Letter Sequence Response to RAI |
---|
|
|
|
|
---|
Category:CORRESPONDENCE-LETTERS
MONTHYEARLIC-99-0098, Forwards Revs to Fort Calhoun Station EPIPs & Emergency Planning Forms Manual.Document Update Instructions & Summary of Changes Are Included on Confirmation of Transmittal Form Attached1999-10-15015 October 1999 Forwards Revs to Fort Calhoun Station EPIPs & Emergency Planning Forms Manual.Document Update Instructions & Summary of Changes Are Included on Confirmation of Transmittal Form Attached ML20217G9261999-10-15015 October 1999 Forwards Insp Rept 50-285/99-10 on 990913-17.One NCV Noted ML20217G2331999-10-14014 October 1999 Forwards Insp Rept 50-285/99-09 on 990913-17.No Violations Noted LIC-99-0091, Submits Suppl Response to GL 99-02, Laboratory Testing of Nuclear-Grade Activated Charcoal, in Response to NRC RAI During 990817 Meeting with Util1999-10-0808 October 1999 Submits Suppl Response to GL 99-02, Laboratory Testing of Nuclear-Grade Activated Charcoal, in Response to NRC RAI During 990817 Meeting with Util LIC-99-0097, Forwards Final RO & SRO License Applications,As Requested in ,Certifying That Training Completed for Six RO Candidates,Three Instant SRO Candidates & One Upgrade SRO Candidate.Without Encls1999-10-0707 October 1999 Forwards Final RO & SRO License Applications,As Requested in ,Certifying That Training Completed for Six RO Candidates,Three Instant SRO Candidates & One Upgrade SRO Candidate.Without Encls ML20217B5111999-10-0606 October 1999 Forwards Amend 193 to License DPR-40 & Safety Evaluation. Amend Revises TS Sections 2.10.4,3.1 & Table 3-3 to Increase Min Required RCS Flow Rate & Change Surveillance require- Ments for RCS Flow Rate ML20216H7231999-09-29029 September 1999 Informs That Util 980325 Response to GL 97-06, Degradation of SG Internals, Provides Reasonable Assurance That Condition of Util SG Internals in Compliance with Current Licensing Bases for Fort Calhoun Station,Unit 1 ML20212L9571999-09-27027 September 1999 Informs That Follow Up Insp for Drill/Exercise Performance Indicator Will Be Conducted During Wk of 991001 LIC-99-0089, Forwards Preliminary License Exam Applications for Six Ros, Three Instant SROs & One Upgrade SRO Candidate,Per Preparation for Ro/Sro Licensing Exams to Be Administered on 991025-29 at Fcs.Without Encl1999-09-24024 September 1999 Forwards Preliminary License Exam Applications for Six Ros, Three Instant SROs & One Upgrade SRO Candidate,Per Preparation for Ro/Sro Licensing Exams to Be Administered on 991025-29 at Fcs.Without Encl LIC-99-0092, Forwards Revised Epips,Including non-proprietary Rev 8 to EPIP-RR-66,rev 3 to EPIP-EOF-24,rev 14 to RERP-Section F,Rev 11 to RERP-Section I,Rev 12 to RERP-Appendix C & RERP & EPIP Indexes.Proprietary Rev 3 to EPIP-EOF-24,pages 1-3,encl1999-09-21021 September 1999 Forwards Revised Epips,Including non-proprietary Rev 8 to EPIP-RR-66,rev 3 to EPIP-EOF-24,rev 14 to RERP-Section F,Rev 11 to RERP-Section I,Rev 12 to RERP-Appendix C & RERP & EPIP Indexes.Proprietary Rev 3 to EPIP-EOF-24,pages 1-3,encl LIC-99-0087, Forwards Response to NRC Administrative Ltr 99-03, Preparation & Scheduling of Operator Licensing Exams1999-09-17017 September 1999 Forwards Response to NRC Administrative Ltr 99-03, Preparation & Scheduling of Operator Licensing Exams LIC-99-0088, Forwards Documentation Associated with SRO License Renewal Application for Cd Darrow.Applicant Has Satisfactorily Completed Applicable FCS Requalification Program.Without Encls1999-09-16016 September 1999 Forwards Documentation Associated with SRO License Renewal Application for Cd Darrow.Applicant Has Satisfactorily Completed Applicable FCS Requalification Program.Without Encls LIC-99-0080, Requests Approval of Attached Rev to QAP Contained in App a of Usar,Revising Commitment Re Qualifications of Personnel Performing Quality Control Insps of Activities Affecting Fire Protection1999-09-16016 September 1999 Requests Approval of Attached Rev to QAP Contained in App a of Usar,Revising Commitment Re Qualifications of Personnel Performing Quality Control Insps of Activities Affecting Fire Protection LIC-99-0085, Forwards Revs 18 & 19 to TDB-VI, COLR for FCS Unit 1,IAW TS 5.9.5.Rev 18 Resulted from Reevaluation of Cycle 18 Setpoints & Rev 19 Resulted from Changes in Cycle 19 Refueling Boron Concentrations & Addition of TS Parameters1999-09-0808 September 1999 Forwards Revs 18 & 19 to TDB-VI, COLR for FCS Unit 1,IAW TS 5.9.5.Rev 18 Resulted from Reevaluation of Cycle 18 Setpoints & Rev 19 Resulted from Changes in Cycle 19 Refueling Boron Concentrations & Addition of TS Parameters IR 05000285/19990081999-09-0707 September 1999 Forwards Insp Rept 50-285/99-08 on 990907-0811.No Violations Noted.Insp Consisted of Exam of Activities Conducted Under License as Relate to Safety & to Compliance with Commission Rules & Regulations & with Conditions of License ML20211P2581999-09-0303 September 1999 Forwards Insp Rept 50-285/99-06 on 990809-12.No Violations Noted.Insp Consisted of Exam of Activities Under License as Related to EP & to Compliance with Commission Rules & Regulations & with Conditions of License LIC-99-0083, Requests Participation in internet-based Y2K Early Warning Sys (Yews),As Noted in NRC Info Notice 99-25.Plant Point of Contact Will Be JW Chase1999-09-0202 September 1999 Requests Participation in internet-based Y2K Early Warning Sys (Yews),As Noted in NRC Info Notice 99-25.Plant Point of Contact Will Be JW Chase ML20211J9231999-09-0202 September 1999 Forwards SE Accepting Licensee 990301 Requests for Relief Re Third 10-year ISI Interval for Plant,Unit 1.Relief Proposed Alternatives to Requirements in ASME B&PV Section XI,1989 Edition,Paragraphs IWA-5242(a) & IWA-5250(a)(2) ML20211L3241999-09-0202 September 1999 Informs That Due to Administrative Error,Page 2-50 of TSs Contained Error on 2.10.2(2) of Amend 192 to License DPR-40 Issued on 990727.Corrected Page Encl LIC-99-0077, Forwards non-proprietary & Proprietary Revised EP Forms, Including FC-EPF Index,Pp 1 Dtd 990805,pp 2 Dtd 990812,rev 11 to FC-EPF-9,rev 12 to FC-EPF-10,rev 9 to FC-EPF-11,rev 2 to FC-EPF-12 & Rev 3 to FC-EPF-38.Proprietary EP Withheld1999-08-27027 August 1999 Forwards non-proprietary & Proprietary Revised EP Forms, Including FC-EPF Index,Pp 1 Dtd 990805,pp 2 Dtd 990812,rev 11 to FC-EPF-9,rev 12 to FC-EPF-10,rev 9 to FC-EPF-11,rev 2 to FC-EPF-12 & Rev 3 to FC-EPF-38.Proprietary EP Withheld ML20211F4491999-08-25025 August 1999 Forwards Ltr from Ja Miller,Dtd 990819,which