Letter Sequence Meeting |
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Administration
- Meeting, Meeting, Meeting, Meeting, Meeting, Meeting, Meeting, Meeting, Meeting, Meeting, Meeting, Meeting, Meeting, Meeting, Meeting, Meeting
Results
Other: ML20076E880, ML20079M106, ML20080E109, ML20100G880, ML20100G888, ML20100H212, ML20112G667, ML20127J807, ML20135B301, ML20135D754, ML20137H372, ML20137S741, ML20141P181, ML20154K144, ML20197C598, ML20197G513, ML20205C845, ML20206B459, ML20207K470, ML20211P495, ML20215E408, ML20215G100, ML20235G758
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MONTHYEARML20076E8801983-05-17017 May 1983
Responds to NRC 830413 Order Re Environ Qualification of safety-related Electrical Equipment,Per 10CFR50.49.Environ Qualification Records Audit Will Be Completed by 831231
Project stage: Other
ML20080E1091983-08-15015 August 1983
Provides Followup to Util Re Environ Qualification of safety-related Electrical Equipment. Justification for Continued Operation W/Components Not Fully Qualified Provided
Project stage: Other
ML20079M1061984-01-0909 January 1984
Advises NRC Re Status of Three Commitments Made in Util Concerning Environ Qualification of safety-related Electrical Equipment.Valve Actuators Tested & Successfully Passed HELB Tests
Project stage: Other
ML20100G8881984-09-11011 September 1984
Four-Minute Isolation of Postulated Steam Line Breaks at Fort St Vrain Nuclear Generating Station
Project stage: Other
ML20112G6671984-12-27027 December 1984
Informs of Efforts to Environmentally Qualify Certain post-accident Monitoring Equipment Per 10CFR50.49.Equipment Identified in Reg Guide 1.97 & Existing in Harsh Environ Will Be Qualified by 850331
Project stage: Other
ML20108A2121985-02-0404 February 1985
Informs of Receipt of Generic Ltr 84-24 on 850121 & Request for Addl Info on Environ Qualification of Electrical Equipment on 850128.Responses to Both Ltrs Will Be Provided by 850328
Project stage: Request
ML20100H2121985-03-25025 March 1985
Forwards Response to NRC 841227 Order Re Certification of Compliance w/10CFR50.49 (Generic Ltr 84-24).Util Previously Submitted Ltrs Re Environ Qualification of safety-related Equipment in Response to IE Bulletin 79-01B
Project stage: Other
ML20100G8801985-03-28028 March 1985
Forwards Addl Info Re Environ Qualification Program. Response to NRC 850128 Concerns & Summary of Completion Schedule for Outstanding Items Encl
Project stage: Other
ML20237L1731985-03-29029 March 1985
Notification of 850403 Meeting W/Util in Bethesda,Md to Discuss Equipment Qualification
Project stage: Meeting
ML20127J8071985-06-11011 June 1985
Maintains Util Position of Full Compliance w/10CFR50.49 in Response to Eh Johnson 850611 Inquiry Re Environ Qualifications of Electrical Equipment Important to Safety. Responses to Each Concern Presented in Encl
Project stage: Other
ML20237L1551985-06-25025 June 1985
Submits Daily Highlight.Notifies of 850702 Meeting W/Util in Bethesda,Md to Discuss State of Compliance of Plant W/ Equipment Qualification Rule 10CFR50.49
Project stage: Meeting
ML20244D4841985-07-10010 July 1985
Provides Feedback on Current NRR Conclusions Re Facility Compliance W/Equipment Qualification Rule & Operator Action Needed to Terminate Design Basis Events.Summary of 850702 Meeting W/Util in Bethesda,Md Encl
Project stage: Meeting
ML20132B9171985-07-11011 July 1985
Discusses Resolution of Technical Issues of Aging & Operability Times Per 850702 Meeting Re Environ Qualification Program.Hold on Reactor Power to 15% Proposed as Initial Limitation
Project stage: Meeting
ML20132F0721985-07-19019 July 1985
Safety Evaluation Documenting Deficiencies in Licensee Program for Environ Qualification of Electric Equipment Important to Safety.Licensee Response to Generic Ltr 84-24 Inadequate.However,Operation at 15% Power Authorized
Project stage: Approval
ML20132F0231985-07-19019 July 1985
