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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:OUTGOING CORRESPONDENCE
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 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 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 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 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 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 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 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 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 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 ML20210B9891999-07-20020 July 1999 Ack Receipt of Transmitting Plant Emergency Plan Implementing Procedure SO123-VIII-1, Recognition & Classification of Emergencies 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 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 ML20196K3351999-06-30030 June 1999 Informs That Effective 990703,NRC Project Management Responsibility for San Onofre Unit 1 Will Be Transferred to Wc Huffman ML20212J3581999-06-24024 June 1999 Final Respons to FOIA Request for Records.App a Records Withheld in Part (Ref Exemptions 1 & 3) ML20209D7851999-06-16016 June 1999 Requests That San Onofre Nuclear Generating Station Be Included as One of Several Reference Plants in GSI-191 Study ML20195J6441999-06-15015 June 1999 Forwards Request for Addl Info Re GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power-Operated Gate Valves. Response Requested within 30 Days of Receipt of Ltr ML20196A7351999-06-15015 June 1999 Requests That Cover Page to NRC Insp Repts 50-361/98-14 & 50-362/98-14 Be Replaced with Encl Page.Originally Issued Page,Signed by T Steka,Was Dated Incorrectly ML20207H4021999-06-14014 June 1999 Requests Addl Info Re Completion of Time for Containment Isolation Valves,Same as for Engineered Safeguards Features ML20196A8001999-06-0909 June 1999 Requests That Pages 14-17 of NRC Insp Repts 50-361/99-04 & 50-362/99-04 Be Replaced with Encl Pages.Initial Issued Rept Contained Some Duplicated Info ML20195E8001999-06-0808 June 1999 Forwards Insp Repts 50-361/99-06 & 50-362/99-06 on 990404- 0515.Violations Identified & Being Treated as Noncited Violations ML20195E8091999-06-0707 June 1999 Ack Receipt of Transmitting Licensee Emergency Plan,Rev 7 Under Provisions of 10CFR50.54(q) ML20195E8281999-06-0707 June 1999 Ack Receipt of Transmitting Licensee Emergency Plan Implementing Proceedure SO123-VIII-1,rev 11 Under Provisions of 10CFR50.54(q) ML20207E6521999-06-0202 June 1999 Responds to Ltr Which Identified Several Inaccuracies within NRC Insp Repts 50-361/98-18 & 50-362/98-18.Forwards Revised Pages for page-by-page Replacement in Insp Repts ML20195D2771999-06-0202 June 1999 Forwards Se,Concluding That Util Has Capability to Perform Reload Design & non-LOCA Analyses for Songs,Units 2 & 3, Based on Review of TR SCE-9801-P & Onsite Audit of Implementation of Reload Technology Transfer Program ML20207A8981999-05-25025 May 1999 Advises That Versions of SCE-9801-P,Rev 0 & CEN-635(S)-P, Rev 00,submitted in 981130 & s & Affidavits & 990225,marked Proprietary,Will Be Withheld from Public Disclosure,Per 10CFR2.790(b)(5) ML20206U3681999-05-18018 May 1999 Forwards Partially Withheld Insp Repts 50-361/99-07 & 50-362/99-07 on 990426-29.Matl Encl Contains Safeguards Info & Will Not Be Placed in PDR (Ref 10CFR2.790) ML20207A2131999-05-14014 May 1999 Submits Summary of 990422 Meeting in San Clemente,Ca Re PPR Results Completed 990211.Informal Discussions Held with Public Following Meeting Re Recent Changes Used to Assess Licensee Performance ML20206P1521999-05-13013 May 1999 Informs That NRC Ofc of NRR Reorganized,Effective 990328. Reorganization