|
---|
Category:CORRESPONDENCE-LETTERS
MONTHYEARML20217P7111999-10-26026 October 1999 Informs That Licensee 990330 Response to GL 97-06 Provides Reasonable Assurance That Condition of Licensee Steam Generator Internals Is in Compliance with Current Licensing Bases for Plant ML20217K3571999-10-21021 October 1999 Discusses Use of SONGS as Generic Safety Issue 191 Ref Plant.Future Requests for Info & Addl Coordination Activities Be Handled Through D Evans of Organization.With Diskette ML20217K8541999-10-21021 October 1999 Forwards Revised Pages to ERDS Data Point Library,Per Requirements of 10CFR50,App E,Section VI.3.a.Described Unit 2 & 3 Changes for 2/3R7813 Were Completed on 990924 ML20217L9491999-10-21021 October 1999 Forwards SONGS Emergency Response Telephone Directory, for Oct-Dec 1999 ML20217J8631999-10-15015 October 1999 Forwards Insp Repts 50-361/99-12 & 50-362/99-12 on 990808- 0918.One Violation Identified Involving Inoperability of Emergency Diesel Generator in Excess of Allowed Outage Time ML20217E3221999-10-13013 October 1999 Forwards MORs for Sept 1999 for Songs,Units 2 & 3.No Challenges Were Noted to Psvs for Either Units 2 or 3 ML20217E7671999-10-12012 October 1999 Forwards Rev 62 to NRC Approved Aug 1983, Physical Security Plan,Songs,Units 1,2 & 3, IAW 10CFR50.54(p).Changes,as Described in Encls 1 & 2,do Not Reduce Effectiveness of Plan.Encl Withheld,Per 10CFR73.21 ML20217B5981999-10-0606 October 1999 Informs That Staff Concluded That All Requested Info for GL 98-01, Year 2000 Readiness in Us Nuclear Power Plants, Provided for San Onofre Nuclear Generating Station,Units 2 & 3 ML20216H8741999-09-29029 September 1999 Provides Requested Written Response to GL 99-02, Lab Testing of Nuclear-Grade Activated Charcoal. Lab Testing of Charcoal Adsorber Samples for Creacus & Pacu Satisfies Listed Requirements ML20216H8541999-09-29029 September 1999 Submits Encl Request for Relief from ASME Code,Section III Requirements in 10CFR50.55(a)(3) to Use Mechanical Nozzle Seal Assembly as Alternate ASME Code Replacement at SONGS, Units 2 & 3 for Period of Operation Beginning with Cycle 11 ML20216J2631999-09-28028 September 1999 Forwards Copy of Final Accident Sequence Precursor (ASP) Analysis of Operational Event at Songs,Unit 2,reported in LER 361/98-003 ML20212H4461999-09-28028 September 1999 Forwards Suppl Info,As Discussed with NRC During 990812 Telcon,To Support Risk Informed Inservice Testing & GL 96-05, Periodic Verification of Design-Basis Capability of Safety-Related Movs ML20212G5611999-09-24024 September 1999 Informs NRC That SCE Remains Committed to Performing Eddy Current Examinations of 100% of Reactor Vessel Head Penetrations at Songs,Unit 3.Exams Will Not Be Performed During Cycle 11 RFO 05000361/LER-1999-005, Forwards 30-day follow-up LER 99-005-00,describing Loss of Physical Train Separation in Control Room.Any Actions Listed Intended to Ensure Continued Compliance with Existing Commitments1999-09-23023 September 1999 Forwards 30-day follow-up LER 99-005-00,describing Loss of Physical Train Separation in Control Room.Any Actions Listed Intended to Ensure Continued Compliance with Existing Commitments ML20212D9921999-09-16016 September 1999 Informs That on 990818,NRC Staff Completed Midcycle PPR of San Onofre.Nrc Plan to Conduct Core Insps & One Safety Issues Evaluation of MOVs at Facility Over Next 7 Months. Details of Insp Plan Through March 2000 Encl ML20212A4061999-09-14014 September 1999 Forwards Revised Pages to ERDS Data Point Library.Described Unit 2 Changes for 2R7817 & 2R7828 Were Completed on 990818 & Unit 3 Change for 3R7828 Was Completed on 990903 ML20216E6031999-09-10010 September 1999 Provides Response to NRC Administrative Ltr 99-03, Preparation & Scheduling of Operator Licensing Exams, Dtd 990820.Schedule Shown on Attachment 1, Operator Licensing Exam Data, Provides Util Best Estimate Through Cy 2003 ML20217B9011999-09-10010 September 1999 Responds to Which Addressed Concerns Re Y2K Issue & Stockpiling of Potassium Iodide (Ki) Tablets by Informing That San Onofre Nuclear Station Already Completed All Work Required to Be Ready for Y2K Transition ML20211K4191999-09-0303 September 1999 Final Response to FOIA Request for Documents.Documents Listed in App a Being Withheld in Part (Ref FOIA Exemptions 5 & 7) ML20211N0261999-09-0303 September 1999 Forwards Exemption from Certain Requirements of 10CFR50.44 & 10CFR50,app A,General Design Criterion 41 in Response to Util Request