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| i Subjects Oyster Creek Nuclear Generating Station l Docket No. 50-219 Tornado Generated Loadings on Diesel Generator Building (SEP) | | i Subjects Oyster Creek Nuclear Generating Station l Docket No. 50-219 Tornado Generated Loadings on Diesel Generator Building (SEP) |
| (1) PLG-0276, Rev. 1 (transmitted by GPUN letter dated September 16, 1983) | | (1) PLG-0276, Rev. 1 (transmitted by GPUN {{letter dated|date=September 16, 1983|text=letter dated September 16, 1983}}) |
| (2) GPUN Letter to NRC " Tornado and Wind Generated Missiles" dated October 15, 1984. | | (2) GPUN Letter to NRC " Tornado and Wind Generated Missiles" dated October 15, 1984. |
| (3) GPUN Calculation 1302 x-322C-A55 (4) NRC Letter to GPUN " Integrated Plant Safety Assessment Section 4.3, Wind ; | | (3) GPUN Calculation 1302 x-322C-A55 (4) NRC Letter to GPUN " Integrated Plant Safety Assessment Section 4.3, Wind ; |
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| Oyster Creek Nuclear Generating Station-Docket No. 50-219 Page 2 GPUN had previously performed a probablistic analysis to determine the frequency of tornado missiles causing damage to the Diesel Generator Building including the exhaust stack and roof gratings, and to evaluate the consequences in terms of core melt ffequency. The results indicate that the probability of: l c missile hitting the exbnust stack opening or. roof gratings is approximately. | | Oyster Creek Nuclear Generating Station-Docket No. 50-219 Page 2 GPUN had previously performed a probablistic analysis to determine the frequency of tornado missiles causing damage to the Diesel Generator Building including the exhaust stack and roof gratings, and to evaluate the consequences in terms of core melt ffequency. The results indicate that the probability of: l c missile hitting the exbnust stack opening or. roof gratings is approximately. |
| 10'7 per year. It was.however,' reported that the missile hit probability of the Diesel Generator Buildings is estimated as 4.6 x 10 -5 (Da-Unit 1) and'5.4 x 10 -6 (DG-Unit 2) per year, respectively. The analysis indicated that neither diesel generater compartment was scabbed on the 18 inch reinforced concrete walls or the 12 inch roof barriers due to tornado missile impact. The description and results of the probablistic analysis were submitted to the NRC on September 16, 1983. | | 10'7 per year. It was.however,' reported that the missile hit probability of the Diesel Generator Buildings is estimated as 4.6 x 10 -5 (Da-Unit 1) and'5.4 x 10 -6 (DG-Unit 2) per year, respectively. The analysis indicated that neither diesel generater compartment was scabbed on the 18 inch reinforced concrete walls or the 12 inch roof barriers due to tornado missile impact. The description and results of the probablistic analysis were submitted to the NRC on September 16, 1983. |
| The NRC letter dated February 10, 1989 (Ref. 6) requested GPUN to perform a structural evaluation of Oyster Creek Diesel Generator Building under the j combined tornado generated missile and wind loads having frequency higher than j 10-6 per' year. | | The NRC {{letter dated|date=February 10, 1989|text=letter dated February 10, 1989}} (Ref. 6) requested GPUN to perform a structural evaluation of Oyster Creek Diesel Generator Building under the j combined tornado generated missile and wind loads having frequency higher than j 10-6 per' year. |
| Subsequently on March 28, 1989, a telephone conference was held between the NRC staff (Messrs. A. Dromerick and H. Ashar) and GPUN representatives. The purpose of the conference was to clarify both the probabilistic and deterministic evaluation performed by GPUN. The results of our analysis show that the East and West walls of the Diesel Generator Building can withstand a missile (a utility pole hitting at a right angle) loading associated with tornado wind speed of up to 168 mph which corresponds to an exceedence frequency of approximate 1y 7x10-6/ year. The North and South walls can withstand a missile loading associated with tornado wind speed much greater j than the 168 mph. It waa j speedcorrecpondingto10~gointedoutthatGinnaNuclearPlantusedawind | | Subsequently on March 28, 1989, a telephone conference was held between the NRC staff (Messrs. A. Dromerick and H. Ashar) and GPUN representatives. The purpose of the conference was to clarify both the probabilistic and deterministic evaluation performed by GPUN. The results of our analysis show that the East and West walls of the Diesel Generator Building can withstand a missile (a utility pole hitting at a right angle) loading associated with tornado wind speed of up to 168 mph which corresponds to an exceedence frequency of approximate 1y 7x10-6/ year. The North and South walls can withstand a missile loading associated with tornado wind speed much greater j than the 168 mph. It waa j speedcorrecpondingto10~gointedoutthatGinnaNuclearPlantusedawind |
| / year occurrence level to justify their Reactor Building structure in their systematic evaluation program. .GPUN believes that | | / year occurrence level to justify their Reactor Building structure in their systematic evaluation program. .GPUN believes that |
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Category:CORRESPONDENCE-LETTERS
