Letter Sequence Draft Other |
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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
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Text
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Company of Colorado 2420 W. 26th Avenue, Suite 1000, Denver, Colorado 80211 May 1, 1986 Fort St. Vrain Unit No. 1 P-86350 Director of Nuciear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, D.C.
20555 Attn:
Mr. H.N. Berkow, Director Standardization and Special Projects Directorate Docket No. 50-267
SUBJECT:
Status of Environmental Qualification Program
REFERENCES:
- 1) NRC letter, Denton to Walker, dated February 7, 1986 (G-86062)
- 2) PSC letter, Warenbourg to Berkow, dated May 1, 1986 (Draft EQ Submittal)
Dear Mr. Berkow:
As requested in Reference 1, PSC is providing a status summary of our Environme-t il Qualification (EQ) Program.
This suninary discusses the status / several major items in our EQ Program.
Additional details on the EQ Program are contained in Reference 2 which includes PSC's EQ Submittal. To obtain a more complete understanding of the PSC EQ Program, the NRC staff is directed to that submittal.
EQ Master Eq-lent List The FSV Master Equipment List and the philosophy used to develup the list has been prepared and is included with Reference 2.
kh Do y
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P-86350 Page 2
,fjay lo 1986 Steam Line Rupture Detection / Isolation System (SLRDIS)
A description of SLRDIS is included in reference 2 and described in greater detail in PSC letter P-86208 dated March 14, 1986.
Subsequent to submittal of P-86208, PSC has developed several logic changes to the system which reduce the probability of a single active failure producing a spurious plant shutdown.
PSC is currently incorporating the changes into our final Technical Specification Proposal on SLRDIS and will provide details of the changes to the NRC. Both documents will be submitted to the NRC in May 1986.
Temperature Profiles As discussed in Reference 2,
temperature profiles and the methodology used to develop them were submitted to the NRC by PSC's letter P-86208 dated March 14, 1986. Composite profiles for the Turbine and Reactor Buildings have been incorporated into the applicable portions of the FSV EQ Program.
EQ Binders The following provides an up-to-date status of the FSV EQ binders. PSC is diligently pursuing completion of the binders and incorporation of the informal NRC comments received to date on sample binders. The cable binders have been identified by PSC and the NRC as ones of major concern and impact. PSC and the NRC are currently attempting to schedule a meeting in May 1986 to discuss this issue.
Current Estimate of Total Number of Binders = 69 Number of Binders Received to Date = 40 Number of Binders with Prelininary Review Coments Incorporated = 34 Number of Binders Completed and Signed Off = 0 Maintenance Records As discussed in Reference 2, PSC has completed the initial review of all historical station service requests and plant trouble reports.
We are currently in the final phase of identifying if the maintenance activities have affected the ability to substantiate EQ qualification of any components and will be meeting with the NRC staff on May 2, 1986 to discuss this subject.
P-86350 Page 3 May 1, 1986 Equipment Urg ades PSC has also completed a field EQ walkdown to identify any field conditions which could affect the ability to substantiate EQ qualification of any components. We have currently finalized upgrade recommendations based upon walkdown results and are implementing those which can be accomplished with the plant at power. As would be expected, this is a small percentage of the total work recommended, and the majority will be accomplished during the upcoming (May 31) EQ outage.
Equipment Replacement During the course of implementing the FSV EQ Program, certain electrical equipment items were determined to fall under the Category 1 guidelines of 10CFR50.49.
To achieve this qualification for certain items, replacement was required. Material procurement is in progress, and all replacements are scheduled for the upcoming E0 outage. The following represents the major equipment replacements required:
Item Quantity Solenoid Valves 350 Transmitters 50 Thermocouples 50 Motors 12 Design Modifications PSC has designed several modifications which facilitate initiation of forced circulation cooling by reducing the total number of manual actions required and reducing the reliance on access into potentially harsh ervironments. PSC will be submitting the details of the manual ac ions and their locations in June 1986 per the NRC request in their le ter dated April 6,1986 (G-86181).
~
P-86250 Page 4 May 1, 1986 Ongoing EQ Program PSC's ongoing EQ Program incorporates new procedures and revisions to procedures to assure that 10CFR50.49 equipment qualification is maintained for the life of the FSV plant. This effort is in progress and less than half done at this time.
The procedures involved include the following areas:
Design Procurement Equipment Qualification Quality Assurance Plant Modifications Operation Maintenance Surveillance Training If you have any questions on this status sumary, please contact Mr. M. H. Holmes at (303) 480-6960.
Very truly yours, 0 p.(Yn d, D. W. Warembourg ager Nuclear Engineering Division DW/FWT:pa
