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Administration
- 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 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 ML20132E6081985-07-19019 July 1985 Supplemental Safety Evaluation Supporting Licensee CRD Mechanisms & Associated Position Instrumentation,Per 850712 Safety Evaluation & Licensee 850710 & 18 Submittals.Control Rod Program Acceptable for Plant Restart Project stage: Request 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 IR 05000267/19850211985-08-30030 August 1985 Insp Rept 50-267/85-21 on 850721-31.No Violation or Deviation Noted.Major Areas Inspected:Operational Safety Verification Project stage: Request 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 ML20137X1241985-09-30030 September 1985 Forwards Safety Evaluation Based on Util 850830,0910,11 & 23 Requests for Authorization to Operate at Max 8% Power,For Up to 45 Days,To Remove Moisture from Rcs.Authorization Granted,Subj to Listed Commitments Project stage: Approval ML20137X1411985-09-30030 September 1985 Safety Evaluation Supporting Util 850830,0910,11 & 23 Requests for Authorization to Operate at Max 8% Power,For Up to 45 Days,To Remove Moisture from RCS Project stage: Approval ML20138E3921985-10-11011 October 1985 Forwards Request for Addl Info on 850924 Request for Special Consideration & Schedule Extension to Equipment Qualification rule,10CFR50.49.Info Requested within 7 Days of Ltr Receipt Project stage: RAI ML20138C8111985-10-21021 October 1985 Forwards Response to 851011 Request for Addl Info Re 850924 Request for Schedule Extension for Environ Qualification Program Under 10CFR50.49 from 851130 to 860331 Project stage: Request ML20138R7331985-10-31031 October 1985 Summary of 851029 Meeting W/Util & ORNL Re Schedule Extension to Equipment Qualification Rule.List of Attendees, Agenda & Matls Presented by Util Encl Project stage: Meeting ML20209J0821985-11-0505 November 1985 Forwards Request for Addl Info Re Equipment Qualification Program & Request for Extension of Deadline for Compliance W/Equipment Qualification Rule,Per 851029 Meeting Project stage: RAI ML20136F6991985-11-19019 November 1985 Modifies Scheduled Commitment for Submittal of Final Draft Proposal of Upgraded Tech Specs for NRC Comment,Per 851008 Request.Revised Submittal Date of 851130 Approved.Revised Tabulation of Commitments Encl Project stage: Draft Other ML20136J1831985-11-21021 November 1985 Staff Requirements Memo Re Commission 851119 Meeting in Washington,Dc on Licensee Environ Qualification Exemption Request.Recommendation on Extension Request Should Be Provided by 851122 Project stage: Meeting ML20136J0151985-11-22022 November 1985 Notifies of Withdrawal of 850924 Schedule Extension Request for Environ Qualification Program.Approval of Revised Schedule Extension for Implementation of Program Beyond 851130 Under Provision of 10CFR50.49 Requested Project stage: Withdrawal 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 ML20137Z3631985-12-0505 December 1985 Staff Requirements Memo Re Affirmation/Discussion & Vote on Extension of 851130 Deadline for Environ Qualification & Revised Post 851130 Environ Qualification Extension Request Project stage: Other ML20138B5121985-12-10010 December 1985 Forwards Evaluations to Document Completion of Confirmatory Actions Required to Support 35% Power Restriction During Environ Qualification Schedule Extension Period Project stage: Other ML20138L4071985-12-10010 December 1985 Rev B to EE-EQ-0019, Engineering Evaluation of Liner Cooling W/Fire Water Following High Energy Line Break from 35% Power Operation at Fort St Vrain Project stage: Other ML20136C8221985-12-26026 December 1985 Forwards Request for Addl Info to Complete Resolution of Confirmatory Action 6 Re Insp of High Energy Piping.Concerns Include Potential for Inservice Degradation & Exam & Insp Methods Project stage: RAI 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 ML20137L9261985-12-31031 December 1985 Heat Stress Mgt Program for Nuclear Power Industry, Interim