MONTHYEARML20217J3341999-10-19019 October 1999 Forwards Request for Addl Info Re Sale of Portion of Land Part of Oyster Creek Nuclear Generating Station Site Including Portion of Exclusion Area ML20217E0181999-10-0606 October 1999 Provides Nj Dept of Environ Protection Comments on Oyster Creek Nuclear Generating Station TS Change Request 267 Re Clarifications to Several TS Sections ML20216J7591999-09-30030 September 1999 Informs NRC That Remediation Efforts for Software Sys Etude & Rem/Aacs/Cico Have Been Completed According to Schedule & Now Y2K Ready 05000219/LER-1998-011, Forwards LER 98-011-02, Three Small Bore Pipe Lines Did Not Meet Design Bases for Siesmic & Thermal Allowables. Engineering Std Will Not Be Completed Until End of 4th Quarter of 1999 Due to Scheduling Conflicts1999-09-30030 September 1999 Forwards LER 98-011-02, Three Small Bore Pipe Lines Did Not Meet Design Bases for Siesmic & Thermal Allowables. Engineering Std Will Not Be Completed Until End of 4th Quarter of 1999 Due to Scheduling Conflicts ML20212J6721999-09-30030 September 1999 Informs of Completion of mid-cycle PPR of Oyster Creek Nuclear Generating Station on 990913.No Areas Identified in Which Licensee Performance Warranted Addl Insp Beyond Core Insp Program.Historical Listing of Plant Issues Encl ML20216K1421999-09-29029 September 1999 Provides NRC with Name of Single Point of Contact for Purpose of Accessing Y2K Early Warning Sys,As Requested by NRC Info Notice 99-025 ML20217D1661999-09-27027 September 1999 Forwards Proprietary Completed NRC Forms 396 & 398,in Support of License Renewal Applications for Listed Individuals,Per 10CFR55.57.Encl Withheld ML20217B2531999-09-24024 September 1999 Informs That on 980903,Region I Field Ofc of NRC Ofc of Investigations Initiated Investigation to Determine Whether Crane Operator Qualification/Training Records Had Been Falsified at Oyster Creek Nuclear Generating Station ML20212E1971999-09-16016 September 1999 Forwards Rev 11 of Gpu Nuclear Operational QAP, Reflecting Organizational Change in Which Functions & Responsibilities of Nuclear Safety & Technical Support Div Were Assigned to Other Divisions ML20212A7921999-09-13013 September 1999 Forwards Second RAI Re GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power-Operated Gate Valves, Issued on 950817 to Plant ML20212B5571999-09-10010 September 1999 Forwards Rev 11 to Oyster Creek Emergency Dose Calculation Manual, IAW 10CFR50,App E,Section V ML20211N2941999-09-0303 September 1999 Responds to NRC 990802 Telcon Request for Environ Impact Assessment of TS Change Request 251 Concerning Movement of Loads Up to 45 Tons with RB Crane During Power Operations ML20211J9831999-09-0202 September 1999 Discusses 990804 Telcon Re Sale of Portion of Oyster Creek Nuclear Generating Station Land.Requests Info Re Location of All Areas within Property to Be Released Where Licensed Radioactive Matl Present & Disposition of Radioactive Matl ML20211J6771999-08-30030 August 1999 Submits Response to NRC 990802 Telcon Request for Gpu to Provide Environ Impact Assessment for Tscr 251 ML20211K2391999-08-23023 August 1999 Forwards fitness-for-duty Performance Data Repts for TMI, Oyster Creek & Corporate Headquarters Located in Parsippany, Nj ML20211C0161999-08-19019 August 1999 Advises That Info Submitted by Ltr,Dtd 990618, Licensing Rept for Storage Capacity Expansion of Oyster Creek Spent Fuel Pool, Holtec Rept HI-981983,rev 4,will Be Withheld from Public Disclosure,Per 10CFR2.790 ML20211B9011999-08-18018 August 1999 Forwards Rev 0 to EPIP 1820-IMP-1720.01, Emergency Public Info Implementing Procedure ML20210U4341999-08-17017 August 1999 Responds to to Chairman Dicus of NRC on Behalf of Fm Massari Concern About Oyster Creek Nuclear Generating Station Not Yet Being Fully Y2K Compliant ML20210Q7331999-08-12012 August 1999 Responds to Re TS Change Request (TSCR)264 from Oyster Creek Nuclear Generating Station.Questions Re Proposed Sale of Property within Site Boundary & Exclusion Area ML20210L6311999-08-0606 August 1999 Discusses Licensee Response to GL 92-01,Rev1,Suppl 1, Rv Structural Integrity, for Plant.Staff Has Revised Info in Rv Integrity Database & Releasing as Rvid Version 2 ML20210D2801999-07-22022 July 1999 Submits Response to Administrative Ltr 99-02 Operating Reactor Licensing Action Estimates. Estimate of Licensing Actions Projected for Fy 2000 Encl.No Projection Provided for Fy 2001 ML20209H5001999-07-14014 July 1999 Forwards Revised TS Pages 3.1-15 & 3.1-17 Which Include Ref to Note (Aa) & Approved Wording of Note H of Table 3.1.1, Respectively ML20210U4411999-07-12012 July 1999 Forwards Article from Asbury Park Press of 990708 Faxed to Legislative Officer by Mutual Constitute Fm Massari Indicating That Oyster Creek Nuclear Generating State Not Fully Y2K Compliant ML20209G1451999-07-0909 July 1999 Forwards Rev 1 to 2000-PLN-1300.01, Oyster Creek Generating Station Emergency Plan. Attachment 1 Contains Brief Summary of Changes,Which Became Effective on 990702 ML20209E0821999-07-0707 July 1999 Forwards TS Change Request 269 for License DPR-16,changing Component Surveillance Frequencies to Indicate Frequency of Once Per Three Months ML20209B7501999-07-0101 July 1999 Responds to NRC Request for Info Re Y2K Readiness at Nuclear Power Plants.Generic Ltr 98-01 Requested Response on Status of Facility Y2K Readiness by 990701.Licensee Y2K Readiness Disclosure for Ocngs,Encl ML20196G1361999-06-23023 June 1999 Provides Status of Corrective Actions Proposed in in Response to Insp Rept 50-219/98-80 & Revised Schedule for Completion of Actions Which Are Not Yet Complete ML20196E6421999-06-22022 June 1999 Forwards Revised Pages of TS Change Request 261,dtd 990618. Replacement Requested Due to Several Dates Being Omitted on Certain Pages ML20195G6541999-06-0707 June 1999 Discusses 981204 Initiation to Investigate Whether Contract Valve Technician,Was Discriminated Against for Raising Concern Re Use of Untrained/Unqualified Workers Performing Valve Repairs.Technician Was Not Discriminated Against ML20195G6631999-06-0707 June 1999 Discusses 981204 Intiation to Investigate Whether Contract Valve Technician Was Discriminated Against for Raising Concern Re Use of Untrained/Unqualified