised 180-day Response to NRC GL 96-05, Periodic Verification of Design-Basis Capability of Safety-Related Motor-Operated Valves. ML18152B6671999-09-17017 September 1999 Forwards Two NRC Forms 536,containing Info on Proposed Site Specific Operator Licensing Exam Schedules & Estimated Number of Applicants Planning to Take Exams And/Or Gfes,In Response to NRC Administrative Ltr 99-03 ML18152B3341999-09-16016 September 1999 Requests Relief from Specific Requirements of Subsection IWE of 1992 Edition with 1992 Addenda of ASME Section XI Re Containment Liner Examination Requirements,For North Anna & Surry Power Stations ML18152B4521999-09-14014 September 1999 Forwards Comments on Review of Preliminary Accident Sequence Precursor Analysis of Operational Event That Occurred at Plant,On 980508,as Reported in LER 98-009 ML20216F1381999-09-0808 September 1999 Forwards Retake Exam Repts 50-280/99-302 & 50-281/99-302 on 990824.One SRO Applicant Who Received re-take Operating Test Passed re-take Exam ML18152B4501999-09-0808 September 1999 Submits in Triplicate,Application for Renewal of License for Rd Scherer,Iaw 10CFR55.57.Requests That Certification of Medical Exam by Facility Licensee,Nrc Form 396,be Withheld from Public Disclosure,Per 10CFR2.790(a)(6) ML18152B4471999-09-0101 September 1999 Requests That NRC Remove Listed Labels from Distribution ML18152B3711999-08-27027 August 1999 Forwards LER 99-005-00,per Plant TS Table 3.7.6.Rept Has Been Reviewed by Station Nuclear Safety & Operating Committee.Commitment Made by Util,Listed ML18152B3851999-08-23023 August 1999 Forwards Revised TS Basis Pages for TS 3.1.B,deleting Reactor Vessel Toughness Data Duplicated in Ufsar.Ref to Applicable UFSAR Section Included in TS Basis ML18152B3661999-08-20020 August 1999 Provides Medical Status Rept for E Washington,As Required by License Conditions.Summary of E Washington Current Physical Exam & Pertinent Lab Data Attached.Encl Withheld,Per 10CFR2.790(a)(6) ML18152B3651999-08-20020 August 1999 Requests Removal of License Condition from Sh Wightman Operator License SOP-21538.Updated NRC Form 396 Is Encl.Form NRC 396 Withheld,Per 10CFR2.790(a)(6) ML18152B3681999-08-20020 August 1999 Submits 30-day Rept Re Two Instances in Which Conditions of Approval in Coc Were Not Observed in Making Shipment.Two Type B Shipments Using Model CNS 8-120B Package Were Made After Expiration of QA Program Approval Between 990531-0628 ML18152B3801999-08-18018 August 1999 Forwards Technical Rept NE-1206,Rev 0, Surry Unit 2,Cycle 16 Startup Physics Tests Rept, Summarizing Results of Physics Testing Program Performed After Initial Criticality on 990525 ML18152B3781999-08-13013 August 1999 Forwards ISI Summary Rept for Surry Power Station,Unit 2 for 1999 Refueling Outage.Rept Provides Summary of Examination Performed During Outage for Third ISI Interval.No New Commitments Were Made ML18152B3751999-08-13013 August 1999 Forwards LER 99-004-00,IAW 10CFR50.73.Commitment Made by Util,Listed ML20210Q7661999-08-0606 August 1999 Requests Exception to 10CFR50.4 Requirement to Provide Total of Twelve Paper Copies When Submitting Surry & North Anna UFSAR Updates.Seek Approval to Submit Only Signed Original & One CD-ROM Version,Per Conversation with J Skoczlas ML18152B4081999-08-0606 August 1999 Forwards Response to NRC 990520 & 0525 RAIs Re North Anna & Surry Responses to GL 95-07, Pressure Locking & Thermal Binding of SR Power-Operated Gate Valves. ML18152B4091999-08-0505 August 1999 Forwards Vepc semi-annual fitness-for-duty Program Performance Data Rept for 990101-990630,IAW 10CFR26.71(d) ML18152B4001999-07-29029 July 1999 Requests Relief from Certain Impractical Requirements of ASME Section XI Code Associated with Partial Exams Conducted During 1998 Surry Unit 1 Refueling Outage.Relief Request SR-020 Encl ML18152B3981999-07-28028 July 1999 Forwards 60-day Response to GL 99-02, Lab Testing of Nuclear-Grade Activated Charcoal. Commitments Contained in Ltr,Listed ML18152B3971999-07-26026 July 1999 Provides Estimates of Licensing Actions Expected to Be Submitted in Fys 2000 & 2001,in Response to NRC AL 99-02 ML18152B3961999-07-23023 July 1999 Forwards Preliminary,Uncertified License Application & Medical Certification for License to Operate Surry Power Station Units 1 & 2 for Ds Cobb.Encl Withheld,Per 10CFR2.790 (a)(6) ML18151A6281999-07-23023 July 1999 Forwards Revised Epips,Including Rev 19 to EPIP-4.02,rev 14 to EPIP-4.16,rev 8 to EPIP-4.21 & Rev 7 to EPIP-4.30.EP & EPIPs Continue to Meet Stds of 10CFR50.47(b) ML18152B3991999-07-23023 July 1999 Requests That License for Jz Laplante Be Canceled as License Is