Forwards Safety Evaluation Re Environ Qualification of Electric Equipment Important to Safety & Authorizes Interim Operation in dry-out Mode at Max 15% of Rated Power,Based on Listed Conditions,Until Technical Review Completed
Project stage: Approval
ML20134M0161985-08-20020 August 1985
Submits Discussion of Technical Issues Re Environ Qualification Program Raised During Meetings W/Nrc.Aging & Operability Time Program Operator Response Time,Temp Profiles & Shutdown Cooling Paths & Equipment Evaluated
Project stage: Meeting
ML20135D7541985-08-30030 August 1985
Advises That Rev of Emergency Procedures Committed to in Deferred to Coincide W/Final Environ Qualification Program Documentation.Procedure Revs at This Time Will Cause More Confusion than Clarity for Operators
Project stage: Other
ML20135B3011985-08-30030 August 1985
Forwards Justification to Operate Facility at Reduced Power Level.Requests That NRC Provide Concurrence for Facility to Be Operated at 8% Power Level for Period of Time Not to Exceed 45 Days.Operation Does Not Pose Undue Safety Risk
Project stage: Other
ML20205C8451985-09-10010 September 1985
Forwards Info Supporting 850830 Request to Operate at 8% Power to Facilitate Core Dryout for 45 Days,Per 850826,0903 & 04 Telcons.Moisture Removal Needed to Maintain Conditions Prescribed in FSAR & Tech Specs
Project stage: Other
ML20205C4811985-09-11011 September 1985
Provides Commitment That Operating Procedures & Operator Training Described in Providing Addl Info in Support of Request to Operate at Up to 8% Power Will Be Complete Prior to Withdrawal of Control Rods
Project stage: Withdrawal
ML20137S7411985-09-23023 September 1985
Forwards Addl Calculations,Clarifying Util Re Predicted Fuel/Pcrv Liner Temps Resulting from Design Basis Event from 8% Power & Subsequent Reactor Cooling Utilizing Liner Cooling Sys.Calculations Confirm Original Position
Project stage: Other
ML20137H3721985-11-26026 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
ML20151N7211985-12-27027 December 1985
Forwards Response to 851105 Request for Addl Info Needed to Determine If Environ Qualification Program Complies W/ Requirements of 10CFR50.49.Sys Description & Temp Profiles Used in Environ Qualification Program Also Encl
Project stage: Request
ML20141P1811986-01-29029 January 1986
Rev 00 to Justification/Analysis:Environ Qualification of Square D Pressure & Temp Switches
Project stage: Other
ML20141M8081986-02-14014 February 1986
Advises That DBAs Re Permanent Loss of Forced Circulation & Rapid Depressurization of Reactor Vessel Must Be Addressed in Equipment Qualification Program.Util Cooperation W/Program Mods Confirmed During 851029 Meeting
Project stage: Meeting
ML20154K1441986-02-28028 February 1986
Forwards Addl Info Re Environ Qualification,Per 851105 Request.Encl Info for Three Line Break Scenarios in Reactor Bldg Will Allow Independent Verification of Temp Profiles Obtained from Ga Technologies Using Computer Programs
Project stage: Other
ML20142A0441986-03-12012 March 1986
Summary of 860221 Onsite Meeting W/Util,Inel,D Benedetto Assoc,S&W,Tenera,Ned & NPD Re Equipment Qualification Program & Steam Line Rupture Detection & Isolation Sys
Project stage: Meeting
ML20141P1771986-03-14014 March 1986
Summary of 860130 Meeting W/Util,Inel,Tenera & Sargent & Lundy Re Equipment Qualification (EQ) Program.List of Attendees,Test Profiles & Review of Sample EQ Package Encl
Project stage: Meeting
ML20205S2591986-04-10010 April 1986
Summary of 860326 Site Meeting W/Util,Dibenedetto Assoc,Inc, Sandia & Sargent & Lundy Re Status of Qualifications of 10CFR50.49 Cables & Maint Records History Review.Viewgraphs & Attendees List Encl
Project stage: Meeting
ML20204A3181986-05-0101 May 1986
Provides Status Summary of Environ Qualification Program. Addl Details on Program Contained in 860501 Draft Environ Qualification Submittal.Major Equipment Replacements Listed
Project stage: Draft Other
ML20197G5131986-05-12012 May 1986
Requests Concurrence Re Inclusion of DBA in Environ Qualification Program Per Berkow .Util Will Not Environmentally Qualify Electric Equipment to Mitigate DBA-1 & DBA-2 Since Equipment Not Exposed to Harsh Environ
