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Category:CORRESPONDENCE-LETTERS
MONTHYEARML20217P0971999-10-20020 October 1999 Forwards Combustion Engineering Third Sample Event Rept in Conjunction with Hdrogeologic Investigation & Ground-Water, Soil & Stream Characterization, as Requested ML20217M1451999-10-19019 October 1999 Forwards Amend 29 to License SNM-33,allowing Requested Time Extension to Certain Commitments in Fundamental Nuclear Matl Control Plan Re Temporary Change to UF6 Receipt Sampling Procedure.Safeguards Evaluation Rept,Encl RA99-138, Forwards Eighth Status Rept on Criticality Safety Program Update (Cspu),Per Cspu Plan & Subsequent Revs. Rept Covers semi-annual Period from 990401-9909301999-10-0808 October 1999 Forwards Eighth Status Rept on Criticality Safety Program Update (Cspu),Per Cspu Plan & Subsequent Revs. Rept Covers semi-annual Period from 990401-990930 ML20212J0161999-09-29029 September 1999 Forwards Insp Rept 70-0036/99-04 on 990907-10.No Violations Noted ML20216E7441999-09-13013 September 1999 Grants six-month Extension of Time for Combustion Engineering to Further Develop & Refine in-situ Leaching (Isl) Process for Recovery of U from Soils Beneath Evaporation Ponds ML20212A8951999-09-10010 September 1999 Forwards Proprietary Updated Physical Security Plan for Protection of Special Nuclear Matl of Low Strategic Significance for ABB Combusting Engineering Nuclear Power, Inc,Hematite Facility,Per 10CFR73.67.Plan Withheld RA99-133, Forwards Third Sampling Event Rept in Conjunction with Hydrogeologic Investigation & Ground-Water,Soil & Stream Characterization. Ltr from Leggette,Brashears & Graham,Inc, Authorizing Reproduction of Repts,Encl1999-08-25025 August 1999 Forwards Third Sampling Event Rept in Conjunction with Hydrogeologic Investigation & Ground-Water,Soil & Stream Characterization. Ltr from Leggette,Brashears & Graham,Inc, Authorizing Reproduction of Repts,Encl ML20211B4291999-08-19019 August 1999 Forwards Amend 28 to License SNM-33,changing Name of Licensee to ABB Combustion Engineering Nuclear Power,Inc & Incorporating Date of 990618,for Decommissioning Financial Assurance.Ser Also Encl ML20210V0971999-08-18018 August 1999 Confirms Meeting Scheduled for 990915 at Licensee Facility in Festus,Missouri.Purpose of Meeting to Discuss Current Plant Performance,Future Plant Activities,Recent Insp Activities & Pond Decommissioning RA99-082, Provides Update on Status of ABB Cenp Former Evaporation Ponds Decommissioning & Planned Actions Regarding Same1999-08-13013 August 1999 Provides Update on Status of ABB Cenp Former Evaporation Ponds Decommissioning & Planned Actions Regarding Same RA99-129, Forwards License Application Pages Reflecting Recent Changes Made to Corporate Name.Ltr Replaces Entire 990729 Submittal1999-08-13013 August 1999 Forwards License Application Pages Reflecting Recent Changes Made to Corporate Name.Ltr Replaces Entire 990729 Submittal ML20210Q3781999-08-11011 August 1999 Forwards Insp Rept 70-0036/99-03 on 990803-04.No Violations Noted RA99-120, Forwards License Application Pages Affected by Corporate Name Change,Consistent with Amend 27 to License SNM-331999-07-29029 July 1999 Forwards License Application Pages Affected by Corporate Name Change,Consistent with Amend 27 to License SNM-33 ML20209B3031999-06-28028 June 1999 Ack Receipt of Transmitting Hydrogeologic Investigation & ground-water,soil & Stream Characterization & Ltr Transmitting Second Sampling Event Rept. Proposed Actions Appear Appropriate ML20195D3741999-06-0303 June 1999 Forwards Application for Amend to License SNM-33 to Transfer Combustion Engineering,Inc Assets & Liabilities Related to NRC Licensed Activities to Combustion Engineering Nuclear Power,Inc ML20195C9991999-06-0202 June 1999 Forwards License SNM-33,amend 26,allowing Time Extension for Distributing Result Repts for Apr 1999,physical Inventory.Temporary Safeguards License Condition SG-1.9,is Being Issued to Read as Listed,Effective Immediately RA99-099, Forwards Second Sampling Event Rept in Conjunction with Hydrogeologic Investigation & Ground-Water,Soil & Stream Characterization, Rept Developed After Second Quarter of Sampling Under CEs Hydrogeologic Work Plan1999-05-26026 May 1999 Forwards Second Sampling Event Rept in Conjunction with Hydrogeologic Investigation & Ground-Water,Soil & Stream Characterization, Rept Developed After Second Quarter of Sampling Under CEs Hydrogeologic Work Plan ML20207A6031999-05-21021 May 1999 Forwards Insp Rept 70-0036/99-02 on 990426-30.No Violations Noted RA99-093, Requests Extension of Time Periods for Submission of Annual Inventory Repts,As Required by Licensee Fundamental Nuclear Matl Plan & NUREG/BR-0007.NRC Forms 742C & 742 Will Be Submitted by 990604 & NRC Form 327 Submitted by 9907021999-05-20020 May 1999 Requests Extension of Time Periods for Submission of Annual Inventory Repts,As Required by Licensee Fundamental Nuclear Matl Plan & NUREG/BR-0007.NRC Forms 742C & 742 Will Be Submitted by 990604 & NRC Form 327 Submitted by 990702 ML20206U5701999-05-19019 May 1999 Confirms Cancellation of 990524 Meeting in Festus,Mo.Meeting Will Be Rescheduled in Future ML20196L2761999-05-19019 May 1999 Forwards Amend 25 to License SNM-33 & Ser.Amend Revised Fundamental Nuclear Matl Control Plan.Nrc Has Completed Review of Submitted Changes & Determined That Changes Do Not Decrease Effectiveness of MC&A Program ML20196L1391999-05-18018 May 1999 Forwards Partially Withheld Insp Rept 70-0036/99-203 Conducted on 990419-23.No Violations Noted.Major Areas Inspected:Mc&A Safeguards Program.Rept Details Withheld,Per 10CFR2.790(d) ML20196L2721999-05-18018 May 1999 Ack Receipt of ,Transmitting Copy of Semiannual Status Rept of C-E Criticality Safety Program Update Covering Period from 981001-990331 RA99-088, Provides Third Response to GL 98-03, NMSS