of 980910,as Supplemented 990719 & SER 05000206/LER-1999-001, Forwards LER 99-001-00 for Occurrence Re Unattended Security Weapon Inside Protected Area.Single Rept for Unit 1 Is Being Submitted,Iaw NUREG-1022,Rev 1,since Condition Involves Shared Sys & Is Applicable to Units 1,2 & 31999-08-31031 August 1999 Forwards LER 99-001-00 for Occurrence Re Unattended Security Weapon Inside Protected Area.Single Rept for Unit 1 Is Being Submitted,Iaw NUREG-1022,Rev 1,since Condition Involves Shared Sys & Is Applicable to Units 1,2 & 3 ML20211H3321999-08-30030 August 1999 Discusses 1999 Emergency Preparedness Exercise Extent of Play & Objectives.Based on Review,Nrc Has Determined That Exercise Extent of Play & Objectives Are Appropriate to Meet Emergency Plan Requirements ML20211J7151999-08-27027 August 1999 Forwards Insp Repts 50-361/99-09 & 50-362/99-09 on 990627- 0807.Two Violations Being Treated as non-cited Violations ML20211H8561999-08-23023 August 1999 Forwards SE Accepting Licensee 970625 Requests for Relief RR-E-2-03 - RR-E-2-04 from Exam Requirements of Applicable ASME Code,Section Xi,For First Containment ISI Interval ML20211J5821999-08-23023 August 1999 Corrected Copy of ,Changing Application Date from 970625 to 990625.Ltr Forwarded SE Accepting Licensee 990625 Requests for Relief RR-E-2-03 - RR-E-2-08 from Exam Requirements of Applicable ASME Code,Section XI as Listed ML20210V4271999-08-16016 August 1999 Forwards Proprietary Certified Renewal Applications for SROs a Harkness,R Grabo & T Vogt & RO D Carter,Submitted on Facsimile Form NRC-398 & Certified NRC Form 396.Encls Withheld ML20210R6681999-08-13013 August 1999 Forwards Response to NRC RAI Re SCE License Amend Applications 173 & 159 for Songs,Units 2 & 3,proposed Change Number 485,which Requests Addition of SR to TS 3.3.9, CR Isolation Signal ML20211A9501999-08-12012 August 1999 Discusses 990720-21 Workshop Conducted in Region IV Ofc,Re Exchange of Info in Area of Use of Risk Insights in Regulatory Activities.List of Attendees,Summary of Topic & Issues,Agenda & Copies of Handouts Encl ML20210Q6451999-08-12012 August 1999 Forwards Monthly Operating Repts for July 1999 for SONGS, Units 2 & 3,per TS 5.7.1.4.There Were No Challenges to Pressurizer Safety Valves for Either Units ML20210P5711999-08-11011 August 1999 Forwards Amend Application Number 189 for License NPF-10 & Amend Application Number 174 to License NPF-15,replacing Analytical Limits Currently Specified as Acceptance Criteria with Allowable Values,Per Encl Calculation E4C-098 ML20210P4681999-08-11011 August 1999 Forwards COLR for Cycle 10 for Songs,Units 2 & 3,IAW TS Section 5.7.1.5.d, Colr. Changes to COLR Parameters Have Been Conducted IAW Approved COLR Methodologies & All Applicable Limits of Safety Analysis Were Met ML20210P6221999-08-10010 August 1999 Forwards Replacement Pages for Attachments E & F of Amend Application Numbers 168 & 154 for Songs,Units 2 & 3.Pages Are Provided to Correct Errors to Pagination & Headings in 970618 Submittal ML20210N9721999-08-10010 August 1999 Responds to Appeal of FOIA Request for Documents Re Osre Issue.No Osre Visit Scheduled for Sept 1996 at Plant,Per 990722 Telcon.V Dricks,In Ofc of Public Affairs Should Be Contacted Re Osre Issue ML20210N0901999-08-0909 August 1999 Informs That 990312 Application Requested Amends to Licenses DPR-13,NPF-10 & NPF-15,respectively,being Treated as Withdrawn.Proposed Change Would Have Modified Facility TSs Pertaining to SONGS Physical Security Plan ML20210N5051999-08-0909 August 1999 Forwards Cycle 10 Update to TS Bases,Which Have Been Revised Between 980101-990630,per 10CFR50.71(e) 05000361/LER-1999-004, Forwards LER 99-004-00 Re Automatic Tgis Actuation.Event Affected Units 2 & 3 Equally Because Tgis Is Shared Sys. Single Rept Is Being Provided for Unit 2 IAW NUREG-1022, Rev 1.No New Commitments Are Contained in Encl1999-08-0606 August 1999 Forwards LER 99-004-00 Re Automatic Tgis Actuation.Event Affected Units 2 & 3 Equally Because Tgis Is Shared Sys. Single Rept Is Being Provided for Unit 2 IAW NUREG-1022, Rev 1.No New Commitments Are Contained in Encl ML20210L2311999-08-0505 August 1999 Forwards ISI Summary Rept,Including Owners Repts of Repairs & Replacements,For Songs,Unit 3.Rept Covers 970916 Through 990509,date Unit 3 Returned to Service Following Cycle 10 Refueling Outage ML20210L1461999-08-0303 August 1999 Informs That NRC Plans to Administer Gfes of Written Operator Licensing Exam on 991006.Requests