Rept Project stage: Other ML20141E5271986-01-0303 January 1986 Forwards Summary of Position on Confirmatory Action 6 Re Insp of Critical Areas of High Energy Piping & Responses to Six Addl Info Requests.Limited Insp Plan Will Be Completed by Middle of Jan 1986.Drawings Encl Project stage: Other ML20141H5341986-01-0808 January 1986 Forwards NDE Procedures,Per DW Warembourg Project stage: Other ML20141H5441986-01-0808 January 1986 Issue 1 to NDE Procedure QCIM-38, Ultrasonic Exam of Class 1 & 2 Piping Welds Joining Similar & Dissimilar Matls Project stage: Other ML20141H5491986-01-0808 January 1986 Issue 5 to NDE Procedure QCIM-30, Radiographic Exam Procedure Project stage: Other ML20137M1091986-01-15015 January 1986 Forwards Addl Info to Support Util Intention to Use Ice Vests to Allow Personnel Access W/Elevated Bldg Temps. T Bernard Prof Opinion Documented in Encl Draft Heat Stress Mgt Program. Rept Available in Central Files Project stage: Draft Other ML20137L9001986-01-21021 January 1986 Forwards EPRI Interim Rept, Heat Stress Mgt Program for Nuclear Power Industry, to Replace Draft Transmitted by Walker ,To Support 35% Power Bldg Access.Rept Will Be Available in Mar as EPRI NP4453 Project stage: Draft Other ML20151R0741986-01-29029 January 1986 Informs That NRR Ltr to Licensee Summarizing Findings Re Environ Qualification Extension Sufficient to Authorize Limited Operation.No License Amend Required to Support Authorization Project stage: Other 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 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 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 ML20154N1501986-03-0303 March 1986 Forwards Final Rept on Inservice Insp Program Performed on High Energy Piping.Program Inspected 35 Critical Areas of Piping Per Safety Evaluation of Confirmatory Item 6. Integrity Verified in Support of 35% Power Operation Project stage: Other 1985-03-28
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Category:LEGAL TRANSCRIPTS & ORDERS & PLEADINGS
MONTHYEARML20237B6261998-08-0606 August 1998 Comment on NUREG-1625 (Draft), Proposed STS for Permanently Defueled W Plants ML20093G4651995-10-16016 October 1995 Comment on Proposed Rules 10CFR2,50 & 51 Re Decommissioning of Nuclear Power Reactors.Endorses Nuclear Industry Comments Provided by NEI ML20072B2751994-08-0303 August 1994 Comments on Proposed Rule Re Consideration of Changes to fitness-for-duty Requirements.Advises That fitness-for-duty Requirements Should Not Be Applied to Sf Storage Facility Licensees Nor to Nonpower Reactor Licensees ML20064L8631994-03-10010 March 1994 Comment Supporting Proposed Rule 10CFR20 Re Developing Radiological Criteria for Decommissioning ML20063J5771994-02-0808 February 1994 Comment Supporting Draft Rept, Revised Analyses of Decommissioning for Ref Pressurized Water Reactor Power Station, NUREG/CR-5884 ML20058E0151993-11-14014 November 1993 Comment Opposing Proposed Rule 10CFR50 Re Exemptions in Accident Insurance for Nuclear Power Plants Prematurely Shut Down ML20046B1361993-06-28028 June 1993 Comment on Proposed Rule 10CFR20 Re Radiological Criteria for Decommissioning NRC-licensed Facilities.Endorses Comments Made by NUMARC ML20128D7061992-12-0101 December 1992 Exemption from Requirement of 10CFR50.54(q) to Change to Biennial Emergency Plan Exercise Rather than Annual Following Completion of Next Scheduled Exercise ML20085M3351991-11-0101 November 1991 Comment on Proposed Rule 10CFR50 Re Decommissioning Funding for Prematurely Shutdown Power Reactors ML20246H6541989-07-0505 July 1989 Comment Opposing Proposed Rule 10CFR50, Acceptance of Products Purchased for Use in Nuclear Power Plant Structures,Sys & Components ML20235T4441989-02-24024 February 1989 Comment on Proposed Rule 10CFR50 Re Ensuring Effectiveness of Maint Programs for Nuclear Power Plants.Potentially Adverse Aspects of Proposed Rule Include Poor Definitions of Maint & balance-of-plant,maint Surveillance & QA ML20206M7721988-11-21021 November 1988 Comment Supporting Proposed Rule 10CFR26 Re