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| {{#Wiki_filter:3 h Public Service- lcWo 2420 W. 26th Avenue, Suite 1000, Denver, Colorado 80211 May 4, 1987 Fort St. Vrain Unit No. 1 P-87171 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D.C. 20555 Attention: Mr. Jose A. Calvo Director, Project Directorate IV Docket No. 50-267 | | {{#Wiki_filter:3 h Public Service-lcWo 2420 W. 26th Avenue, Suite 1000, Denver, Colorado 80211 May 4, 1987 Fort St. Vrain Unit No. 1 P-87171 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D.C. |
| | 20555 Attention: Mr. Jose A. Calvo Director, Project Directorate IV Docket No. |
| | 50-267 |
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| ==SUBJECT:== | | ==SUBJECT:== |
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| ==Dear Mr. Calvo:== | | ==Dear Mr. Calvo:== |
| | | PSC has completed the special test that was discussed in PSC's Response 7 in Attachment 1 of the above Reference. |
| PSC has completed the special test that was discussed in PSC's Response 7 in Attachment 1 of the above Reference. The results of this test are evaluated in " Evaluation of Test Data for the Confirmation of Fire Water Flow Rate to the Circulator Water Turbine During EES Cooldown for Safe Shutdown Cooling," EE-EQ-0057, Rev. A. | | The results of this test are evaluated in " Evaluation of Test Data for the Confirmation of Fire Water Flow Rate to the Circulator Water Turbine During EES Cooldown for Safe Shutdown Cooling," EE-EQ-0057, Rev. A. |
| One copy of EE-EQ-0057, Rev. A is enclosed for your information in accordance with PSC's Response 7 in Attachment 1 of the above Reference. | | One copy of EE-EQ-0057, Rev. A is enclosed for your information in accordance with PSC's Response 7 in Attachment 1 of the above Reference. |
| If you have any questions about this evaluation, please contact Mr. | | If you have any questions about this evaluation, please contact Mr. |
| M. H. Holmes at (303) 480-6960. | | M. H. Holmes at (303) 480-6960. |
| Very truly yours, 8705080288 870504 PDR ADOCK 05000267 H. L. Brey, Manager F PDR Nuclear Licensing and Fuels Division HLB /AW:jmt I | | Very truly yours, 8705080288 870504 PDR ADOCK 05000267 H. L. Brey, Manager F |
| g60 Enclosure cc: Regional Administrator, Region IV Mr. R. E. Farrell Attn. Mr. J. E. Gagliardo, Chief Senior Resident Inspector Reactor Projects Branch Fort St. Vrain | | PDR Nuclear Licensing and Fuels Division HLB /AW:jmt I g60 Enclosure cc: Regional Administrator, Region IV Mr. R. E. Farrell Attn. Mr. J. E. Gagliardo, Chief Senior Resident Inspector Reactor Projects Branch Fort St. Vrain |
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Letter Sequence Other |
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Results
Other: 05000267/LER-1986-020, :on 860711,determined That FSAR Analyses for Safe Shutdown Cooling Following 90-minute Loss of Forced Cooling May Be Invalid.Caused by Design Omission.Three Options Presently Being Investigated, 05000267/LER-1986-026, :on 860917,FSAR Analysis for Safe Shutdown Cooling W/Firewater Invalid.Caused by Incomplete Analysis/ Inadequate Review.Review & Reanalysis Will Be Performed on Various Accidents Described in FSAR, ML19306G340, ML20137H372, ML20197B076, ML20204G924, ML20205T170, ML20206B329, ML20206B459, ML20206F887, ML20207K386, ML20207K441, ML20207K446, ML20207K506, ML20207K512, ML20207P779, ML20207P991, ML20207P993, ML20209E329, ML20209F187, ML20209G043, ML20210A740, ML20210A748, ML20210A757, ML20210T436, ML20210T655, ML20210T686, ML20211D992, ML20211E058, ML20211E084, ML20211E110, ML20211G583, ML20211N368, ML20214Q988, ML20214Q998, ML20214S836, ML20215H964, ML20215H973, ML20215J855, ML20215J871, ML20234C109, ML20235E520, ML20235F508, ML20245C018
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MONTHYEARML20137H3721985-11-26026 November 1985
Memorandum & Order Granting Extension of 851130 Deadline for Environ Qualification of Electrical Equipment to 860531 & Approving Proposal to Allow Operation w/35% Reactor Power Limit During Interim.Served on 851127
