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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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I JWO l
Southem Califomia Edison Company P. O. BOX 128 SAN CLEMENTE, CALWORNIA92674-0128 8
WALTER C. P/AHSH TELEPHONE MANAGER OP NUCLEAR REQULATORY AF'F AIR $ (714)368-7501 U. S. Nuclear Regulatory Commission Attention: Document Control Desk l Washington, D.C. 20555
]
Gentlemen: !
l
Subject:
Docket Nos. 50-361 and 50-362 '
Emergency Loading of the Emergency Diesel Generators San Onofre Nuclear Generating Station Units 2 and 3 This letter is to request NRC approval of a change to the design bases for the San Onofre Units 2 and 3 emergency diesel generators (EDGs). The change affects the minimum EDG terminal voltage (75'4 of nominal) which Southern !
California Edison (Edison) is currently committed to maintain at all times during load sequencing.
Calculations show that with appropriate load margin retained in the EDG dynamic analysis to accommodate future load growth, the EDG voltage may dip below the 75'4 of nominal voltage for a very short period under unlikely accident conditions when two high pressure safety injection (HPSI) pumps are automatically started from the same emergency bus. The following paragraphs describe (1) the plant design, (2) the postulated accident conditions that
! create the potential for a voltage dip, (3) the current EDG testing and design l basis for EDG terminal voltage, and (4) an evaluation using analytical and
! test results that demonstrates the voltage dip has no safety significance. ,
1 l Plant Design The engineered safety features (ESF) of San Onofre Units 2 and 3 include three )
high pressure safety injection (HPSI) pumps: a Train A primary pump; a Train B primary pump; and a swing pump, which can be aligned with either Train A or Train B. Each pump is capable of starting automatically in response to a safety injection actuation signal (SIAS). As explained in Section 6.3.2.5.2 )
of the Updated Final Safety Analysis Report (UFSAR), the function of the swing pump is to allow one of the primary HPSI pumps to be taken out for maintenance during plant operation. In this scenario, the two pumps switch functions. In the plant safety analysis, credit is taken for the operability of only one pump on each train. i 1
! The plant design automatically starts only the swing pump when both a primary l t pump and the swing pump are aligned to the same train and a SIAS is received.'
1 The swing pump breaker, when racked in, disables the SIAS start of the associated primary pump. This design feature is intended to ensure that no more than one HPSI pump would automatically start on either Train A or 040097
' 9606040321 960531 PDR P
ADOCK 05000361 PDR pg (g
- 1 1
l l
I .. .
Document Control Desk Train B. The reason for this restriction is that the original plant design, !
electrical analysis, and refueling interval ESF tests were all based on only l one HPSI pump starting at time t=0. (t=0 refers to the time when EDG terminal i l voltage and frequency have reached their nominal values, the EDG breaker has i l been closed, and the associated ESF 4 KV bus undervoltage relays have been I reset.)
Recently Identified Condition As explained below, under certain accident conditions more than one HPSI pump could automatically start on the same train.
( Certain plant evolutions, such as filling safety injection tanks, maintaining i refueling water storage tank chemistry, testing check valves, and pump inservice testing, require a HPSI pump to be run during normal plant operation. Even though these evolutions occur infrequently, in some of these I cases they require alignments that render the HPSI pump incapable of performing its safety injection function. For this reason, the preferred pump for these evolutions is the primary pump aligned to the same train as the l
swing pump. This arrangement keeps the swing HPSI pump and the primary pump !
on the opposite train operable, thus maintaining two HPSI trains operable.
This satisfies the requirements in Section 3/4.5.2 of the existing Units 2 and 3 Technical Specifications (TSs) for plant operating Modes 1, 2, and 3, and the equivalent requirements in Section 3.5.2 of the new TSs that have been l approved for implementation by Unit 2 Amendment No.127 and Unit 3 Amendment No. 116. These new TSs will be replacing the existing TSs by August 9, 1996.
- The HPSI pumps are not automatically stripped from their associated 4 KV buses l on a Loss Of Voltage Signal (LOVS). As a result, if a HPSI pump is running l during one of the infrequent evolutions discussed above, and a SIAS with LOVS occurs, the diesel for that train would be loaded with two HPSI pumps at time t=0. This particular scenario, postulating the simultaneous loading of two HPSI pumps on one train, was not considered in the original plant design, electrical analysis, or ESF tests. Conservative probabilistic risk analysis
! calculations show that this scenario has a very low probability of occurrence (about 1.0E-7 per year) .
EDG Testing and Design Basis for EDG Terminal Voltage The EDG terminal voltage is verified as part of the ESF test, which is conducted on both EDGs during every refueling outage. The ESF test requirements are specified in Section 4.8.1.1.2.d.7 of the existing TSs and Section 3.8.1.19 of the new TSs.