Project stage: Other
ML20198H4561986-05-27027 May 1986
Summary of 860505 Meeting W/Util Re Status of Equipment Qualification Program.Considerable Work Remains Before Approval of Full Power Operation Can Be Granted.Staff Recommended Util Continue to Complete Program
Project stage: Meeting
ML20205S2341986-06-0101 June 1986
Summary of 860502 Meeting W/Util & Inel in Bethesda,Md Re Equipment Qualification Program Problem Areas.Attendees List & Supporting Documentation Encl
Project stage: Meeting
ML20206R6241986-06-20020 June 1986
Forwards Environ Qualification Submittal Re Activities to Assure Compliance w/10CFR50.49 & Incorporating Comments on Draft 860502 Submittal.Evaluations Will Be Available for Review Before Request for Release to Full Power
Project stage: Draft Request
ML20203B6181986-07-15015 July 1986
Summary of 860613 Meeting W/Util in Bethesda,Md Re Status of Plant Equipment Qualification Program.List of Attendees, Environ Qualification of Plant Safe Shutdown Cable & Cable Qualification Binders Encl
Project stage: Meeting
ML20204H6531986-07-31031 July 1986
Responds to 860724 Request for Documentation Re Use of Thermal Lag Analysis in Environ Qualification of Electrical Equipment in Plant.Thermal Analysis Will Be Performed Per Rev 3 to CENPD-255-A
Project stage: Request
ML20206P5971986-08-15015 August 1986
Summary of 860724 Meeting W/Util,Inel,Wyle Labs,Sargent & Lundy & Tenera in Bethesda,Md Re Util Draft Documentation to Justify Qualification of safety-related Cabling at Plant. List of Attendees Encl
IR 05000267/19860251986-10-30030 October 1986
Insp Rept 50-267/86-25 on 860816-0930.Violations Noted: Failure to Follow Procedures,To Review Mod Control Procedures & to Sufficiently Document Design Verification
Project stage: Request
ML20197C5631986-10-30030 October 1986
Forwards Draft FATE-86-117, Review of Convection Heat Transfer Coefficients Utilized in Fort St Vrain Main Steam Line Break Analyses, Technical Evaluation Rept (Ter).Ter Addresses Details Used in Temp Profile Calculations
Project stage: Draft Approval
ML20197C5981986-10-31031 October 1986
Review of Convection Heat Transfer Coefficients Utilized in Fort St Vrain Main Steam Line Break Analyses, Technical Evaluation Rept
Project stage: Other
ML20214Q0951986-11-25025 November 1986
Summary of 861027 Meeting W/Util to Discuss Schedule for Ie/Nrr Insp of Equipment Qualification Program.Attendance List & Viewgraphs Encl
Project stage: Meeting
ML20214U7071986-12-0202 December 1986
Summary of 861120 Meeting W/Util,Ornl,Ga Technologies & Eg&G Re Temp Profiles for Equipment Qualification.List of Attendees & Viewgraphs Encl
Project stage: Meeting
ML20215E4081986-12-12012 December 1986
Forwards Analyses of Three Steam Line Break Scenarios for Reactor Bldg & Three Scenarios for Turbine Bldg Using Convective Heat Transfer Coefficient of 1.0,per NRC 861120 Request
Project stage: Other
ML20215G1001986-12-19019 December 1986
Forwards Second Formal Submittal Re Turbine Bldg Temp Profiles Resulting from Steam Line Breaks,Per 861120 Request.Composite Temp Profile Curves Originally Submitted as Basis for Environ Qualification Program Appropriate
Project stage: Other
ML20207K4701986-12-31031 December 1986
Final Review of Convection Heat Transfer Coefficients Utilized in Fort St Vrain Main Steam Line Break Analysis, Technical Evaluation Rept
Project stage: Other
ML20207K4021987-01-0202 January 1987
Forwards Final FATE-86-117, Review of Convection Heat Transfer Coefficient Utilized in Fort St Vrain Main Steam Line Break Analysis, Technical Evaluation Rept,For Info
Project stage: Approval
ML20207Q4431987-01-16016 January 1987
Confirms 870126-30 Equipment Qualification Insp,Per 870113 Meeting at Region IV Ofcs.Mgt Entrance Meeting Scheduled for 870126 at Site Visitors Ctr & Exit Meeting Tentatively Scheduled for 870130 at Plant Site
Project stage: Meeting
ML20210P5241987-01-29029 January 1987