Submittal of Ltr Identifying Individuals Taking Exam,Personnel Allowed Access to Exams & Mailing Address for Exams ML20216D9671999-07-29029 July 1999 Provides Response to RAI to Support Proposed TS Change 460 Re Containment Isolation Valve Completion Time for SONGS, Units 2 & 3.Rev 3 to Abnormal Operating Instruction SO23-13-14, Reactor Coolant Leak, Encl ML20210C1821999-07-22022 July 1999 Forwards Rept Providing Results of Insp of Eggcrate Tube Supports Done on Secondary Side of Sgs,Using Remote Controlled Visual Equipment ML20210B2451999-07-21021 July 1999 Forwards Response to NRC 990615 RAI Re GL 95-07, Pressure Locking & Thermal Bldg of SR Power-Operated Gate Valves, for Songs,Units 2 & 3 ML20210B9891999-07-20020 July 1999 Ack Receipt of Transmitting Plant Emergency Plan Implementing Procedure SO123-VIII-1, Recognition & Classification of Emergencies ML20209J5241999-07-19019 July 1999 Provides Clarification of Util Intentions Re Disposition of Systems for Which Exemption & TS Changes Were Requested in Licensee .Deferment of Action Re Hydrogen Monitors,Encl ML20210N2881999-07-19019 July 1999 Forwards Rev 61 to Physical Security Plan,Rev 21 to Safeguards Contingency Plan & Rev 20 to Security Force Training & Qualification Plan,Per 10CFR50.54(p),for Plant. Screening Criteria Forms Encl.Plans Withheld ML20210A2911999-07-19019 July 1999 Submits Withdrawal Request Submitted by Ltr Dtd 990312, Requesting NRC Approval of Revs to Physical Security Plan & Safeguards Contingency Plan Tactical Response Plan ML20209G3421999-07-15015 July 1999 Forwards Table of 16 Affected Tube Locations in SG E089, Discovered During Cycle 10 Outage Insp,Which Were Probably Not Examined by Bobbin During Cycle Outage Insp ML20209D8051999-07-12012 July 1999 Discusses Licensee Response to RAI Re GL 92-01,Rev 1,Suppl 1, Rc Structural Integrity, Issue on 950519 to Plant. NRC Revised Info in Reactor Vessel Integrity Database & Is Releasing It as Rvid Version 2 ML20209F5681999-07-0909 July 1999 Forwards Insp Repts 50-361/99-08 & 50-362/99-08 on 990516- 0626.One Violation Identified & Being Treated as Noncited Violation,Consistent with App C of Enforcement Policy ML20209C1571999-07-0202 July 1999 Forwards Response to NRC RAI Re SCE Submittal Dtd 980710,re GL 96-06, Assurance of Equipment Operability & Containment Integrity During Design-Basis Accident Conditions ML20196K6721999-07-0202 July 1999 Discusses 990628 Meeting Conducted in Region IV Office Re Status of San Onofre Nuclear Generating Station Emergency Preparedness Program.List of Attendees & Licensee Presentation Encl 1999-09-03
[Table view] Category:INCOMING CORRESPONDENCE
MONTHYEARML20217L9491999-10-21021 October 1999 Forwards SONGS Emergency Response Telephone Directory, for Oct-Dec 1999 ML20217K3571999-10-21021 October 1999 Discusses Use of SONGS as Generic Safety Issue 191 Ref Plant.Future Requests for Info & Addl Coordination Activities Be Handled Through D Evans of Organization.With Diskette ML20217K8541999-10-21021 October 1999 Forwards Revised Pages to ERDS Data Point Library,Per Requirements of 10CFR50,App E,Section VI.3.a.Described Unit 2 & 3 Changes for 2/3R7813 Were Completed on 990924 ML20217E3221999-10-13013 October 1999 Forwards MORs for Sept 1999 for Songs,Units 2 & 3.No Challenges Were Noted to Psvs for Either Units 2 or 3 ML20217E7671999-10-12012 October 1999 Forwards Rev 62 to NRC Approved Aug 1983, Physical Security Plan,Songs,Units 1,2 & 3, IAW 10CFR50.54(p).Changes,as Described in Encls 1 & 2,do Not Reduce Effectiveness of Plan.Encl Withheld,Per 10CFR73.21 ML20216H8741999-09-29029 September 1999 Provides Requested Written Response to GL 99-02, Lab Testing of Nuclear-Grade Activated Charcoal. Lab Testing of Charcoal Adsorber Samples for Creacus & Pacu Satisfies Listed Requirements ML20216H8541999-09-29029 September 1999 Submits Encl Request for Relief from ASME Code,Section III Requirements in 10CFR50.55(a)(3) to Use Mechanical Nozzle Seal Assembly as Alternate ASME Code Replacement at SONGS, Units 2 & 3 for Period of Operation Beginning with Cycle 11 ML20212H4461999-09-28028 September 1999 Forwards Suppl Info,As Discussed with NRC During 990812 Telcon,To Support Risk Informed Inservice Testing & GL 96-05, Periodic Verification of Design-Basis Capability of Safety-Related Movs ML20212G5611999-09-24024 September 1999 Informs NRC That SCE Remains Committed to Performing Eddy Current Examinations of 100% of Reactor Vessel Head Penetrations at Songs,Unit 