No Longer Required ML18152B3931999-07-16016 July 1999 Forwards Updated NRC Form 396 & Ltr,Which Documents Medical Status of Mb Gross,License SOP-20476-2.Encl Withheld from Public Disclosure,Per 10CFR2.790(a)(6) ML18152B4401999-07-0101 July 1999 Informs NRC That on 990511,Dominion Resources,Inc,Executed Amended & Restated Agreement & Plan of Merger with Consolidated Natural Gas Co ML18152B4371999-06-24024 June 1999 Forwards Response to NRC Request for Clarification of Relief Requests Submitted on 990212,requesting Relief from Performing Hydrostatic Testing for Certain Small Diameter Class 1,RCS Pressure Boundary Connections ML18152B4361999-06-22022 June 1999 Forwards Response to RAI Re Surry & North Anna Power Stations,Units 1 & 2,per GL 96-06 ML18152B4301999-06-0303 June 1999 Informs of Util Intention to Revise Schedule for Submittal of License Renewal Applications for Surry & North Anna Power Stations to March 2002 ML18152B4261999-05-28028 May 1999 Provides Formal Notification of Effect of Recent Organizational Restructuring on OLs of North Anna & Surry Power Stations,Per NRC 990513 Telcon Request ML18152B4221999-05-27027 May 1999 Forwards Info Concerning Changes to ECCS Evaluation Models & Application in Existing Licensing Analyses for Surry & North Anna Power Stations,Units 1 & 2 ML18152B4231999-05-26026 May 1999 Informs That Vepc Will Revise 180 Day Response to NRC GL 96-05,within 120 Days of Date of Ltr to Incorporate Commitment to Participate in Joint Owners Group Program as Applicable ML18152B4211999-05-25025 May 1999 Forwards Rev 1 to Relief Request P-11 to Clarify Original Intent of Request by Specifically Requesting Relief from Requirements of Section 6.1 of OM-6 ML18152A4741999-05-19019 May 1999 Forwards Completed Registration Form for Renewal of ASTs at Surry Nuclear Power Station,Iaw Section 9VAC 25-91-100.F ML18152B4171999-05-17017 May 1999 Provides Notification of Number of Steam Generator Tubes That Were Plugged During Spring 1999 Refueling Outage Planned ISI ML20217D6621999-05-14014 May 1999 Forwards NRC Operator Licensing Exams 50-280/99-301 & 50-281/99-301 (Including Completed & Graded Exams) for Tests Administered on 990329-0401 & 990412-15.Nine Candidates Passed (& One Failed) Exam ML18152A3701999-05-13013 May 1999 Submits Proposal to Use Provisions of ASME Section XI Code Case N-597 for Analytical Evaluation of Class 1,2 & 3 Carbon & Low Alloy Steel Piping Components Subjected to Wall Thinning as Result of Flow Accelerated or Other Corrosion ML18152B4121999-05-0303 May 1999 Forwards Application for Renewal of License for SV Ross. Encl Withheld Per 10CFR2.790(a)(6) ML18152B4101999-04-29029 April 1999 Forwards Scope & Objectives for 990803 Surry Power Station Emergency Exercise.Without Encls ML18152B6561999-04-23023 April 1999 Forwards Annual Radioactive Effluent Release Rept for Surry Power Station,Jan-Dec 1998, Which Includes Summary of Quantities of Radioactive Liquid & Gaseous Effluents & Solid Waste Released During CY98 ML18152B6491999-04-13013 April 1999 Forwards MOR for Mar 1999 for Surry Power Station,Units 1 & 2.MOR for Feb 1999 Incorrectly Stated Gross Electrical Energy Generated (Mwh) for Unit 2.Rept Should Have Stated Monthly Figure as 568965.0 ML18151A5851999-03-31031 March 1999 Forwards Rept on Status of Decommissioning Funding for Each of Four Nuclear Power Reactors,Per 10CFR50.75(f)(1) ML18152A2801999-03-30030 March 1999 Forwards Summary of Structural Integrity Evaluation of Thermally Induced Over Pressurization of Containment Penetration Piping During DBA for SPS & Naps,Units 1 & 2,per GL 96-06.Draft Proposed UFSAR Revised Pages,Encl ML18153A2721999-03-29029 March 1999 Forwards LER 99-002-00 Per 10CFR50.73.Listed Commitments Contained in Ltr 1999-09-08
[Table view] Category:INCOMING CORRESPONDENCE
MONTHYEARML18152B3571999-10-22022 October 1999 Requests Relief from Temporary Repair of Through Wall Leak Discovered on 30 Inch Component Cooling Heat Exchanger Discharge Pipe Associated with Service Water Sys Common to Surry Units 1 & 2 ML18152B3581999-10-14014 October 1999 Submits Response to Violations Noted in Insp Repts 50-280/98-201 & 50-281/98-201.Corrective Actions:Visual Insps Were Completed on Accessible Coatings Inside Containment for Both Units 1 & 2 ML18152B3541999-10-12012 October 1999 Requests Use of Code Case N-532 & N-619,per Provisions of 10CFR50.55a(a)(3).Detailed Info Supporting Request,Encl. Attachment 2 Includes Technical White Paper That Provides Further Technical Info ML18152B3391999-09-27027 September 1999 Forwards Revised Relief Request IWE-3,which Now Includes Addl Visual Exam Requirement After