Licensee & Certificate Holders Year 2000 Readiness. Licensee Has Upgraded Systems Having Safety or Safeguards Functions & Is Y2K Ready & Y2K Compliant1999-05-12012 May 1999 Provides Third Response to GL 98-03, NMSS Licensee & Certificate Holders Year 2000 Readiness. Licensee Has Upgraded Systems Having Safety or Safeguards Functions & Is Y2K Ready & Y2K Compliant ML20206G9341999-05-0303 May 1999 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Rept 70-0036/99-01 Issued on 990323 ML20206B0371999-04-26026 April 1999 Forwards Insp Rept 70-0036/99-202 on 990405-09.No Violations Noted RA99-074, Responds to NRC Re Violations Noted in Insp Rept 70-0036/99-01.Corrective Actions:Special Evaluation Traveler Was Implemented to Assure That Sys to Prevent Overfilling of UF6 Cold Trap Would Perform Intended Safety Function1999-04-22022 April 1999 Responds to NRC Re Violations Noted in Insp Rept 70-0036/99-01.Corrective Actions:Special Evaluation Traveler Was Implemented to Assure That Sys to Prevent Overfilling of UF6 Cold Trap Would Perform Intended Safety Function RA99-075, Forwards App A,Figure 10 from Hydrogeologic Investigation & Groundwater,Soil & Stream Characterization Rept.Figure Was Inadvertently Ommitted from Original Submission1999-04-21021 April 1999 Forwards App A,Figure 10 from Hydrogeologic Investigation & Groundwater,Soil & Stream Characterization Rept.Figure Was Inadvertently Ommitted from Original Submission ML20205R6161999-04-19019 April 1999 Confirms Meeting Scheduled for 990524 in Festus,Missouri to Discuss Current Plant Performance,Future Plant Activities, Recent Insp Activities & Progress of Nuclear Criticality Safety Upgrade Program ML20205P5241999-04-0909 April 1999 Forwards Amend 24 to License SNM-33,changing Mailing Addresses of Corporate Ofc & of Facility at Which Licensed Activity Will Be Conducted.Ser Also Encl RA99-068, Informs That Info Re Facility Has Been Reviewed & Verified, with Listed Discrepancies Noted,As Requested by NRC 990323 Fascimile1999-04-0707 April 1999 Informs That Info Re Facility Has Been Reviewed & Verified, with Listed Discrepancies Noted,As Requested by NRC 990323 Fascimile RA99-070, Forwards Criticality Safety Program Update Seventh Status Rept for Oct 1998 - Mar 1999. Next Rept Will Be Submitted by 9910071999-04-0707 April 1999 Forwards Criticality Safety Program Update Seventh Status Rept for Oct 1998 - Mar 1999. Next Rept Will Be Submitted by 991007 ML20204J2981999-03-23023 March 1999 Forwards Insp Rept 70-0036/99-01 on 990301-05 & NOV Re Failure to Implement Program,As Required,For Testing,Calibr & Insp of Component Defined by Integrated Sa/Hazard Analysis ML20205M4321999-03-18018 March 1999 Forwards Amend 23 to License SNM-33 & Ser.Amend Incorporates Changes Made to Emergency Plan.Safety Condition S-1 Revised to Include Date of 990115 ML20207M1231999-03-11011 March 1999 Informs That Encl Ltr Explains How NRC Plans to Institute Round Robin Sample Exchange Program Administered by Nbl for Verifying Quality of Licensee U Destructive Measurement Sys.Invoice FL0232-99 Encl RA99-045, Forwards Hydrogeologic Investigation & Ground-Water,Soil & Stream Characterization, Rept Developed After First Quarter of Sampling Under Hydrogeologic Work Plan Dtd 980428. Reproduction Release Authorization,Also Encl1999-03-0909 March 1999 Forwards Hydrogeologic Investigation & Ground-Water,Soil & Stream Characterization, Rept Developed After First Quarter of Sampling Under Hydrogeologic Work Plan Dtd 980428. Reproduction Release Authorization,Also Encl ML20207K2711999-03-0404 March 1999 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Rept 70-0036/98-204. Implementation of Corrective Actions Will Be Reviewed During Future Insps ML20206S5091999-02-0505 February 1999 Forwards Insp Rept 70-0036/99-201 on 990118-22.No Violations Noted.One Violation,Nine Inspector Followup Items & Two Unresolved Items Closed ML20203B2941999-01-27027 January 1999 Forwards Amend 22 to License SNM-33.Amend Allows Requested Time Extension to Certain Specified Commitments in Fundamental Nuclear Matl Control Plan.Safeguards Evaluation Rept,Encl ML20202B4791999-01-26026 January 1999 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Rept 70-0036/98-04 Issued on 981021.Response Indicated That Licensee Conducted Root Cause Analysis & Scheduled 990209 Meeting to Discuss Issues ML20202B5541999-01-26026 January 1999 Confirms Meeting Scheduled for 990209 in Lisle,Illinois to Discuss Recent Insp Findings on CE Assessment of Lapel Air Samples & Results of Root Cause Assessment & Procedure non-conformance ML20199G3851999-01-19019 January 1999 Forwards Partially Withheld Insp Rept 70-0036/98-204 on 981207-11 & Notice of Violation.Violations Noted.Rept Details Withheld (Ref 10CFR2.790) RA99-006, Forwards Revised Pages to Hematite Nuclear Fuel Mfg Facility Emergency Plan, Revising Sections 2.1.6 & 2.1.7 Re Postulated Fire & Explosion Incidents1999-01-15015 January 1999 Forwards Revised Pages to Hematite Nuclear Fuel Mfg Facility Emergency Plan, Revising Sections 2.1.6 & 2.1.7 Re Postulated Fire & Explosion Incidents RA99-005, Informs That CE Will Present follow-up Info in Response to Violations Noted in Insp Rept 70-0036/98-04,at Meeting with Region Iii.Licensee Has Conducted Root Cause Analysis of Causes That Lead to Violation & Reviewed DAs for 19981999-01-15015 January 1999 Informs That CE Will Present follow-up Info in Response to Violations Noted in Insp Rept 70-0036/98-04,at Meeting with Region Iii.Licensee Has Conducted Root Cause Analysis of Causes That Lead to Violation & Reviewed DAs for 1998 RA99-002, Requests Temporary Change to UF6 Receipt Sampling Procedure to Allow Drawing & Analyzing of UO2F2 Samples for Cylinders by 990401,as Discussed on 990107 with Tn Pham.Doe/Nrc Form 741, Nuclear Matl Transaction Rept Encl1999-01-0808 January 1999 Requests Temporary