Project stage: Other
ML20211E0841986-02-20020 February 1986
Issue a to Fort St Vrain:Delayed Firewater Cooldown;Effect of Liner Cooling on Orifice Valve Temps
Project stage: Other
ML20209F1871986-03-18018 March 1986
Fort St Vrain Steam Generator Temps During Interruption of Forced Cooling from 105% Power
Project stage: Other
05000267/LER-1986-020, :on 860711,determined That FSAR Analyses for Safe Shutdown Cooling Following 90-minute Loss of Forced Cooling May Be Invalid.Caused by Design Omission.Three Options Presently Being Investigated1986-08-10010 August 1986
- on 860711,determined That FSAR Analyses for Safe Shutdown Cooling Following 90-minute Loss of Forced Cooling May Be Invalid.Caused by Design Omission.Three Options Presently Being Investigated
Project stage: Other
ML20211E0581986-09-30030 September 1986
Effect of Delayed Firewater Cooldown W/Loss of Liner Cooling on Pcrv Temps
Project stage: Other
05000267/LER-1986-026, :on 860917,FSAR Analysis for Safe Shutdown Cooling W/Firewater Invalid.Caused by Incomplete Analysis/ Inadequate Review.Review & Reanalysis Will Be Performed on Various Accidents Described in FSAR1986-10-17017 October 1986
- on 860917,FSAR Analysis for Safe Shutdown Cooling W/Firewater Invalid.Caused by Incomplete Analysis/ Inadequate Review.Review & Reanalysis Will Be Performed on Various Accidents Described in FSAR
Project stage: Other
ML20211G5831986-10-22022 October 1986
Anticipates Completion of Steam Generator Analysis & App R Modeling Reanalysis Work by Feb 1987,per 860918 Telcon W/Nrc Re Steam Generator Cool Down Studies for App R
Project stage: Other
ML20197B0761986-10-22022 October 1986
Informs That Util Will Update & Submit Rept on Chernobyl Accident by 861126.Update Will Ctr on Graphite Related Concerns,Including Analysis of Worst Case Explosive Gas Mixtures & Comparison of Reactor Kinetics Behavior
Project stage: Other
ML20207K5121986-11-13013 November 1986
Fort St Vrain Calculations for Circulator Temp-Related Operating Limits
Project stage: Other
ML20207K5011986-12-0404 December 1986
Effect of Firewater Cooldown Using Economizer-Evaporator- Superheater (EES) Bundle on Steam Generator Structural Integrity. Draft Rept of Steam Generator Ability to Withstand post-App R Firewater Cooldown Transient Encl
Project stage: Draft Other
ML20207K4461986-12-12012 December 1986
Issue a to Effect of Firewater Cooldown Using Reheater on Steam Generator Structural Integrity
Project stage: Other
ML20211N3681986-12-12012 December 1986
Forwards Restart Interaction Schedule,Per 861205 Request
Project stage: Other
ML20207K5061986-12-22022 December 1986
Issue a to Effect of Intentional Depressurization on Cooldown from 39% Power Using One Reheater Module (1-1/2 H Delay)
Project stage: Other
ML20207K4411986-12-23023 December 1986
Issue a to Economizer-Evaporator-Superheater (EES) Cooldown from 39% & 78% Power Using Condensate or Firewater (1.5 H Delay)
Project stage: Other
ML20207K3861986-12-30030 December 1986
Forwards Analyses Supporting Power Operation Up to 39% Power Based on Safe Shutdown Cooling Following 90 Min Interruption of Forced Circulation.Conclusions of Repts Listed.Corrective Actions for LERs 86-020 & 86-026 Also Listed
Project stage: Other
ML20207P7791987-01-0707 January 1987
Forwards Current Integrated Schedule for Restart & Power Ascension Activities.Schedule Incorporates Consolidated Schedular Info on Both Interaction Activities.Updates Will Be Provided Twice Per Month.W/One Oversize Graph
Project stage: Other
ML20207P9931987-01-13013 January 1987
SAR for Tech Spec Limiting Condition for Operation 4.3.1 Change Permitting Safe Shutdown Cooling W/Evaporator- Economizer-Superheater
Project stage: Other
ML20207P9871987-01-15015 January 1987
Forwards Application for Amend to License DPR-34,changing Tech Specs to Require Both evaporator-economizer Superheater Sections & Both Reheater Sections to Be Available During Operation at Power.Fee Paid
Project stage: Request
ML20207P9911987-01-15015 January 1987