Workers Performing Valve Repairs.Technician Was Not Discriminated Against ML20209B0561999-06-0404 June 1999 Informs That NRR Has Reorganized,Effective 990328.Forwards Organizational Chart ML20195D0551999-06-0303 June 1999 Forwards TS Change Request 226 to License DPR-16,permitting Operation with Three Recirculation Loops.Certificate of Svc & Tss,Encl ML20195C5511999-05-25025 May 1999 Forwards Book of Controlled Drawings Currently Ref But Not Contained in Plant Ufsar.Drawings Were Current at Time of Submittal ML20206N7711999-05-11011 May 1999 Forwards Rev 0 to Oyster Creek Emergency Plan, IAW 10CFR50.47(b) & 10CFR50.54(q).Changes Became Effective on 990413 ML20206H9441999-04-28028 April 1999 Forwards Application for Amend to License DPR-16,requesting Approval to Handle Loads Up to & Including 45 Tons Using Reactor Bldg Crane During Power Operations,Per NRC Bulletin 96-002 ML20206B6991999-04-26026 April 1999 Forwards Copy of Rev 11 to UFSAR & Rev 10 to Oyster Creek Fire Hazards Analysis Rept. Without Fire Hazard Analysis ML20206D3801999-04-26026 April 1999 Forwards Rev 11 to UFSAR, & Rev 10 to Fire Hazards Analysis Rept, for Oyster Creek Nuclear Generating Station, Per 10CFR50.712(e) ML20206A9931999-04-22022 April 1999 Forwards Number of Personnel & Person Rems by Work & Job Function Rept for Period Jan-Dec 1998. Included in Rept Is Listing of Number of Station,Util & Contractor Personnel as Well as Diskette Reporting 1998 Occupational Radiation ML20206C8261999-04-22022 April 1999 Submits Financial Info IAW Requirements of 10CFR50.71(b) & 10CFR140.21 ML20205P8411999-04-15015 April 1999 Forwards TS Change Request 267 to License DPR-16,modifying Items in Sections 2 & 3 of Ts,Expanding Two Definitions in Section 1 & Modifying Bases Statements in Sections 2,3 & 4. Certificate of Svc Encl ML20205P5381999-04-14014 April 1999 Ack Receipt of Re Request for Exception to App J. Intended Correction Would Need to Be Submitted as Change to TS as Exceptions to RG 1.163 Must Be Listed in Ts,Per 10CFR50,App J ML20205P9401999-04-12012 April 1999 Informs NRC That Gpu Nuclear Is Modifying Oyster Creek FSAR to Reflect Temp Gradient of 60 F & to Correct Historical Record ML20205P0651999-04-0909 April 1999 Discusses 990225 PPR & Forwards Plant Issues Matrix & Insp Plan.Results of PPR Used by NRC Mgt to Facilitate Planning & Allocation of Insp Resources 05000219/LER-1998-015, Forwards LER 98-015-01,as Original Submittal on 981028 Inadvertently Indicated That Suppl Would Be Submitted.Suppl Should Not Have Been Required as Only Change Is on Cover Page1999-04-0505 April 1999 Forwards LER 98-015-01,as Original Submittal on 981028 Inadvertently Indicated That Suppl Would Be Submitted.Suppl Should Not Have Been Required as Only Change Is on Cover Page ML20205J3281999-04-0101 April 1999 Discusses Arrangements Made on 990323 for NRC to Inspect Licensed Operator Requalification Program at Oyster Creek Nuclear Generating Station During Week of 990524 ML20205H1081999-03-31031 March 1999 Forwards Current Funding Status for Decommissioning Funds Established for OCNPP,TMI-1,TMI-2 & SNEC ML20205F0611999-03-25025 March 1999 Submits Info on Sources & Levels of Property Insurance Coverage Maintained & Currently in Effect for Oyster Creek Nuclear Generating Station,Iaw 10CFR50.54(w)(3) ML20205E1171999-03-24024 March 1999 Forwards Rev 39 to Oyster Creek Security Plan & Summary of Changes,Iaw 10CFR50.54(p).Rev Withheld ML20207F0331999-03-0404 March 1999 Forwards Insp Rept 50-219/98-12 During Periods 981214-18, 990106-07 & 20-22.Areas Examined During Insp Included Implementation of GL 89-10 & GL 96-05.No Violations Noted ML20207K2471999-02-25025 February 1999 Forwards Fitness for Duty Performance Data Repts for TMI, Oyster Creek & Corporate Headquarters Located in Parsippany, Ny 1999-09-30
[Table view] Category:INCOMING CORRESPONDENCE
MONTHYEARML20217E0181999-10-0606 October 1999 Provides Nj Dept of Environ Protection Comments on Oyster Creek Nuclear Generating Station TS Change Request 267 Re Clarifications to Several TS Sections 05000219/LER-1998-011, Forwards LER 98-011-02, Three Small Bore Pipe Lines Did Not Meet Design Bases for Siesmic & Thermal Allowables. Engineering Std Will Not Be Completed Until End of 4th Quarter of 1999 Due to Scheduling Conflicts1999-09-30030 September 1999 Forwards LER 98-011-02, Three Small Bore Pipe Lines Did Not Meet Design Bases for Siesmic & Thermal Allowables. Engineering Std Will Not Be Completed Until End of 4th Quarter of 1999 Due to Scheduling Conflicts ML20216J7591999-09-30030 September 1999 Informs NRC That Remediation Efforts for Software Sys Etude & Rem/Aacs/Cico Have Been Completed According to Schedule & Now Y2K Ready ML20216K1421999-09-29029 September 1999 Provides NRC with Name of Single Point of Contact for Purpose of Accessing Y2K Early Warning Sys,As Requested by NRC Info Notice 99-025 ML20217D1661999-09-27027 September 1999 Forwards Proprietary Completed NRC Forms 396 & 398,in Support of License Renewal Applications for Listed Individuals,Per 10CFR55.57.Encl Withheld ML20212E1971999-09-16016 September 1999 Forwards Rev 11 of Gpu Nuclear Operational QAP, Reflecting Organizational Change in Which Functions & Responsibilities of Nuclear Safety & Technical Support Div Were Assigned to Other Divisions ML20212B5571999-09-10010 September 1999 Forwards Rev 11 to Oyster Creek Emergency Dose Calculation Manual, IAW 10CFR50,App E,Section V ML20211N2941999-09-0303 September 1999 Responds to NRC 990802 Telcon Request for Environ Impact Assessment of TS Change Request 251 Concerning Movement of Loads Up to 45 Tons with RB Crane During Power Operations ML20211J6771999-08-30030 August 1999 Submits Response to NRC 990802 Telcon Request for Gpu to Provide Environ Impact Assessment for Tscr 251 