Change to UF6 Receipt Sampling Procedure to Allow Drawing & Analyzing of UO2F2 Samples for Cylinders by 990401,as Discussed on 990107 with Tn Pham.Doe/Nrc Form 741, Nuclear Matl Transaction Rept Encl ML20199D8761999-01-0404 January 1999 Requests Addl Info for Info Not Found During Review of Listed Licensing Documents.Nrc Is in Process of Preparing Rtm Suppl for Each Fc Facility,Per .Suppl Assist NRC Incident Response Staff as Emergency Assessment Tool RA98-836, Provides Response 2 to GL 98-03, NMSS Licensees & Certificate Holders Y2K Readiness1998-12-31031 December 1998 Provides Response 2 to GL 98-03, NMSS Licensees & Certificate Holders Y2K Readiness ML20198E8001998-12-18018 December 1998 Informs That NRC Received Ltr Dtd 981201,clarifying Intent of Section 4.2 of Hematite Evaporation Ponds Dcommissioning Plan ML20197H4111998-12-0707 December 1998 Discusses 981030 Meeting with Hematitle Fuel Operations & NRC at Region III Office Re General Plant Topics Which Included Part 70 Rulemaking & Nuclear Criticality Safety Program Updates ML20197G8621998-12-0101 December 1998 Informs of Licensee Determination That Uranium Is Present in Evaporation Pond at Depth of Sixteen Feet Below Ground Surface.Core Sampling Will Be Taken & Statistical Analysis Will Be Performed to Demonstrate Recommendation Criteria 1999-09-29
[Table view] Category:INCOMING CORRESPONDENCE
MONTHYEARML20217P0971999-10-20020 October 1999 Forwards Combustion Engineering Third Sample Event Rept in Conjunction with Hdrogeologic Investigation & Ground-Water, Soil & Stream Characterization, as Requested RA99-138, Forwards Eighth Status Rept on Criticality Safety Program Update (Cspu),Per Cspu Plan & Subsequent Revs. Rept Covers semi-annual Period from 990401-9909301999-10-0808 October 1999 Forwards Eighth Status Rept on Criticality Safety Program Update (Cspu),Per Cspu Plan & Subsequent Revs. Rept Covers semi-annual Period from 990401-990930 ML20212A8951999-09-10010 September 1999 Forwards Proprietary Updated Physical Security Plan for Protection of Special Nuclear Matl of Low Strategic Significance for ABB Combusting Engineering Nuclear Power, Inc,Hematite Facility,Per 10CFR73.67.Plan Withheld RA99-133, Forwards Third Sampling Event Rept in Conjunction with Hydrogeologic Investigation & Ground-Water,Soil & Stream Characterization. Ltr from Leggette,Brashears & Graham,Inc, Authorizing Reproduction of Repts,Encl1999-08-25025 August 1999 Forwards Third Sampling Event Rept in Conjunction with Hydrogeologic Investigation & Ground-Water,Soil & Stream Characterization. Ltr from Leggette,Brashears & Graham,Inc, Authorizing Reproduction of Repts,Encl RA99-082, Provides Update on Status of ABB Cenp Former Evaporation Ponds Decommissioning & Planned Actions Regarding Same1999-08-13013 August 1999 Provides Update on Status of ABB Cenp Former Evaporation Ponds Decommissioning & Planned Actions Regarding Same RA99-129, Forwards License Application Pages Reflecting Recent Changes Made to Corporate Name.Ltr Replaces Entire 990729 Submittal1999-08-13013 August 1999 Forwards License Application Pages Reflecting Recent Changes Made to Corporate Name.Ltr Replaces Entire 990729 Submittal RA99-120, Forwards License Application Pages Affected by Corporate Name Change,Consistent with Amend 27 to License SNM-331999-07-29029 July 1999 Forwards License Application Pages Affected by Corporate Name Change,Consistent with Amend 27 to License SNM-33 ML20195D3741999-06-0303 June 1999 Forwards Application for Amend to License SNM-33 to Transfer Combustion Engineering,Inc Assets & Liabilities Related to NRC Licensed Activities to Combustion Engineering Nuclear Power,Inc RA99-099, Forwards Second Sampling Event Rept in Conjunction with Hydrogeologic Investigation & Ground-Water,Soil & Stream Characterization, Rept Developed After Second Quarter of Sampling Under CEs Hydrogeologic Work Plan1999-05-26026 May 1999 Forwards Second Sampling Event Rept in Conjunction with Hydrogeologic Investigation & Ground-Water,Soil & Stream Characterization, Rept Developed After Second Quarter of Sampling Under CEs Hydrogeologic Work Plan RA99-093, Requests Extension of Time Periods for Submission of Annual Inventory Repts,As Required by Licensee Fundamental Nuclear Matl Plan & NUREG/BR-0007.NRC Forms 742C & 742 Will Be Submitted by 990604 & NRC Form 327 Submitted by 9907021999-05-20020 May 1999 Requests Extension of Time Periods for Submission of Annual Inventory Repts,As Required by Licensee Fundamental Nuclear Matl Plan & NUREG/BR-0007.NRC Forms 742C & 742 Will Be Submitted by 990604 & NRC Form 327 Submitted by 990702 RA99-088, Provides Third Response to GL 98-03, NMSS Licensee & Certificate Holders Year 2000 Readiness. Licensee Has Upgraded Systems Having Safety or Safeguards Functions & Is Y2K Ready & Y2K Compliant1999-05-12012 May 1999 Provides Third Response to GL 98-03, NMSS Licensee & Certificate Holders Year 2000 Readiness. Licensee Has Upgraded Systems Having Safety or Safeguards Functions & Is Y2K Ready & Y2K Compliant RA99-074, Responds to NRC Re Violations Noted in Insp Rept 70-0036/99-01.Corrective Actions:Special Evaluation Traveler Was Implemented to Assure That Sys to Prevent Overfilling of UF6 Cold Trap Would Perform Intended Safety Function1999-04-22022 April 1999 Responds to NRC Re Violations Noted in Insp Rept 70-0036/99-01.Corrective Actions:Special Evaluation Traveler Was Implemented to Assure That Sys to Prevent Overfilling of UF6 Cold Trap Would Perform Intended Safety Function RA99-075, Forwards App A,Figure 10 from Hydrogeologic Investigation & Groundwater,Soil & Stream Characterization Rept.Figure Was Inadvertently Ommitted from Original Submission1999-04-21021 April 1999 Forwards App A,Figure 10 from Hydrogeologic Investigation & Groundwater,Soil & Stream Characterization Rept.Figure Was Inadvertently Ommitted from