EDG Testing per Existing TSs:
Surveillance requirement 4.8.1.1.2.d.7 of the existing TSs requires that EDG
] operability be demonstrated at least once per refueling interval by
" Simulating a loss of offsite power in conjunction with an ESF test signal, and 1
I
! Document Control Desk " a) Verifying de-energization of the emergency busses and load shedding from the emergency busses.
l " b) Verifying the diesel starts on the auto-start signal, energizes i' the emergency busses with permanently connected loads within 10 seconds, energizes the auto connected emergency (accident) loads through the load sequence and operates for greater than or equal to 5 minutes while its generator is loaded with the emergency
, loads. After loading, the steady state voltage and frequency of l the emergency bue ; shall be maintained at 4360 1 436 volts and i
60 + 1.2/-0.3 H_ during this test."
Section B 3/4.8 of the Bases to the existing TS and Appendix 3A, Section
- 3A.1.9 and Section 8.1.4.3.2 of the UFSAR commit Units 2 and 3, with l exceptions, to the ESF test acceptance criteria contained in Regulatory Guide l (RG) 1.9, Revision 0, entitled " Selection of Diesel Generator Set Capacity for Standby Power Supplies." Section 8.1.4.3.2 of the UFSAR provides details of our existing commitment and describes exceptions taken to RG 1.9, Revision 0.
According to Regulatory Position C4 of RG 1.9, Revision 0, at no time during the EDG loading sequence should the voltage decrease to less than 75% of nominal and voltage should be restored to within 10% of nominal in less than 40% of each load sequence time interval.
EDG Testing per New TS:
Future EDG ESF tests will be conducted in accordance with the new TS.
Surveillance Requirement (SR) 3.8.1.19 of the new TS requires that the ESF test be conducted as follows:
" Verify on an actual or simulated loss of offsite power signal in conjunction with an actual or simulated ESF actuation signal:
- a. De-energization of emergency buses;
- b. Load shedding from emergency buses;
- c. DG auto-starts from standby condition and:
- 1. energizes permanently connected loads in s 10 seconds;
- 2. energizes auto-connected emergency loads through the programmed time interval load sequence;
- 3. achieves steady state voltage 2 3924 V and s 4796 V; i
- 4. achieves steady state frequency 2 58.8 Hz and s 61.2 Hz; and
- 5. supplies permanently connected and auto-connected emergency loads for 2 5 minutes.
1
Document Control Desk As explained in Section B 3.8.1 of the Bases for the new TS, the new ESF test acceptance criteria will be based on the recommendations of RG 1.9, Revision 3.
i Regulatory Position C1.4 of RG 1.9, Revision 3, states in part:
l "Section 5.1.2, " Mechanical and Electrical Capabilities," of IEEE Std 387-1984 pertains, in part, to the starting and load-accepting capabilities of the diesel generator unit. In conformance with Section 5.1.2, each diesel generator unit should be capable of starting and l accelerating to rated speed, in the required sequence, all the needed engineered safety feature and emergency shutdown loads. The diesel generator unit design should be such that at no tima during the loading sequence should the frequency decrease to less than 95 percent of nominal nor the voltage decrease to less than 75 percent of nominal (a
- larger decrease in voltage and frequency may be justified for a diesel l generator unit that carries only one large connected load). Frequency l should be restored to within 2 percent of nominal in less than 60 l percent of each load-sequence interval for stepload increase and in less than 80 percent of each load-sequence interval for disconnection of the single largest load, and voltage should be restored to within 10 percent of nominal within 60 percent of each load-sequence time interval."
Thus, RG 1.9, Revision 0 and Revision 3, both contain the same EDG minimum terminal voltage criterion of 75% of nominal, while Revision 3 allows 60% of the sequencing interval (versus 40% allowed by Revision 0) for voltage restoration.
During the past refueling outages of San Onofre Units 2 and 3, Train A and Train B have generally been tested by running a combined ESF test on both trains. With the single exception of the special ESF test conducted last year on Unit 3 for voltage verification purposes (see discussion below), the concurrent loading of the primary pump and the swing pump has not been considered in the ESF tests. The reason for this is that when the swing pump and a primary pump are both aligned to Train A or Train 8 during normal plant operation (Modes 1 through 3), the design of the HPSI pumps control circuitry prevents the automatic start of both pumps from one diesel. The ESF test method described above is consistent with this design feature and with the plant safety analyses, where credit is taken for the operability of only one pump on each train, j Evaluation of Recently Identified Condition
- A review of the accident scenario discussed above in light of Regulatory Position C4 of RG 1.9, Revision 0, led Edison to evaluate the EDG voltage for Units 2 and 3, and also to perform a special ESF test on a Unit 3 EDG to verify the actual minimum voltage. The evaluation and the test considered the
. loading of two HPSI pumps on one train at time t=0.
d
- Document Control Desk l The results of the evaluation were
! 1. With no margin for future load growth included in the analysis, the i calculated EDG terminal voltage stays above 75% of nominal voltage
. throughout load sequencing.