Fitness for Duty Program ML20155F9961988-09-30030 September 1988 Exemption from Schedular Requirements of Property Insurance Rule 10CFR50.54(w)(5)(i),effective 881004.Exemption Granted ML20151K8281988-07-25025 July 1988 Comments Opposing Proposed Mods to 10CFR170 & 171 Re Making Licensing Fees More Appropriate to NRC Costs Incurred in Providing Svcs to Each Reactor.Supports Option to Defer Effect of 10CFR170 Until Next Yr ML20154F8661988-05-10010 May 1988 Exemption from Technical Requirements of App R,Sections Iii.G & Iii.J to 10CFR50 ML20215J2721987-06-17017 June 1987 Transcript of 870617 Public Meeting in Washington,Dc Re Discussion/Possible Vote on Util Authorization to Exceed 35% Power Level.Pp 1-62.Supporting Documentation Encl ML20212G2131987-02-26026 February 1987 Transcript of 870226 Meeting in Washington,Dc.Pp 1-72. Supporting Documentation Encl ML20203P1951986-10-17017 October 1986 Transcript of Commission 861017 Briefing in Washington,Dc Re Facility.Pp 1-70.Supporting Documentation & Meeting Viewgraphs Encl ML20155A6511986-04-0202 April 1986 Transcript of ACRS Subcommittee on Fort St Vrain 860402 Meeting.Pp 1-249.Supporting Documentation Encl ML20137R8771985-11-26026 November 1985 Transcript of 851126 Affirmation/Discussion & Vote in Washington,Dc Re Extension of Environ Qualification Deadline for Fort St Vrain & Pilgrim.Pp 1-5 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 ML20137L3521985-11-19019 November 1985 Transcript of 851119 Meeting in Washington,Dc Re Environ Qualification Exemption Request for Fort St Vrain.Pp 1-71. Viewgraphs Encl 1998-08-06
[Table view] Category:ORDERS
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 1985-11-26
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UNITED STATES OF AMERICA fiUCLEAR REGULATORY COMMISSION I:' ,
COMMISSIONERS:
Nunzio J. Palladino, Chairman SERVED NOV 2; Ica;~
Thomas M. Roberts James K. Asselstine Frederick M. Bernthal Lando W. Zech, Jr.
)
PUBLIC SERVICE COMPANY OF COLORAD0 )
) Docket No. 50-267 O b (Fort St. Vrain Nuclear Generating )
Station) )
)
MEMORANDUM AND ORDER By letters dated September 24, 1985, and October 22, 1985, the Public Service Company of Colorado (PSC) requested that the Commission grant an extension until March 31, 1986, for environmental qualification of electrical equipment at the Fort St. Vrain Nuclear Generating Station (FSV). In a subsequent meeting with the NRC staff on November 18, 1985, the licensee agreed to modify its position, and provided a revised request by letter dated November 22, 1985. The Commission met with the staff on November 19 to review the licensee's request; at this meeting utility representatives responded to several Conmission questions on equipment qualification and related matters.
The Commission has reviewed in detail the licensee's submittals, the staff's analysis and recommendation as set forth in SECY-85-370, and 0512020377 051126 PDR ADOCK 05000267
}3ch
2 has considered all additional information provided at the November 19 meeting. Based on this review the Conmission fir,is that the licensee has demonstrated exceptional circumstances warranting approval of its revised request. However, in accordance with the staff's request, the licensee will be required to provide an acceptable confirmatory submittal before plant operation is approved.
The Commission most recently addressed the environmental qualifica-tion issue in Generic Letter 85-15, issued August 6, 1985. In that letter the Commission stated that extensions from the November 30 deadline established in 10 C.F.R. 50.49(g) would be granted "only in rare circumstances." The Commission further stated that extension requests "must clearly identify the exceptional nature of the case, e.g. , why, through events entirely beyond its control, the licensee will not be in compliance on November 30; the date when compliance will be achieved; and a justification for continued operation until compliance will be achieved." The Commission also set forth an enforcement policy regarding failure to meet the deadline.