Original Submission RA99-070, Forwards Criticality Safety Program Update Seventh Status Rept for Oct 1998 - Mar 1999. Next Rept Will Be Submitted by 9910071999-04-0707 April 1999 Forwards Criticality Safety Program Update Seventh Status Rept for Oct 1998 - Mar 1999. Next Rept Will Be Submitted by 991007 RA99-068, Informs That Info Re Facility Has Been Reviewed & Verified, with Listed Discrepancies Noted,As Requested by NRC 990323 Fascimile1999-04-0707 April 1999 Informs That Info Re Facility Has Been Reviewed & Verified, with Listed Discrepancies Noted,As Requested by NRC 990323 Fascimile RA99-045, Forwards Hydrogeologic Investigation & Ground-Water,Soil & Stream Characterization, Rept Developed After First Quarter of Sampling Under Hydrogeologic Work Plan Dtd 980428. Reproduction Release Authorization,Also Encl1999-03-0909 March 1999 Forwards Hydrogeologic Investigation & Ground-Water,Soil & Stream Characterization, Rept Developed After First Quarter of Sampling Under Hydrogeologic Work Plan Dtd 980428. Reproduction Release Authorization,Also Encl RA99-006, Forwards Revised Pages to Hematite Nuclear Fuel Mfg Facility Emergency Plan, Revising Sections 2.1.6 & 2.1.7 Re Postulated Fire & Explosion Incidents1999-01-15015 January 1999 Forwards Revised Pages to Hematite Nuclear Fuel Mfg Facility Emergency Plan, Revising Sections 2.1.6 & 2.1.7 Re Postulated Fire & Explosion Incidents RA99-005, Informs That CE Will Present follow-up Info in Response to Violations Noted in Insp Rept 70-0036/98-04,at Meeting with Region Iii.Licensee Has Conducted Root Cause Analysis of Causes That Lead to Violation & Reviewed DAs for 19981999-01-15015 January 1999 Informs That CE Will Present follow-up Info in Response to Violations Noted in Insp Rept 70-0036/98-04,at Meeting with Region Iii.Licensee Has Conducted Root Cause Analysis of Causes That Lead to Violation & Reviewed DAs for 1998 RA99-002, Requests Temporary Change to UF6 Receipt Sampling Procedure to Allow Drawing & Analyzing of UO2F2 Samples for Cylinders by 990401,as Discussed on 990107 with Tn Pham.Doe/Nrc Form 741, Nuclear Matl Transaction Rept Encl1999-01-0808 January 1999 Requests Temporary Change to UF6 Receipt Sampling Procedure to Allow Drawing & Analyzing of UO2F2 Samples for Cylinders by 990401,as Discussed on 990107 with Tn Pham.Doe/Nrc Form 741, Nuclear Matl Transaction Rept Encl RA98-836, Provides Response 2 to GL 98-03, NMSS Licensees & Certificate Holders Y2K Readiness1998-12-31031 December 1998 Provides Response 2 to GL 98-03, NMSS Licensees & Certificate Holders Y2K Readiness ML20197G8621998-12-0101 December 1998 Informs of Licensee Determination That Uranium Is Present in Evaporation Pond at Depth of Sixteen Feet Below Ground Surface.Core Sampling Will Be Taken & Statistical Analysis Will Be Performed to Demonstrate Recommendation Criteria RA98-826, Responds to NRC Re Violations Noted in Insp Rept 70-0036/98-04.Corrective Actions:Radiation Worker Refresher Training Was Conducted for Plant Operations Personnel & NCS Training Was Provided for Plant Personnel1998-11-20020 November 1998 Responds to NRC Re Violations Noted in Insp Rept 70-0036/98-04.Corrective Actions:Radiation Worker Refresher Training Was Conducted for Plant Operations Personnel & NCS Training Was Provided for Plant Personnel ML20155G7341998-11-0303 November 1998 Forwards Info Which Provides Missing Drawings & Replaces Other Drawings with Clarified Ones.Biennial Update to SNM-33 Demonstration Sections Inadvertently Omitted Figures at End of Chapter 14 RA98-817, Provides 10CFR70.50 Written Rept as follow-up to C-E 980925 Initial Rept to NRC Operations Ctr Re Yellowish Residue Noticed on Asphalt Driveway Between Bldg 230 & Bldg 240 on 980924.No Mfg Equipment Failed or Malfunctioned1998-10-23023 October 1998 Provides 10CFR70.50 Written Rept as follow-up to C-E 980925 Initial Rept to NRC Operations Ctr Re Yellowish Residue Noticed on Asphalt Driveway Between Bldg 230 & Bldg 240 on 980924.No Mfg Equipment Failed or Malfunctioned RA98-808, Provides Addl Info Requested by NRC Re C-E Response to Violations Noted in Insp Rept 70-0036/98-03,dtd 9807301998-10-0505 October 1998 Provides Addl Info Requested by NRC Re C-E Response to Violations Noted in Insp Rept 70-0036/98-03,dtd 980730 ML20154A5441998-09-28028 September 1998 Forwards Revised Safety Demonstration Sections to License Application.Editorial Changes & Corrections Have Also Been Made & Sections Have Been Repaginated ML20154B1291998-09-25025 September 1998 Forwards Criticality Safety Program Update Sixth Status Rept, for Period Mar-Sept 1998.Progress on Criticality Safety Program Update for Period Has Fallen Behind Schedule Due Primarily to Diversion of Resources ML20153G6751998-09-21021 September 1998 Provides Response to Request for Info Re Year 2000 Readiness for Licensees or Certificate Holders for UF6 Production Plants,U Enrichment Plants & U Fuel Fabrication Plants RA98-793, Confirms 980827 Telcon in Which NRC Agreed W/Licensee That Biennial Update of Demonstration Section of SNM-33 Will Be Submitted by 980928.Submittal Will Fulfill Requirements of License Condition 1.6(d)1998-08-28028 August 1998 Confirms 980827 Telcon in Which NRC Agreed W/Licensee That Biennial Update of Demonstration Section of SNM-33 Will Be Submitted by 980928.Submittal Will Fulfill Requirements of License Condition 1.6(d) ML20237E9001998-08-27027 August 1998 Responds to NRC Re Violations Noted in Insp Rept 70-0036/98-03.Corrective Actions:Weekly & Monthly Preventative Maint Checks Required by Procedure O.S.604.12 Incorporated Into Maint Work Order Sys ML20236W7281998-07-31031 July 1998 Responds to NRC Re Violations Noted in Insp Rept 70-0036/98-202.Corrective Actions:Updated Item Control Data Base by Deleting Items RA98-774, Forwards Revised Chapter 4, Nuclear Criticality Safety, as Suppl Info Requested During