post-repair or Mod Pressure Testing Is Completed,Per Telcon with NRC ML18152B3401999-09-27027 September 1999 Requests That Ma Walker Be Removed from List of Individuals Scheduled to Take Exam IAW Guidance Provided in NUREG-1021, Operator Licensing Exam Stds for Power Reactors ML18152B3381999-09-21021 September 1999 Forwards in Triplicate,Applications for Renewal of License for Bf Jurewicz & JW Heide.Without Encls ML18152B3331999-09-17017 September 1999 Forwards Revised 180-day Response to NRC GL 96-05, Periodic Verification of Design-Basis Capability of Safety-Related Motor-Operated Valves. ML18152B6671999-09-17017 September 1999 Forwards Two NRC Forms 536,containing Info on Proposed Site Specific Operator Licensing Exam Schedules & Estimated Number of Applicants Planning to Take Exams And/Or Gfes,In Response to NRC Administrative Ltr 99-03 ML18152B3341999-09-16016 September 1999 Requests Relief from Specific Requirements of Subsection IWE of 1992 Edition with 1992 Addenda of ASME Section XI Re Containment Liner Examination Requirements,For North Anna & Surry Power Stations ML18152B4521999-09-14014 September 1999 Forwards Comments on Review of Preliminary Accident Sequence Precursor Analysis of Operational Event That Occurred at Plant,On 980508,as Reported in LER 98-009 ML18152B4501999-09-0808 September 1999 Submits in Triplicate,Application for Renewal of License for Rd Scherer,Iaw 10CFR55.57.Requests That Certification of Medical Exam by Facility Licensee,Nrc Form 396,be Withheld from Public Disclosure,Per 10CFR2.790(a)(6) ML18152B4471999-09-0101 September 1999 Requests That NRC Remove Listed Labels from Distribution ML18152B3711999-08-27027 August 1999 Forwards LER 99-005-00,per Plant TS Table 3.7.6.Rept Has Been Reviewed by Station Nuclear Safety & Operating Committee.Commitment Made by Util,Listed ML18152B3851999-08-23023 August 1999 Forwards Revised TS Basis Pages for TS 3.1.B,deleting Reactor Vessel Toughness Data Duplicated in Ufsar.Ref to Applicable UFSAR Section Included in TS Basis ML18152B3651999-08-20020 August 1999 Requests Removal of License Condition from Sh Wightman Operator License SOP-21538.Updated NRC Form 396 Is Encl.Form NRC 396 Withheld,Per 10CFR2.790(a)(6) ML18152B3681999-08-20020 August 1999 Submits 30-day Rept Re Two Instances in Which Conditions of Approval in Coc Were Not Observed in Making Shipment.Two Type B Shipments Using Model CNS 8-120B Package Were Made After Expiration of QA Program Approval Between 990531-0628 ML18152B3661999-08-20020 August 1999 Provides Medical Status Rept for E Washington,As Required by License Conditions.Summary of E Washington Current Physical Exam & Pertinent Lab Data Attached.Encl Withheld,Per 10CFR2.790(a)(6) ML18152B3801999-08-18018 August 1999 Forwards Technical Rept NE-1206,Rev 0, Surry Unit 2,Cycle 16 Startup Physics Tests Rept, Summarizing Results of Physics Testing Program Performed After Initial Criticality on 990525 ML18152B3781999-08-13013 August 1999 Forwards ISI Summary Rept for Surry Power Station,Unit 2 for 1999 Refueling Outage.Rept Provides Summary of Examination Performed During Outage for Third ISI Interval.No New Commitments Were Made ML18152B3751999-08-13013 August 1999 Forwards LER 99-004-00,IAW 10CFR50.73.Commitment Made by Util,Listed ML18152B4081999-08-0606 August 1999 Forwards Response to NRC 990520 & 0525 RAIs Re North Anna & Surry Responses to GL 95-07, Pressure Locking & Thermal Binding of SR Power-Operated Gate Valves. ML20210Q7661999-08-0606 August 1999 Requests Exception to 10CFR50.4 Requirement to Provide Total of Twelve Paper Copies When Submitting Surry & North Anna UFSAR Updates.Seek Approval to Submit Only Signed Original & One CD-ROM Version,Per Conversation with J Skoczlas ML18152B4091999-08-0505 August 1999 Forwards Vepc semi-annual fitness-for-duty Program Performance Data Rept for 990101-990630,IAW 10CFR26.71(d) ML18152B4001999-07-29029 July 1999 Requests Relief from Certain Impractical Requirements of ASME Section XI Code Associated with Partial Exams Conducted During 1998 Surry Unit 1 Refueling Outage.Relief Request SR-020 Encl ML18152B3981999-07-28028 July 1999 Forwards 60-day Response to GL 99-02, Lab Testing of Nuclear-Grade Activated Charcoal. Commitments Contained in Ltr,Listed ML18152B3971999-07-26026 July 1999 Provides Estimates of Licensing Actions Expected to Be Submitted in Fys 2000 & 2001,in Response to NRC AL 99-02 ML18151A6281999-07-23023 July 1999 Forwards Revised Epips,Including Rev 19 to EPIP-4.02,rev 14 to EPIP-4.16,rev 8 to EPIP-4.21 & Rev 7 to EPIP-4.30.EP & EPIPs Continue to Meet Stds of 10CFR50.47(b) ML18152B3991999-07-23023 