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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: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
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f55 Southem Califomia Edison Company P. O. BOX 128 BAN CLEMENTE, CALIFORNIA 92674-0128 i August 13, 1996 J. L. RAINSBERRY TELEPHONE i SAN ONO R N EA N T G STATON l
U. S. Nuclear Regulatory Commission Attention: Document Control Desk {
Washington, D.C. 20555 Gentlemen:
Subject:
Docket No. 50-361 Reactor Water Level Probe Inoperability San Onofre Nuclear Generating Station Unit 2
References:
(1) Letter from W. C. Marsh (Edison) to USNRC Document Control Desk, dated May 19, 1995;
Subject:
Reactor Water Level Probe Inoperability (2) Generic Letter 88-17, dated October 17, 1988,
Subject:
Loss of Decay Heat Removal-The purpose of this letter is to inform the NRC of Southern California Edison's (Edison's) planned course of action to address inoperability of the Reactor Water Level Probe (RWLP). Compensatory actions being taken in place of the RWLP are specified to allow reduced inventory operations and testing of the replacement system during the Unit 2 Cycle 9 Refueling Outage. These actions are necessary because of repeated RWLP failures. TN actions being taken at Unit 2 are identical to those used at Unit 3 to rJdress a similar RWLP failure (see Reference 1).
BACKGROUND: ,
Currently, San Onofre Units 2 and 3 are each provided with five methods to determine reactor coolant system water level when the RCS is in a reduced inventory condition: (1) Refuelin Junction Thermocouple Probes, (3) thegReactor Water Level VesselIndication, Water Level(2)Sightglass, the Heated (4) water inventory control, and (5) the Reactor Water Level Probe (RWLP).
Because the fifth method, the RWLP, is no longer functional the Draindown Level Monitoring System (DLMS) will be installed in place of the RWLP during the Units 2 and 3 Cycle 9 Refueling Outages. Each of these methods is described below.
Refueling Water Level Indication The Refueling Water Level Indication (RWLI) system provides the primary control room indication for monitoring the Reactor Coolant Syst 9608150214 960813 PDR ADOCK 05000361 P PDR g O
2 d i / U D .I.
i Document Control Desk reduced inventory operations in Modes 5 and 6. There are two differential pressure transmitters, one wide range and one narrow range. The wide range and narrow range transmitters share common sensing lines, which are connected to a drain line on the hotleg and to the vent line from a condensation chamber ,
on the pressurizer. An adjustable Hi/Lo level alarm is provided for each differential pressure loop which actuates a common alarm in the control room.
The RWLI is only connected during Modes 5 and 6. During Modes 1 through 4 the RWLI instrumentation piping is isolated and capped off (See Figure)
Heated Junction Thermocouple Probes The Heated Junction Thermocouple (HJTC) Reactor Vessel Level Monitoring System provides an alternate indication of reactor vessel water level. Two safety-related HJTC probes are provided (Channels A and B), The HJTC probes remain in the reactor vessel during Modes 1 through 5 to provide direct reactor vessel water level indication and are primarily used during design basis accident conditions. Each HJTC probe has eight sensors. Three of the eight sensors are located within the hotleg region at 42, 21, and 0 inches above the bottom of the hotleg. During reduced inventory operations the 21-inch sensor provides a control room low level indication and alarm as a supplement to the RWLI and DLMS indication. The 21-inch sensor and alarm is located above the level where vortexing of the shutdown cooling (SDC) suction line would occur under normal flow conditions.
Reactor Vessel Water Level Sightglass A sightglass is installed during Modes 5 and 6 to provide direct reactor vessel water level indication. The sightglass, which must be read locally, is located inside containment. The sightglass uses the same common sensing lines as the RWLI narrow range and wide range transmitters.
Water Inventory Control San Onofre has performed extensive benchmarking of the water inventory required to change water level from one level to another. The volume of water removed from the reactor vessel is monitored closely when the reactor coolant system is drained for reduced inventory operations. San Onofre has had excellent success and agreement between actual conditions and expected values when using the benchmarking described above. This method represents an additional diverse measure to validate the reactor coolant system level control during drain down.