Forwards Draft Evaluation of Confinement Environ Temps Following High Energy Line Breaks Proposed for Fort St Vrain Environ Qualification Program, Technical Evaluation Rept,In Response to Util 861212 & 19 Submittals
Project stage: Draft Other
ML20210P6451987-01-31031 January 1987
Draft Evaluation of Confinement Environ Temps Following High Energy Line Breaks Proposed for Fort St Vrain Environ Qualification Program, Technical Evaluation Rept
Project stage: Draft Other
ML20211P4951987-02-25025 February 1987
Informs of Present Status & Plans Re Completion of Environ Qualification Program,Per Open Items Identified During 870130 Site Insp.Program & Implementing Procedures to Assure Environ Qualification in Place.Status of Open Items Encl
Project stage: Other
1986-10-31
[Table View] |
Text
_ _ _ _
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UNITED STATES f
g g
NUCLEAR REGULATORY COMMISSION
'; j WASHINGTON, D. C. 20555
\\...../
November 25, 1986 Docket No. 50-267
(
MEMORANDUM FOR: Herbert N. Berkow, Director Standardization and Special Projects Directorate Division of PWR Licensing-B THRU:
- 0. D. T. Lynch, Jr., Section Leade Standardization and Special L
Projects Directorate N
b Division of PWR Licensing-B FROM:
Kenneth L. Heitner, Project Manager Standardization and Special Projects Directorate Division of PWR Licensing-B
SUBJECT:
SUMMARY
OF MEETING WITH PUBLIC SERVICE COMPANY OF COLORADO TO DISCUSS SCHEDULE FOR I&E/NRR INSPECTION OF FORT ST. VRAIN EQUIPMENT QUALIFICATION (EQ) DR0 GRAM, OCTOBER 27, 1986 This meeting was held at the Nuclear Regulatory Commission's Region IV office on October 27, 1986. The purpose of this meeting was to discuss, in detail,theFortSt.Vrain(FSV)EQprogrammajorclosureactionsschedule projection. Meeting attendees are listed in Enclosure 1.
The Public Service Company of Colorado's (PSC) staff reviewed the status of the FSV EQ program and its relationship to the forthcoming EQ inspection, currently scheduled for the week of January 5,1987. The then-current PSC plan was to submit a request to NRC in mid-November to operate the plant at an eight-percent power level beginning December 15, 1986. The purpose of this request is to initiate core moisture dryout which will take approximately 60-days. PSC stated that the plant could operate at a 35-percent power level for the period of February 15 to March 15, 1987. The plant would then shut down on March 15 for two-weeks to install two six-inch vent lines and be ready to operate at an eighty-percent power level on April 1,1987.
The schedule presented by PSC is based on an EQ outage completion date of December 4, 1986. This schedule could be impacted by the EQ work currently in progress on Limitorque motor operators and Rachem splices.
The FSV Program Plan and Major Program Closure Actions Schedule Projection are presented in Enclosures 2 and 3, respectively.
'The FSV temperature profile issue was discussed. The peak tgmperature (U )
F predicted by PSC utilizing the CONTEMPT computer code is 375 while the peak temperature predicted by our consultant, Battelle, using the COBREE j
8612040516 861125 PDR ADOCK 05000267 P
PDR
7----
November 25, 1986 i,'
0 computer code is 487. A rreeting to discuss this issue was scheduled (and i
held) on November 20, 1986.
In view of the importance of this matter to the FSV EQ program, PSC was requested to formulate alternate proposals to address the resolution of this issue.
Original si Kenneth L. gned byHeitner, Project Manager Standardization and Special i
Projects Directorate Division of PWR Licensing-B
Enclosures:
As stated t
cc w/ enclosures:
See next page i
DISTRIBUTION:
l
/ Docket {11e7' NRC PDR r
Local PDR PBSS Reading i
JPartlow JBerkow KHeitner 1'
OGC-Bethesda EJordan BGrimes ACRS(10)
NRC Participants cc: Licensee and Plant Service List 4
t i
4 i
PBSS P-PBS
~
i o rian KHeitner:ac
/
HBerpow 11
/86 11/1 # 86 11/)f/86 11/u/86
1
'o
' computer code is 487. Ameetingtodiscussthisissuewasschebuled(and 0
held) on November 20, 1986.