July 1999 Requests That License for Jz Laplante Be Canceled as License Is No Longer Required ML18152B3961999-07-23023 July 1999 Forwards Preliminary,Uncertified License Application & Medical Certification for License to Operate Surry Power Station Units 1 & 2 for Ds Cobb.Encl Withheld,Per 10CFR2.790 (a)(6) ML18152B3931999-07-16016 July 1999 Forwards Updated NRC Form 396 & Ltr,Which Documents Medical Status of Mb Gross,License SOP-20476-2.Encl Withheld from Public Disclosure,Per 10CFR2.790(a)(6) ML18152B4401999-07-0101 July 1999 Informs NRC That on 990511,Dominion Resources,Inc,Executed Amended & Restated Agreement & Plan of Merger with Consolidated Natural Gas Co ML18152B4371999-06-24024 June 1999 Forwards Response to NRC Request for Clarification of Relief Requests Submitted on 990212,requesting Relief from Performing Hydrostatic Testing for Certain Small Diameter Class 1,RCS Pressure Boundary Connections ML18152B4361999-06-22022 June 1999 Forwards Response to RAI Re Surry & North Anna Power Stations,Units 1 & 2,per GL 96-06 ML18152B4301999-06-0303 June 1999 Informs of Util Intention to Revise Schedule for Submittal of License Renewal Applications for Surry & North Anna Power Stations to March 2002 ML18152B4261999-05-28028 May 1999 Provides Formal Notification of Effect of Recent Organizational Restructuring on OLs of North Anna & Surry Power Stations,Per NRC 990513 Telcon Request ML18152B4221999-05-27027 May 1999 Forwards Info Concerning Changes to ECCS Evaluation Models & Application in Existing Licensing Analyses for Surry & North Anna Power Stations,Units 1 & 2 ML18152B4231999-05-26026 May 1999 Informs That Vepc Will Revise 180 Day Response to NRC GL 96-05,within 120 Days of Date of Ltr to Incorporate Commitment to Participate in Joint Owners Group Program as Applicable ML18152B4211999-05-25025 May 1999 Forwards Rev 1 to Relief Request P-11 to Clarify Original Intent of Request by Specifically Requesting Relief from Requirements of Section 6.1 of OM-6 ML18152B4171999-05-17017 May 1999 Provides Notification of Number of Steam Generator Tubes That Were Plugged During Spring 1999 Refueling Outage Planned ISI ML18152A3701999-05-13013 May 1999 Submits Proposal to Use Provisions of ASME Section XI Code Case N-597 for Analytical Evaluation of Class 1,2 & 3 Carbon & Low Alloy Steel Piping Components Subjected to Wall Thinning as Result of Flow Accelerated or Other Corrosion ML18152B4121999-05-0303 May 1999 Forwards Application for Renewal of License for SV Ross. Encl Withheld Per 10CFR2.790(a)(6) ML18152B4101999-04-29029 April 1999 Forwards Scope & Objectives for 990803 Surry Power Station Emergency Exercise.Without Encls ML18152B6561999-04-23023 April 1999 Forwards Annual Radioactive Effluent Release Rept for Surry Power Station,Jan-Dec 1998, Which Includes Summary of Quantities of Radioactive Liquid & Gaseous Effluents & Solid Waste Released During CY98 ML18152B6491999-04-13013 April 1999 Forwards MOR for Mar 1999 for Surry Power Station,Units 1 & 2.MOR for Feb 1999 Incorrectly Stated Gross Electrical Energy Generated (Mwh) for Unit 2.Rept Should Have Stated Monthly Figure as 568965.0 ML18151A5851999-03-31031 March 1999 Forwards Rept on Status of Decommissioning Funding for Each of Four Nuclear Power Reactors,Per 10CFR50.75(f)(1) ML18152A2801999-03-30030 March 1999 Forwards Summary of Structural Integrity Evaluation of Thermally Induced Over Pressurization of Containment Penetration Piping During DBA for SPS & Naps,Units 1 & 2,per GL 96-06.Draft Proposed UFSAR Revised Pages,Encl ML18153A2721999-03-29029 March 1999 Forwards LER 99-002-00 Per 10CFR50.73.Listed Commitments Contained in Ltr ML18153A3421999-03-26026 March 1999 Provides Updated Medical Status Rept for Wb Gross in Accordance with License SOP-20476-02,Docket 55-5228,as Amended by 980320 License Amend.Informs That Gross Exhibits No Performance Problems & Will Continue on Current Medicine ML20204H0331999-03-17017 March 1999 Forwards Rev 5 to PSP for Surry & North Anna Power Stations & Associated Isfsis.Description & Justification for Changes Included with Plan Rev.Rev 5 to PSP Withheld Per 10CFR73.21 ML18153A3411999-03-15015 March 1999 Forwards Signed Applications & Medical Certificates for Initial License at Surry Power Station Units 1 & 2 for Listed Individuals.Without Encls 1999-09-08
[Table view] |
Text
...PRI*ORITY 1~ .ACCELERATED RIDS PROCESSI:':G)9 REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS) ACCESSION NBR:9505050201 DOC.DATE:
95/04/28 NOTARIZED:
NO DOCKET# FACIL:50-281 Surry Power Station, Unit 2, Virginia Electric & Powe 05000281 AUTH.NAME AUTHOR AFFILIATION O'HANLON,J.P.