Notified State of Iowa of Deficiency Identified During 990810,Fort Calhoun Station Biennial Exercise.One Deficiency Identified for Not Adequately Demonstrating Organizational Capability LIC-99-0076, Forwards fitness-for-duty Program Performance Data for Six Month Period from Jan-June 1999,IAW 10CFR26.71(d)1999-08-20020 August 1999 Forwards fitness-for-duty Program Performance Data for Six Month Period from Jan-June 1999,IAW 10CFR26.71(d) LIC-99-0078, Forwards Rev 16C to FCS Site Security Plan,Per Provisions of 10CFR50.54(p).Rev Has Been Determined Not to Degrade Effectiveness of Current Security Plans.List of Changes, Provided.Encl Withheld1999-08-20020 August 1999 Forwards Rev 16C to FCS Site Security Plan,Per Provisions of 10CFR50.54(p).Rev Has Been Determined Not to Degrade Effectiveness of Current Security Plans.List of Changes, Provided.Encl Withheld ML20210R1491999-08-13013 August 1999 Forwards Insp Rept 50-285/99-07 on 990719-23.No Violations Noted.Nrc Identified One Issue Which Was Evaluated Under Risk Significance Determination Process & Was Determined to Be of Low Risk Significance LIC-99-0075, Forwards Monthly Operating Rept for July 1999 for Fcs,Unit 1,per Plant TS 5.9.1.Revised Rept for June 1999,encl Due to Inadvertent Reporting of Gross Electrical Energy Data When Net Electrical Energy Data Was Required1999-08-13013 August 1999 Forwards Monthly Operating Rept for July 1999 for Fcs,Unit 1,per Plant TS 5.9.1.Revised Rept for June 1999,encl Due to Inadvertent Reporting of Gross Electrical Energy Data When Net Electrical Energy Data Was Required ML20211A9501999-08-12012 August 1999 Discusses 990720-21 Workshop Conducted in Region IV Ofc,Re Exchange of Info in Area of Use of Risk Insights in Regulatory Activities.List of Attendees,Summary of Topic & Issues,Agenda & Copies of Handouts Encl ML20211B7881999-08-10010 August 1999 Transmits Summary of Two Meetings with Risk-Informed TS Task Force in Rockville,Md on 990514 & 0714 ML20210N1991999-08-0909 August 1999 Informs That as Result of NRC Review of Licensee Responses to GL 92-01,rev 1,suppl 1 & Suppl 1 Rai,Staff Revised Info in Reactor Vessel Integrity Database & Releasing Database as Rvid Version 2 ML20210P8991999-08-0909 August 1999 Forwards FEMA Final Rept for 990630 Offsite Medical Drill. No Deficiencies or Areas Requiring Corrective Action Identified During Drill LIC-99-0072, Requests That Licensee 990526 Application for Amend & Related Documents,Be Withdrawn.Util Requests That NRC Review Attached Responses to Ensure That Upcoming Submittal Will Be Acceptable1999-08-0606 August 1999 Requests That Licensee 990526 Application for Amend & Related Documents,Be Withdrawn.Util Requests That NRC Review Attached Responses to Ensure That Upcoming Submittal Will Be Acceptable ML20210L1461999-08-0303 August 1999 Informs That NRC Plans to Administer Gfes of Written Operator Licensing Exam on 991006.Requests Submittal of Ltr Identifying Individuals Taking Exam,Personnel Allowed Access to Exams & Mailing Address for Exams LIC-99-0068, Documents OPPD Response to Requested Actions in GL 99-02, Laboratory Testing of Nuclear-Grade Activated Charcoal1999-08-0202 August 1999 Documents OPPD Response to Requested Actions in GL 99-02, Laboratory Testing of Nuclear-Grade Activated Charcoal LIC-99-0040, Forwards Rept of Changes,Tests & Experiments Performed Per 10CFR50.59 & Revs to USAR Other than Those Resulting from 10CFR50.59.Encl Info Covers Period of 981101-9903311999-07-28028 July 1999 Forwards Rept of Changes,Tests & Experiments Performed Per 10CFR50.59 & Revs to USAR Other than Those Resulting from 10CFR50.59.Encl Info Covers Period of 981101-990331 LIC-99-0070, Requests Reinstatement of SRO License Previously Held by K Grant-Leanna (License SOP-43569).Operator Is Current on All requalification-training Topics & Has Completed License Reactivation Program1999-07-28028 July 1999 Requests Reinstatement of SRO License Previously Held by K Grant-Leanna (License SOP-43569).Operator Is Current on All requalification-training Topics & Has Completed License Reactivation Program ML20210G1851999-07-27027 July 1999 Forwards Amend 192 to License DPR-40 & Safety Evaluation. Amend Consists of Changes to TS in Response to 990129 Application LIC-99-0057, Forwards 1999/2000 Statement of Cash Flow from Operations, as Guarantee of Payment of Deferred Premiums for Period of 990630 to 0006301999-07-26026 July 1999 Forwards 1999/2000 Statement of Cash Flow from Operations, as Guarantee of Payment of Deferred Premiums for Period of 990630 to 000630 ML20216D6951999-07-26026 July 1999 Informs That During 990614 Review of Fort Calhoun,Nrc Noted That Drill/Exercise Performance Indicator Has Entered White Band,Which Indicated Level of Licensee Performance That Warranted Increased Regulatory Response LIC-99-0071, Informs That Util Expects to Submit Four Licensing Actions in Each of Fys 2000 & 2001,in Response to Administrative Ltr 99-02, Operating Reactor Licensing Action Estimates1999-07-26026 July 1999 Informs That Util Expects to Submit Four Licensing Actions in Each of Fys 2000 & 2001,in Response to Administrative Ltr 99-02, Operating Reactor Licensing Action Estimates LIC-99-0069, Forwards non-proprietary & Proprietary Epips,Including FC- Epf Index Page & Page 2 ,rev 0 to FC- EPF-42,EPIP Index (Page 1 of 2) & EPIP-OSC-2, Cover & Pages 19 & 20.Proprietary Encls Withheld1999-07-23023 July 1999 Forwards non-proprietary & Proprietary Epips,Including FC- Epf Index Page & Page 2 ,rev 0 to FC- EPF-42,EPIP Index (Page 1 of 2) & EPIP-OSC-2, Cover & Pages 19 & 20.Proprietary Encls Withheld ML20210D9471999-07-22022 July 1999 Forwards Amend 191 to DPR-40 & Safety Evaluation.Amend Authorizes Rev to Licensing Basis as Described in Updated Safety Analysis Rept to Incorporate Mod for Overriding Containment Isolation ML20210C2041999-07-20020 July 1999 Discusses 990715 Mgt Meeting with Midamerican Energy Co Re risk-informed Baseline Insp Program Recently Implemented at Cooper & Fort Calhoun Stations ML20210C0201999-07-20020 July 1999 Informs That Due to Administrative Oversight,Revised TS Bases Provided in to Fort Calhoun Station Were Not Dated.Dated Pages to TS Encl ML20210B0761999-07-19019 July 1999 Forwards Insp Rept 50-285/99-05 on 990601-0710.No Violations Noted ML20209G5351999-07-15015 July 1999 Informs That Staff Incorporated Rev of TS Bases Provided by Licensee Ltr Dtd 980904,into Fort Calhoun Station Tss. Staff Finds Revs to Associated TS Bases to Be Acceptable. Revised