Reactor Water Level Probe The Reactor Water Level Probe (RWLP) provided a secondary means of control room indication for monitoring the reactor coolant system level during reduced inventory operations in Modes 5 and 6. The RWLP was a heated junction thermocouple based reactor vessel water level detection probe which resided in an in-core instrument guide path and provided inputs to the Critical Functions Monitoring System (CFMS) for monitoring the reactor vessel water level during reactor coolant system reduced inventory operations. Heated junction thermocouples were spaced three inches apart from five inches below the top to
.. {
l l
Document Control Desk . .
four inches above the bottom of the hotleg in the hotleg region. The presence of water at a specific elevation was detected by monitoring the temperature difference between the heated junction thermocouple and the bulk water temperature. In addition to control room indication, the RWLP also provided an adjustable low level alarm via the CFMS. The RWLP remained in the reactor vessel during Modes 1 through 5, however it was only used during Mode 5. The RWLP was installed in the reactor vessel upper guide structure and removed with it during refueling.
l On November 26, 1994, during Unit 3 Cycle 7, the Unit 3 RWLP failed a routine quarterly test. This test failure indicated that the RWLP, which is only used during Mode 5, was not functional. Subsequent investigation found stress corrosion cracking in the RWLP sheath material (Inconel 600) pure. Thiswater ;
cracking resulted in water intrusion into the RWLP and subsequent short circuits within the RWLP heaters and thermocouples. This was the second RWLP to fail at Unit 3, the first having failed during Cycle 6 from what is believed to be the same cause. On December 12, 1995, the Unit 2 RWLP failed its routine quarterly test from what may be the same cause as the Unit 3 RWLP failures. The RWLPs were designed to last for the life of the plant; however due to repeated failures Edison will be substituting a different design (see i following) for the RWLP.
Draindown Level Monitoring System I
The Draindown Level Monitoring System (DLMS) is the system selected by Edison to meet Edison's commitment to the recommendations of Generic Letter 88-17 and thus replaces the RWLP. The DLMS uses quartz crystal pressure transducers to measure referance pressure and Reactor Coolant System (RCS) head which are used to calculate water level. A reference transducer is attached near the top of the pressurizer. Two RCS head transducers are used to measure coolant head. One transducer is connected to a two-inch header connected to the '
bottom of one hotleg. (TheRWLIisalsoconnectedtothesametwo-inch header.) The other transducer is attached to the sixteen-inch shutdown (See cooling)
Figure. pump suction lineprovide The transducers attached to signals input the bottom of the opposite to a dedicated hotleg.
personal computer located in the computer room which will calculate and display reactor l vessel water level based on the transducer input. The DLMS also transmits the '
calculated level to the CFMS for display and provides an adjustable low-level !
alarm.
Regulatory Commitments ,
1 Generic Letter (GL) 88-17, Loss of Decay Heat Removal, (Reference 2) recommends the following:
" Provide at least two independent, continuous RCS water level indications whenever the RCS is in a reduced inventory condition."
Edison met this recommendation by installing the RWLP as the second independent reactor coolant system water level indicator. The RWLI is the primary level indicator. The NRC accepted the RWLP in Inspection Report Nos. 50-361/91-34 and 50-362/91-34 as meeting the recommendation in GL 88-17.
o Document Control Desk The Units 2 and 3 Updated Final Safety Analysis Report (UFSAR)
(Section 7.6.2.4 " Reactor Water Level Probe") states Edison's use of the RWLP as a backup to the RWLI to meet the recommendation in GL 88-17. The Units 2 and 3 UFSAR will be updated to delete the RWLP and add the DLMS to meet Edison's commitment to the recommendations of GL 88-17.
Previous to installation of the RWLP, Edison used the HJTC probes for alternate reactor coolant system level indication. The NRC staff, however, noted that the HJTC probe did not have the level resolution necessary for all reduced inventory operations and thus did not satisfy the recommendation in GL 88-17.
DISCUSSION:
As noted above, Edison has experienced repeated failures of the RWLP probes.
Because of the repeated RWLP failures and high replacement costs, Edison will be replacing the RWLP with the DLMS during the Unit 2 Cycle 9 Refueling Outage, which is currently scheduled to begin in late November 1996. The DLMS will also be installed at Unit 3 as a replacement for its failed RWLP during l the Unit 3 Cycle 9 Refueling Outage. To allow time to install and test the DLMS, Edison plans to use the same action plan used to address RWLP inoperability used at Unit 3 during the Cycle 8 Refueling Outage (see Reference 1). This plan is outlined below.
l Planned Compensatory Actions to Address RWLP Inoperability It is planned to perform the Unit 2 Cycle 9 Refueling Outage and any unscheduled reactor coolant system reduced inventory operations during the current Unit 2 Cycle 8 without the RWLP probe with the provision that the ,
following compensatory measures be implemented: I
- 1. Provide an Alternate Method of Correlating RWLI When decreasing reactor coolant system level the RWLI narrow range indication will be correlated using an alternate method. This method will . utilize the reactor vessel water level sightglass.