ML20211K2391999-08-23023 August 1999 Forwards fitness-for-duty Performance Data Repts for TMI, Oyster Creek & Corporate Headquarters Located in Parsippany, Nj ML20211B9011999-08-18018 August 1999 Forwards Rev 0 to EPIP 1820-IMP-1720.01, Emergency Public Info Implementing Procedure ML20210D2801999-07-22022 July 1999 Submits Response to Administrative Ltr 99-02 Operating Reactor Licensing Action Estimates. Estimate of Licensing Actions Projected for Fy 2000 Encl.No Projection Provided for Fy 2001 ML20209H5001999-07-14014 July 1999 Forwards Revised TS Pages 3.1-15 & 3.1-17 Which Include Ref to Note (Aa) & Approved Wording of Note H of Table 3.1.1, Respectively ML20210U4411999-07-12012 July 1999 Forwards Article from Asbury Park Press of 990708 Faxed to Legislative Officer by Mutual Constitute Fm Massari Indicating That Oyster Creek Nuclear Generating State Not Fully Y2K Compliant ML20209G1451999-07-0909 July 1999 Forwards Rev 1 to 2000-PLN-1300.01, Oyster Creek Generating Station Emergency Plan. Attachment 1 Contains Brief Summary of Changes,Which Became Effective on 990702 ML20209E0821999-07-0707 July 1999 Forwards TS Change Request 269 for License DPR-16,changing Component Surveillance Frequencies to Indicate Frequency of Once Per Three Months ML20209B7501999-07-0101 July 1999 Responds to NRC Request for Info Re Y2K Readiness at Nuclear Power Plants.Generic Ltr 98-01 Requested Response on Status of Facility Y2K Readiness by 990701.Licensee Y2K Readiness Disclosure for Ocngs,Encl ML20196G1361999-06-23023 June 1999 Provides Status of Corrective Actions Proposed in in Response to Insp Rept 50-219/98-80 & Revised Schedule for Completion of Actions Which Are Not Yet Complete ML20196E6421999-06-22022 June 1999 Forwards Revised Pages of TS Change Request 261,dtd 990618. Replacement Requested Due to Several Dates Being Omitted on Certain Pages ML20195D0551999-06-0303 June 1999 Forwards TS Change Request 226 to License DPR-16,permitting Operation with Three Recirculation Loops.Certificate of Svc & Tss,Encl ML20195C5511999-05-25025 May 1999 Forwards Book of Controlled Drawings Currently Ref But Not Contained in Plant Ufsar.Drawings Were Current at Time of Submittal ML20206N7711999-05-11011 May 1999 Forwards Rev 0 to Oyster Creek Emergency Plan, IAW 10CFR50.47(b) & 10CFR50.54(q).Changes Became Effective on 990413 ML20206H9441999-04-28028 April 1999 Forwards Application for Amend to License DPR-16,requesting Approval to Handle Loads Up to & Including 45 Tons Using Reactor Bldg Crane During Power Operations,Per NRC Bulletin 96-002 ML20206B6991999-04-26026 April 1999 Forwards Copy of Rev 11 to UFSAR & Rev 10 to Oyster Creek Fire Hazards Analysis Rept. Without Fire Hazard Analysis ML20206D3801999-04-26026 April 1999 Forwards Rev 11 to UFSAR, & Rev 10 to Fire Hazards Analysis Rept, for Oyster Creek Nuclear Generating Station, Per 10CFR50.712(e) ML20206C8261999-04-22022 April 1999 Submits Financial Info IAW Requirements of 10CFR50.71(b) & 10CFR140.21 ML20206A9931999-04-22022 April 1999 Forwards Number of Personnel & Person Rems by Work & Job Function Rept for Period Jan-Dec 1998. Included in Rept Is Listing of Number of Station,Util & Contractor Personnel as Well as Diskette Reporting 1998 Occupational Radiation ML20205P8411999-04-15015 April 1999 Forwards TS Change Request 267 to License DPR-16,modifying Items in Sections 2 & 3 of Ts,Expanding Two Definitions in Section 1 & Modifying Bases Statements in Sections 2,3 & 4. Certificate of Svc Encl ML20205P9401999-04-12012 April 1999 Informs NRC That Gpu Nuclear Is Modifying Oyster Creek FSAR to Reflect Temp Gradient of 60 F & to Correct Historical Record 05000219/LER-1998-015, Forwards LER 98-015-01,as Original Submittal on 981028 Inadvertently Indicated That Suppl Would Be Submitted.Suppl Should Not Have Been Required as Only Change Is on Cover Page1999-04-0505 April 1999 Forwards LER 98-015-01,as Original Submittal on 981028 Inadvertently Indicated That Suppl Would Be Submitted.Suppl Should Not Have Been Required as Only Change Is on Cover Page ML20205H1081999-03-31031 March 1999 Forwards Current Funding Status for Decommissioning Funds Established for OCNPP,TMI-1,TMI-2 & SNEC ML20205F0611999-03-25025 March 1999 Submits Info on Sources & Levels of Property Insurance Coverage Maintained & Currently in Effect for Oyster Creek Nuclear Generating Station,Iaw 10CFR50.54(w)(3) ML20205E1171999-03-24024 March 1999 Forwards Rev 39 to Oyster Creek Security Plan & Summary of Changes,Iaw 10CFR50.54(p).Rev Withheld ML20207K2471999-02-25025 February 1999 Forwards Fitness for Duty Performance Data Repts for TMI, Oyster Creek & Corporate Headquarters Located in Parsippany, Ny ML20206S2541999-01-20020 January 1999 Confirms Resolution of Thermo-Lag Fire Barriers in Fire Zones OB-FZ-6A & OB-FZ-6B (480 Switchgear Rooms) IAW Previous Commitments Contained in Gpuns Ltrs to NRC & 971001 ML20199J2631999-01-18018 January 1999 Requests That Listed Changes Be Made to Correspondence Distribution List for Oyster Creek Generating Station ML20199D0271999-01-11011 January 1999 Requests Listed Addl Info in Order to Effectively Review TS Change Request 264 Re Ownership of Property within Exclusion Area ML20199A6521999-01-0707 January 1999 Notifies That Reactor Operators G Scienski,License SOP-11319 & D Mcmillan,License SOP-3919-4 Have Terminated Licenses at Oyster Creek Nuclear Generating Station, Effective 990101 ML20198T1061999-01-0606 January 1999 Forwards Rev 15 to Gpu Nuclear Corporate Emergency Plan for TMI & Oyster Creek Nuclear Station. with Summary of Changes Which Reflect Use of EALs Approved in NRC Ltr to Gpun on 980908 & Other Changes Not Related to Use of New EALs ML20198K0331998-12-23023 December 1998 Forwards Change Request 268 for Amend to License DPR-16. Amend Would