Telcon W/H Felsher of Nrc. Requested Changes Have Been Made to 980611 Version & Entire Chapter 4 Is Resubmitted W/Current Date1998-07-10010 July 1998 Forwards Revised Chapter 4, Nuclear Criticality Safety, as Suppl Info Requested During Telcon W/H Felsher of Nrc. Requested Changes Have Been Made to 980611 Version & Entire Chapter 4 Is Resubmitted W/Current Date RA98-755, Forwards Revised Chapter 4, Criticality Safety, as Addl Info Requested During Telcon W/H Felsher of Nrc.Addl Changes That Were Beyond Licensee Scope of First Submission Will Be Addressed in Future Submittal1998-06-11011 June 1998 Forwards Revised Chapter 4, Criticality Safety, as Addl Info Requested During Telcon W/H Felsher of Nrc.Addl Changes That Were Beyond Licensee Scope of First Submission Will Be Addressed in Future Submittal ML20248K3341998-06-0505 June 1998 Responds to NRC Re Violations Noted in Insp Rept 70-0036/98-01.Corrective Actions:Affected Clevis Pins Were Verified to Meet Lifting Requirements for Full UX-30 Overpacks ML20217Q0931998-04-28028 April 1998 Forwards Rev 1 to Hydrogeologic Investigation & Ground- Water/Surface Water Monitoring Work Plan for Combustion Engineering,Mo,Site, Which Was Presented at 970925 Meeting in Jefferson City,Mo RA98-708, Forwards Criticality Safety Program Update Fifth Status Rept 971001-980331 & Updated Gantt Chart,Per Agreement Contained in NRC1998-03-31031 March 1998 Forwards Criticality Safety Program Update Fifth Status Rept 971001-980331 & Updated Gantt Chart,Per Agreement Contained in NRC ML20212H2551998-03-27027 March 1998 Submits Response to Violations Noted in Unresolved Item Insp Rept 70-0036/97-204.Corrective Actions:Emergency Alarm Sys, Smoke Detectors,Heat Detectors & Associated Relays Serviced & Tested at Least Annually by Contractor ML20217E3581998-03-20020 March 1998 Forwards Response to 980219 RAI on Hydrogeologic Investigation & Groundwater Surface Water Monitoring Work Plan Submitted on 971021.Revised Work Plan Will Contain NRC & Missouri Dept of Natural Resources Comments ML20248L2681998-03-13013 March 1998 Responds to NRC Re Violations Noted in Insp Rept 70-0036/98-201.Corrective Actions:Suspended Fissile Aqueous Solution Transfers from Safe to Unsafe Geometry Vessels in Wet Recovery Sys & Will Revise Sampling Procedures ML20216H8411998-03-13013 March 1998 Responds to NRC Re Violations Noted in Insp Rept 70-0036/98-201.Corrective Actions:Fissile Aqueous Solution Transfers from Safe to Unsafe Geometry Vessels in Wet Recovery Sys Have Been Suspended ML20202G2861998-02-12012 February 1998 Provides Updated Listing of Individuals Authorized to Make License Commitments & Preferred Distribution of Correspondence from NRC ML20202B0881998-02-0606 February 1998 Forwards Response to 971125 Rai,Isa for Hydrofluoric Acid Absorber Sys,Slides Presented at 980115 Meeting W/Nrc & Engineering Drawings of Sys.Authorization to Release Hf for Unrestricted Use Requested by 980216 ML20199H9281998-01-30030 January 1998 Forwards Detailed Supplemental Info Re Criticality Safety of Hf Absorber Sys,Per 980120 Discussion ML20199J3551998-01-30030 January 1998 Forwards Response to 971103 RAI Re Licensee Application Requesting Rev to Chapter 4 of License SNM-33.Revised Chapter 4, Nuclear Criticality Safety, Pages,Encl ML20203L4911997-12-31031 December 1997 Submits Effluent Monitoring Data for Facilities Operated Under License SNM-33.Effluent Release Data Covers Period Jul-Dec 1997 ML20198C5091997-12-19019 December 1997 Forwards Responses to Questions Posed in Re Amend Request to Update Decommissioning Plan for Evaporation Ponds ML20198B3751997-12-19019 December 1997 Confirms Agreement to Make Presentation to NRC on 980113 Re Chemical Safety Questions on Hf Absorber Sys.Submission of Any Written Matl in Response to RAI Should Be Delayed Until After 980113 Meeting ML20203H2121997-12-0808 December 1997 Forwards Responses to Questions Posed in .Revised Dose Assessment for Proposed Release of Hf,Attached ML20203D5901997-12-0808 December 1997 Forwards Proprietary Sections 2-5 & 8 of Fundamental Nuclear Matl Control Plan, Supplementing 970613 Submittal for Amend & NRC Ltr .Enclosed Revised Sections Replace Previous Sections in Entirety.Encl Withheld ML20202E3951997-11-26026 November 1997 Requests Addl Time to Respond to RAI Re Chapter 4 of License SNM-33.Extension to 980131 Is Required to Provide Response to Forty Questions Re Chapter 4 of License 1999-09-10
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March 27,1998 Docket No. 70-3 License No. SNM-33 Director, Office of Nuclear Material Safety and Safeguards U.S. Nuclear Regulatory Commission Attn: Document Control Desk i
Washington, D.C. 20555
Subject:
Response to Unresolved Item 70-36/97-204-09 t
Gentlemen:
NRC Ileadquarters staff recently conducted a fire protection inspection at Combustion Engineering's Hematite, MO, nuclear fuel manufacturing facility. The report for that inspection, number 70-36/97-204 dated February 18,1998, establishes Unresolved Item (URI) 70-36/97-204-009 regarding potential performance weaknesses related to the implementation of l
commitments contained in Sections 2.1.6 and 2.1.7 of our Emergency Plan (EP). The report requests our response to the URI, specifically including: (1) identification of the extensive engineered safeguards used to control fire and explosion; (2) how those safeguards, including the fixed fire extinguishing equipment, are maintained available and reliable; (3) the identification of administrative controls for combustibles; (4) the performance of fire hazard inspections and audits, and; (5) actions taken or planned to assure that fire and life-safety issues receive prompt management review and timely disposition, including implementation of any compensatory measures needed to assure adequate safety until final corrective actions can be completed.