3.Exams Will Not Be Performed During Cycle 11 RFO 05000361/LER-1999-005, Forwards 30-day follow-up LER 99-005-00,describing Loss of Physical Train Separation in Control Room.Any Actions Listed Intended to Ensure Continued Compliance with Existing Commitments1999-09-23023 September 1999 Forwards 30-day follow-up LER 99-005-00,describing Loss of Physical Train Separation in Control Room.Any Actions Listed Intended to Ensure Continued Compliance with Existing Commitments ML20212A4061999-09-14014 September 1999 Forwards Revised Pages to ERDS Data Point Library.Described Unit 2 Changes for 2R7817 & 2R7828 Were Completed on 990818 & Unit 3 Change for 3R7828 Was Completed on 990903 ML20216E6031999-09-10010 September 1999 Provides Response to NRC Administrative Ltr 99-03, Preparation & Scheduling of Operator Licensing Exams, Dtd 990820.Schedule Shown on Attachment 1, Operator Licensing Exam Data, Provides Util Best Estimate Through Cy 2003 05000206/LER-1999-001, Forwards LER 99-001-00 for Occurrence Re Unattended Security Weapon Inside Protected Area.Single Rept for Unit 1 Is Being Submitted,Iaw NUREG-1022,Rev 1,since Condition Involves Shared Sys & Is Applicable to Units 1,2 & 31999-08-31031 August 1999 Forwards LER 99-001-00 for Occurrence Re Unattended Security Weapon Inside Protected Area.Single Rept for Unit 1 Is Being Submitted,Iaw NUREG-1022,Rev 1,since Condition Involves Shared Sys & Is Applicable to Units 1,2 & 3 ML20210V4271999-08-16016 August 1999 Forwards Proprietary Certified Renewal Applications for SROs a Harkness,R Grabo & T Vogt & RO D Carter,Submitted on Facsimile Form NRC-398 & Certified NRC Form 396.Encls Withheld ML20210R6681999-08-13013 August 1999 Forwards Response to NRC RAI Re SCE License Amend Applications 173 & 159 for Songs,Units 2 & 3,proposed Change Number 485,which Requests Addition of SR to TS 3.3.9, CR Isolation Signal ML20210Q6451999-08-12012 August 1999 Forwards Monthly Operating Repts for July 1999 for SONGS, Units 2 & 3,per TS 5.7.1.4.There Were No Challenges to Pressurizer Safety Valves for Either Units ML20210P5711999-08-11011 August 1999 Forwards Amend Application Number 189 for License NPF-10 & Amend Application Number 174 to License NPF-15,replacing Analytical Limits Currently Specified as Acceptance Criteria with Allowable Values,Per Encl Calculation E4C-098 ML20210P4681999-08-11011 August 1999 Forwards COLR for Cycle 10 for Songs,Units 2 & 3,IAW TS Section 5.7.1.5.d, Colr. Changes to COLR Parameters Have Been Conducted IAW Approved COLR Methodologies & All Applicable Limits of Safety Analysis Were Met ML20210P6221999-08-10010 August 1999 Forwards Replacement Pages for Attachments E & F of Amend Application Numbers 168 & 154 for Songs,Units 2 & 3.Pages Are Provided to Correct Errors to Pagination & Headings in 970618 Submittal ML20210N5051999-08-0909 August 1999 Forwards Cycle 10 Update to TS Bases,Which Have Been Revised Between 980101-990630,per 10CFR50.71(e) 05000361/LER-1999-004, Forwards LER 99-004-00 Re Automatic Tgis Actuation.Event Affected Units 2 & 3 Equally Because Tgis Is Shared Sys. Single Rept Is Being Provided for Unit 2 IAW NUREG-1022, Rev 1.No New Commitments Are Contained in Encl1999-08-0606 August 1999 Forwards LER 99-004-00 Re Automatic Tgis Actuation.Event Affected Units 2 & 3 Equally Because Tgis Is Shared Sys. Single Rept Is Being Provided for Unit 2 IAW NUREG-1022, Rev 1.No New Commitments Are Contained in Encl ML20210L2311999-08-0505 August 1999 Forwards ISI Summary Rept,Including Owners Repts of Repairs & Replacements,For Songs,Unit 3.Rept Covers 970916 Through 990509,date Unit 3 Returned to Service Following Cycle 10 Refueling Outage ML20216D9671999-07-29029 July 1999 Provides Response to RAI to Support Proposed TS Change 460 Re Containment Isolation Valve Completion Time for SONGS, Units 2 & 3.Rev 3 to Abnormal Operating Instruction SO23-13-14, Reactor Coolant Leak, Encl ML20210C1821999-07-22022 July 1999 Forwards Rept Providing Results of Insp of Eggcrate Tube Supports Done on Secondary Side of Sgs,Using Remote Controlled Visual Equipment ML20210B2451999-07-21021 July 1999 Forwards Response to NRC 990615 RAI Re GL 95-07, Pressure Locking & Thermal Bldg of SR Power-Operated Gate Valves, for Songs,Units 2 & 3 ML20210A2911999-07-19019 July 1999 Submits Withdrawal Request Submitted by Ltr Dtd 990312, Requesting NRC Approval of Revs to Physical Security Plan & Safeguards Contingency Plan Tactical Response Plan ML20210N2881999-07-19019 July 1999 