Virginia Power (Virginia Electric & Power Co.) RECIP.NAME RECIPIENT AFFILIATION p Document Control Branch (Document Control Desk)
SUBJECT:
Requests relief from certain requirements of ASME Seeton XI associated w/partial exams conducted during 1995 plant refueling outage ISI. DISTRIBUTION CODE: A047D COPIES RECEIVED:LTR ) ENCL _l_ SIZE: :2-c) TITLE: OR Submittal:
Inservice/Testing/Relief from ASME Code -GL-89-04 R 0 . NOTES: 05000281 R RECIPIENT ID CODE/NAME PD2-l LA BUCKLEY,B INTERNAL:
ACRS~--. C!~;i~D~01 OGC/HDS2 EXTERNAL:
LITCO BROWN,B NOAC NOTES: NOTE TO ALL "RIDS" RECIPIENTS:
COPIES LTTR ENCL 1 1 1 1 6 1 1 1 1 1 1 6 1 1 0 1 1 1 RECIPIENT ID CODE/NAME PD2-1 PD AEOD/SPD/RAB NRR/DE/EMCB NUDOCS-ABSTRACT RES/DSIR/EIB LITCO RANSOME,C NRC PDR PLEASE HELP US TO REDUCE WASTE! CONTACT THE DOCCMENT CO!\:TROL DESK, ROOl'vt Pl-37 (EXT 504-2083)
TO ELil\H:--JATE YOUR \/A\1E FRO\! DISTRIBUTION LISTS FOR DOCLME:--JTS YOU DON'T NEED' TOTAL NUMBER OF COPIES REQUIRED:
LTTR 21 ENCL 20 COPIES LTTR ENCL 1 1 1 1 1 1 1 1 1 1 1 1 1 1 T y 1 D 0 C u M E N T e -VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND, VIRGINIA 23261 April 28, 1995 United States Nuclear Regulatory Commission Attention:
Document Control Desk Washington, D. C. 20555 Gentlemen:
VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION UNIT 2 INSERVICE INSPECTION PROGRAM RELIEF REQUESTS Serial No.95-176 NO/ETS Docket Nos. 50-281 License Nos. DPR-37 During the recent refueling outage, Surry Unit 2 completed its second ten-year interval inservice inspections.
Examinations during this interval were conducted to the requirements of the 1980 Edition and Winter 1980 Addenda of ASME Section XI. Pursuant to 1 O CFR 50.55a (g) 5, relief is requested from certain requirements of ASME Section XI associated with partial examinations conducted during the 1995 Surry Unit 2 refueling outage. Relief requests, SR-22 through SR-26, are attached and provide the basis of this request. These relief requests have been reviewed and approved by the Station Nuclear Safety and Operating Committee.
Should you have any additional questions or require additional information, please contact us. Very truly yours, !!ri~6or.
Senior Vice President
-Nuclear Attachment cc: U. S. Nuclear Regulatory Commission Region II -----101 Marietta Street, N. W. Suite 2900 Atlanta, Georgia 30323 Mr. M. W. Branch NRC Senior Resident Inspector Surry Power Station 9505050201 950428 *, -. ---., PDR . A DOCK 050Q028 i *, *. 1 ______ Q ___ ---*. -.. '..-.~-------~)
. J
- J' Attachment 1 Surry Power Station Unit 2 ISi Examination Relief *
'!, ./ e RELIEF REQUEST SR-22 I. IDENTIFICATION OF COMPONENT Mark/Weld#
Line# H-006 12"-SI-247-1502 H-007 12"-SI-245-1502 Drawing# 11548-WMKS-122A1 11548-WMKS-122L1 II. IMPRACTICABLE CODE REQUIREMENTS Class The 1980 edition, Winter 1980 Addenda (inclusive) of ASME Section XI Table IWB-2500-1, examination category B-K-1, item number B10.10 does not allow any limitations to the required volumetric or surface examinations.
Code Case N-460, Alternative Examination Coverage for Class 1 and Class 2 Welds, allows a reduction in coverage, if it is less than 10%. III. BASIS FOR REL~EF The components listed above has been examined to the extent practical as required by the Code. Due to interferences from pipe support structures and the location of the supports at the point where the pipe passes through the floor, a reduction in coverage of the surface examinations of 50% was necessary.
Figure SR-22-1 is provided detailing the limitations experienced.
The figure is similar for both support structures.
Alternative components could not be substituted for examination due to the mandatory selection requirements of the Code. IV. ALTERNATE PROVISIONS It is proposed that the examination already completed at the reduced coverage be counted as meeting the Code requirements.
V. STATUS Pending 2 -INTEGRAL ATTACHMENTS (1' THICK) INTEGRAL ATTACHMENT
'---~ FLOOR PENETRATION SIDE VIE\v' \v'ALL .-----+I-II----.
1 II 1 TOP VIE\v' Figure SR-22-1 FLOOR MOUNTED SUPPORT FLOOR PENETRATION
- a 6 5 3 *----REFERENCE ORAWINGS1 WIIM*Otl 12:845..34-V,,S*llZlAI ll,.ll-c:&'1*1!186ASl<ETl ll'°'ll<ex*es'IEISHE!fl 115<'11..,..S*llZ*I 115'8-f"P*IIA 11,._ll>fi'*l!B ltS48of"P'*12A W*STtt00JSE lSO'IETll!C WELD l'<EC>W<IOIL Sl<ETQ< rs1a.*ss:r1c11ono,.s.:u.:vrrc,i
.... t>G ISICt.*SSIFICAllt,,I eo,,.:"'" [)RA11N, ,lP'ES1ltESS5'<E1'" :::::::::
,11*1NC-111><G VIRGINlA POWER NORTH CAROL I NA POWER NUCLE.AR ENGlt.EERI~
SERv'icrs RICHMO!'<O, VIRGINIA INSERV!CE INSPECTION ISOME'RIC SI SYS: LOW HEAD SAFETY l~J. LOOP 3 SURRY POWER STATION UNI i 2 VIRGINIA PO'<<ER 0 "'* I
/ *-*-***--*******
- -*------*.--*------------------*------*------------------------
- -------------------*---**
ACCUMULATOR TAN!( l!l!...l rou,48 *-S-ftC*!Z*I J__ . --2 VIRGINIA POWER NORTH CAROLINA POWER NUCLEAR E~Gl'-E[RlNG SE~VICES 1---------RICt-.."!.J',O,VIRGJNJA INSERVICE INSPECTION ISOMETRIC SI SYS: S~FETY INJECTION LOOP I SURRY PO\..'E~ STATION UN: f 2 VIRGiN!A POWER -~-2-j_J ______ !_~_, ---~ __ ,_L__~1=-;:f-1S=~-~-:i.--H-~l~:~~}-FF.R~=Bd~Ff+4~~~HdM.~+
1~~&.ff~-'
f~~-°-:_:J:~~~~;~
I I ___ ., ______ _ D (
- RELIEF REQUEST SR-23 I. IDENTIFICATION OF COMPONENT Mark/Weld#
Drawing# Class 1-11 11548-WMKS-CH-E-3 1 II. IMPRACTICABLE CODE REQUIREMENTS The 1980 edition, Winter 1980 Addenda (inclusive) of ASME Section XI Table IWB-2500-1, examination category B-D, item number B3.150 does not allow any limitations to the required volumetric or surface examinations.