Bases Pages Encl ML20209F5741999-07-12012 July 1999 Ack Receipt of Transmitting Exercise Scenario for Upcoming Biennial Offsite Exercise Scheduled 990810.Scenario Reviewed & Acceptable ML20209G5591999-07-0808 July 1999 Forwards Detailed Listing of Staff Concerns with C-E TR NPSD-683,rev 3 & RCS pressure-temperature Limits Rept LIC-99-0066, Forwards Fort Calhoun Performance Indicators Rept for May 19991999-07-0707 July 1999 Forwards Fort Calhoun Performance Indicators Rept for May 1999 LIC-99-0060, Forwards Proprietary & non-proprietary Revs to Fort Calhoun Station Emergency Plan Forms (Epf),Including FC-EPF,FC-EPF-1 & FC-EPF-17.Proprietary Info Withheld1999-07-0101 July 1999 Forwards Proprietary & non-proprietary Revs to Fort Calhoun Station Emergency Plan Forms (Epf),Including FC-EPF,FC-EPF-1 & FC-EPF-17.Proprietary Info Withheld ML20209D8771999-07-0101 July 1999 Summarizes 990630 Public Meeting Conducted in Fort Calhoun, Ne Re Results of Completed Culture Survey,Plant Status, Facility Activities Re New NRC Oversight Process & License Renewal.Licensee Handout & Attendance List Encl LIC-99-0063, Requests Termination of License Held by MR Anderson (License SOP 43812) for Fort Calhoun Station.Anderson Ended Employment Effective 9906241999-07-0101 July 1999 Requests Termination of License Held by MR Anderson (License SOP 43812) for Fort Calhoun Station.Anderson Ended Employment Effective 990624 1999-09-08
[Table view] Category:INCOMING CORRESPONDENCE
MONTHYEARLIC-99-0098, Forwards Revs to Fort Calhoun Station EPIPs & Emergency Planning Forms Manual.Document Update Instructions & Summary of Changes Are Included on Confirmation of Transmittal Form Attached1999-10-15015 October 1999 Forwards Revs to Fort Calhoun Station EPIPs & Emergency Planning Forms Manual.Document Update Instructions & Summary of Changes Are Included on Confirmation of Transmittal Form Attached LIC-99-0091, Submits Suppl Response to GL 99-02, Laboratory Testing of Nuclear-Grade Activated Charcoal, in Response to NRC RAI During 990817 Meeting with Util1999-10-0808 October 1999 Submits Suppl Response to GL 99-02, Laboratory Testing of Nuclear-Grade Activated Charcoal, in Response to NRC RAI During 990817 Meeting with Util LIC-99-0097, Forwards Final RO & SRO License Applications,As Requested in ,Certifying That Training Completed for Six RO Candidates,Three Instant SRO Candidates & One Upgrade SRO Candidate.Without Encls1999-10-0707 October 1999 Forwards Final RO & SRO License Applications,As Requested in ,Certifying That Training Completed for Six RO Candidates,Three Instant SRO Candidates & One Upgrade SRO Candidate.Without Encls LIC-99-0089, Forwards Preliminary License Exam Applications for Six Ros, Three Instant SROs & One Upgrade SRO Candidate,Per Preparation for Ro/Sro Licensing Exams to Be Administered on 991025-29 at Fcs.Without Encl1999-09-24024 September 1999 Forwards Preliminary License Exam Applications for Six Ros, Three Instant SROs & One Upgrade SRO Candidate,Per Preparation for Ro/Sro Licensing Exams to Be Administered on 991025-29 at Fcs.Without Encl LIC-99-0092, Forwards Revised Epips,Including non-proprietary Rev 8 to EPIP-RR-66,rev 3 to EPIP-EOF-24,rev 14 to RERP-Section F,Rev 11 to RERP-Section I,Rev 12 to RERP-Appendix C & RERP & EPIP Indexes.Proprietary Rev 3 to EPIP-EOF-24,pages 1-3,encl1999-09-21021 September 1999 Forwards Revised Epips,Including non-proprietary Rev 8 to EPIP-RR-66,rev 3 to EPIP-EOF-24,rev 14 to RERP-Section F,Rev 11 to RERP-Section I,Rev 12 to RERP-Appendix C & RERP & EPIP Indexes.Proprietary Rev 3 to EPIP-EOF-24,pages 1-3,encl LIC-99-0087, Forwards Response to NRC Administrative Ltr 99-03, Preparation & Scheduling of Operator Licensing Exams1999-09-17017 September 1999 Forwards Response to NRC Administrative Ltr 99-03, Preparation & Scheduling of Operator Licensing Exams LIC-99-0088, Forwards Documentation Associated with SRO License Renewal Application for Cd Darrow.Applicant Has Satisfactorily Completed Applicable FCS Requalification Program.Without Encls1999-09-16016 September 1999 Forwards Documentation Associated with SRO License Renewal Application for Cd Darrow.Applicant Has Satisfactorily Completed Applicable FCS Requalification Program.Without Encls LIC-99-0080, Requests Approval of Attached Rev to QAP Contained in App a of Usar,Revising Commitment Re Qualifications of Personnel Performing Quality Control Insps of Activities Affecting Fire Protection1999-09-16016 September 1999 Requests Approval of Attached Rev to QAP Contained in App a of Usar,Revising Commitment Re Qualifications of Personnel Performing Quality Control Insps of Activities Affecting Fire Protection LIC-99-0085, Forwards Revs 18 & 19 to TDB-VI, COLR for FCS Unit 1,IAW TS 5.9.5.Rev 18 Resulted from Reevaluation of Cycle 18 Setpoints & Rev 19 Resulted from Changes in Cycle 19 Refueling Boron Concentrations & Addition of TS Parameters1999-09-0808 September 1999 Forwards Revs 18 & 19 to TDB-VI, COLR for FCS Unit 1,IAW TS 5.9.5.Rev 18 Resulted from Reevaluation of Cycle 18 Setpoints & Rev 19 Resulted from Changes in Cycle 19 Refueling Boron Concentrations & Addition of TS Parameters LIC-99-0083, Requests Participation in internet-based Y2K Early Warning Sys (Yews),As Noted in NRC Info Notice 99-25.Plant Point of Contact Will Be JW Chase1999-09-0202 September 1999 Requests Participation in internet-based Y2K Early Warning Sys (Yews),As Noted in NRC Info Notice 99-25.Plant Point of Contact Will Be JW Chase LIC-99-0077, Forwards non-proprietary & Proprietary Revised EP Forms, Including FC-EPF Index,Pp 1 Dtd 990805,pp 2 Dtd 990812,rev 11 to FC-EPF-9,rev 12 to FC-EPF-10,rev 9 to FC-EPF-11,rev 2 to FC-EPF-12 & Rev 3 to FC-EPF-38.Proprietary EP Withheld1999-08-27027 August 1999 Forwards non-proprietary & Proprietary Revised EP Forms, Including FC-EPF Index,Pp 1 Dtd 990805,pp 2 Dtd 990812,rev 11 to FC-EPF-9,rev 12 to FC-EPF-10,rev 9 to FC-EPF-11,rev 2 to FC-EPF-12 & Rev 3 to FC-EPF-38.Proprietary EP Withheld LIC-99-0078, Forwards Rev 16C to FCS Site Security Plan,Per Provisions of 10CFR50.54(p).Rev Has Been Determined Not to Degrade Effectiveness of Current Security Plans.List of Changes, Provided.Encl Withheld1999-08-20020 August 1999 Forwards Rev 16C to FCS Site Security Plan,Per Provisions of 10CFR50.54(p).Rev Has Been Determined Not to Degrade Effectiveness of Current Security Plans.List of Changes, Provided.Encl Withheld LIC-99-0076, Forwards fitness-for-duty Program Performance Data for Six Month Period from Jan-June 