Letter Sequence Meeting |
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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
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Text
m i
- 4 WE%q'o UNITED STATES f-
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NUCLEAR REGULATORY COMMISSION g
-i
- j-WASHINGTON, D. C. 20555 February 5, 1987 Docket No. 50-267 MEMORANDUM FOR
Herbert N. Berkow, Director 4
Standardization and Special Projects Directorate Division of PWR Licensing-B, NRR THRU:
Oliver D. T. Lynch, Jr., Section Lead Standardization and Decommissioning S on Standardization and Special Projects Directorate Division of PWR Licensing-B, NRR FROM:
Kenneth L. Heitner, Project Manager Standardization and Decommissioning Section Standardization and Special Projects Directorate Division of PWR Licensing-B, NRR
SUBJECT:
SUPWARY OF MEETING WITH PUBLIC SERVICE COMPANY OF COLORADO (PSC) ON THE FORT ST. VRAIN (FSV)
EQUIPMENT QUALIFICATION (EQ) PROGRAM AND APPROVALS REQUIRED FOR PLANT RESTART A meeting was held with PSC on January 13, 1987 to discuss FSV's status with regard to completion of the EQ program. At this meeting, the status of other approvals required for plant restart was also discussed.
Attendees at this meeting are given in the enclosure.
Status of the EQ Program PSC reviewed the status of the FSV EQ program and its relationship to the upcoming EQ inspection. Discussions between NRC and PSC focused on the status of EQ documentation (including procedures and qualification binders), the EQ Master List, plant EQ modification and maintenance activities, and logistics for the inspection. During the meeting PSC stated that they planned to have all EQ efforts (including any necessary corrective action resulting from the EQ inspection) completed by the middle of February 1987.
PSC plans to certify that FSV conforms with the requirements of 10 CFR 50.49 at that time. Based on the information provided in the meeting, the NRC confirmed the EQ inspection for the week of January 26, 1987.
8702130277 870205 PDR ADOCK 05000267 P
PDR
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{.
2_
Approvals Required for Plant Restart The staff and licensee reviewed the approvals required for plant restart.
The specific focus of this discussion.was the proposals by PSC to initially operate the plant based on the analyses that supported continued use of the steam generator reheaters up to 39% of full power. The staff noted that continued use of the reheaters for safe shutdown cooling posed additional technical problems. Specifically, the licensee's analyses and tests had shown that only 2 or 3 of the 6 reheater modules would receive cooling water. The " dry" modules would be subject to high temperatures which could lead to failure of the tubes or supporting structures. Thus, justification of this mode of operation would be largely based on the materials analyses and posed potentially complex issues.
By contrast, an alternative basis for plant operation was available at 35%
of full power, based on using the liner cooling system.
In view of the small additional power level gained by the new analyses, it was mutually agreed by the staff and PSC that further consideration of this approach offered little safety or economic benefit. Hence,it was agreed that PSC would request that initial operation of the plant be based on the liner cooling system with a power level limit at 35%. PSC would review their prior bases for operating in this mode, and the NRC's prior approval for any potential changes and inform the staff of their review. PSC would commit to this interim power limit (35%) until the staff had reviewed and approved the changes associated with the proposed high power limit (P2),
estimated to be 82% of full power.
At this time, the Region IV staff also noted that they would request a
" hold" on FSV at 10% of full power, to evaluate operational performance.
~
PSC said they would agree to a " hold" at that power level so that the NRC could evaluate PSC's operational performance before proceeding to higher power levels.
l Kenneth L. Heitner, Project Manager Standardization and Decommissioning Section Standardization and Special Projects Directorate t
Division of PWR Licensing-B, NRR l
Enclosure:
l As stated cc w/ enclosure:
j See next page
'~
Mr. R. O. Williams
~ ~ ~
~
Public Service Company of Colorado Fort St. Vrain cc:
Mr. D. W. Warembourg, Manager Albert J. Hazle, Director Nuclear Engineering Division Radiation Control Division Public Service Company Department of Health of Colorado 4210 East lith Avenue P. O. Box 840 Denver, Colorado 80220 Denver, Colorado 80201 Mr. David Alberstein, 14/159A Mr. J. W. Gahm, Manager GA Technologies, Inc.