Chart Encl ML20206P4051999-05-12012 May 1999 Responds to Re Request of TS Interpretation. Instrumentation with Battery Backup,But Lacking DG Backup Cannot Be Excluded from Provisions of Action B.2 ML20206Q2481999-05-10010 May 1999 Forwards Insp Repts 50-361/99-05 & 50-362/99-05 on 990426-30.No Violations Noted ML20206H4881999-05-0707 May 1999 Informs That on 990407,NRC Administered Gfes of Written Operator Licensing Exam.Licensee Facility Did Not Participate in Exam,However,Copy of Master Exam with Aswer Key,Encl for Info.Without Encl ML20206H7651999-05-0606 May 1999 Forwards Exam Repts 50-361/99-301 & 50-362/99-301 on 990416. Two Operators & Two Senior Operators Were Evaluated.Four Applicants Satisfied Requirements of 10CFR55 & Appropriate Licenses Issued IR 05000361/19983021999-05-0303 May 1999 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Repts 50-361/98-302 & 50-362/98-302 Issued on 990104.Review Found Reply Responsive to Concerns Raised ML20206K5061999-04-30030 April 1999 Discusses Closure of OI Investigation 4-1998-04 Re Southern California Edison Led Joint Util Audit of Inst of Nuclear Power Operations Fitness for Duty & Access Authorization Programs.Synopsis from Subj Rept Encl ML20206B4921999-04-20020 April 1999 Forwards Insp Repts 50-361/99-04 & 50-362/99-04 on 990221-0403.Three Violations Occurred & Being Treated as non-cited Violations ML20205S2941999-04-20020 April 1999 Forwards RAI Re Licensee 981230 Request to Implement risk-informed IST Program During Remainder of Second 10-year Interval for SONGS & to 970313 Response to GL 96-05 ML20206B4241999-04-20020 April 1999 Forwards Insp Repts 50-361/99-03 & 50-362/99-03 on 990205-0312.One Violation Occurred & Being Treated as non-cited Violation,Consistent with App C of NRC Enforcement Policy ML20205Q6171999-04-19019 April 1999 Forwards SE Authorizing Licensee 980826 Request for Relief from ASME B&PV Code,Section XI Requirements for Certain ISIs at Plant,Units 2 & 3 ML20205R0101999-04-16016 April 1999 Discusses Request for Approval of Deviation from Approved Fire Protection Program.Forwards SE Related to Request for Approval Incorporating Certain Requirements of App R to 10CFR50 ML20205M9421999-04-13013 April 1999 Forwards Emergency Response Data System Implementation Documents.Data Point Library Updates for Kewaunee (271), San Onofre (272) & Clinton (273) Encl.Also Encl Plant Attribute Library Update for Grand Gulf (274).Without Encls ML20205M9891999-04-0707 April 1999 Informs That L Raghavan Assumed Project Manager Responsibilities Effective 990329 & Dembek Assumed Responsibilities as Section Chief for SONGS ML20205E5441999-03-30030 March 1999 Forwards Insp Repts 50-361/99-01 & 50-362/99-01 on 990103- 0220.Three non-cited Violations Were Identified 1999-09-03
[Table view] |
Text
. . _ _ _ . _ _ _ _ _ - . _ .-_. _ _ _ . . _ - _ _ - -
May 30, 1997 l Mr. Dwight E. Nunn !
Vice President Southern California Edison Company i San Onofre Nuclear Generating Station ;
P. O. Box 128 '
San Clemente, California 92674-0128
SUBJECT:
SAN ONOFRE NUCLEAR GENERATING STATION UNIT 3 STEAM GENERATOR -
EGGCRATE DEGRADATION ISSUE
Dear Mr. Nunn:
The purpose of this letter is to acknowledge the commitments made in your 7 letter dated May 16, 1997, regarding the recent findings of eggcrate degradation in the San Onofre Unit 3 steam generators. Specifically, Southern !
California Edison (SCE) committed to submit a comprehensive evaluation of the condition of the San Onofre Unit 3 steam generators at least 7 days prior to entry into Mode 4. Following submittal of this report, SCE will meet with the NRC staff to discuss this evaluation prior to Mode 4 entry. SCE further >
committed to submit a final report within 90 days after restart from the current refueling outage. !
