Letter Sequence Other |
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Results
Other: 05000267/LER-1983-043-01, /01T-0:on 831011,during Spec LCO 4.1.9 Review, Assumptions Supporting Analysis Discovered Nonconservative, Obviating Basis for Spec.Interim Conservative Guidelines Followed Until Analysis Completed, ML20082A843, ML20082S949, ML20083F063, ML20084J011, ML20091E302, ML20095A385, ML20125D934, ML20202E952, ML20212G878, ML20214W452, ML20216H730, ML20236U722, ML20237E005
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MONTHYEAR05000267/LER-1983-043-01, /01T-0:on 831011,during Spec LCO 4.1.9 Review, Assumptions Supporting Analysis Discovered Nonconservative, Obviating Basis for Spec.Interim Conservative Guidelines Followed Until Analysis Completed1983-10-25025 October 1983
/01T-0:on 831011,during Spec LCO 4.1.9 Review, Assumptions Supporting Analysis Discovered Nonconservative, Obviating Basis for Spec.Interim Conservative Guidelines Followed Until Analysis Completed
Project stage: Other
ML20082A8431983-11-0707 November 1983
RO 83-43:on 831011,util Notified NRC of Various Nonconservative Errors Made in Original Analyses Which Constitute Basis of Tech Spec 4.1.9.GA Technologies Provided Interim Curves Which Corrected Deficiencies
Project stage: Other
ML20082S9491983-11-30030 November 1983
Forwards Figure for Limiting Condition for Operation 4.1.9-1 Re Circulation Flow/Core Power,To Replace Figure Submitted w/831107 Ltr.Portions of Less Conservative Figure Deleted. Limit Will Be Observed Until Tech Spec Changed
Project stage: Other
ML20083F0631983-12-15015 December 1983
Proposed Tech Specs Revising Limiting Condition for Operation 4.1.9 Re Core Region Temp Rise
Project stage: Other
ML20083F0611983-12-15015 December 1983
Application for Amend to License DPR-34,revising Tech Spec Limiting Condition for Operation 4.1.9 Re Core Region Temp Rise,Per Previous Commitments.Class III Amend Fee Encl
Project stage: Request
ML20086R7281984-02-24024 February 1984
Responds to Request for Addl Info Re Proposed Amend to Limiting Condition for Operation 4.1.9 Re Average Core Temp During Shutdown
Project stage: Request
ML20084J0111984-04-0606 April 1984
ORNL Assistance in Evaluating Licensing Request - Fsv Limiting Condition for Operation 4.1.9, Monthly Rept for Mar 1984
Project stage: Other
ML20091E3021984-05-0909 May 1984
Interim Rept on ORNL Assistance in Evaluating Licensing Request - Amend of Fort St Vrain Reactor Tech Spec Limiting Condition for Operation 4.1.9
Project stage: Other
ML20095A3851984-08-14014 August 1984
Forwards Response to ORNL Concerns & Proposal Identified in NRC .Basis for Discussion of Ornl/Util Concerns & Resolution of Issues Delaying Implementation of Revised Limiting Condition for Operation 4.1.9 Discussed
Project stage: Other
ML20098H1721984-08-21021 August 1984
Provides Replies & Comments to Util Re Tech Spec Limiting Condition for Operation 4.1.9 in Advance of 840823 Meeting W/Util in Arlington,Tx
Project stage: Meeting
ML20099H7931984-11-20020 November 1984
Submits Addl Info Requested by NRC During 840823 Meeting Re Proposed Amend to Limiting Condition for Operation 4.1.9 Concerning Automated Orifice Valve Adjustments.Work Continuing on Listed Remaining Issues
Project stage: Meeting
ML20125D9341985-05-20020 May 1985
Submits Current Status of Work on Tech Spec Limiting Condition for Operation 4.1.9 Re Core Region Temp Rise. Calculational Differences Between Thermal/Hydraulic Analyses Being Investigated.Summary of Open Items Provided
Project stage: Other
ML20133K6751985-10-17017 October 1985
Notifies That Draft Proposed Rev to Tech Spec Limiting Condition for Operation 4.1.9 Re Core Region Temp Rise Will Be Submitted for Review by 851122
Project stage: Draft Other
ML20137E4941985-11-22022 November 1985
Forwards Draft Rev to Tech Spec Limiting Condition for Operation 4.1.9 Re Min Helium Flow/Core Region Temp Rise for Review.Formal Request for Amend to License DPR-34 Will Be Submitted Upon Resolution of NRC Comments
Project stage: Draft Request
ML20141B7451986-03-28028 March 1986
Summary of 860313 Meeting W/Util in Arlington,Tx Re Tech Spec Limiting Condition for Operation 4.1.9 Covering Frequency of Manipulation of Reactor Controls.Supporting Documentation Encl
Project stage: Meeting
ML20211E9171986-06-13013 June 1986
Advises That Formal Application for Tech Spec Rev Re Limiting Condition for Operation 4.1.9, Min Helium Flow & Max Core Region Temp Rise, Will Be Submitted by 860703. Extension Required for Resolution of NRC 860606 Comments
Project stage: Request
ML20202E9261986-07-0909 July 1986