1999,IAW 10CFR26.71(d)1999-08-20020 August 1999 Forwards fitness-for-duty Program Performance Data for Six Month Period from Jan-June 1999,IAW 10CFR26.71(d) LIC-99-0075, Forwards Monthly Operating Rept for July 1999 for Fcs,Unit 1,per Plant TS 5.9.1.Revised Rept for June 1999,encl Due to Inadvertent Reporting of Gross Electrical Energy Data When Net Electrical Energy Data Was Required1999-08-13013 August 1999 Forwards Monthly Operating Rept for July 1999 for Fcs,Unit 1,per Plant TS 5.9.1.Revised Rept for June 1999,encl Due to Inadvertent Reporting of Gross Electrical Energy Data When Net Electrical Energy Data Was Required LIC-99-0072, Requests That Licensee 990526 Application for Amend & Related Documents,Be Withdrawn.Util Requests That NRC Review Attached Responses to Ensure That Upcoming Submittal Will Be Acceptable1999-08-0606 August 1999 Requests That Licensee 990526 Application for Amend & Related Documents,Be Withdrawn.Util Requests That NRC Review Attached Responses to Ensure That Upcoming Submittal Will Be Acceptable LIC-99-0068, Documents OPPD Response to Requested Actions in GL 99-02, Laboratory Testing of Nuclear-Grade Activated Charcoal1999-08-0202 August 1999 Documents OPPD Response to Requested Actions in GL 99-02, Laboratory Testing of Nuclear-Grade Activated Charcoal LIC-99-0040, Forwards Rept of Changes,Tests & Experiments Performed Per 10CFR50.59 & Revs to USAR Other than Those Resulting from 10CFR50.59.Encl Info Covers Period of 981101-9903311999-07-28028 July 1999 Forwards Rept of Changes,Tests & Experiments Performed Per 10CFR50.59 & Revs to USAR Other than Those Resulting from 10CFR50.59.Encl Info Covers Period of 981101-990331 LIC-99-0070, Requests Reinstatement of SRO License Previously Held by K Grant-Leanna (License SOP-43569).Operator Is Current on All requalification-training Topics & Has Completed License Reactivation Program1999-07-28028 July 1999 Requests Reinstatement of SRO License Previously Held by K Grant-Leanna (License SOP-43569).Operator Is Current on All requalification-training Topics & Has Completed License Reactivation Program LIC-99-0071, Informs That Util Expects to Submit Four Licensing Actions in Each of Fys 2000 & 2001,in Response to Administrative Ltr 99-02, Operating Reactor Licensing Action Estimates1999-07-26026 July 1999 Informs That Util Expects to Submit Four Licensing Actions in Each of Fys 2000 & 2001,in Response to Administrative Ltr 99-02, Operating Reactor Licensing Action Estimates LIC-99-0057, Forwards 1999/2000 Statement of Cash Flow from Operations, as Guarantee of Payment of Deferred Premiums for Period of 990630 to 0006301999-07-26026 July 1999 Forwards 1999/2000 Statement of Cash Flow from Operations, as Guarantee of Payment of Deferred Premiums for Period of 990630 to 000630 LIC-99-0069, Forwards non-proprietary & Proprietary Epips,Including FC- Epf Index Page & Page 2 ,rev 0 to FC- EPF-42,EPIP Index (Page 1 of 2) & EPIP-OSC-2, Cover & Pages 19 & 20.Proprietary Encls Withheld1999-07-23023 July 1999 Forwards non-proprietary & Proprietary Epips,Including FC- Epf Index Page & Page 2 ,rev 0 to FC- EPF-42,EPIP Index (Page 1 of 2) & EPIP-OSC-2, Cover & Pages 19 & 20.Proprietary Encls Withheld LIC-99-0066, Forwards Fort Calhoun Performance Indicators Rept for May 19991999-07-0707 July 1999 Forwards Fort Calhoun Performance Indicators Rept for May 1999 LIC-99-0060, Forwards Proprietary & non-proprietary Revs to Fort Calhoun Station Emergency Plan Forms (Epf),Including FC-EPF,FC-EPF-1 & FC-EPF-17.Proprietary Info Withheld1999-07-0101 July 1999 Forwards Proprietary & non-proprietary Revs to Fort Calhoun Station Emergency Plan Forms (Epf),Including FC-EPF,FC-EPF-1 & FC-EPF-17.Proprietary Info Withheld LIC-99-0063, Requests Termination of License Held by MR Anderson (License SOP 43812) for Fort Calhoun Station.Anderson Ended Employment Effective 9906241999-07-0101 July 1999 Requests Termination of License Held by MR Anderson (License SOP 43812) for Fort Calhoun Station.Anderson Ended Employment Effective 990624 LIC-99-0061, Submits Response to GL 98-01, Y2K Readiness of Computer Sys at Nuclear Power Plants. Disclosure Encl1999-06-30030 June 1999 Submits Response to GL 98-01, Y2K Readiness of Computer Sys at Nuclear Power Plants. Disclosure Encl LIC-99-0056, Forwards Rev 2 to EA-FC-90-082, Potential Over- Pressurization of Containment Penetration Piping Following Main Steam Line Break in Containment, to Facilitate Review of Response to GL 96-061999-06-22022 June 1999 Forwards Rev 2 to EA-FC-90-082, Potential Over- Pressurization of Containment Penetration Piping Following Main Steam Line Break in Containment, to Facilitate Review of Response to GL 96-06 LIC-99-0059, Provides Formal Notification to NRC of Plans Re Renewal of Operating License DPR-40 for Unit 1.Util Will Continue to Inform NRC of Decisions Relative to License Renewal in Order to Facilitate NRC Resource Planning1999-06-22022 June 1999 Provides Formal Notification to NRC of Plans Re Renewal of Operating License DPR-40 for Unit 1.Util Will Continue to Inform NRC of Decisions Relative to License Renewal in Order to Facilitate NRC Resource Planning LIC-99-0054, Forwards Manual Containing Description of Fort Calhoun Station 1999 Emergency Preparedness Exercise, to Be Conducted on 9908101999-06-0808 June 1999 Forwards Manual Containing Description of Fort Calhoun Station 1999 Emergency Preparedness Exercise, to Be Conducted on 990810 LIC-99-0052, Forwards Fort Calhoun Station Performance Indicators, for Apr 19991999-06-0202 June 1999 Forwards Fort Calhoun Station Performance Indicators, for Apr 1999 LIC-99-0045, Forwards Application for Amend to License DPR-40,proposing to Relocate pressure-temp Curves,Predicated NDTT Shift Curve & LTOP Limits & Values from FCS TS to OPPD Controlled Document.Rev 3 to TR CE NPSD-683 & Supporting TSs Encl1999-05-26026 May 1999 Forwards Application for Amend to License DPR-40,proposing to Relocate pressure-temp Curves,Predicated NDTT Shift Curve & LTOP Limits & Values from FCS TS to OPPD Controlled Document.Rev 3 to TR CE NPSD-683 & Supporting TSs Encl LIC-99-0046, Forwards Scope & Objectives for Plant 1999 EP Exercise to Be Conducted 990810.Info Provided Ninety Days Prior to Exercise IAW Established Stds.Complete Scenario Package Will Be Submitted to NRC & FEMA Sixty Days Prior to Exercise1999-05-12012 May 1999 Forwards Scope & Objectives for Plant 1999 EP Exercise to Be Conducted 990810.Info Provided Ninety Days Prior to Exercise IAW Established