Nuclear Production Division Post Office Box 85608 Public Service Company of Colorado San Diego, California 92138 16805 Weld County Road 19-1/2 Platteville, Colorado 80651 Mr. H. L. Brey, Manager Nuclear Licensing and Fuel Division Mr. P. F. Tomlinson, Manager Public Service Company of Colorado Ouality Assurance Division P. O. Box 840 Public Service Company of Colorado Denver, Colorado 80201 16805 Weld County Road 19-1/2 Platteville, Colorado 80651 Senior Resident Inspector U.S. Nuclear Regulatory Commission Mr. R. F. Walker P. 0. Box 840 Public Service Company of Colorado Platteville, Colorado 80651 Post Office Box 840 Denver, Colorado 80201-0840 Kelley, Stansfield & 0'Donnell Public Service Company Building Commitment Control Program Room 900 Coordinator 550 15th Street Public Service Company of Colorado Denver, Colorado 80202 2420 W. 26th Ave. Suite 100-D Denver, Colorado 80211 Regional Administrator, Region IV U.S. Nuclear Regulatory Commission 611 Ryan Plaza Drive, Suite 1000 Arlington, Texas 76011 Chairman, Board of County Commissioners of Weld County, Colorado Greeley, Colorado 80631 1
I Regional Representative Radiation Programs Environmental Protection Agency 1 Denver Place 999 18th Street, Suite 1300 i
Denver, Colorado 80202-2413 l
l l
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'f.
Enclosure NRC-PSC MEETING JANUARY 13, 1987 Name Organization Ken Heitner NRC/NRR/DPWRL-B
.C. H. Fuller Public Service Company of Colorado Don Waremboung Public Service Company of Colorado Mike Niehoff
.Public Service Company of Colorado John Waage Public Service. Company of Colorado Tim Prenger Public Service Company of Colorado D. J. Brown Public Service Company of Colorado H. L. Brey Public Service Company of Colorado G. T. Hubbard NRC/IE/VPB D. E. Norman NRC/RIV H. N. Berkow NRC/NRR/DPWRL-B J. P. Jaudon CH/PSA/RIV/NRC J. E. Gagliardo NRC/RIV, Proj. Branch Ch.
R. E. Ireland NRC/RIV, Ch. E.S.
A. R. Johnson NRC/RIV/RSB/ES R. E. Hall NRC/DRSP R. O. Williams VP/NUC/PSC i
i
February 5, 1987
. Approvals Required for Plant Restart The staff and licensee reviewed the approvals required for plant restart.
The specific focus of this discussion was the proposals by PSC to initially operate the plant based on the analyses that supported continued use of the steam generator reheaters up to 39% of full power. The staff noted that continued use of.the reheaters for safe shutdown cooling posed additional technical problems. Specifically, the licensee's analyses and tests had shown that only 2 or 3 of the 6 reheater modules would receive cooling water. The " dry" modules would be subject to high temperatures which could lead to failure of the tubes or supporting structures. Thus, justification of this made of operation would be largely based on the materials analyses and posed potentially complex issues.
By contrast, an alternative basis for plant operation was available at 35%
of full power, based on using the liner cooling system.
In view of the small additional power level gained by the new analyses, it was mutually agreed by the staff and PSC that further consideration of this approach offered little safety or economic benefit. Hence,it was agreed that PSC would request that initial operation of the plant be based on the liner cooling system with a power level limit at 35%.
PSC would review their prior bases for operating in this mode, and the NRC's prior approval for any potential changes and inform the staff of their review.
PSC would commit to this interim power limit (35%) until the staff had reviewed and approved the changes associated with the proposed high power limit (P2),
estimated to be 82% of full power.
At this time, the Region IV staff also noted that they would request a
" hold" on FSV at 10% of full power, to evaluate operational performance.
PSC said they would agree to a " hold" at that power level so that the NRC could evaluate PSC's operational performance before proceeding to higher power levels.
Original signed by Kenneth L. Heitner, Project Manager Standardization and Decommissioning.Section Standardization and Special Projects Directorate Division of PWR Licensing-B, NRR
Enclosure:
As stated cc w/ enclosure:
See next page DISTRIBUTION:
! Docket File " NRC PDR ACRS (10)
PBSS Reading Local PDR NRC Participants PNoonan OGC-Beth Licensee and Plant Service Lists XHeitner EJordan Olynch BGrimes
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PBSS 'XH r
onan KHeitner:ac Olyngh 02/4//87 02/+/87 02/g/87
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