Proposed Tech Specs,Requiring Both evaporator-economizer Superheater Sections & Both Reheater Sections to Be Available During Operation at Power as Min Number of HXs
Project stage: Other
ML20207P9891987-01-15015 January 1987
Application for Amend to License DPR-34,requiring Both evaporator-economizer Superheater Sections & Both Reheater Sections to Be Available During Operation at Power as Min Number of Operable HXs
Project stage: Request
ML20211E1101987-01-26026 January 1987
Rev a to Engineering Evaluation of Procedure to Recover from Actuation of Steam Line Rupture Detection/Isolation Sys for Power Levels Through P2
Project stage: Other
ML20210A7571987-01-30030 January 1987
Fort St Vrain 1987 Power Ascension Plan
Project stage: Other
ML20210A7481987-01-30030 January 1987
Requests Concurrence to Start Up & Operate Facility Through Graduated Rise to Power Up to 100% of Rated Power,Subj to Listed Constraints. Fort St Vrain 1987 Power Ascension Plan Encl
Project stage: Other
IR 05000267/19870021987-01-30030 January 1987
Partially Withheld Insp Rept 50-267/87-02 on 870106-09 (Ref 10CFR73.21).No Violations or Deviations Noted.Major Areas Inspected:Matl Control & Accounting
Project stage: Request
ML20210A7401987-02-0202 February 1987
Forwards Updated Nrc/Public Svc Co of Colorado Restart Interaction Schedule, Reflecting Current Target Dates & Recently Completed Items
Project stage: Other
ML20209G0431987-02-0202 February 1987
Forwards Current Integrated Schedule for Plant Restart & Power Ascension Activities.W/One Oversize Encl
Project stage: Other
ML20210N8831987-02-0303 February 1987
Forwards Request for Addl Info on 861230 & 870115 Submittals Re Analysis of Firewater Cooldown from 82% of Full Power
Project stage: RAI
ML20210P0191987-02-0505 February 1987
Summary of 870113 Meeting W/Util Re Completion of Equipment Qualification Program & Program & Approvals Required for Plant Restart
Project stage: Meeting
ML20210T6861987-02-0505 February 1987
Rev a to Engineering Evaluation of Reanalysis of FSAR Accidents/Transients Relying on EES Cooling. W/Four Oversize Drawings
Project stage: Other
ML20211D9921987-02-0505 February 1987
Issue a to Economizer-Evaporator-Superheater Cooldowns for Equipment Qualification & App R Events W/Vent Lines (1.5 H Delay)
Project stage: Other
ML20210T6551987-02-0606 February 1987
Provides Results of Confirmatory Analyses for FSAR Accidents Which Utilize Either EES or Reheater Section of Steam Generator for DHR
Project stage: Other
ML20210T4361987-02-11011 February 1987
Requests Publication of Fr Notice of Consideration of Issuance of Amend to License DPR-34 & Proposed NSHC Determination & Opportunity for Hearing on 870115 Request Re Operation of evaporator-economizer-superheater Sections
Project stage: Other
ML20211E9791987-02-12012 February 1987
Forwards Proposed Agenda & Slides for 870226 Meeting W/ Commission & Staff to Secure Commission Approval for Full Power Operation of Facility
Project stage: Meeting
ML20211D8901987-02-17017 February 1987
Forwards Response to NRC 870203 Request for Addl Info Re Firewater Cooldown from 82% of Full Power,Per Util 861230 & s
Project stage: Request
ML20207Q7941987-03-0303 March 1987
Forwards Second Request for Addl Info Re Util Analysis of Firewater Cooldown from 82% of Full Power Operation,Based on Review of 861230,870115 & 0217 Submittals
Project stage: Approval
ML20204G9241987-03-20020 March 1987
Forwards Restart & Power Ascension Schedule,Incorporating Consolidated Schedular Info on NRC-util Interaction Activities.Brief Narrative Description of Scope of Each Line Item Activity Also Encl.W/One Oversize Encl
Project stage: Other
ML20205B3441987-03-20020 March 1987
Forwards Response to NRC 870303 Second Request for Addl Info Re Firewater Cooldown from 82% of Full Power (Safe Shutdown Cooling)
Project stage: Request
ML20205M8901987-03-30030 March 1987
Forwards Third Request for Addl Info Re Util 861230,870115 & 0217 Submittals Concerning Analysis of Firewater Cooldown from 82% of Full Power.Major Concerns Re Effects of Transient Loading Due to Seismic Motion or Flow