Stds.Complete Scenario Package Will Be Submitted to NRC & FEMA Sixty Days Prior to Exercise LIC-99-0028, Provides NRC with Status of Corrective Actions Re Plant Fire Protection Program,As Result of NRC Insp Rept 50-285/97-06. Mod to MOV Is in Design Phase & Currently Scheduled for Installation During 1999 Refueling Outage1999-04-30030 April 1999 Provides NRC with Status of Corrective Actions Re Plant Fire Protection Program,As Result of NRC Insp Rept 50-285/97-06. Mod to MOV Is in Design Phase & Currently Scheduled for Installation During 1999 Refueling Outage LIC-99-0036, Submits Annual Rept of 1998 Loca/Eccs Models Per 10CFR50.46. Small & Large Break LOCA PCT Values Continue to Remain Less than 10CFR50.46(b)(1) Acceptance Criterion of 2200 F1999-04-28028 April 1999 Submits Annual Rept of 1998 Loca/Eccs Models Per 10CFR50.46. Small & Large Break LOCA PCT Values Continue to Remain Less than 10CFR50.46(b)(1) Acceptance Criterion of 2200 F LIC-99-0043, Forwards Fort Calhoun Performance Indicators Rept for Mar 19991999-04-28028 April 1999 Forwards Fort Calhoun Performance Indicators Rept for Mar 1999 LIC-99-0041, Informs That Util Has Implemented Necessary Actions Associated with Open TACs M92926,M99885,M98619 & M98933 Issues.Items Considered Ready to Close,Subject to Agreement by Nrc/Nrr Project Manager1999-04-27027 April 1999 Informs That Util Has Implemented Necessary Actions Associated with Open TACs M92926,M99885,M98619 & M98933 Issues.Items Considered Ready to Close,Subject to Agreement by Nrc/Nrr Project Manager LIC-99-0037, Responds to NRC 990126 RAI Re GL 97-01, Degradation of CRDM Nozzle & Other Vessel Closure Head Penetrations. Response Confirms with NRC & NEI Recommendations to Utilize Generic Industry Response to Issue1999-04-26026 April 1999 Responds to NRC 990126 RAI Re GL 97-01, Degradation of CRDM Nozzle & Other Vessel Closure Head Penetrations. Response Confirms with NRC & NEI Recommendations to Utilize Generic Industry Response to Issue LIC-99-0039, Forwards Diskette Containing 1998 Annual Rept of Individual Monitoring for Fcs,Per 10CFR20.2206.Diskette Follows File Structure of Reg Guide 8.7,App a1999-04-20020 April 1999 Forwards Diskette Containing 1998 Annual Rept of Individual Monitoring for Fcs,Per 10CFR20.2206.Diskette Follows File Structure of Reg Guide 8.7,App a LIC-99-0038, Forwards 1998 Radiological Environ Operating Rept & Annual Rept for TS Section 5.9.4.A for 980101-981231, for Fcs,Unit 1.Rept Is Presented in Format Outlined in Reg Guide 1.21,rev 1.Results of Quarterly Dose Calculations,Encl1999-04-20020 April 1999 Forwards 1998 Radiological Environ Operating Rept & Annual Rept for TS Section 5.9.4.A for 980101-981231, for Fcs,Unit 1.Rept Is Presented in Format Outlined in Reg Guide 1.21,rev 1.Results of Quarterly Dose Calculations,Encl LIC-99-0033, Forwards Addl Info to Support NRC Review of Response to GL 97-04, Assurance of Sufficient Net Positive Suction Head for ECC & Containment Heat Removal Pumps1999-04-15015 April 1999 Forwards Addl Info to Support NRC Review of Response to GL 97-04, Assurance of Sufficient Net Positive Suction Head for ECC & Containment Heat Removal Pumps LIC-99-0035, Forwards Proprietary Rev 2b to FCS Emergency Plan Form FC-EPF-17 & non-proprietary Revised FC-EPF Forms Index,Rev 5a to FC-EPF-1 & Rev 4 to FC-EPF-15.Proprietary Info Withheld from Public Disclosure1999-04-0808 April 1999 Forwards Proprietary Rev 2b to FCS Emergency Plan Form FC-EPF-17 & non-proprietary Revised FC-EPF Forms Index,Rev 5a to FC-EPF-1 & Rev 4 to FC-EPF-15.Proprietary Info Withheld from Public Disclosure LIC-99-0031, Forwards Application for Amend to License DPR-40,increasing Min Required RCS Flow Rate & Changing SRs for RCS Flow Rate1999-03-31031 March 1999 Forwards Application for Amend to License DPR-40,increasing Min Required RCS Flow Rate & Changing SRs for RCS Flow Rate LIC-99-0032, Forwards Fort Calhoun Station Performance Indicators, for Feb 19991999-03-31031 March 1999 Forwards Fort Calhoun Station Performance Indicators, for Feb 1999 LIC-99-0029, Forwards Response to 990226 RAI for GL 97-05, SG Tube Insp Techniques1999-03-30030 March 1999 Forwards Response to 990226 RAI for GL 97-05, SG Tube Insp Techniques LIC-99-0027, Forwards Rev 16B to FCS Site Security Plan,Rev 2 to FCS Safeguards Contingency Plan & Rev 6 to FCS Training & Qualification Plan.Encls Withheld1999-03-16016 March 1999 Forwards Rev 16B to FCS Site Security Plan,Rev 2 to FCS Safeguards Contingency Plan & Rev 6 to FCS Training & Qualification Plan.Encls Withheld LIC-99-0022, Agrees with NRC Request That Proposed Wording of USAR Section 9.2.5 Included in Be Revised to Indicate That Use of Letdown Sys Following Transient.Revs of Appropriate Pages to ,Encl1999-03-12012 March 1999 Agrees with NRC Request That Proposed Wording of USAR Section 9.2.5 Included in Be Revised to Indicate That Use of Letdown Sys Following Transient.Revs of Appropriate Pages to ,Encl LIC-99-0024, Informs That OPPD Withdraws Applications Submitted by 950626 &1999-03-12012 March 1999 Informs That OPPD Withdraws Applications Submitted by 950626 & LIC-99-0016, Requests Relief from Certain Requirements of Paragraphs IWA- 5242(a) & IWA-5250(a)(2) of ASME Section Xi,For Remainder of Third 10-year Insp Interval on Basis of Attached Proposed Alternatives1999-03-0101 March 1999 Requests Relief from Certain Requirements of Paragraphs IWA- 5242(a) & IWA-5250(a)(2) of ASME Section Xi,For Remainder of Third 10-year Insp Interval on Basis of Attached Proposed Alternatives LIC-99-0023, Forwards FCS Performance Indicators for Jan 19991999-03-0101 March 1999 Forwards FCS Performance Indicators for Jan 1999 LIC-99-0020, Forwards non-proprietary EPIP Index,Page 1 of 2,rev 31 to EPIP-OSC-1, Emergency Classification, FC-EPF Forms Index, Page 1 of 2, Rev 8 to FC-EPF-14 & Rev 15 to RERP-Appendix a, Rerp. Proprietary Version of Rev 15 to RERP, Included1999-02-24024 February 1999 Forwards non-proprietary EPIP Index,Page 1 of 2,rev 31 to EPIP-OSC-1, Emergency Classification, FC-EPF Forms Index, Page 1 of 2, Rev 8 to FC-EPF-14 & Rev 15 to RERP-Appendix a, Rerp. Proprietary Version of Rev 15 to RERP, Included LIC-99-0011, Forwards 1999 Biennial Decommissioning Funding Status Rept for Fort Calhoun Station,Unit 11999-02-0505 February 1999 Forwards 1999 Biennial Decommissioning Funding Status Rept for Fort Calhoun Station,Unit 1 1999-09-08
[Table view] |
Text
- _ _ - _ - - _ - - _ - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - . . --
?.