Forwards Rev 61 to Physical Security Plan,Rev 21 to Safeguards Contingency Plan & Rev 20 to Security Force Training & Qualification Plan,Per 10CFR50.54(p),for Plant. Screening Criteria Forms Encl.Plans Withheld ML20209J5241999-07-19019 July 1999 Provides Clarification of Util Intentions Re Disposition of Systems for Which Exemption & TS Changes Were Requested in Licensee .Deferment of Action Re Hydrogen Monitors,Encl ML20209G3421999-07-15015 July 1999 Forwards Table of 16 Affected Tube Locations in SG E089, Discovered During Cycle 10 Outage Insp,Which Were Probably Not Examined by Bobbin During Cycle Outage Insp ML20209C1571999-07-0202 July 1999 Forwards Response to NRC RAI Re SCE Submittal Dtd 980710,re GL 96-06, Assurance of Equipment Operability & Containment Integrity During Design-Basis Accident Conditions ML20210N9871999-07-0101 July 1999 Appeals Denial of Documents Re Sept 1996 Osre for San Onofre Nuclear Generating Station.Requests Copies of Sept 1996 Osre Rept & Any More Recent Osre Repts ML20209B3571999-06-28028 June 1999 Submits Response to GL 98-01,Suppl 1 Y2K Readiness of Computer Sys at Nuclear Power Plants. GL 98-01 Requested Response on Status of Facility Y2K Readiness by 990701. Disclosure Encl ML20209B4831999-06-25025 June 1999 Requests NRC Approval of Six Relief Requests from ASME Code Requirement for Containment ISI Exams.Six Relief Requests, Provided as Enclosures 1-6,are as Listed ML20196A9801999-06-17017 June 1999 Responds to NRC 990420 RAI Re Proposed risk-informed Inservice Testing & GL 96-05 Programs at Songs,Units 2 & 3. Revised Pages to risk-informed Inservice Testing Program, Encl ML20195G8091999-06-14014 June 1999 Forwards Response to RAI Made During 990511 Telcon Re LARs 184 & 170 for SONGS Units 2 & 3.Amend Applications Proposed Restriction on Operation with Channel of RAS or Efas in Tripped Condition ML20195K4201999-06-11011 June 1999 Forwards LERs 99-003-00 & 99-004-00 Re Manual Esfas (Reactor Trips) Due to Problems with Main Feedwater Control.Two Events Are Being Reported Separately Because Actual Causes Are Considered Different & Independent of Each Other ML20195H1561999-06-10010 June 1999 Forwards MORs for May 1999 for Songs,Units 2 & 3.There Were No Challenges to Pressurizer Safety Valves for Either Unit 2 & 3 ML20195E4981999-06-0808 June 1999 Forwards Application for Amends 188 & 173 to Licenses NPF-10 & NPF-15 for SONGS Units 2 & 3,respectively.Amends Would Revise TS 3.5.2,3.1.9,3.7.1 & 5.1.7.5 Re Small Break LOCA Charging Flow & Main Steam Safety Valve Setpoints ML20196L3191999-05-24024 May 1999 Forwards ISI Summary Rept,Including Owners Repts of Repairs & Replacements for Songs,Unit 2.Rept Covers Period of 970916-990226 ML20207A3831999-05-24024 May 1999 Responds to NRC 990326 RAI on DG Srs.Proposed to Add Listed Sentence to TS Bases for SRs 3.8.1.7,3.8.1.12 & 3.8.1.15,as Result of Discussion with NRC During 990427 Telcon ML20211K4261999-05-18018 May 1999 FOIA Request for Documents Re San Onofre OI Repts 4-98-041, 4-98-043 & 4-98-045 ML20206S7161999-05-17017 May 1999 Forwards MORs for Apr 1999 for Songs,Units 2 & 3.There Were No Challenges to Pressurizer Safety Valves for Either Unit 2 or 3 ML20206N4711999-05-13013 May 1999 Provides Info Requested by NRC Re Reduced Pressurizer Water Vol Change Amends Application 172 & 158 for Songs,Units 2 & 3,respectively.Proposed Change Will Reduce Pressurizer Water Level Required for Operability ML20206M7791999-05-13013 May 1999 Informs NRC of Changes Being Made to Emergency Response Data Sys (ERDS) at SONGS Unit 3.Revised Page to ERDS Data Point Library Is Provided in Encl ML20206K6891999-05-11011 May 1999 Forwards Approved Amends to NPDES Permits CA0108073,Order 94-49 & CA0108181,Order 94-50 & State Water Resources Board Resolution ML20206M0681999-05-10010 May 1999 Submits Correction to Info Contained in Licensee to NRC Re Proposed TS Change Number NPF-10/15-475.Stated Info Was Incorrect in That Overtime Provisions Were Not Contained in TR at Time of Was Submitted ML20206H0451999-05-0404 May 1999 Forwards Annual Financial Repts for Listed Licensees of Songs,Units 1,2 & 3.Each Rept Includes Appropriate Certified Financial Statement Required by 10CFR50.71(b) ML20206H1931999-05-0303 May 1999 Forwards 1998 Annual Rept, for SONGS Units 2 & 3 & PVNGS Units 1,2 & 3.SCEs Form 10K Annual Rept to Securites & Exchange Commission for Fiscal Yr Ending 981231,encl ML20206C5151999-04-29029 April 1999 Forwards 1998 Radiological Environ Operating Rept for Songs,Units 1,2 & 3. Annual Radiological Environ Operating Rept Covers Operation of Songs,Units 1,2 & 3 During CY98 & Includes Summaries Interpretations & Analysis of Trends ML20206E5851999-04-29029 April 1999 Forwards Annual Radioactive Effluent Release Rept for 1998 for SONGS Units 1,2 & 3. Also Encl Are Rev 13 to Unit 1 ODCM & Rev 31 to Units 2 & 3 Odcm 1999-09-29