Enclosed is a list of areas that, as a minimum, should be thoroughly addressed l in the forthcoming report. If you have any questions, please call me at (301) i 414-3062.
l Sincerely, Original Signed By )
l Mel B. Fields, Project Manager Project Directorate IV-2 l Division of Reactor Projects III/IV
! Office of Nuclear Reactor Regulation
> Docket No. 50-362 DISTRIBUTIOJ:
g Docket File g
Enclosure:
Eggerate Evaluation Areas PUBLIC g PDIV-2 Reading JRoe ,
E cc w/ enc 1: See next page EAdensam l h
g WBateman MFields w EPeyton Q ACRS, TWFN i
! g OGC, 015B18 l j ,,,,.,,a KPerkins, RIV/WCF0 %gok ~
g PGywnn, RIV M DOCUMENT NAME:
ce_i EGGCRATE. NUN !
- OFC PDIV-2/PM PDIV-2/LA r 1(} !
NAME Mhs EPe M $ h
- DATE 5/f>/97 5flC/97 0FFICIALRECOD.CgPg ,
9706050257 970530 t PDR ADOCK 05000362
, P PDR c.,
i
ga r.rzo 5
j
[b k UNITED STATES
- Ij NUCLEAR REGULATORY COMMISSION
. e WASHINGTON, D.C. 20066 4 001 8 May 30,1997
\ . . . . . ,o Mr. Dwight E. Nunn Vice President Southern California Edison Company ;
San Onofre Nuclear Generating Station P. O. Box 128 San Clemente, California 92674-0128
SUBJECT:
SAN ON0FRE NUCLEAR GENERATING STATION UNIT 3 STEAM GENERATOR EGGCRATE DEGRADATION ISSUE
Dear Mr. Nunn:
The purpose of this letter is to acknowledge the commitments made in your letter dated May 16, 1997, regarding the recent findings of eggerate degradation in the San Onofre Unit 3 steam generators. Specifically, Southern ,
California Edison (SCE) committed to submit a comprehensive evaluation of the l condition of the San Onofre Unit 3 steam generators at least 7 days prior to entry into Mode 4. Following submittal of this report, SCE will meet with the NRC staff to discuss this evaluation prior to Mode 4 entry. SCE further committed to submit a final report within 90 days after restart from the current refueling outage. , l l
Enclosed is a list of areas that, as a minimum, should be thoroughly addressed i in the forthcoming report. If you have any questions, please call me at (301) {
415-3062. 1 Sincerely, ,
- f. .2 , W7%
Mel B. Fields, Project Manager Project Directorate IV-2 Division of Reactor Projects III/IV .
Office of Nuclear Reactor Regulation l Docket No. 50-362
Enclosure:
Eggerate Evaluation Areas l cc w/ encl: See next page i
. Mr. Dwight E. Nunn :
cc w/ encl: ,
i Mr. R. W. Krieger, Vice President Resident Inspector / San Onofre NPS !
Southern California Edison Company c/o U.S. Nuclear Regulatory Commission. - !
San Onofre Nuclear Generating Station Post Office Box 4329 ;
P. O. Box 128 San Clemente, California 92674 :
San Clemente, California 92674-0128 ,
Mayor Chairman, Board of Supervisors City of San Clemente County of San Diego 100 Avenida Presidio ,
1600 Pacific Highway, Room 335 San Clemente, California 92672 ;
San Diego, California 92101 Mr. Harold B. Ray Alan R. Watts, Esq. Executive Vice President ,
Woodruff, Spradlin & Smart Southern California Edison Company 701 S. Parker St. No. 7000 San Onofre Nuclear Generating Station Orange, California 92668-4702 P.O. Box 128 San Clemente, California 92674-0128 i Mr. Sherwin Harris Resource Project Manager Public Utilities Department City of Riverside 3900 Main Street Riverside, California 92522 Dr. Harvey Collins, Chief Division of Drinking Water and Environmental Management L California Department of Health Services P. O. Box 942732 Sacramento, California 94234-7320
. Regional Administrator, Region IV
! U.S. Nuclear Regulatory Connission '
Harris Tower & Pavilion 611 Ryan Plaza Drive, Suite 400 Arlington, Texas 76011-8064 ,
Mr. Terry Winter Manager, Power Operations San Diego Gas & Electric Company P.O. Box 1831 San Diego, California 92112-4150 '
1 l Mr. Steve Hsu
- Radiologic Health Branch i
State Department of Health Services Post Office Box 942732 i Sacramento, California 94234 i
, _ _ _ _ _ _ . . _. _ _ __. _ __~ _
l l
l SAN ON0FRE NUCLEAR GENERATING STATION UNIT 3 STEaN GENERATOR EGGCRATE ISSUE.