! 2. With margin included for future load growth, the calculated EDG terminal j voltage dips below 75% of nominal voltage for approximately 0.2 secs.
i However, the associated ESF motor loads would still accelerate to their i rated speeds in the required time without any safety implication or l
failure to meet TS required response times. Consistent with Regulatory Position C4 of RG 1.9, Revision 0, the EDG frequency remains within 2%
- of nominal (60 Hertz base) and the EDG voltage / frequency recovery times are less than the maximum limit (40% of load sequence time interval). ,
- The overall system performance is acceptable from an engineering as well
] as safety standpoint, and the safety analysis in the UFSAR is not
{ affected by the short voltage dip below 75%.
i' The special ESF test was performed on Unit 3 in September 1995 during the Cycle 8 refueling outage. During this special test Edison started two HPSI pumps on Train A and a single HPSI pump on Train B at time t=0 (whereas previous ESF tests started only one HPSI pump on each train at time t=0). The acceptance criteria used -for this test were a minimum Train A voltage equal to 75.5% of nominal bus voltage and a minimum Train B voltage equal to 82.5% of nominal bus voltage. The test demonstrated that these criteria were satisfied.
For Train A, which is more heavily loaded than Train B, the minimum voltage during the special ESF test was 86.33% of the nominal voltage (4.36 kV) and the minimum frequency was 98.25% of the nominal frequency (60 Hertz). The ESF test cannot simulate worst case accident conditions, and its results must be supplemented with analytical results. The results of our August 1993 dynamic analysis simulating the Unit 2 ESF test with one HPSI pump starting indicated a close match between the calculated voltage and frequency values and the actual test values. With the validity of our analytical model thus established, we have concluded that a close match exists between analytical values and actual test values under the two HPSI pumps starting scenario.
Therefore, the special ESF test conducted in September 1995 need not be <
repeated in the future.
-Conclusions Based on analysis and testing, Edison concludes that, in the unlikely event of two HPSI pumps loading simultaneously during ESF load sequencing, the associated EDG will perform its intended safety function. Even if future loading results in a voltage dip below 75% of the EDG terminal voltage, there will be no safety implication as long as the analytic modeling demonstrates that the associated ESF motor loads accelerate to their rated speed in the required time. The ESF test procedure validates the analytic model which in turn demonstrates satisfactory EDG performance with simultaneous loading of two HPSI pumps.
[ . . . . .
l l Document Control Desk l
! Section 8.1.4.3.2 of the UFSAR describes our existing commitment to RG 1.9, l
Rev. O, concerning the Units 2 and 3 EDGs and takes two exceptions (numbered A and B) to RG 1.9, Rev. O, recommendations. Based on a valid analytic model, it was concluded that a diesel generator voltage dip below 75% of nominal has no safety implication. Therefore, Edison proposes to add a third exception (C) as follows:
l
" Electrical analyses demonstrate that each diesel generator can l successfully accelerate all the required Engineered Safety Feature (ESF) i motors to their rated speed in the required time sequence throughout the load sequencing duration, even if the diesel generator voltage dips below 75% of nominal. Refueling interval diesel testing, using available loads, revalidates the analytic model which demonstrates acceptable performance under worst case loading."
The NRC is requested to approve deviating from the UFSAR "75% of nominal l minimum EDG voltage criterion," as recommended in RG 1.9, Revision 0 and Revision 3. If our request for deviation from RG 1.9, Revision 0 and Revision 3, is approved by the NRC, the next UFSAR revision (Revision 13) will reflect this deviation.
l The next ESF tests will be conducted during the Cycle 9 refueling outages, l which are scheduled to start in November 1996 and March 1997 for Units 2 l and 3, respectively. Edison plans to conduct future ESF tests on the Units 2 and 3 EDGs as in the past, which is consistent with both the allowed loading l of only one HPSI pump on each EDG and the analysis requiring the loading of only one HPSI pump on each train.
If you have any questions, please let me know.
Sincerely, l Acer cc: L. J. Callan, Regional Administrator, NRC Region IV J. E. Dyer, Director, Division of Reactor Projects, Region IV l 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 and 3 I