[Table view] |
Text
_- . - _ _ - _
^ -ga soy,mmu- uo_a so_
J EDISON E=b am, An LDISON INTERNAlIONAL"* Company i
July 2,1999 U. S. Nuclear Regulatory Commission Attention: Document Control Desk Washington D.C. 20555 Gentlemen:
Subject:
Docket Nos. 50 361 and 50-362 Additional Information Regarding Generic Letter 96-06: " Assurance of Equipment Operability and Containment Integrity During Design-Basis Accident Conditions" San Onofre Nuclear Generating Station, Units 2 and 3
Reference:
Letter dated July 10,1998, from J. L. Rainsberry to Document Control l Desk (NRC),
Subject:
Docket Nos. 50-361 and 50-362, Generic Letter 96-06: " Assurance of Equipment Operability and Containment Integrity '
During Design-Basis Accident Conditions," San Onofre Nuclear Generating Station Units 2 and 3 p Provided as an Enclosure is information requested by the NRC in a telephone conversation on June 11,1999. The NRC requested additional information regarding Southern California Edison's (SCE's) submittal dated July 10,1998, regarding Generic Letter 96-06, " Assurance of Equipment Operability and Containment Integrity During Design-Basis Accident Conditions." SCE agreed to provide a sample calculation, for the staff's information only, to demonstrate how the requirements of the acceptance criteria in Section 2 of the enclosure to the July 10,1998 letter have been met.
9907090187 990702 PDR ADOCK 05000361 p PDR P. O. Box 128 Sam Clemente, CA 92674-0128 949-368-7501 Fax 949-368-7575 080021
_ - - - _ _ - - - - - 1
Document Control Desk July 2, 1999 If you have any additional questions on this subject, please feel free to contact me or Jack Rainsberry at (949) 368-7420.
Sincerely, l
Enclosure .
1 cc: E. W. Merschoff, Regional Administrator, NRC Region IV l J. A. Sloan, NRC Senior Resident inspector, San Onotre Units 2 & 3 L. Raghavan, NRC Project Manager, San Onofre Units 2 and 3
f:
I I
ENCLOSURE RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION Generic Letter 96-06:
Assurance of Equipment Operability and Containment Integrity J During Design-Basis Accident Conditions
)
l
I Acceptance Criteria l As noted in Section 2, Acceptance Criteria, of the enclosure to Southern California
{
Edison's (SCE's) July 10,1998 letter, the stress limits in the ASME Code,1989 Edition, no Addenda, Appendix F, Article F-1331 were used. A finite element based analysis was performed to determine the thermal-structural response of containment penetrations and the attached piping in order to calculate the trapped water pressure and the stresses resulting from a loss of coolant accident (LOCA) as a function of time.
This approach was adopted in lieu of the alternative simplified, and more conservative, approach / stress and pressure limits given in Article'F-1430. The application of the acceptance criteria of choice, as defined in Article F-1331, is further discussed below.
F-1331.1(a). General Primary 9mbrane Stress Intensity (Pm l '
The stress limit on the general primary membrane stress intensity, Pm , is based on Appendix F, Article F-1331.1(a). The value of Pm was based on the results of the finite element analysis, and acceptability was determined based on Pm s lesser of 2.4 Smand 0.7 S u-where Smis the allowable stress intensity, and S uis the ultimate tensile strength. Both values were obtained from Appendix 1.
For a pipe, Pmis calculated due to internal pressure only as defined in Table NB-3217-
- 2. In this case, Pm is given by Pm =lS-Sl i 3 where S3 = hoop stress S3 = radial compressive stress F-1331.1(c). Primary Membrane (General or Local) Plus Primary Bendina Stress Intensity (P t P) 3 The trapped water pressure was calculated as a function of time during a LOCA using ;
the finite element method. To simplify the analysis, the finite element model did not include the external bending loads due to deadweight (DW) and design basis earthquake (DBE). The bending loads are available from existing stress calculations of the piping attached to the analyzed penetrations. These loads were used to calculate the combined bending stress, S3, due to DW and DBE.