Enclosed is our response to the URI. Additional information is provided regarding our fire pump and combustible loading in the cantilever rack and filtrate storage areas. After closer review, it is clear that there was no impairment of the fire pump, and that storage in the cantilever rack and filtrate areas is consistent with NFPA recommendations.
We are in compliance with Section 2 of our EP. However, we recognize that improvements can be made, and we will submit changes to the EP regarding the extensive engineered controls. A schedule is provided in the enclosure. Fire safety improvements, both engineered and programmatic, have been ongoing for several years, and will continue. At this point, we have not identified areas where compensatory measures are warranted.
I 9804010236 980327 IT
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PDR ADOCK 07000036H C
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ABB CENO Fuel Operations Cornbushon Engineenng inc 33CO State Road P Telepnone (314) 937-469i Post Omce Box 107 St Lou >s (314) 2%5640 HemaMe. Mssoun ti3047 Fai (314) 937-7355
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I hereby affirm that the statements made in this response are true and correct to the best of my knowledge and belief. If you have any questions or need further information, please contact me or Kevin Ilayes of my staff at (314)937-4691.
Sincerely, COMBUSTION ENGINEERING, INC.
/ turok 27, /T 76 t
y Robert W. Sharkey Director, Regulatory Affairs cc:
Pat Ililand, NRC Region III Enclosures RA98/704
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Response to URI 70-36/97-204-09 Page 2 of 2
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' Combustion Engineering, Inc.
Docket 70-36
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License No. SNM-33 RESPONSE TO AN UNRESOLVED ITEM INSPECTION REPORT 70-36/97-204 (1) Identification Of The Extensive Engineered Safeguards Used To Control Fire And Explosion.
Sections 2.1.6 and 2.1.7 of the Emergency Plan (EP) provide a brief description of postulated fire or explosion incidents that potentially could release uranium to the atmosphere, and our engineered safeguards for those postulated accidents. The engineered safeguards described in Section 2.1.6 are used to prevent or mitigate the release of uranium from a minor fire, and include: (1) IIEPA filtered ventilation system in the buildings; (2) smoke detectors in the ventilation systems; (3) the size of the fuel fabrication buildings, and; (4) availability of fixed and portable fire extinguishing equipment.
The engineered safeguards described in Section 2.1.7 are used to prevent or mitigate a fire or explosion that could cause radioactive material to spread beyond the area of origin. Such an incident is postulated to require a large driving force, such as flammable solvents, flammable wastes, explosive liquids or gases, or other chemicals that support fires and/or explosions. Two postulated situations are evaluated in that section for the purpose of including events that would involve evacuating the facility. Based on existing safeguards described in the EP, the probability of either event actually occurring is considered remote. The first situation considered a major fire or explosion that destroys major portions of the facility, including HEPA ventilation systems. The primary source of such an explosion is identified as hydrogen. flydrogen is not stored on site, but is used as it is generated. In addition to those previously listed, the engineered safeguards to prevent or mitigate this scenario include: (5) flow controllers; (6) emergency cutoffs; (7) use of non-combustible and fire resistant material; (8) fire resistant filters; (9) infrared furnace pilot light monitors, and; (10) zonal heat rise detectors.
The second situation postulates a worst case explosion at a furnace after assuming that all precautionary steps fail. This includes failure of a passive engineered safeguard: (11) entrance and exit doors that are designed to relieve pressure in the event of an explosion. In this very conservative assumption, the maximum postulated dose to the nearest resident is projected to be 1.9 mrem. This is well below the annual operating limit of 100 mrem per year, or the i rem accident limit in 10 CFR 10.22(i)(1)(i).
Significant facility changes had recently been made at the time the EP was drafted. Many of those changes were directly related to upgraded fire safety, including the installation of a 200,000 gallon gravity dual-use water tank, a 1,500 gpm diesel fire pump, a 600 kW diesel emergency power generator, a replacement criticality alarm system, and a new emergency alarm system. When considering these and other improvements, by relative terms the safeguards are extensive. A submittal revising the sections referring to extensive engineered safeguards will be made to the NRC.
(2) llow Those Safeguards, Including The Fixed Fire Extinguishing Equipment, Are Maintained Available And Reliable.
Each of the engineered safeguards is maintained available and reliable in part by management of change. Change to the facility, its processes, and safety-related equipment requires management review and approval, including a review to determine whether fire safety evaluations are required. Significant changes require a Plant Safety Committee review, and may require review and approval by an authority having jurisdiction, such as the Jefferson County Building Commission, our insurer, and the NRC.
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Response to URI 70-36/97-204-09
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RA98/7(M, Page 1 of 5
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Combustion Engineering, Inc.
Docket 70-36 License No. SNM-33 j
Inspections and tests of engineered safeguards are periodically performed by employees and/or contractors. The fire pump, for example, is checked and started every week by maintenance personnel.
The fire pump and sprinkler systems are checked and tested quarterly by a fire system engineering and service contractor, who also performs our annual fire pump test. Our emergency alarm system, smoke detectors, heat detectors, and associated relays are serviced and tested at least annually by a contractor.