0998 Omaha PWic Power Ostnct 444 South 16th Street Mat Onaha, Nebraska 681@2247 January 5,1999 LIC-99-0002 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Mail Station P1-137 Washington, DC 20555
References:
- 1. Docket No. 50-285
- 2. Letter to OPPD (S. K. Gambhir) from NRC (L. R. Wharton) dated December 7,1998
Subject:
Response to Request for Additional Information Related to GL 97-04,
" Assurance of Sufficient Net Positive Suction Head for Emergency Core Cooling and Containment Heat Removal Pumps" (TAC No. M99992)
The Reference 2 letter documented information requested by the NRC Staff sad discussed during several telephor,a calls conceming Omaha Public Power District (OPPD) submittals in response to GL 9. 04 Enclosed are the OPPD responses to the information requests.
Please contact me if you have any additional questions.
Si carely,
'M k
S. K. Gambhir Division Manager Nuclear Operations TCM/ tem '
l I
c: E.W. Merschoff, NRC Regional Administrator, Region IV ,
L.R. Wharton, NRC Project Manager W.C. Walker, NRC Senior Resident inspector Winston and Strawn 9901200229 990105 PDR ADOCK 05000285 p PDR I
psm tmooyment utn taa opportunn
~. ._. _ . _ . _ _ _
i ,
LIC-99-0002 ,
Enclosure Page 1 ~
Omaha Public Power District Responses to NRC Request for Additiona'l Information Generic Letter 97-04 ,
i.
REFERENCES:
(1) ABB IOC PSA-75-013, dated January 23,1975, Verification of the CONTRANS Digital Computer Code (2) ABB Topical Report Number CENPD-140-A, dated June 1976, Description of the CONTRANS Digital Computer Code for Containment Pressure and Temperature Transient Analysis (3)- USNRC letter from Olan D. Parr to A. E. Scherer, Topical Report Evaluation of CONTRANS code NRC REQUESTS:
- 1. In calculation O-MECH-CALC-021 Rev. 00, Appendix D, explain the difference between I the CONTRANS analyses for cases AVOC and OSNVBV97.
l i
Response: ;
Case AVOC is a LOCA peak containrpent pressure case in which its inputs are biased to )
w . maximize the containment pressure / temperature response. Case OSNVBV97 is a maximum i safeguards case. A comparison of the inputs and assumptions for these two cases is included in Table 1.
- 2. Please confirm that only case OSNVBV97is being used to calculate the subcooling ;
available and explain why that is acceptable. l Response: I Case OSNVBV97 is the case from which the subcooling credit is extracted. The following information is provided to clarify the GL 97-04 response. When calculation O-MECH-CALC-021 Rev. 00 was done, ABB-CE reviewed the large LOCA containment transient analyses available at the time. The results of that review were provided in ABB-CE memo OPS-92-0653, which is included in Appendix D to 0-MECH-CALC-021 Rev. 00.' The memo states, The CONTRANS analysis mns chosen from References (1) and (2) are either tha analysis of record, Case
- AVOC (Reference 3), orprovide a scenario where the sump temperature would be maximized
' and the containment pressure minimized, Case #AGTL and Case #0SNVBV97 (Reference 1 and 2)." Reference (2)is ABB-CE calculation 002-NT90-C-012 Rev. 00, which addresses 26
~!
t
~
l l
LIC-99-0002 Enclosure l
Page 2 different large LOCA analytical cases (including AVOC and AGTL). Reference (1)is ABB-CE calculation 002-AS91-C-001 Rev. 00, which includes largo LOCA case OSNVBV97. The ABB- i CE memo indicates that of the 27 large LOCA containment transient analysis cases available for l review at the time, case OSNVBV97 had the lowest sump subcooling and at that time it was identified as a limiting case. With respect to LOCA, ABB-CE and OPPD only have containment analyses for the large break event for Fort Calhoun Station.
CONTRANS is a four-region model, with Region 11 being the containment sump. Due to the use of the containment sprays and shutdown cooling heat exchanger (s) during the recirculation phase of a LOCA, the sump is an integral part of the containment model, which must be valid to j support the calculation of the containment pressure and temperature response. The degree of l
conservatism in the CONTRANS model is a function of the inputs chosen for the particular l analysis. Thus, due to the flexibility of these various inputs, CONTRANS can be biased to suit l whatever containment application may be required. )
i
- 3. O-MECH-CALC-021 Rev. 00 assumes that the height of the waterin the sump is 6 feet l l based on Reference 3.11. However, page 4 of 25 of the current USAR Section 6.2 only l l assumes 2.8 feet of water. Explain why there is a difference in assumed height of water in the sump.
Response
The 996.8' recirculation phase water elevation used in USAR 6.2.1 is an assumption in calculation O-SEC-23 done by Combustion Engineering in 1968 (i.e., before the containment was built). That calculation formed the basis for the recirculation phase NPSH information in i section 6.2.1 of the 1971 Final Safety Analysis Report. Reference 3.11 of O-MECH-CALC-021 Rev. 00 is a more recent computation which indicates water depth would be six feet (elevation 1000') for a LOCA in which the SIRWT and Si Tanks' inventory is transferred to containment. In view of this, the existing USAR 6.2.1 value for recirculation phase sump water level is conservatively low for large break LOCA NPSH considerations.
l
- 4. Explain why the NPSH calculations are not time dependent or based on the temperature of the sump during your design basis accident.
Response
The AP between the containment atmospheric pressure and the sump water saturation pressure was determined as a function of time after a large LOCA. This is shown in the data tables in O-MECH-CALC-021 Rev. 00 Appendix D. For maximum conservatism, the time point at which this AP is minimized was found, and the subcooling credit taken as a fraction of that AP. Given this methodology, it is not necessary to calculate available NPSH as a function of time after the accident.
i l
l l
g l
LIC-99-0002 Enclosure Page 3 Psr the purposes of the NPSH assessment, a maximum spray pump flow value (based on system hydraulic calculations) and corresponding NPSHa value are used. (The maximum per- i pump flow requires less than three spray pumps to be operating. The per-pump flow and corresponding NPSHn will be lower if all three spray pumps are operating.)