I
l It should be noted that stresses due to thermal expansion were excluded since they are classified as secondary and peak stresses (classifications P., O and F in Table NB-3217-2). Per Article F-1310, only limits on primary stresses are prescribed.
Results of the finite element analysis showed that the local primary membrane stress intensity, Pt , evaluated at the discontinuity formed by the weld attaching the .ed head to the penetration's neck extension, is bounded by the general primary membrane stress , Pm. This can be explained based on the stiffening effect of the flued head, which constrains the penetration's neck extension radial deformation due to pressurization. Figure 1 in the attachment shows the components of the penetration and the weld location.
The value of the combined bending stress was compared to the axial stress, S , due to the pressurization of the trapped water. In all cases, the calculated S3 was less than S,.
In one case only, S3 was about equal to S., i.e.,
)
I 1
So s S.
~
Accordingly, it was concluded that the combined bending stress plus axial pressure stress is 2 0.
The state of stress can be represented schematically as, a
S, (hoop stress) l e 7 S, + S (axial stress)
~
V Since S, = W the hoop stress, it was also concluded that S, + So s S, < P m where P is less than or equal to 2.4 Smper F-1331.1(a). It follows that the higher allowable of F-1331.1( c) is also met. A Mohr's circle representation of the following i loadings is attached in Figure A: '
2
(a) Internal pressure only, (b) Internal pressure plus bending moment, on the tension side of the bending moment, (c) Internal pressure plus bending moment, on the compression side of the bending moment.
The stress intensity is enveloped by P in all cases.
A bounding simplified check was performed to evaluate Pt + P . Using the equation from F-1430(b) for calculating the combined pressure plus bending stress (S + S )
provided a simplified, and conservative, check of the Pt + P3 limit given in F-1331(c). In ;
this confirmatory check of Pt + P , the allowable stress of 3.0 S per F-1430(b) was !
used for this evaluation, and no credit was taken for the higher allowable stress of 3.6 Smgiven in F-1331(c).
A detailed numerical example of the calculations described above is attached for penetrations 45 and 46.
Nomenclature DBE = design basis earthquake DW = deadweight F = peak stress intensity P,. = primary bending stress intensity P, = expansion stress intensity Pt = local primary membrane stress intensity Pm = general primary membrane stress Intensity Q = secondary stress intensity S, = pressure stress in the axial direction Se = bending stress Sm = allowable stress intensity Su = ultimate tensile strength j i
l l
i 3 ;
TA $/
< x-Sa ,
i
~ 0~
(a) Internal Pressure Only T l /
la+Sg p+ Ss y S
cr e y- :.
(b) Internal Pressure + Bending, (c) Internal Pressure + 8ending, Tension Side Compression Side Figure A Mohr's Circle Representation 4 I i
i i
1 l
Attachment i
1 l
Detailed Example - Penetrations No. 45 and 46 5
o . , ,
Desian Data Figure 1 shows a drawing of containment penetrations No. 45 and 46. A summary of the design input used in the annlysis for this penetration is given below.
System description : Chilled water inlet (penetration 45 - chilled water inlet)
- Chilled water outlet (penetration 46 - chilled water outlet)
Penetration location : elevation 31'-6" (penetration 45 - chilled water inlet),
elevation 31'-6" (penetration 46 - chilled water outlet),
Penetration type :4 Penetration material . SA-106 Gr B Head diameter : 18" Line No. : 1513ML698 (penetration 45 - chilled water inlet) 1513MLO41 (penetration 46 - chilled water outlet)
Pipe size : 8" sch 40 Design Pressure : 150/125 psi (inlet / outlet)
Design Temperature : 95'F (penetration 45 - chilled water inlet)
- 95'F (penetrahoa 46 - chilled water outlet)
Operating Pressure : 80 psi (penetration 45 - chilled water inlet)
Operating Temperature : 44*F (penetration 45 - chilled water inlet)
Operating Pressure 12 psi (penetration 46 - chilled water outlet)
Operating Temperature : 60*F (penetration 46 - chilled water outlet)
Pipe material SA-106 Gr B Isolation valves HV9900 (penetration No. 45, inside containment)
HV9920 (penetration No. 45, outside containment)
HV9971 (penetration No. 46, inside containment)
HV9921 (penetration No. 46, outside containment)
Calculation of the Maximum Pressure Due to LOCA A finite element analysis was performed to calculate the overpressure in the penetration due to a LOCA. This analysis was performed using the general purpose ,
finite element analysis program ANSYS. An axisymmetric finite element (FE) model of
{
the penetration was generated, as shown in Figure 2. The analysis was performed in i the following two steps:
Step 1 A thermal transient analysis was used to calculate the temperature time history of the pipe, penetration, and the trapped water. The model was generated using ANSYS element type PLANE 55, which can be used to solve two-dimensional axisymmetric heat transfer problems. In addition to the penetration, the model shown in Figure 2 include.= the inboard and outboard isolation valves, and pipe segments extending a distance of several pipe '
6
diameters beyond the inboard isolation valve to account for the heat transferred to the trapped water via the adjacent piping. The model also includes the containment wall and the containment carbon steel lining.