Project stage: RAI
ML20205T1701987-04-0101 April 1987
Forwards Oversize Current Integrated Schedule for Facility Restart & Power Ascension Activities Required for Equipment Qualification Completion Certification,Startup/Plant Criticality & Power Ascension to 82%.Related Info Encl
Project stage: Other
ML20206B6031987-04-0101 April 1987
Forwards Comments Re Implication of Chernobyl Reactor Accident.Design Differences Between Fort St Vrain & Chernobyl Preclude Accident Similar to Chernobyl from Occurring at Fort St Vrain
Project stage: Approval
ML20206B4591987-04-0303 April 1987
Forwards Summary of Equipment Qualification (EQ) Insp Conducted by NRR & IE on 870126-30.EQ Program Approved. Detailed Results of Insp Will Be Provided
Project stage: Other
ML20206B3291987-04-0707 April 1987
Submits Daily Highlight.Public Svc Co of Colorado Authorized to Restart & Operate Facility HTGR at Level of Up to 35% Full Power.Facility Out of Operation Since 860531,when Shut Down for Equipment Qualification Mods
Project stage: Other
ML20206F8871987-04-10010 April 1987
Submits Requested Addl Info for Analysis of Firewater Cooldown for 82% Power Operation,Per
Project stage: Other
ML20209E3291987-04-27027 April 1987
Provides Written Authorization to Operate Reactor at Up to 35% Full Power,Per Section IV of 870406 Confirmatory Order Modifying License DPR-34
Project stage: Other
ML20215H9641987-04-30030 April 1987
Forwards Updated Ga Technologies Procedure 909410, Buckle Users Manual, Per 870330 Request.Manual Updated to Include Revs to Computer Code Required by High Temps & Short Times Assumed for Steam Generator Tube Stress Analysis
Project stage: Other
ML20215H9731987-04-30030 April 1987
Revised Buckle Users Manual:Creep Collapse of Thin-Walled Circular Cylindrical Shells Subj to Radial Pressure & Thermal Gradients
Project stage: Other
ML20215J8711987-05-0404 May 1987
Rev a to Evaluation of Test Data for Confirmation of Fire Water Flow Rate to Circulator Water Turbine During EES Cooldown for Safe Shutdown Cooling
Project stage: Other
ML20215J8551987-05-0404 May 1987
Forwards Rev a to EE-EQ-0057, Evaluation of Test Data for Confirmation of Fire Water Flow Rate to Circulator Water Turbine During EES Cooldown for Safe Shutdown Cooling
Project stage: Other
ML20214S8361987-05-27027 May 1987
Requests Insp & Audit Per 10CFR50,App B of Licensee Activities Supporting Request for 82% Power Operation. Requests That Insp Be Conducted & Completed within 180 Days
Project stage: Other
ML20214Q9881987-05-29029 May 1987
Forwards Rept GA909438,Issue Nc, Verification Rept for Buckle Computer Program. Edition of Buckle Code Covered by User Manual Validated & Independently Verified by Rept
Project stage: Other
1987-02-11
[Table View] |
Text
3 h Public Service-lcWo 2420 W. 26th Avenue, Suite 1000, Denver, Colorado 80211 May 4, 1987 Fort St. Vrain Unit No. 1 P-87171 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D.C.
20555 Attention: Mr. Jose A. Calvo Director, Project Directorate IV Docket No.
50-267
SUBJECT:
Additional Information for Analysis of Firewater Cooldown for 82% Power Operation
REFERENCE:
PSC letter, Brey to Berkow, dated March 20, 1987 (P-87110)
Dear Mr. Calvo:
PSC has completed the special test that was discussed in PSC's Response 7 in Attachment 1 of the above Reference.
The results of this test are evaluated in " Evaluation of Test Data for the Confirmation of Fire Water Flow Rate to the Circulator Water Turbine During EES Cooldown for Safe Shutdown Cooling," EE-EQ-0057, Rev. A.
One copy of EE-EQ-0057, Rev. A is enclosed for your information in accordance with PSC's Response 7 in Attachment 1 of the above Reference.
If you have any questions about this evaluation, please contact Mr.
M. H. Holmes at (303) 480-6960.
Very truly yours, 8705080288 870504 PDR ADOCK 05000267 H. L. Brey, Manager F
PDR Nuclear Licensing and Fuels Division HLB /AW:jmt I g60 Enclosure cc: Regional Administrator, Region IV Mr. R. E. Farrell Attn. Mr. J. E. Gagliardo, Chief Senior Resident Inspector Reactor Projects Branch Fort St. Vrain
.