l EVALUATION AREAS
]
- 1. The ATH0S code was used to assist in the prediction of flow accelerated corrosion (FAC) regions areas for the San Onofre Unit 3 cteam generators i (SGs). Discuss the ability of ATH0S to predict the lack of FAC regions ,
observed in the SONGS Unit 2 SGs. '
- 2. Discuss your approach for determining the eggerate degradation i mechanism. Discuss the cause of the degradation mechanism, how it will !
be minimized or eliminated and how this will be verified. Discuss '
implications for the Unit 2 SGs and relevant actions that will be taken.
- 3. Discuss the objectives and results from secondary side visual (and eddy current, if applicable) inspections. Discuss how the baseline condition !
(current condition) of the eggcrates is being determined, how and which structural elements are being measured, and in what form the baseline conditions are being recorded.
- 4. Discuss the extent of the eggerate degradation and how this affects SG tube integrity for the' full range of test, normal operating, and accident conditions. Discuss the design bases for the eggerate structures in the SONGS SGs and how the design bases are affected by the degradation. Discuss the criteria and the basis for criteria that will be applied for dispositioning tubes potentially affected by loss of eggerate support. I 1
- 5. Discuss future inspection plans related to the eggerates for both SONGS units. Discuss the' techniques, the scope, and the disposition process (acceptance criteria).
]
- 6. Discuss the approach to be used to determine the potential growth rate l of degradation of the eggerate structures. 1
- 7. Discuss how the potential growth rate of degradation of the eggerate ,
structures is being incorporated into the assessment of the length of the next operating cycle. Discuss the proposed length of the next operating cycle for Unit 3 and provide the basis for the proposed length. Address the probability for tube rupture to occur during the !
l current operating cycle for Unit 2 and during the next operating cycle for Unit 3 as a result of operating with potential or actual degradation l of the eggcrate structures and whether or not the probability of tube rupture has increased. Discuss the possibility that the margins of safety in the eggerate structures and affected tubes have decreased as a result of the observed degradation.
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. 8. Explain in sufficient detail the analysis performed to verify the functionality of the Unit 3 SG tubes under design basis accident conditions, considering the identified degradation of the eggerates.
- State if the analysis is linear or non-linear and explain how the gaps i between the tubes and support plates are represented in the structural model. Also, explain how each loading is applied to the tubes, and how tube deformations / stresses are determined under combined loading conditions.
- 9. Identify the materials used for all the structural elements associated with the tube supports (e.g., eggerate supports, baffle, deflector, -
vertical support grids, diagonal spacer strips, wrapper bar). Also identify the design and acceptance criteria used for determining the. ,
adequacy of tube support structural elements. Specifically, state the Code, Section and Editions from which the acceptance criteria were established and provide the basis for your choice.
- 10. In assessing the fluid-elastic instability of the SG tubes due to critical flow-induced vibration, discuss the details of the formulas used for determining the critical flow velocity under degraded SG eggerate condition. Justify any empirical parameters used.
- 11. Confirm the calculated cross flow velocities by actual measurements of some critical local cross flow velocities in the secondary side flow of the SG under the degraded conditions.
- 12. . Confirm the calculated natural frequency of the most critical SG tubes with available test data which is representative of the degraded eggerate and inboard lattice bars conditions.
- 13. For the evaluation of SG tube stresses under accident conditions, confirm that the normal flow-induced vibration load under degraded conditions is combined with the accident loads.
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