Fire prevention and protection issues are also an element of the quarterly facility inspections required by our License. Safeguard numbers 5,6,9, and 11 noted in item 1 of our response are specifically associated with our dewaxing and sintering furnaces. Operaiion of the furnaces is associated with operation of safeguards 5,6, and 9, i.e. the furnace will either shut down or will not cycle if the safeguards are not working. Their condition is checked during each operating shift by Operators and QC Technicians using written procedures.
(3) The Identification Of Administrative Controls For Combustibles.
Procedure NIS 215, Fire Protection, establishes a general requirement to minimize combustible loading at all times in any area. Procedure NIS 213, llazardous Materials Management, establishes limits on the storage of flammable liquids in the facility. Individual Operation Sheets may contain additional precautions that are specific to a process. The inspection report indicates that we have met the requirements of those procedures throughout the process areas, except for combustible loading in the incinerator room and a warehouse. We disagree with the findings regarding the warehouse, as described Items 7 and 8 of this response. Internal reviews had already identified opportunities to strengthen our procedures concerning fire safety, and we are in the process of revising those procedures at this time. Comments received from the NRC and other sources are being considered during the revision process. Additional controls will be based on applicable recommendations from integrated safety assessments in progress for the facility.
(4) The Performance Of Fire liazard Inspections And Audits.
We historically have considered the loss prevention surveys performed by our fire insurer to constitute an audit. Our perspective was reinforced by the broad scope of their activities, and the fact that they frequently went beyond the scope of national consensus standards. Each recommendation or concern erablished as a result of those audits was subject to management review and response. The status of each item was then updated in subsequent audits. We should note that we recently changed insurance providers. Our new insurer has concluded that there are no fire protection issues which they believe require corrective action. This effectively closes any open or contended issues from our former insurer. An audit of the facility was also conducted this past February by a certified fire marshal. A schedule that explicitly includes such audits has been generated as part of our self assessment program.
Facility condition and fire protection equipment operability inspections are periodically performed by employees and/or contractors. Our quarterly inspection report, for example, includes information regarding sprinkler flow alarm tests, tamper switch tests, inspections of sprinkler and control valves, inspection of hydrants, and fire pump operability. As we continue to revise our self assessment program, we have drafted maintenance and llealth Physics procedures that more formally document these inspection activities.
Response to URI 70-36/97-204-09 RA98/7N, Page 2 of 5
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Combustion Engineering, Inc.
Docket 70-36 License No. SNM-33 (5) Acti,ons Taken Or Planned To Assure That Fire And Life-Safety Issues Receive Prompt Management Review And Timely Disposition, Including Implementation Of Any Compensatory Measures Needed To Assure Adequate Safety Until Final Corrective Actions Can Be Completed.
Issues related to external sources or agencies are tracked in the Regulatory Affairs Commitment Tracking Database. External feedback typically comes to management attention through exit meetings, inspection or audit reports, and review of existing commitments. Issues resulting from internal activities, such as safety committees and quarterly inspections, are tracked in the minutes or reports associated with those activities. Those documents are distributed for management information and consideration. The facility is also subject to constant surveillance by Regulatory Affairs personnel, from which any problems are communicated to the cognizant professional (s) for evaluation and action.
Issues requiring compensatory measures or corrective action are brought to raanagement's attention.
We are not aware of any fire or life-safety issues requiring compensatory measures at this time.
SUPPLEMENTAL INFORMATION REGARDING TIIE SITE FIRE PUMP AND WAREIIOUSE SPRINKLER SYSTEM INSPECTION REPORT 70-36/97-204 (6) Impairment Of The Site Fire Pump, IFI 70-36/97-204-05.
This item is established to track alleged failure to promptly address potential degradation of the site's fire pump, or to prov'ide appropriate compensatory measures during the seven months of that alleged degradation. The basis for this allegation is a pump test on September 26,1996, that was aborted when the diesel engine overheated during the 150% run. The report states that this problem was not abated, and that its cause was not identified, until a subsequent pump test on April 11, 1997.
The pump coolant inlet strainers were promptly checked by the inspector from our service contractor when the diesel engine overheated during the September test. The inspector found that pebbles had obstructed the strainers. He removed the pebbles, then restarted and monitored the pump to ensure that the problem was eliminated. The inspector believed that the pebbles came from a break that occurred years earlier during installation of the 10-inch pipe from our gravity tank. Review of our weekly test and quarterly inspection records shows that no further coolant flow problems were encountered during the period of alleged degradation. The fire pump and backflow preventers were dismantled and checked in April, and the second pump test was successfully performed. Only one pebble was found in, and removed from, an outer vane of the pump impeller. No actual damage was found in the pump or check valves.
The fire pump was not impaired for seven months as alleged in the inspection report. The cause of the September overheating problem was immediately identified and corrected. The effectiveness of the corrective action was successfully tested, and was subject to frequent surveillance. Compensatory measures were therefore not required between these pump tests.
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Response to URI 70-36/97-204-09 RA98/704, Page 3 of 5
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Combustion Engineering, Inc.
Docket 70-36 o
License No. SNM-33 (7) Maintenance Of Warehouse Sprinkler System Design Criteria, IFI 70-36/97-204-03.
This item relates to the inspector's concern that storage and rack configuration exceeds a sprinkler j
system's design criteria for a maximum height of 12 feet. We conclude that the report is referring to I
our cantilever rack in the Building 230 warehouse, where the storage height is typically up to 15 feet.
The top cantilever of the rack is approximately 12 feet high. The rack has been used in this manner since the building opened in 1993. Storage height in the rest of the facility is at or below 12 feet.
The sprinkler system in question was designed to conform with Ordinary llazard Group 3 of NFPA 13, I
Standard for the Installation of Sprinkler Systems,1989 Edition. Within that standard, the design basis assigns a general storage height limit of 12 feet. The cantilever rack represents a specific hazard because it clearly exceeds the general storage height limit. NFPA 231C, Standard for Rack Storage of Materials, which is referenced in NFPA 13, is the standard that must be used to determine whether the rack's configuration is within the design criteria of the existing sprinkler system.