The NPSH calculations are r based on the temperature of the sump during a DBA, because (1) the subcooling contribution is based on the difference between the containment atmospheric pressure and the sump water saturation pressure, and (2) sump water saturation pressure is a function of its temperature. Sump water temperature is not used by itself because the subcooling available depends on the containment atmospheric pressure present at the time.
For the large LOCA event of interest, containment pressure will be elevated above atmospheric.
- 5. The staff believes that you are referencing NRC SER dated April 11,1976, which reviewed CONTRANS Revision 1. Please confirm that the CONTRANS code usedin the 1992 analysis is the same as the code accepted in 1976.
- 6. Have there been any modifications to the CONTRANS code since its acceptance by the NRC? Provide the current version number of the code that was used for this analysis. If modifications have been made, provide the basis for the modifications to the code.
Response
Questions 5 and 6 will be answered together.
The version used for case OSNVBV97 is CONTRANS2-MOD 1. The CONTRANS code used in the 1992 analysis is a different revision of the same code accepted by NRC in 1976. The changes made in that period are of a nature which does not affect the results as calculated by the code. While more options have been added to the CONTRANS computer code, the basic vapor space, sump response, and long term boil-off model calculations have not been changed since its inception. As stated in the NRC SER (Ref. 3), ' Future applications which utilize this code and reference CENPD-140 must indicate the code revision number and if different from that reviewed as par 1 of this topical report, all modifications to the code must be identified."
Using this and ABB-CE's Quality Procedures as guidance, each analysis calculation clearly l indicates the current version of the code being used, together with the reference of the l Verification and Validation report which directly indicates or can be used to trace the differences l to the code since its inception. Additionally, as stated in Reference (3), "The staff does not intend to repeat the review of CENPD-140 when it appears as a reference in a particular licensing application." By ABB-CE's adherence to its approved Quality Procedures, the use and l intent of the CONTRANS code has not been compromised, and the version used has clearly l been indicated in the recorded calculations.
i Since the original version of the CONTRANS code was documented in Reference (1) to support
- Reference (2), subsequent versions have been documented in accordance with the approved ABB-CE Quality Procedures in effect when the revisions were created. Each of these new I
I
+.
l l
l LIC-99-0002 !
Enclosure Page 4 versions has been benchmarked to the old with no or negligible difference from the previous version. The need for these updated versions of CONTRANS has ranged from changing to different models of the old mainframe computers, to different types of workstations. A )
conversion from FORTRAN IV to V has been documented, as well as options which make the code easier to use by providing additional output information and which give the user the flexibility to utilize NRC-initiated issues.
The chronology of CONTRANS versions up to the 1991/1992 time frame is as follows:
- CONTRANS Revision 0 (CENPD-140, PSA-75-013) l This was the original version submitted in the April,1974 topical transmittal.
- CONTRANS Revision 1 (CENPD-140-A, PSA-75-013, PSA-75-075)
This was the version which incorporated NRC comments and was the approved model
)
j documented in the SER for the June,1975 topical re-issue. l 1
. CONTRANS Revision 1D Identical to Rev.1 with the following additions: ;
extended range of the convective heat transfer coefficient properties j extended fan capability in annulus building (so that the EBASCO designs could be l l
accommodated) e CONTRANS Rev. 2, Cyber 855 Mainframe (00000-OPS-002, Rev. 00)
This was an interim FORTRAN IV version on a different mainframe computer.
- CONTRANS Revision 2, CDC 7600 Mainframe (00000-OPS-002, Rev. 01)
This was different from the Rev.1D version because it included an option to model the first CCT(40) walls using the heat transfer coefficients specified in NUREG-0588 for equipment environmental qualification (EO). This option is only used when studying the !
maximum temperature sensed by a piece of equipment for EO purposes. The verification shows that '.nis modification did not affect the containment peak pressure !
since the peak conta' ament pressures from the benchmark runs were identical. This l was also the first FORTRAN V version of CONTRANS.
- CONTRANS2 Version NPL, CDC 990 Mainframe An interim FORTRAN V version of the code.
. CONTRANS2 IV.OD1 (CTN2M1U/CTN2M1L), CDC 990 Mainframe (K-FS-C-042)
An updated version which had some output format changes, and the incorporation of the option to account for reevaporation of condensate from the heat sinks, per NUREG-0588 guidelines. This would only be used for EQ application during a MSLB.
l
.. , j LiC-99-0002 Enclosure Page 5 4
. CONTRANS2 MOD 1 (pooh / users /fisib/ appl /ctn2m1/exe/ctn2m1) Apollo Domain N10000, 400 Series (CODES-FS-C-003)
Minor changes included to make the code run on the workstation. Very good agreement j shown with previous test cases. ;
- 7. For the CONTRANS analysis, provide the inputs, assumptions, and bias that were used to ensure that the containment pressure was minimized.
See responses to Questions 1 and 2. Case OSNVBV97 is a " maximum safeguards" case in which the overall containment pressure response is more benign than the AVQC peak pressure case.
- 8. According to calculation 0-MECH-CALC-021 Rev. 00, page D2, the pump manufacturer suggested that "any type of orifice or control valve is possible to alter the system curve to reduce the potential of run out flow. An orifice within the pump would also achieve similar results by a steeper head / capacity curve causing less run out flow." Explain why this option was not chosen to resolve the run out flowissue.
- 9. Since the run out flow condition occurs during the recirculation phase, are there any procedures in place that instruct the operators to throttle the containment spray pumps in order to prevent the run out flow condition? If not, explain why this option was not considered feasible.
Response
Questions 8 and 9 will be answered together.
If a fixed resistance (such as an orifice) was added to the containment spray system, the increased resistance would decrease system flow during the injection phase of a LOCA, which is when spray flow is most important for LOCA containment peak pressure mitigation. The existing containment spray pump hydraulic performance operability limit for LOCA peak pressure mitigation does not have margin which can accommodate a substantial increase in system hydraulic resistance. This is why a fixed resistance was not chosen as a resolution to this issue.
Floating Step F " Containment Spray Termination"in Emergency Operating Procedures EOP-03 and EOP-20 instructs the operators to terminate spray when containment atmospheric pressure falls below 3 psig. There are no steps in the EOPs instructing the operators to throttle containment spray flow. Crediting throttling capability in the long term of an accident would require a modification to the spray header valves. The OSNVBV97 analysis results indicate that sump subcooling will be available for the large LOCA event, and NPSH will be adequate for the pumps in the recirculation phase. It was therefore not considered justifiable to modify the spray header valves and impose an additional post-DBA procedural burden on the Operators to throttle spray flow, i.e., create an operator work-around and potential human performance issue.
. LIC-99-0002 TABLE 1 Enclosure COMPARISON OFINPUT DATA -
4 a
Page 6 (PEAK PRESSURE CASE AVQC VS. MAXIMUM SAFEGUARDS CASE OSNVBV97)
Card VariatWe AVQC Value OSNVBV97 Units Variable Description Remarks
- Name Value 8 CCT(26) 105.0 -85.0 *F RWT Temperature for A higher temperature is worse for .