The moden. boundary inside containment is exposed directly to the accident environment, and appropriate heat transfer coefficients were calculated as a function of time. These coefficients include the effect of condensation. A typical natural convection value of .2 BTU /hr ft *F was applied to the boundary outside containment.
The thermal transient analysis was performed in several time steps starting at the onset of the LOCA (t=0) to t=10 seconds.
Steo 2 A structural analysis was used to calculate the stresses and the trapped water pressure using the results of the thermal transient analysis. The finite element model in this case has identical geometry to the thermal analysis model.
The structural model uses ANSYS element type FLUID 79 for the trapped water and PLANE 42 otherwise.
The pressure calculation methodology using the finite element method was verified by hand calculation for a simple geometry, and was shown to be very accurate. The difference between the FE results and hand calculations was on the order of only 0.24%.
Table 1 gives a summary of the trapped water pressure time history due to a LOCA.
The maximum pressure, Pmo, of 3,194 psi occurs at 300,000 seconds.
l Table 1 Pressure Time History for Penetrations No. 45 and 46 Time Pressure Time Pressure (seconds) (psi) yseconds) (psi) 300 1 40,000 964 500 2 60,000 1,435 1,000 5 100,000 2,132 3,000 25 300,000 3,194 10,000 156 500,000 3,100
, 20,000 416 1,000,000 2,845 l 7
Calculations The maximum general membrane stress intensity, P , per the detailed finite element analysis results (see below)is P, = 41,520 psi < S,% (=42,000 psi) l where S,% = the lesser of 0.7 So and 2.4 S.
= 0.7 So (< 2.4 S, of 48,000 psi)
= 42,000 psi (for SA-106 Gr B at 200*F) 4 The maximum P, corresponds to the maximum pressure of 3.194 psi.
Maximum Membrane Stress per FEA Results j 1
- POST 1 LINEARIZED STRESS LISTING *****
INSIDE NODE = 68 oUTSIDE NODE = 50 i LOAD STEP 16 SUBSTEP= 3 TIME = 83.333 LOAD CASE = 0 l l l ** AXISYMMETRIC OPTION ** RHO = .32791E+12
) THE FOLLOWING X,Y,Z STRESSES ARE IN SECTION COORDINATES. i
SX SY SZ SXY SYZ SXZ
-1403. -1761. .3974E+05 -99.54 .0000E+00 .0000E+00 S1 S2 S3 SINT SEQV
.3974E+05 -1377. -1787 !41525+05 .4132E+05 The following bounding deadweight moments were obtained from the piping stress calculations:
I M,.ow = -444 ft-lb My .ow = 239 ft-Ib M,e y = 2,816 ft-Ib 1
Similarly, the DBE moments are M,.o.e = 1,799 ft-Ib My.o e = 486 ft-Ib 8
M,.o e = 2,826 ft-lb The resultant moment M,, is M, = M,.ow + M,.ose 2 2 2
= (M,.ow + M y.ow + y,,0w )x + (M,.o e 2+ M .o 2 y e + yz-DBE )
= 2,861 + 3,385
= 6,246 ft-lb The section modulus, Z, is Z = nR,2t
= 17.43 in 8 The axial stress due to internal pressure, S., is combined with the bending stress due to deadweight +DBE stress, So, l 1
i Bi PD/2t + B2 M/Z = S, + S.
l = 0.7.5x3,194x8.625/(2x0.322) +
) 1.5x6,246x12/17.43 38,533 < 3.0 S (=60,000 psi) where the stress indices are given by Bi = 0.75 1 B2 = 1.5 In the above equation, the right hand side consists of two terms:
S, = 0.75x3,194x8.625/(2x0.322) l
= 32,083 psi l S. = 1.5x6,246x12/17.43 i
= 6,450 psi l Since the value of So is less than S , the combined stress is tensile in the penetration.
Furthermore, it is noted that the value of S, + S is less than the value of P, calculated j previously.
\
l l
9
".- s -
j 3,
% ~ _
r-G 5
4 o
1 o
3'
- N i
t n
o sN ..
l s
e t
a r
e n
i s
= '
x .
b X c - P e
E i f -
n o _.
p s
( -
ta c i o 0 -
e s 1 .
n .
e _
' ;y
. l .
h m i
i
/ - % _
D d
e l
i a -
t _
y e
%'s D
- _ 1
.' lt u e
r v c u a d e ig
=
l F
% - l
- n. d e d e
r o
n i EQ A I F
n Ii r t c.
)
(
7 s
}l il e _
w !
u fra !
h n
e i
n i
i . t a
- } _
tn l .
i d I
s C
1 I "l ..
_. t.
z P( ne .
5 f
1 m i e
, d l 1
1 *e le
- e. ,. , 1I.
a ,.
il M
p y G. t n
- e m \, 2*
r m
m -
e i
l f f !.
t i
Ck l
E 1 l
a I
.t ## CIu M
it e 1 a n _
w s i
i F
h l
- l. 2 M e H
r u _
t ig .
g )
ir F _
y d i s
- ,.- ut _
l n _
@e p
w( er e
m e
fi c
- a -
o W pr
_