In view of the importance of this m ltter to the FSV EQ program, PSC was requested to formulate alternate proposa ls to address the resolution of this issue.
l l
Kenneth L. Heitner, Project Manager Standardization and Special Projects Directorate Division of PWR Licensing-B
Enclosures:
As stated cc w/ enclosures:
See next page l
l
Mr. R. O. Williams Public Service Company of Colorado Fort St. Vrain cc:
Mr. D. W. Warembourg, Manager Albert J. Hazle, Direc tor 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 1
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. L. W. Singleton, Manager Public Service Company of Colorado Quality 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 92138 Kelley, Stansfield & 0'Donnell Public Serv. ice 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 Regional Representative Radiation Programs Environmental Protection Agency 1 Denver Place 999 18th Street, Suite 1300 Denver, Colorado 80202-2413
T j
a ENCLOSURE 1 MEETING ATTENDEES I
NRC - Region IV R. E. Ireland J. Jaudon T. Westeman D. Noman M. Skow R. Farrell A. Johnson NRC - I&E G. Hubbard R. F. Heishman NRC - STAFT P. Shemanski PSC M. Niehoff D. Warembourg J. Johns T. Prenger C. Fuller J. Waagg
f ENCLorO RE 2.
FSV EQ PROGRAM PLAN 10CFR50.49 COMMITMENT (PROGRAM DEFINTION) 1 i
r lf DEFINTION OF DESIGN BASIS EVENTS 2
If lf lf if ACCIDENT ACCIDENT ACCIDENT LOCATION (S)
PROFILE (S)
RECOVERY secn sa.4s e 3
4 5
1f I
(a) 7 (d)(3) jf
!!!!a!l!$!$$l IDENTIFICATION OF (e)(+1
!U${!$.(ests).
REQUIRED EQUIPMENT s
. th) 3) 6 (MEL) it!!!!:!!!-
!!!(t).
7
<d)(a) e laj.(h). 03 DETERMINATION OF s
to)t?). (e)te).
EQUIPMENT OPERATING
! ll$ll ! !!Nl PARAMETERS AND jgjJ1(t).
PREFORMANCE SPECIFICATION if iir il 111 if 14 II If II DEVELOPMENT OF LICENSING DEVELOPMENT Of tFD/OR/tt.F/NED EVALURTION AND SUBMITTAL (S)
OUALIFICATION PROGRAM REVIEW S
INCLUDING TECH SPEC g
DATA PACKAGES 10 Y
NRC If lf If If IMPLEMENTATION OF IMPLEMENTATION OF IMPLEMENTATION OF DESIGN CHANGES MATERIAL MANAGEMENT OPERATION, MAIPITENANCE gi AND MODIFICATIONS 12 ACTIVITIES AND SURVEILLANCE 13 ACTIVITIES
_lf_
FINAL CLOSEOUT AND 14 CERTIFICATION
r FORT ST. VRAIN EQ PROGRAM MAJOR PROGRAM CLOSURE ACTIONS E NCL0 TOV.E 3 SCHEDULE PROJECTION Program Area /
Schedule Interim Progrq;ss Major Closure Action Complete 10/24 11/10 12/8 AREA 1 Issue Final Program Document 11/21 Draft in Review AREA 2, 3, 4, S Complete AREA.6 Finalize Engineering Evaluations 10/28 11
'15 15 Total Complete Independent Review 11/7 85%
100%
AREA 7 Complete AREA 8 Approval Of SLRDIS Tech Specs 11/10 Completion Of Profiles SER AREA 9 Equipment Binders Approved 11/19 33 39 46 46 Total-Cable Binders Approved 12/15 10 30 36 Total AREA 10 Prepare / Revise Program Procedures Complete 47 Total Complete Internal Audit 11/14 70%
100%
Finalize Procedures 11/26 AREA 11 Complete EQ Modification Work 12/14 80%
88%
99%
65 EQ CN's Complete Final EQ CN Review 12/19 60%
90%
40 Total AREA 12 350 471 471 Total Complete Final EQ P.O. Review 11/E6 AREA 13 Complete EQ Maintenance SSR's 12/4 915 1005 1150 1150 Total Complete Final SSR Review 12/12 175 800 1050 1150 Total