- 2. Change Procedures for Operator Response to Abnormal Conditions The water level during reactor coolant system reduced inventory operations is nominally well above 21 inches above the bottom of the hotleg (i.e., about 26 inches). At the 21-inch level the time available for operator responses to abnormal conditions will be greater than it would be at the current minimum water level when the RWLP is operable.
In addition, the following will be implemented during reduced inventory operations while the RWLP is unavailable:
A. RWLI narrow range control room indication and alarm will be maintained functional; and
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Document Control Desk . .
B. At least one channel with 21-inch (No. 6) HJTC Low Level indication and alarm will be maintained operable; and C. If a HJTC probe 21-inch low level alarm is received, Operations will:
(1) stop draining; and (2) validate the alarm using the other HJTC #6 (if available--if a second HJTC #6 is not available then the alarm will be assumed valid); and (3) if the alarm is valid, add water until the alarm clears. l If a second 21-inch HJTC probe low level alarm is received during the I same midloop operations, Operations will immediately refill and maintain level above 21 inches using a method which is independent of RWLI (e.g.,
HJTC #5 at 42 inches above the bottom of the hotleg, a camera positioned ,
within the steam generator, or through some other means). l These actions will be taken until RWLI instruments are verified to be operable.
Acceptability of Edison's Proposed Course of Action A 10 CFR 50.59 Safety Evaluation found that, with implementation of the planned compensatory measures, operation in a reduced inventory condition with the RWLP inoperable does not present an unreviewed safety question.
Therefore, Edison concludes that using the HJTC probe as a backup to the RWLI during the period that the RWLP is inoperable and being replaced is acceptable.
Previous Edison reactor coolant system reduced inventory practices included reducing the reactor coolant system water level to as low as 17.5 inches above the bottom of the hotleg. Operation with the reactor coolant system water level this low required operation within an area in which the HJTC probes do not provide indication. Raising the midloop level was made possible in 1993 when the level required for installing nozzle dams was increased from 17.5 to 26 inches by procurement of a new type of nozzle dam which is positioned higher in the steam generators. This change has significantly reduced the risk associated with midloop operations and has made it possible to utilize the HJTC probe as backup to the RWLI while at midloop when the RWLP is out of service. This increase in midloop operating level gives further assurance of the acceptability of use of the HJTC probe as a backup to the RWL1 during the period that the RWLP is inoperable and being replaced.
In addition to the above, existing station procedures require at least two means of providing inventory makeup during reduced inventory operations (this requirement is ncrmally met by maintaining one High Pressure Safety Injection (HPSI) pu p operable and one additional HPSI or Containment Spray pump available .
o Document Control Desk .
SUMMARY
1 Edison believes it is acceptable to perform reduced inventory operations with <
the RWLP probe inoperable for the following reasons: l e The primary means of reactor vessel water level indication (RWLI wide and narrow range indication) will be available and is reliable; and e The reactor vessel water level sightglass is normally monitored while reducing reactor vessel level and will be monitored when reducing reactor vessel level until the level is stable and correlates satisfactorily; and e The HJTC probe provides an independent indication of an unanticipated reactor coolant system draindown and will alert operators to such an event; and e The nominal reactor coolant system level during reduced inventory operations has been increased to 21 inches above the bottom of the hotleg; and e Operating procedures will be modified to improve operator response to unanticipated reactor coolant system draindown events; and e A 10 CFR 50.59 Safety Evaluation shows that performing reduced inventory operations while the RWLP is inoperable with the compensatory measures in place does not present an unreviewed safety question.
It is expected that the DLMS will be av'ailable for use at each unit by the end of their respective Cycle 9 Refueling Outages.
If you have any questions or would like additional information on this subject, please let me know.
Sincerely, s
f~*
C Enclosure cc: L. J. Callan, Regional Administrator, NRC Region IV J. E. Dyer, Director, Division of Reactor Projects, Region IV K. E. Perkins, Jr., Director, Walnut Creek Field Office, NRC Region IV J. A. Sloan, NRC Senior Resident Inspector, San Onofre Units 2 & 3 M. B. Fields, NRC Project Manager, San Onofre Units 2 an,d 3 ik
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