Change TS to Specify Surveillance Frequency of Once Per Three Months ML20198H0181998-12-22022 December 1998 Forwards Attachment Addressing New Info & Modifying 980505 Submittal Re Request for Change to Licensing Bases for ECCS Overpressure,In Response to NRC Bulletin 96-03, Potential Plugging of ECCS by Debris in Bwrs ML20198H8521998-12-16016 December 1998 Dockets Completion of Physical Inventory Performed in July 1997,as Addl Info to Nuclear Matl Balance Rept Submitted on 980416 ML20196H4461998-12-0202 December 1998 Provides Final Response to NRC GL 96-01, Testing of Safety-Related Logic Circuits ML20196B4471998-11-23023 November 1998 Provides Required Response 2 to NRC Bulletin 96-003, Potential Plugging of ECC Suction Strainers in Bwrs. During Recently Completed 17R Refueling Outage,New Strainers Were Installed ML20195J8451998-11-12012 November 1998 Forwards Rev 11 to 1000-PLN-7200.01, Gpu Nuclear Operational QA Plan, as Change Previously Made Without Appropriate Notification to NRC ML20195C7201998-11-11011 November 1998 Forwards 120-day Required Response to GL 98-04, Potential for Degradation of ECCS & CSS After LOCA Because of Construction & Protective Coating Deficiencies & Foreign Matl in Containment, ML20195E1221998-11-10010 November 1998 Notifies NRC of First Time Usage of Code Case N-504 & Inclusion Into OCNGS ISI Program,As Accepted by RG 1.147, Inservice Insp Code Case Acceptability ML20155J6851998-11-0505 November 1998 Forwards TS Change Request 266,to Modify Safety Limits & Surveillances of LPRM & APRM Sys & Related Bases to Ensure APRM Channels Respond within Necessary Range & Accuracy & Verify Channel Operability ML20155H5641998-11-0202 November 1998 Informs That Bne Has No Comments on Proposed Change 259 to Ts,Correcting Required Water Level in Condensate Storage Tank So That Design Basis Is Correctly Implemented ML20155G3741998-10-29029 October 1998 Forwards Response to NRC 980619 RAI Re GL 96-06, Assurance of Equipment Operability & Containment Integrity During Design-Basis Accident Conditions 1999-09-30
[Table view] Category:UTILITY TO NRC
MONTHYEARML20059L2551990-09-14014 September 1990 Advises of Preparation for Final Refueling Outage to Complete Second 10-yr Interval for Inservice Insps ML20059F5121990-09-0505 September 1990 Requests Exemption from Filing Requirement of 10CFR55.45(b)(2)(iii) to Allow Submittal of NRC Form 474, Simulator Facility Certification, After 910326 Deadline & to Allow Administering of Simulator Portion of Test ML20059F7441990-08-31031 August 1990 Forwards Util Review of NRC Backfit Analysis for Hardened Wetwell Vent.Nrc Analysis Does Not Support Conclusion That Hardening Existing Vent Is cost-beneficial Mod for Plant ML20059E9061990-08-30030 August 1990 Forwards Response to 900808 Request for Addl Info Re NRC Bulletin 90-002, Loss of Thermal Margin Caused by Fuel Channel Box Bow ML20059G1841990-08-29029 August 1990 Ack NRC Request to Perform Type C Testing During Unscheduled Outage,As Plant Conditions Will Allow.Type C Exemptions Should Remain in Effect Until New Outage Start Date ML20059C8231990-08-27027 August 1990 Advises That SPDS Enhancements Described in Completed,Per 900628 Request.Offline & Online Testing Completed & Enhancements Considered to Be Operational ML20059C8571990-08-24024 August 1990 Provides Results of Evaluation of Ability to Meet Acceptance Criteria for Eccs,In Response to 900804 Notice of Violation. Plant Meets Acceptance Criteria Contained in 10CFR50.46 W/ Valve Logic Design Deficiency in Containment Spray Sys ML20058N0781990-08-0909 August 1990 Submits Info Re pressure-temp Operating Limits for Facility, Per Generic Ltr 88-11.Util Recalculated Adjusted Ref Temp for Each Belt Line Matl as Result of New Displacement Per Atom Values ML20063P9521990-08-0909 August 1990 Advises That Response to NRC 900523 Request for Assessment of Hazardous Matl Shipment Will Be Sent by 910531 ML20058L9521990-08-0303 August 1990 Forwards Rev 2 to Security Contingency Plan.Rev Withheld (Ref 10CFR73.21) ML20058L9551990-08-0303 August 1990 Responds to SALP Rept 50-219/88-99.Although Minor,Several Factual Errors Noted.Dialogue Promotes & Identifies Areas Where Improvements Should Be Made ML20056A2071990-07-30030 July 1990 Forwards Response to NRC Bulletin 90-001, Loss of Fill-Oil in Transmitters Mfg by Rosemount. Record Review Performed & Sys Walkdowns Completed to Assemble Requisite List ML20055H7961990-07-20020 July 1990 Advises of Change to Preventive Maint Program for Electromatic Relief Valves.Rebuild Schedule Will Be Modified to Require Rebuilding Two or Three Valves During Refueling Outage & Remaining Valves During Next Refueling Outage ML20058N9911990-07-20020 July 1990 Partially Withheld Response to NRC Bulletin 90-002 Re Loss of Thermal Margin Caused by Box Bow (Ref 10CFR2.790(b)(1)) ML20055J0481990-07-19019 July 1990 Requests 2-wk Extension for Submittal of Response to Re Installation of Hardened Wetwell Vent W/ Appropriate Extension Period to Be Decided Pending Outcome of 900724 Meeting Discussion W/Bwr Owners Group ML20064A1221990-07-11011 July 1990 Discusses 900710 Telcon W/Nrc Re Util Corrective Actions in Response to NRC Finding That Operator Received Passing Grade on Administered Requalification Exam in 1989 Should Have Received Failing Grade.Corrective Actions Listed ML20055F8491990-07-10010 July 1990 Forwards Application for Amend to License DPR-16,consisting of Tech Spec Change Request 188,reducing Low Condenser Vacuum Scram Setpoint ML20043H7471990-06-21021 June 1990 Confirms Telcon W/A Dromerick Re Util Plans to Inspect CRD Hydraulic Control Units During Plant Walkdown to Address USI A-46, Seismic Qualification of Equipment in Operating Nuclear Power Plants. Walkdown Planned in Oct 1992 ML20043H2301990-06-14014 June 