Forwards Application for Amend to License DPR-34,changing Tech Specs to Incorporate Min Helium Flow & Max Core Region Temp Rise Surveillance Requirements.Fee Paid
Project stage: Request
ML20202E9371986-07-0909 July 1986
Application for Amend to License DPR-34,changing Tech Specs to Incorporate Helium Flow & Max Core Region Temp Rise Surveillance Requirements
Project stage: Request
ML20202E9521986-07-0909 July 1986
Proposed Tech Specs,Incorporating Min Helium Flow & Max Core Region Temp Rise Surveillance Requirements
Project stage: Other
ML20214W4521986-10-16016 October 1986
Review of Proposed Tech Spec Change:Core Inlet Orifice Valves/Min Helium Flow & Max Core Region Temp Rise, Technical Evaluation Rept
Project stage: Other
ML20237E0051986-10-16016 October 1986
Forwards Final Version of Facility Limiting Condition for Operation 4.1.9 Technical Evaluation Rept for Review & Approval.Related Info Encl
Project stage: Other
ML20214W4361986-12-0505 December 1986
Forwards Review of Proposed Tech Spec Change:Core Inlet Orifice Valves/Min Helium Flow & Max Core Region Temp Rise. Requests Submittal Addressing Staff Concerns within 45 Days of Ltr Date
Project stage: Approval
ML20212G8781987-01-14014 January 1987
Advises That Util Will Submit Revised Proposal for Tech Spec 4.1.9 Re Min Helium Flow & Max Core Region Temp Rise by 870225.Util Finalizing Curves That Determine Allowed Outage Times for DHR Equipment for Inclusion in Tech Specs
Project stage: Other
ML20216J4731987-06-25025 June 1987
Forwards Application for Amend to License DPR-34,changing Tech Spec Limiting Condition for Operation 4.1.9 to Reduce Potential for Flow Stagnation & Prevent Excessive Fuel Temps in Core & Spec 5.1.8 to Incorporate Requirements.Fee Paid
Project stage: Request
ML20216H7301987-06-25025 June 1987
Proposed Tech Specs,Adding Definition of Calculated Bulk Core Temp & Core Average Inlet Temp for Determination of Core Temp
Project stage: Other
ML20216H7221987-06-25025 June 1987
Application for Amend to License DPR-34,changing Tech Spec Limiting Condition for Operation 4.1.9 to Reduce Potential for Flow Stagnation & Prevent Excessive Fuel Temps in Core & Spec 5.1.8 to Incorporate Associated Requirements
Project stage: Request
ML20236U7221987-08-0606 August 1987
Addendum to Review of Proposed Tech Spec Change:Core Inlet Valves/Min Helium Flow & Max Core Region Temp Rise, Limiting Conditon for Operation 4.1.9, Technical Evaluation Rept
Project stage: Other
ML20236U5041987-11-23023 November 1987
Forwards Amend 57 to License DPR-34 & Safety Evaluation. Amend Revises Tech Specs to Ensure Sufficient Helium Coolant Flow to Prevent Overheating of Fuel While in Low Power or Shutdown Modes
Project stage: Approval
1985-10-17
[Table View] |
Text
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. s.
O Public Service ~
~~ s.,*.
Cmnpany of Cokendo 2420 W. 26th Avenue, Suite 1000, Denver, Colorado 80211 January 14, 1987 Fort St. Vrain Unit No. 1 P-87020 Director of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission Washington, D.C.
20555 Attention:
Mr. H. N. Berkow, Director Standardization and Special Projects Directorate Docket No. 50-267
SUBJECT:
Fort St. Vrain Technical Specification LCO 4.1.9
REFERENCE:
- 1) NRC letter, Heitner to Williams, dated 12/5/86 (G-86631)
- 2) PSC letter, Williams to Berkow, dated 7/9/86 (P-86451)
Dear Mr. Berkow:
This is to advise the NRC that Public Service Company of Colorado (PSC) will submit a revised proposal for Technical Specification LCO 4.1.9, Minimum Helium Flow and Maximum Core Region Temperature Rise, by February 25, 1987.
In Reference 1,
the NRC identified several concerns about the assurances provided for decay heat removal at Fort St.
Vrain (FSV),
as addressed in the LCO 4.1.9 proposal of Reference 2.
PSC was requested to revise the proposed Technical Specification to include curves for explicitly determining allowed outage times for decay heat removal equipment, based on the actual decay heat.
This revised submittal was requested by January 16, 1987.
PSC is finalizing the requested curves, with the intent of including them in the FSV Technical Specifications.
However, FSV personnel are d(
currently concentrating their efforts on equipment qualification and v
8701210220 870114 PDR ADOCK 05000267 ko P
PDR
3
.s P-87020' Page 2 January 14, 1987 plant restart, with the result that.the date for re-submittal of LCO 4.1.9 must be extended.
If you have any questions regarding this letter, please contact Mr.
M. H. Holmes at (303) 480-6960.
Very truly yours, H. L. Brey, Manager Nuclear Licensing and Fuels Division HLB /SWC/ paw i
I.
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