SIP flow containment P/T response CCT(27) 2900 1410 sec Time of RAS A function of SIP & spray flow used. Shorter time worse for long term temperature response.
CCT(29) 55.306293 147.95 lbm/ Total Si pump flow Case OSNVBV97 assumed full Si pump sec after RAS flow, therefore it is greater than one Si train
- assumed in Case AVOC. This' reflects only HPSI flow.
, CCT(30) 442.45035 797.84 lbm/ Total Si pump flow Case OSNVBV97 assumed full Si pump
, sec before RAS flow, therefore it is greater than one Si train assumed in Case AVQC. This reflects HPSI/LPSI flow.
13 KCOOL 6 3 -
Number of values in Userinput l CFC table TINT (l) 120.0 90.0 *F Initial heat sink temp Higher temperature is more conservative for containment P/T 22 PAIR 16.85365 14.351 pria Partial pressure of air Higher pressure is more conservative for.
in containment containment P/T 24 PSTM 0.84635 0.349 psia Partial pressure of Higher pressure is more conservative for steam in containment containment P/T TSTM 120.0 90.0 *F Initial Temp of Higher temperature is more conservative for containment vapor containment P/T space i 25 PWTR 17.7 14.7 psia initial pressure of Higher pressure is more conservative for containment vapor containment P/T space 1
_ _ _ _ m__ _ . _ _ _ _ _ _ _ _ . _ _ . _ _ . _ __ _.__..m___.._.__._mm-__.__._.____.-.-.______________m _____._______..._.____.m.__.__ . .._____________.___m_______m_____ . _ . _ _ _ _ _ _ _ _ _ _ . _ _ . -
. ?i LIC-99-0002 TABLE 1 Enclosure COMPARISON OF INPUT DATA - 1 Page 7 (PEAK PRESSURE CASE AVQC VS. MAXIMUM SAFEGUARDS CASE OSNVBV97) ;
Card Variable AVQC Value OSNVBV97 Units Variable Description Remarks
- Name Value TWTR 120.0 90.0 F Initial Temp of sump Higher temperature is more conservative for ,
water containment P/T, however, only a small amount of initial sump inventory is used to initiate the code.
28 DELTBL(M) .002,.005, .002,.005, sec Time step size Only one point difference as shown
.005, S.,10., .005, 5.,15.,
20.,50. 20.,50.
38 COOLN 0.0 1.0 -
Number of CFCs Case AVQC did not assume the operation running before of any CFCs. This is conservative for STFAN1 containment P/T analyses.
STFAN1 100E+07 45.0 sec Time at which fan Case OSNVBV97 simulated a realistic coolers switch from switchover from one to two CFC units.
COOLN to COOLN1 COOLN1 0 2.0 -
Number of CFCs Case AVQC did not assume the operation running after STFAN1 of any CFCs. This is conservative for containment P/T analyses.
39, TSCOOL(M) 0.0,120., 90.,288., F Temperature for CFC Not used for Case AVQC. Best data 40 185.,244., 500. performance table available at that time for Case OSNVBV97.
288.,500 QHCOOL ,
QHCOOL(M) 0.0, 0.0, 0.0,58333., Btu / CFC performance for Not used for Case AVQC. Best data ,
12900., 58333. sec use with TSCOOL available at that time for Case OSNVBV97.
24600.,
33343.,33343 41 SPRAYO(l) 0.,0.,0.,2085 0., 0., 0., gpm Containment spray flow Less spray flow is more conservative for 5100 cont. P/T analysis. Full spray flow assumed for Case OSNVBV97.
t
__=-_._. _ . _ _ _ _ _
-a j '
LIC-99-0002 - TABLE 1 Enclosure -*
COMPARISON OF INPUT DATA Page 8 '(PEAK PRESSURE CASE AVQC VS. MAXIMUM SAFEGUARDS CASE OSNVBV97)
Card Variable . - AVQC Value OSNVBV97 Units Variable Description Remarks
- Name Value TSPRAY(1,1) 0.,0.,0.,-5.0 0., 0., 0., -
For Case AVQC, the More realistic spray start time used for Case psig 55.0 sec absolute value of OSNVBV97.
TSPRAY (4,1) is the CSAS setpoint. For Case OSNVBV97, this -
is the time at which sprays are actuated.
TSPRAY(1,2) 0., 0., -2900., 0., 0., 0., sec For Case AVQC, the More realistic spray operation used for
-159.99 1410.0 absolute values of Case OSNVBV97.
TSPRAY(3.2) and (4.2) are the shutoff time and delay time after setpoint is reached.
For Case OSNVBV97, this is the time at which sprays end injection mode.
43 SDUMPQ(1) 2085.0 5100.0 gpm Cont. spray flow after Less spray flow is more conservative for recirc. cont. P/T analysis. Full spray flow assumed for Case OSNVBV97.
TSUMP(1,1) 2900.0 1410.0 sec Time at which recirc Time of RAS spray flow starts 44 TRFTNK 105. 85.0 F RWT temp for spray Higher temperature is more conservative for flow cont. P/T analysis.
46 AREH 5020.0 10040.0 ft2 Area of SDCHX One SDCHX for Case AVOC and two SDCHXs for Case OSNVBV97-49 QSEC 2407.0 4814.0 gpm CCW flow rate CCW flow rate to one vs. two SDCHXs TINSEC 120.0 90.0 *F CCW temp Higher temperature is more conservative for containment P/T analysis.
____.__._m.__.___ _ _ . _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ - _ _ _ _ _ _ _ . _ _ . _ _ _ _ _ - _ - . _ . . _ _ _ . , _ _ . . , _ _ . . _ _ , , - , ~~vm.. .,- _ .._ _ 4, .,m. , ,. . . . _ - -~.-# .,_. .
.-__s - . - _ . .
~
. 9 - '
~~
., 3:
- LIC-99-0002 a= . TABLE 1
. Enclosure COMPARISON OF INPUT DATA Page 9 . .(PEAK PRESSURE CASE AVQC VS. MAXIMUM SAFEGUARDS CASE OSNVBV97)
Card Varistne AVQC Value OSNVBV97 Units Variatne Description Remarks
-#. Name . Value 81 TZERO 2900.0 1410.0 sec Time of RAS A function of Si and spray flow used. Early time worse for long term temperature .~
response.
TEND 442.45035 797.84 Lbm/ Si pump flow before Case OSNVBV97 assumed full Si pump :
sec RAS flow, therefore it is greater than one Si train assumed in Case AVQC. This reflects !
HPSI/LPSI flow.
TEND 1 55.306293 147.95 Lbm/ Si pump flow after RAS Case OSNVBV97 assumed full SI pump sec flow, therefore it is greater than one Si train assumed in Case AVQC. This reflects only -
HPSI flow.
82 PCT 1.2 1.0 -
Decay heat multiplier A larger decay heat multiplier is more conservative for long term release model since more energy will be released to . t containment.
Acronym Definitions:
RWT Refueling Water Tank i P/T Presr>ure/ Temperature SIP Safety injection Pump r RAS ~ Recirculation Actuation Signal CFC Containment Fan Coolers CSAS Containment Spray Actuation Signal e SDCHX Shutdown Cooling Heat Exchanger .
CCW Cornponent Cooling Water HPSI High Pressure Safety injecton LPSI Low Pressure Safety injection
. - . . _ . . . .-- - - . . . . . . - . - . . - _ . . . . - - . . - . .-