Code Case N-460, Alternative Examination Coverage for Class 1 and Class 2 Welds, allows a reduction in coverage, if it is less than 10%. III. BASIS FOR RELIEF The component listed above has been examined to the extent practical as required by relief request SR-018 of the Inservice Inspection Program for Unit 2 Second Interval.
Due to interferences from a support clamp the reduction in coverage of the surface examination was 14.6%. Figure SR-23-1 is provided detailing the limitations experienced.
Alternative components could not be substituted for examination due to the mandatory selection requirements of the Code. IV. ALTERNATE PROVISIONS It is proposed that the examination already completed at the reduced coverage be counted as meeting the Code requirements.
V. STATUS Pending 2-CH-E-3 LLtxLtxl /2 11 1 -1 1 / A ~L------~
A Angle iron is attached to larger structure and cannot be moved. Figure SR-2Lt-l 20. 5" circurnf erence 6.5" A-A r----S----L--.,...=-.,iR'-EG_E_N_E.JR_A_TI_V_E4....,:=.:::::,,.~.:;..........1.
__ ~.....,.-~...,C....L-......:.---~:::...-..L----
3---......L..----
2----...._----l---~
1-16 A 22-JUN-1qq2 0q,55 ZGS: C 355, 0021CHE000003.
OGN A HEAT EXCHANGER 2-CH-_5:_ ____ I E-3 . TU8ESHEET
.1 SHELL 0 7 q.25* DIA X 0.875' THICK A213 TP 304 SS CTYP OF 3l . SHELL 0 8 3" SCH 80 PIPE CTYP 2 PLACES) ELEVATION LOOKING WEST B ISi ISi CLASS 2A CLASS IA TO 11548 -WMKS-CH-8 CaF-4) REV I SEO PER WALKDOWN I ND ISi REVIEW 0 INITIAL ISSUE -... _ ...... _..,_,,,_
SECTION °8° SECTION "A" VIRGINIA POWER NORTH CAROLINA POWER IIJC1EAR ENG lt£ER I tiO SERVICES Rl~,Vliwi~IA INSERVICE INSPECTION DETAIL DRAWING REGENERATIVE HEAT EXCHANGER:2-CH-E-3 SURRY POWER STATION UNIT 2 VIRGINIA POWER OSGI SlJ'Y ARF CAO NO. CHE0000113 MBL DJSPL ENOR WFM mAVIJr<<l NO. lr.r-r--r,-r-,-,.-r-r-r-,--t---M-B-L---1-LE-AD_EHOR
___________ -l 11548-WMKS-CH-E-3 SCALE NONE l.fLESS OTI-ER'i 1 SI:: NJTED 2 E C A
., RELIEF REQUEST SR-24 I. IDENTIFICATION OF COMPONENT Mark/Weld#
Drawing# Class 1-01 11548-WMKS-CH-FL-4A/B 2 II. IMPRACTICABLE CODE REQUIREMENTS The 1980 edition, Winter 1980 Addenda (inclusive) of ASME Section XI Table IWC-2500-1, examination category c-A, item number Cl.20 does not allow any limitations to the required volumetric or surface examinations.
Code Case N-460, Alternative Examination Coverage for Class 1 and Class 2 Welds, allows a reduction in coverage, if it is less than 10%. , III. BASIS FOR RELIEF The component listed above has been examined to the extent practical as required by the Code. Due to interferences from three permanent support legs the reduction in coverage of the ultrasonic examination was 35% (12 11 out of 34 11). Figure SR-24-1 is provided detailing the limitations experienced.
Alternative components could not be substituted for examination due to the mandatory selection requirements of the Code. IV. ALTERNATE PROVISIONS It is proposed that the examination already completed at the reduced coverage be counted as meeting the Code requirements. , V. STATUS Pending A CH-FL-4A/B A 19" 15" A-A Figure SR-24-1 31" 3 4 II ,__________, ----O" 3.5"
- . ..... . , .*~~-* *-**--* ~--*-* GENERAL ELEVATION NOTESi *i.=::~i~~~rg,,~s~1 REFERENCE DRAWINGS:
- L'l*Z*ll<:0' l~$*CS>1*0a8CSl<EtfZ D*'l'U*2B03 11<<8*U!H7A wESTl><<;>0.1$£ (s,>,ETAtt ISICLASS!l'!CAT!O,.!ICU'()AIIY D1'A11:*G C0>9<£W.:l"I.