1990 Documents Licensee Commitment to Improve Seismic Restraints for Diesel Generator Switchgear Encls,Per 900613 Telcon W/ Nrc.Engineering Will Be Finalized & Mods Completed Prior to 900622 ML20043F7581990-06-0707 June 1990 Responds to Request for Info Re Util Compliance W/Generic Ltr 88-01 & Insp Plans for Upcoming 13R Outage.Frequency of Insp of Welds Classified as IGSCC Categories C,D & E Will Not Be Reduced During 13R Outage ML20043C5801990-05-25025 May 1990 Provides Descriptions & Conclusions of Three Remaining Issues of SEP Topic III-7B.Issues Include,Evaluation of Drywell Concrete Subj to High Temp & Thermal Transients ML20043C2461990-05-25025 May 1990 Forwards Rev 7 to EPIP 9473-IMP-1300.06 & Rev 4 to Radiological Controls Policy & Procedure Manual 9300-ADM-4010.03, Emergency Dose Calculation Manual. ML20043B2981990-05-21021 May 1990 Responds to NRC 900420 Ltr Re Violations Noted in Insp Rept 50-219/90-06.Corrective Actions:Incident Critique Rept Incorporated as Required Reading for Appropriate Operations Personnel & Change Made to Procedure 201.1 ML20043D0701990-05-17017 May 1990 Provides NRC W/Addl Info Re SPDS & Responds to Concerns Raised During 900117 & 18 SPDS Audit Documented in 900130 Ltr ML20043B3901990-05-0909 May 1990 Responds to NRC 900408 Ltr Re Violations Noted in Insp of License DPR-16.Corrective Actions:Two Narrow Range Drywell Pressure Monitoring Instruments to Be Provided During Cycle 14R Refueling Outage,Per Reg Guide 1.97,Category 1 ML20042G7071990-05-0808 May 1990 Forwards Summary of Initiatives & Accomplishments Re SALP, Per 891031 Commitment at mid-SALP Meeting.Plant Div Responsibilities Now Include Conduct of Maint Outages & Emergency Operating Procedure Training Conducted ML20042G2291990-05-0707 May 1990 Forwards Application for Amend to License DPR-16,consisting of Tech Spec Change Request 180,revising Tech Specs Re Fuel cycle-specific Parameters ML20042G2601990-05-0404 May 1990 Forwards Application for Amend to License DPR-16,consisting of Tech Spec Change Request 187,revising Tech Specs to Accommodate Implementation of 24-month Plant Refueling Cycle ML20042E9431990-04-20020 April 1990 Forwards Revised Epips,Consisting of Rev 7 to 9473-IMP-1300.01,Rev 4 to 9473-1300.11 & Rev 2 to 9473-ADM-1319.04.Deleted EPIPs Listed,Including Rev 3 to 9473-1300.19,Rev 2 to 9473-1300.21 & Rev 5 to 9473.1300.24 ML20042E6371990-04-16016 April 1990 Informs of Plans to Install Safety Grade Check Valve in Supply Line Inside Emergency Diesel Generator Fuel Tank Room Coincident W/Replacement or Repair of Emergency Diesel Generator Fuel Oil Tank ML20042E5001990-04-13013 April 1990 Forwards Rev 1 to Topical Rept 028, Oyster Creek Response to NRC Reg Guide 1.97. ML20012E8711990-03-28028 March 1990 Lists Property Insurance Coverage,Effective 900401,per 10CFR50.54(w)(2) ML20012D4391990-03-19019 March 1990 Forwards Application for Amend to License DPR-16,consisting of Tech Spec Change Request 186,allowing Idle Recirculation Loop to Be Isolated During Power Operation by Closing Suction,Discharge & Bypass Valves ML20012B6781990-03-0202 March 1990 Requests Exemption of Specified Local Leak Rate Test Intervals to Include Next Plant Refueling Outage Scheduled for Jan 1991,per 10CFR50,App J ML20012A1501990-02-23023 February 1990 Forwards Application for Amend to License DPR-16,consisting of Tech Spec Change Request 184,removing 3.25 Limit on Extending Surveillance Intervals,Per Generic Ltr 89-14 ML20011F2571990-02-21021 February 1990 Advises That 891003 Request for Appropriate Tech Specs for Chlorine Detection Re Control Room Habitability,Not Warranted ML20006G0101990-02-21021 February 1990 Discusses 900110 Meeting W/Nrr Re 13R Insp Criteria for RWCU Welds Outboard of Second Containment Isolation Valve. All Welds Required 100% Radiography Based on Review of Piping Spec.Response to Generic Ltr 88-01 Will Be Revised ML20006F5931990-02-20020 February 1990 Forwards Application for Amend to License DPR-16,consisting of Tech Spec Change Request 177.Amend Changes Tech Spec 4.7.B to Include Battery Svc Test Every Refueling Outage & Mod of Frequency of Existing Battery Performance Test ML20011F6641990-02-20020 February 1990 Responds to NRC 900122 Notice of Violation & Forwards Payment of Civil Penalty in Amount of $25,000.Corrective Actions:Change Made to Sys Component Lineup Sheets in 125- Volt Dc Operating Procedure to Include Selector Switches ML20006F9181990-02-15015 February 1990 Forwards Application for Amend to License DPR-16,consisting of Tech Spec Change Request 183,permitting No Limitation on Number of Inoperable Position Indicators for 16 ASME Code Safety Valves During Power Operation ML20006D2551990-01-30030 January 1990 Forwards Response to Generic Ltr 89-13 Re Plant Svc Water Sys.Insp Program for Intake Structure at Plant Implemented During Past Two Refueling Outages & Emergency Svc Water Currently Chlorinated to Prevent Biofouling ML19354E8571990-01-24024 January 1990 Forwards Omitted Pages of 900116 Ltr Re State of Nj DEP Comments on Draft full-term OL SER & Clarification of Page 10,fourth Paragraph on New Seismic Floor Response Spectra ML20006B2171990-01-23023 January 1990 Responds to Unresolved Items & Weaknesses Identified in Insp Rept 50-219/89-80.Corrective Actions:Procedure Re Containment Spray sys-diagnostic & Restoration Actions Revised to Stand Alone Re Installation of Jumpers ML19354E3891990-01-19019 January 1990 Responds to Violations Noted in Insp Rept 50-219/89-27. Corrective Actions:Procedure 108 Revised to Allow Temporarily Lifting of Temporary Variation ML19354E8441990-01-19019 January 1990 Forwards Revised Tech Spec Table 4.13-1, Accident Monitoring Instrumentation Surveillance Requirements, in Support of Licensee 890630 Tech Spec Change Request 179,per NRC