Our storage rack is a double-row rack as defined by NFPA 213C,1995 Edition. The nature of the material being stored on it, usually boxes of empty fuel rod tubing, meets the definition for non-encapsulated Commodity Class 11. There are 8-foot aisles on three sides of the rack; the fourth side abuts the building wall. The sprinkler system in question uses 165 F heads only at the ceiling; in-rack sprinklers are not provided. Review of Chapter 6 and Table 6-12 (see Enclosure 2) reveals that the required ceiling sprinkler density for this configuration can be detennined by using Figure 6-12(b),
2 2
Curve F (see Enclosure 2). That curve specifies a density of 0.37 gpm/ft over the 2,100 ft or application affected by the rack. That density may be modified in accordance with Figure 6-9.2 (see ) to reDect actual storage heights. A 40% reduction in density is allowed for storage of up to 15 feet, which is our practice. Thus, the sprinkler design criteria for the cantilever storage rack is 2
2 0.22 gpm/ ft over 2,100 ft, which equates to a demand of 470 gpm at the sprinkler riser.
Flow tests on February 24 and 25,1998, demonstrated an available flow of 790 gpm at the Building 230 sprinkler riser with the fire pump bypassed (impaired), and 1,680 gpm with the fire pump running.
Under NFPA 231C, the existing sprinkler configuration and available flow under normal conditions i
would allow a storage height of up to 20 feet. This clearly demonstrates that the cantilever rack's fire load is well within the capability of the existing sprinkler system, the design criteria of which has not been exceeded.
(8) Storage of Filtrates, IFI 70-36/97-204-07.
The context of the inspection report indicates a misconception that a problem with coverage by the cantilever rack means that coverage for other areas, specifically the filtrate storage area, is reduced.
This premise could be true only if the system were designed to operate in the deluge mode, which it is not. Furthermore, the cantilever rack and filtrate storage areas are separated by approximately 100 feet The inspection report makes no mention of any concenu with combustible matenal storage within that separation. There is no credible accidental ignition source in the warehouse that could cause concurrent and widely separated points of fire origin, and there is no requirement to consider that scenario for this occupancy. These areas are considered remote to each other for the purpose of designing sprinkler coverage, which is adequate for the occupancy.
Enclosure i Response to URI 70-36/97-204-09 RA98/704, Page 4 of 5
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Combustion Engineering, Inc.
Docket 70-36 License No. SNM-33 (9) Schedule 0,f Actions
- A revision of the EP sections discussed in item I will be submitted to the NRC by August,1998.
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The procedural revision process discussed in Items 3 and 4 will be complete by May,1998.
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i integrated Safety Assessments discussed in item 3 have been scheduled in correspondence to the NRC i
- on October 23,1996. Fire safety is an element of these assessments.
i Response to URI 70-36/97-204-09 RA98/704, Page 5 of 5
r-Colnbustion Engineering, Inc.
Docket 70-36 License No. SNM-33 cciu=f Prinkler WWer Demiand N
y,g, (ft)
Sprinklers With In. Rack Sprinklere without lo-Rack Sprinklers Ceaunoslity Emcap.
(4 4,1)
Mandatory Apply Fig.
Apply Fig.
licight Class sulasesi (54 11.2)
In Rack Fig.
Curves 69.2 Fig.
Curves 6-9.2 No 4
No 412(a)
C&D 6-12(a)
G&ll Yes 8
A&B E&F Yes 4
No 012(e)
C&l) 612(c)
G&ll Yes 4:
8 AkB F&F No 4
No 612(b)
C&D 6-12(b)
G&H Yes j
,y g
8 A&ll E&F c5 Yes 4
No 6-12(c)
C&D 612(e)
G&H Yes E.8 j H
A&ll E&F b:
No 4
No li-12(c)
C&D 412k) G&ll Yes al 8
A&B E&F j
Yes 4
1 Level ti.12(f)
CkD a
8 A&B R
No 4
No 612(d)
C&D 612(d) G&ll Yes 8
AkB E&F
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Yes 4
I Irvel 6 12(g)
C&D H
A&ll No 4
No 6-12(a)
C&D 6-12(a)
G&ll Yes H
A&ll E&F g
Yes i
l inel 6-12(c)
C&D e
8 A&Il y
No 4
No 412(b)
C&D G 12(b)
G&ll Yes 8
A&B E&F y
g
i Level 6 12(e)
C&D 8
No 4
No 6-12(c)
C&D 6-12(c)
G&li Yes 8
Akil gg C~
$j 8
Akil 1.& F g,
3 Yes 4
I l o ci 612(!)
C&D
_E H
A&ll No 4
No 6-12(d)
C&D 412(d)
G&H Yes H
A&ll E&f g g, Yes 4
1 1.evel fi-12(g)
C&D 8
A&B No 4
No fi-12(a)
C&D 6-12(a)
Gkil Yes 8
A&B F&F Yes 4
1 inel 6-12(e)
C&D e
8 A&B p)
No 4
No 612(b)
C&D lbl2(b)
G&H Yes 8
A&ll E&F
,y g
=9 Yes 4
11.evel 612(c)
C&D N
M A&Il gg t-No 4
No 6-12(c)
CAD 6-12(c)
G&li Yes 6}
8 A&B E&F g
e Yes 4
1 Leel 612(D C&D E
8 A&B 1
No-4-
6-12(d)
C&D 8
TkB
"'I Yes 4
612(g)
C&D 8
Akil Foi Et umsw I h o.sotti ai Table 6-12 Single-or Double-Row Racks. Storage lleight up to and including 25 ft, Aisles Wider than 4 ft, without Solid Shelves.
Response to URI 70-36/97-2N-09 RA98/7M, Page 1 of 2
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4 Combustion Engineering, Inc.
Docket 70-36 License No. SNM-33 a
Curve lagend Curve L.mgand Ceiing spnn>Jer dansay(Utnin)/m 4.1 61 81 10 2 122 14 3 16 3 18.3 20 4 A-Single-or double ow rechs F - Sergie.or doublem sacks g
wrth 49 (2 44 m) asles weh 8 9 (2.44-m) asles wah IB61 (141%)
and 2861 (141*C) coding A.
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a Cahng spriniderdensay(gpm/ff )
m rack sprmklers.
cedmg sprinWers Figure 6-12(b) Sprinkler system design curves ft (6.1-m) high rack storage - Class Il nonencapsulated commodities - conventional pallets He@t Of alorace (m) 3.66 3.05 4 57 6.10 7.62 9.14 10.67 o
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10 12 15' 20 25 30 35 HeightOf storage (ft)
Figure 6-9.2 Ceiling sprinkler density vs. storage height Response to URI 70-36/97-204-09 RA98/704, Page 2 of 2