The Fort St. Vrain facility is a high-temperature gas-cooled reactor (HTGR) located in north-central Colorado. It is the only commercial reactor of its kind operating in the United States. This type of reactor utilizes helium as coolant and graphite as a moderator, and thus is very different in operating characteristics from other commercial power reactors, in which water performs the dual function of coolant and moderator. In its decision authorizing construction of this facility, the Conmission noted that this design incorporates certain unique safety features:
4 3
These include: the strong prompt negative temperature coeffi-cient of the reactor; the ability of graphite, from which all structural members within the core are to be fabricated, to maintain mechanical integrity to very high temperatures; the chemically inert nature of the reactor's helium coolant and the fact that most of the radioactive fission products produced in operation will be retained inside the multiple layers of pyrolytic carbon and silicon carbide which will coat the fuel particles in the reactor core.
Public Service Cocoany of Colorado (Fort St. Vrain Nuclear Generating Station), 4 AEC 214, 215 (1969). These factors lead to a slow core thermal response to a loss of coolant circulation. While in a light-water reactor a loss-of-coolant accident must be recovered on the order of minutes and hours, the FSV design allows up to several days before fuel failure could be expected. This additional time would allow many more operator actions to be taken to restore coolant circulation in the event of an accident.
The licensee apparently relied on these inherent safety character-istics in maintaining, as early as 1980, that FSV met the Commission's requirements for environmental qualification of electrical equipment irarcrtant to safety. The licensee held to that position after the Commission promulgated 10 C.F.R. 50.49 in early 1983. The NkC staff did not undertake a detailed review of the licensee's position on equipment qualification until 1984. As this review progressed it became clear that there was substantial disagreement between the staff and the licensee on the applicability of 10 C.F.R. 50.49 requirements to FSV.
Numerous meetings have been held between the staff and licensee to resolve technical issues, and the licensee has made several major submittals in response to staff questions.
f 4
This interchange, albeit late in the Commission's intended schedule for completion of the equipment qualification program, has now resulted in substantial agreement between the licensee and the staff on what steps must be taken to place FSV in compliance with 10 C.F.R. 50.49.
However, the licensee will be unable to complete all aspects of its equipment qualification program until the end of May 1986. The licensee has therefore requested an extension from the November 30 deadline [see 10 C.F.R. 50.49(g)] until May 31, 1986. Initially this request was for full-power operation, with an extension to March 31, 1986.
The staff, however, was unable to accept the licensee's justifica-tion for operation at 100 percent power given the current status of the FSV qualification program. Based upon engineering calculations performed independently by the licensee crd the staff, however, it became clear that operation at no greater than thirty-five percent power could be justified for the interim period until the environmental qualification program could be completed. The licensee modified its request for authorization to operate at or below the thirty-five percent level pending acceptance by the staff of the licensee's equipment qualification program. The licensee requested an extension of the November 30, 1985 deadline until May 31, 1986. The Commission discussed this approach with the staff at the November 19 meeting, and reviewed ,
the details of the proposal provided in SECY-85-370.
The record indicates that FSV's unique design contributed to its current difficulties, as did the lack of a detailed staff review of its equipment qualification program until late in the section 50.49(g) schedule. The record also shows that the licensee has in the recent
5 past devoted increased resources and management attention to this important safety matter, leading to an expected completion of the program within six months.
Under these circumstances, the Commission finds that the licensee has met the criteria for an exceptional case and grants an extension from the November 30 deadline to May 31, 1986. The Commission also concit. des that the proposal to allow operation in the interim with a limit on reactor power level of thirty-five percent will not present an undue risk to the public health and safety in the interim period, contingent upon the staff's acceptance of the licensee's confirmatory analyses. PSC will submit the results of its confirmatory analyses and the NRC staff will review and approve those analyses before FSV is permitted to operate at power levels up to the thirty-five percent power restriction. This extension of the environmental qualification deadline is subject to three conditions:
- 1. During the interim period, until the environmental qualification progran is complete, reactor power shall be limited to thirty-five percent.
- 2. Actual authorization of operation up to thirty-five percent shall be made by the Director, NRR, upon finding the licensee's confirmatory analyses acceptable.
- 3. Operation above thirty-five percent power is conditicnal upon completion of the equipment qualification program
6 and its approval by the Director, NRR, and the Director, IE.
It is so ORDERED.
40 ; 4f For the Comission
! fs
- .%9 f/o/ b ~
SAMUEL J. CHILK h.x' 44,,, Secretary of tlie Comission Dated at Washington, D.C.
this25[dayofNovember,1985.