I'll.IE~~
C."RP COl+IEIICllll.F[LlE!lSC'..'AP""'GtJIOl<<lD*q*o-iiu., VIRGINIA POWER NORTH CAROLINA POWER ~VCLEf,R (NGJSEEAINO
's"Eiw!CES "l!CM"4G,',C,Vli'<.CilNl1:1 i r-*
- t~)
- * *:.tt'* t~, ;~ c-::-~;.i*
__ * *******;****************--***-**-**--*******************.
- -******----------*------*
- --*-*----******-*----**-*****---------*--*--***
- .. : .********-------------------*--*---------.
*-'------*-------------*-------*--**--:--*-*-*:--:-*----:-*-:
__ :1f;/~'-.. , .. J. ~-----'-----,-----'*-*------,.---------------,-------------,---------;**If
- 'l
- B 7 6 .5 4 3 2 E * . ,* ' r =:.i. I ',i *; ! :j j :j I f 'I i D j I i 1* ,,) >*-j*1 ; ;~-; ~---j ,.,, ! N.!T
- IS.I CLASS 29 j2'*C~*l76*l':>lll*\
- . -** -. GENERAL ELEVATION
__J. .*, -*~ **--D--NOTES, i.=:=R[F:~~£~:~~:~~:~~rj REFERENCE OR~W!NGS1 VIR*2*13N U5'8-cBM*031!CS>'CET2 0-,*U*21!11J uu~H.cl'5*17A ltESfl~EISCf'IETRIC ISIC1.ASSl~!:1>flO><&~YORA"'I"'° C!JMo<EltCIAl.~fLJEIISC~, CQ+ltRC!<>I.
1'11,.l(IIS Cor:u> !>I',: DRC NCI D-q..iu,20Ul VIRGINIA POWER NORTH CAROL I NA POWER ~UCLEAR Ei.C:N!:.::i.lr,.G SERVICES t-------"~"~'"_.:_-.o.v:i:i_c,_,_,.
______ _ INSERVJC£ iNSPECTION DETAIL DR4WING SEAL !NJECTION FILTER, 2-CH-FL-'3 SURRY PCWER STATION UNIT ? VIRGINIA POWER F l: ,. **. ' le I
.. . ., RELIEF REQUEST SR-25 I. IDENTIFICATION OF COMPONENT Mark/Weld#
Line# Drawing# Class 1-09 31 11-RC-308-2501R 11548-WMKS-RC-10~1 1 II. IMPRACTICABLE CODE REQUIREMENTS The 1980 edition, Winter 1980 Addenda (inclusive) of ASME Section XI Table IWB-2500-1, examination category B-J, item number B9.11 does not allow any limitations to the required volumetric or surface examinations.
Code Case N-460, Alternative Examination Coverage for Class 1 and Class 2 Welds, allows a reduction in coverage, if it is less than 10%. III. BASIS FOR RELIEF The component listed above has been examined to the extent practical as required by the Code. Due to the geometry of the weld crown the reduction in coverage of the volumetric examinations are detailed in Table SR-25-1. Figure SR-25-1 is provided detailing the limitations experienced.
Substituting with another weld of the same size would not necessarily improve *the examination coverage since similar geometric conditions are expected.
IV. ALTERNATE PROVISIONS It is proposed that the examination already completed at the reduced coverage be counted as meeting the Code requirements.
V. STATUS Pending Mark/Weld#
1-09 50 2 83 UT Scan Direction Definitions UT Scan Coverage%
!. 72 72 Table SR-25-1 Surry Unit 2 Examination coverage Estimates 11548~WMKS=RC-10-1 category B-J, Item B9.11 Surface Examination Coverage%
100 Reason For Partial The geometry of the weld crown limits the coverage in the area of pipe to weld and weld to elbow. Material type, ASTM A-351 austentic steel casting, limits the use of an extended V-path examination.
2 -Axial scan, 180 degrees from isometric flow direction.
5 -Axial scan, the same direction as the isometric flow. 7 -Circumferential scan, clockwise rotation when viewing in the direction of isometric flow. 8 -Circumferential scan, counterclockwise rotation when viewing in the direction of isometric flow. e
'C' S/G FLOW .. PIPE 2. 6" 3.6" 31 "-RC-308-2501 R WELD 1 -09 FIGURE SR-25-1 FLOW .. ELBOW 3. OS" * . . e
_/ ;.:;t*\i 1"~:J; C -:*1 l E ---J' ,. l ,J ; lD-U'*" l5J'J.C"-",/
- ~ '(!;';afil, R-1 ~;-(n.1r-, 1,,11i"/*'
1C1Tt,v(Jll(t>1tSOWG1tlrWus,e--s*11C*!9*2 I .,-_,'.*** *NOTES1 *-L=~~CN==,.il~Jfll~~--, Z.M.L P!P!MG ts 151 CUSS,.. 111*1l£lSM'.l[DIA[Sl'OCIICl~CW.WUC.fCJl1NtSrsct"IETRIC.
t.VEUJS I-ti nau l*Zl W L,IKJ1UIINJlt.
£UClllOSlJIIG IICl.DS. ---.... . ' :~:a ~vn.os l*V
- 1-23 ric5TJrU.ED 1'11'1 Lva.DSl.+l.1~1_..,.,L--,,14'1REPUICIJll"I,.._
7 0 F'O'IC£1llll..SOFTHEREllCTIJIV£Ua..S[tll541!*111<<S*2'-f'C+I LF"QIIO(Tllll..SOFTHESTtM<iOICFYITOR,SE£tl,-.1*-S*2-RC-E*IC
'I.FIJIC(TAllSOFMREacJOllcoo..,,o,T;,i,,P.SE(lt~--s-2.,ic
... ie l&f!JIDETAILSOFJM!LOQPSTCJ'*A!.YESMJ'l'*~IMCN*~S£E11'48*-5*
...rw-2WMCJMCN-25'15.FIE5'1:CftrnY.