Project Manager Request ML20006B2881990-01-18018 January 1990 Forwards Results from Feedwater Nozzle Exam,In Accordance w/NUREG-0619 Insp Format ML20005G8161990-01-16016 January 1990 Provides Assessment of State of Nj Concerns Re full-term OL Plant,Per NRC 891222 Request.Comments Did Not Raise Any Concerns That Refute Conclusions Reached by NRC That Facility Will Continue to Operate W/O Endangering Safety ML19354D8281990-01-15015 January 1990 Responds to Violation Noted in Insp Rept 50-219/89-21. Corrective Action:Procedure A000-WMS-1220.08, Mcf Job Order Revised to Provide Detailed Guidance for Performance of Immediate Maint ML20042D4891989-12-28028 December 1989 Forwards Response to Generic Ltr 89-10, Safety-Related Motor-Operated Valve Testing & Surveillance, Fulfilling 6-month Reporting Requirement ML20005E1401989-12-22022 December 1989 Forwards Integrated Schedule Semiannual Update for Dec 1989 1990-09-05
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a GPU Nuclear Corporation V3 ~
k;- W.d fI Ng gpIggn Hw wMs One Upper Pond Road Parsippany, New Jersey 07054 201-316-7000 TELEX 136-482 Writer's Direct Dial Number: j i '
July 24, 1989 5000-89-2793 l
l U.S. Nuclear Regulatory Commission Attention Document Control Desk j Washington, D.C. 20555 j I
Gentlemen
i Subjects Oyster Creek Nuclear Generating Station l Docket No. 50-219 Tornado Generated Loadings on Diesel Generator Building (SEP)
(1) PLG-0276, Rev. 1 (transmitted by GPUN letter dated September 16, 1983)
(2) GPUN Letter to NRC " Tornado and Wind Generated Missiles" dated October 15, 1984.
(3) GPUN Calculation 1302 x-322C-A55 (4) NRC Letter to GPUN " Integrated Plant Safety Assessment Section 4.3, Wind ;
and Tornado Loadings - Cyster Creek" dated March 8, 1986. 1 (5) GPUN letter to NRC " Tornado Missile" dated Aug. 14, 1987 (6) NRC letter to GPUH CRequest for Additional Information - OCNGS - Tornado Generated Loadings on Diesel Cenerator Buildlug" dated Feb. 10, 1989.
I During the integreted assessment of SEP Topic No. III-4A, Tornado Missiles, the l NRC staf f stated that although there are multiple sourcos of water and supply j rfysteme on which Oyster Creek can rely to accomplish safe shutdown, they are not protected from tornado missiles. It was also the staff's position that .
redundancy is not acceptable protection for tornado missiles. j GPUN initially proposed to prov0de a porteble pump in a protected area and a hose connection to a protected water supply to be used in conjunction with the isolation condenser to achieve the hot shutdown (IPSAR Section 4.6.4).
1 l l Subsequently, through a detailed field walkdown and line loss analysis of an i i existing system interconnection between the Core Spray and the Condensate and Demineralized Water Transfer Systems, it was determined that the existing plant l configuration is capable of supplying make-up water to the Isolation Condenser
! from the suppression chamber and is, therefore, sufficient to address the
! staff's concern (Ref. 5).
- l. The z.taff, after their detailed review, concluded that the use of the existing l system is acceptablc if the diesel generator, which powers the Core Spray pump upon a loss of offsite power, is protected from tornado wind and missile i loadings.
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GPU Nuclear Corporation is a subsidiary of General P,.3ic Utikties Corporation I
Oyster Creek Nuclear Generating Station-Docket No. 50-219 Page 2 GPUN had previously performed a probablistic analysis to determine the frequency of tornado missiles causing damage to the Diesel Generator Building including the exhaust stack and roof gratings, and to evaluate the consequences in terms of core melt ffequency. The results indicate that the probability of: l c missile hitting the exbnust stack opening or. roof gratings is approximately.
10'7 per year. It was.however,' reported that the missile hit probability of the Diesel Generator Buildings is estimated as 4.6 x 10 -5 (Da-Unit 1) and'5.4 x 10 -6 (DG-Unit 2) per year, respectively. The analysis indicated that neither diesel generater compartment was scabbed on the 18 inch reinforced concrete walls or the 12 inch roof barriers due to tornado missile impact. The description and results of the probablistic analysis were submitted to the NRC on September 16, 1983.
The NRC letter dated February 10, 1989 (Ref. 6) requested GPUN to perform a structural evaluation of Oyster Creek Diesel Generator Building under the j combined tornado generated missile and wind loads having frequency higher than j 10-6 per' year.
Subsequently on March 28, 1989, a telephone conference was held between the NRC staff (Messrs. A. Dromerick and H. Ashar) and GPUN representatives. The purpose of the conference was to clarify both the probabilistic and deterministic evaluation performed by GPUN. The results of our analysis show that the East and West walls of the Diesel Generator Building can withstand a missile (a utility pole hitting at a right angle) loading associated with tornado wind speed of up to 168 mph which corresponds to an exceedence frequency of approximate 1y 7x10-6/ year. The North and South walls can withstand a missile loading associated with tornado wind speed much greater j than the 168 mph. It waa j speedcorrecpondingto10~gointedoutthatGinnaNuclearPlantusedawind
/ year occurrence level to justify their Reactor Building structure in their systematic evaluation program. .GPUN believes that
)!
the safety afforded by protection to a windspoed associated with a probability of 10 -5 per year is adequate. This probability level is considered cc,ngruent I with the protection levels associated with other severe' natural phenomena, such l as earthquakes and flooding, and with postulated events, such as pipe break.
