Letter Sequence Meeting |
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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
p public Service Company Cf OcBomHe P.O. BOX 840 DENVER, COLORADO 80201 November 20, 1984 Fort St. Vrain Unit No. 1 P-84504 ggggy@ k Regional Administrator Region IV U. S. Nuclear Regulatory Commission 611 Ryan Plaza Drive, Suite #1000 NOV231984 Arlington, Texas 76011 g
ATTN: Mr. Eric H. Johnson DOCKET NO. 50-267
SUBJECT:
Additional Information on Proposed Amendment to LC0 4.1.9 l
1
REFERENCE:
NRC Memorandum, Wagner to Ireland, Dated September 6, 1984 (G-84345)
Dear Mr. Johnson:
This letter addresses the additicnal information requested by the NRC l
during a meeting on August 23, 1984 regarding the proposed amendment to LC0 4.1.9.
PSC has evaluated automating orifice valve adjustments as a potential means of reducing the transition time between equal flow and equal l
outlet temperature orifice patterns.
We have considered the suggestions made during the meeting. However, due to the complexity of the adjustment process and the potential complications and accident possibilities associated with operatirg orifice valves without direct operator control, it has been concluded that the most practical and advantageous modification would be to simply provide the operator with the capability to reposition each valve faster than l4 0 0 T h 8411280311 e41120 DRADOCK05000g gj\\/
L_
O the existing indexer permits.
Responsibility for developing a suitable modification to permit faster orifice valve repositioning has been assigned to the Nuclear Engineering Division.
LC0 4.2.1 and LC0 4.2.2 are being revised to ensure that the capability to resume core helium flow within a predetermined period of time based on core afterheat using at least one helium circulator will be maintained.
The predetermined period -of time shall be limited such that fuel damage will tiot occur. The revised Technical Specification will include requirements for power, low power and shutdown conditions which will define the minimum levels of circulator operability for each case.
The proposed Technical Specification Amendment is expected-to be submitted to the NRC by December 31, 1984.
We have also reevaluated the existing LCOs 4.1.3, 4.1.7, and 4.1.9 with consideration to integrating the. requirements into a single limitation.
Our conclusion is tha+ the LCOs are not amenable to being integre.ed. The fundamental difticulty is that they deal with diverse and independent parameters.
LC0 4.1.3 - Rod Sequence deals with control rod reactivity worth, while LC0 4.1.7 Inlet Orifice Valves deals with region outlet coolant temperature variances, and LCO 4.1.9 - Core Region Temperature Rise deals with coolant flow.
Integration of these LCOs would necessitate a technical specification significantly more complex, more confusing, and more difficult to implement than the current ones. Therefore, we have decided not to attempt to integrate them.
Work is continuing on the following remaining issues:
Sources of core flow and core power level indications available to the operator.
The impact of a limited number of mispositioned orifice valves on the transition between equal flow valve positions and equal outlet temperature valve positions.
Correcting the nonconservatism in the calculation of the pressure drop through the orifice valve discovered in July 1
1984.
Evaluating various sources of motive power to enhance circulator helium flow capabilities.
m
l 3
Additional information on these issues will~ be submitted by January 15, 1984. If you have any questions in the meantime, please contact Mr. M. H. Holmes at (303) 571-8409.
Very truly yours,
)]-tWW H. L. Brey Executive Staff Assistant Electric Production HLB /JL/kt L'