REFERENCE DRAWINGS:
¥11't-Hl911 llSll-a,,l-t118(;,19Efi 3 U!S411.<<SZ*lll2.I ll5,I.B.fP*8111 l~ll.f'l'*B8
- zs=,~~-nc:
I'll'( n.nraiu,, -.m; SKtT :::: :::: 0 VIRGINIA POWER NOR TH CAr\OL 1 N:\ PO\rrl'EA M.JCl.E~ ENGIN:ERI~
SERVICES 1 HC~.YIRCINIA dj mj ITT3 . 1 1 1 1 , -~-;;;::.~;;, ;;;: .. .,,. .... -...... _ . *=' :tJ , , , _;__J__:_, __ , __!_j_,_1
___ 1_u_1-~1 _1_L, 1 / 1 , 1 1 1 1 _u1 / I 1 , 1 1 1 1 1 I 1 1 ! J ,~ IUSERVICE INSPECTION ISOMETR'C RC SYS,LOO? C REAC,OR COOLANT PIPE SURRY ?Q\.IER ST,HICN UNlr 2 VIRGINIA PO'..iER . ~.::i --<-****"*:*
-~<::;.:*.:.*, -.,::,:: *'i'.\-~:>:*
,,JA,-1,---*;*i-::*-.
- .;::,:
-*;-~*-:,,-;*.,~-:
--~*-'.----~~-:--:;*.:,,:;'
-~:;! .. *1(*:.:*J~*.;i-
.. -*"'cc*:cst-c!;'*,:,*:,::c;;:.;~ "W:,:,:.;
- .. ,... --*---------
--3 -~m '"'""'" ""' -,_ ' *,i:: ,z<-*,-,.A:.o/:
0 C e RELIEF REQUEST SR-26 I. IDENTIFICATION OF COMPONENT Mark/Weld#
Drawing# Class 2-05 11548-WMKS-RS-P-2A 2 II. IMPRACTICABLE CODE REQUIREMENTS The 1980 edition, Winter 1980 Addenda (inclusive) of ASME .Section XI Table IWC-2500-1, examination category C-G, item number C6.10 does not allow any limitations to the required volumetric or surface examinations.
Code Case N-460, Alternative Examination Coverage for Class 1 and Class 2 Welds, allows a reduction in coverage, if it is less than 10%. III. BASIS FOR RELIEF The component listed above has been examined to the extent practical as required by the Code. Due to interferences from a pump casing support the reduction in coverage of.the surface examination was 25%. Figure SR-26-1 is provided detailing the limitations experienced.
No other alternative is available for substitution since the "B" pump has the same limitation . ** *** .-... .: .,**: -~ : ....... *,r IV. ALTERNATE PROVISIONS It is proposed that the examination already completed at the reduced coverage be counted as meeting the Code requirements.
V. STATUS. Pending
- . 1 . RS-P-2A \v'ALL SIDE VIE\J \JALL TOP VIE\J Figure SR-26-1
- 8 7 F D E D VS LC ~' '* D 6 ./2-Rs-'\ OUTSIDE RECIRC SPRAY PUMP TO 11548 -WMKS-0123NI 1DD-7l / I ~0*-Rs-10q-1s~
8 ~DISCHARGE . '--._ GAUGE CONNECTION
__ CAN DRAIN <l'P!Pt:I -SEE 11448-FV-SA IOET El -FOR VIBRAl!ON
~LATE DETAIL /0 -2'Xl/2'THK RING 5 /wELOED TO CASING c:!:====!=i*
ACCESSIBLE EL 12'-0' C 8 A Sl lFFENING RIB ITYP *1 --.:i~idi'ii,~IZ
[E[j/ IOB-7> '" 12'-RS-107-153-
! '"' ----.:, 6-MAR-l q'10 121-iq OSA3: { 3S5, rZ-021RSP0002A:.
OGN / -. ----INACC.ESSIBLE
~--;II l_ DETAIL A BOWL BASE LUBE LINES 20 -I 3/8' DIA HOLES VENT TO SUCT CAN DRAIN/ <I' PIPE> SECT 8-8 4 12'SCH 405 PIPE 1 \ J ,/ LONGITUDIN!,L WE*. 0 DET A DET 8 DET C *ii_ OISCHAaGE
- 32' DIA FL,)NGE IIIITIAL.
ISSUE 2 DET D ! 31** -..--~---SECT A-A 0 RING SLOTS\~ \ *. DET E VIRGINifl POWER NORTH CAROLINA POWER POWER El'<GIN£[Rlt<G SERY1C£S 1-c~~=-~-~-"-Rl,_,CccH>O-Oc=-, YIRG_IN_I_A_~----
I NS ERV [ [E INSPECTION DETAIL DRAWING OUTSIDE REC1RC SPRAY PUMP:2-RS-P-2A SURRY POWER STATION UNIT 2 1-----.--___yj RGI NI A POW ER 0SC,, SUPY /ll; CAO HJ. RSP00a2AI
~WN MB!.. DI~ E~OO ~AW1"'1 M'J. Rt:~. ::.it 1-L-,..,-,-,.--,,-=:u::C--1 1154B-WMKS-RS-P-2A 0 -~~-+----------------~--~----<
p E D C B A