As you requested during the telephone conference, our technical discussion on this issue is documented below: l I. INTRODUCTION In order to better understand the tornado missile analysis, it helps to briefly review the types of missiles considered, the' characteristics oi' the various portions of the Diesel Generator Building, and the failure modes to be considered.
The missiles can be divided into three categories:
l (1) Penetrator Missiles (SRP Section 3.5.1.4 Misslle Spectrum B; A l through E) l (2) Utility Pole (F)
(3) Automobile (G) 1 DOCKET 50 .
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Oyster Creek Huclear Gansrating Station pocket No. 50-219 Page 3 The Diesel Generator (DG) building can be considered in the following units:
(1) The 18-inch thick reinforced concrete North and South walls (the short walls)
(2) The 18-inch thick reinforced concrete East and West walls (the long walls)
(3) The 18-inch thick reinforced concrete Diesel Oil Tank Compartment walls (similar to (1) above)
(4) The 12-inch thick precast concrete roof panels (5) The gratinQ covered intaka and exhaust roof openings (6) The exhaust stack opening Failure can come from one of four general modes:
(1) Entry of a missile through an opening (2) Penetration through a wall, roof slab, or grating (3) Scabbing of a concrete wall or roof slab (4) Structural failure of a wall, roof slab or grating II. FJNETRATOR MISSILES For the first category of missiles listed above (penet rator missiles Table III-1 of Ref. I shows impact frequencies as high as 4.6 x 10-5,)
but also reports that no scabbing or perforation damage occurred in the tornado missile simulations. The exhaust stack openings were entered by missiles at a frequency of 1.1 x 10~7, which is acceptably low. 'The penetrator type missiles are not considered to be capable of causing a structural type failure.
III. 21IkITY POLE MISSILES The second category of missiles (utility pole) is in Table III-1 of Reference 2 and in a GPUN calculation (Ref. 3). The table shows impact frequencies es high as 4.5 x 10-6, but no scabbing or perforation damage occurred in the tornado missile simulation. This probabilistic analysis did not consider structural typ3 failures, which are analyzed separately in the GPUN structural calculation.
'The structural calculation showed that the North and South walla of the DG building could withstand a utility pole missile carried by tornado winds of up to 240 mph, including the effect of the wind itself.
Depressurization (pressure drop) was not considered due to the large open areas of the bzilding. The 240 mph windspeed has a frequency of exceedence of approximately 1 x 10-6 per year as reported in Ref. 1 and approximately 5 x 10-7 per year in Ref. 4, which is a more realistic {
assessment. Based on this low frequency for the wind alone, the ut.lli.ty I pole impact on these wallo in conjunction with the wind han a very low, and clearly acceptable, frequency.
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1 Oyster Crssk Nuclear Gansrating Station Docket No. 50-219 Page 4 i
l This structural calculation applies equally well to the Diesel Oil Tank f compartment walls, which exe very similar to the North and South walls of j the DG building. l l
The diesel fuel supply lins (3 inch diameter) for the Diesel Oil Tank and )
a valve are installed outside the North wall of the Diesel Oil Tank I compartmer't. Most portions of the supply line is installed underground before re-sarfacing by the North wall. The line penetrates the wall at approximately a foot above the grade level. The target area (i.e., the line and the valve) is only a small fractior of the Diesel Generator <
Compartment and therefore, the probr5111ty of the target crea being hit by I a missile is expected to be well be aw lx10-6 per year. The fuel supply line passes through a six inch diameter penetration sleeve embedded in the North wall of the tank compartment. The penetration is sealed with fire proof foam. Consequently, if a missile impacts the North wall, the vib:atory effects of the wall will not impair the structural integrity of the fuel line, i I
The structural calculation showed that the East and West walls of the DG l building could withstand a utility pole missile carried by tornado winds )
oi up to 168 mph, including the effect of the wind itself. Pressure drop, ]
as discussed above, was not considered. The 168 mph wind has a frequency j of exceedence of approximately 2 x 10-5 per year as reported in Ref. 1 )
and approximately 7 x 10-6 per year in Ref. 4, which is a more realistic '
j assessment. The frequency of utility pole impacts on these walls in conjunction with the 168 mph or greater windepeed has a lower frequency than does the wind alone. Additionally, the frequency of missile impacts includes oblique impacts, which statistically are more common thcn impacts at 90' to the target, and which impart less energy to the target. Another SEP plant, Ginna, used 10-5 per year as the acceptance criteria for tornado wind protection, and on that basis this result would be acceptable i without further analysis. j l
9tility pole niissile impactn on the roof of the building have a very low frequency. The som of 'the impact frequencies on the gratings and exhaust openings (from Ref. 2) is approximately 3 x 10-7 Since these targets total about 1/4 of the total roof area, the total impact frequency would be approximately 1.2 x 10-6 For the roof, especially, impacts tend to i be at low angles (as described in Ref. 1, pages III-9 to 13). These obligae impacts impart less energy to the roof structure.
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. e Oyster Crock Nuclear Gansrating Station D,ocket No. 50-219 Page 5 IV. AUTOMOBILE MISSILES The third category of missiles listed above (the automobile missile) can be discussed most readily by reference to Table III-l of Ref. 1. Only targets numbered 1 and 2 (which include buildin were impacted at a frequency greater than 10~7.g Im units 1, 2 and 4 above) velocities (>57 mph) were rare, less than 2 X 10-8. pacts at higher Impacts at lower velocities are not expected to cause failure, especially when tha energy absorbing (deformation) characteristics of the automobile missile are considered. In addition, the impact frequency includes oblique impacts, which statistically are more common than impacts at 90" to the target, and which impart less energy'to the target.
Based on the above discussion we believe that the Diesel Generator Building at Oyster Creek Nuclear Generating Station is adequately protected from the postulated tornado generated missiles and tornado wind.
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- b. K. Croneberge Acting Director, Technical Functions cc Regional Administrator Region I U.S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406 Resident Inspector Oyster Creek Nuclear Generating Station Mr. Alex Dromerick U.S. Nuclear Regulatory Commission Mail Station Pl-137 Washington, DC 20555 l
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