Letter Sequence Other |
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Results
Other: 05000336/LER-1986-010-02, :on 861006,inconsistency Identified Between Safety Analysis for Control Element Assembly (CEA) & Tech Specs for Modes 3,4 & 5.Caused by Assumption That Hot Zero Power Results for CEA Withdrawn, B12238, Forwards Item II.K.3.31,NUREG-0737,Small-Break LOCA Evaluation,Large-Break LOCA Evaluation, Per Wg Counsil to DG Eisenhut & EP Rahe to Co Thomas. Analyses Will Be Ref in Proposed License Amend, B12310, Proposed Tech Specs Allowing Reduction in RCS Flow Rate from Current Value of 350,000 to 340,000 Gpm & Reducing Total Integrated Radial Peaking Factor, B12440, Startup Test Rept Cycle 8, ML20207S981, ML20209E851, ML20209F721, ML20211M265, ML20215K241, ML20215N796, ML20215N827
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MONTHYEARB12238, Forwards Item II.K.3.31,NUREG-0737,Small-Break LOCA Evaluation,Large-Break LOCA Evaluation, Per Wg Counsil to DG Eisenhut & EP Rahe to Co Thomas. Analyses Will Be Ref in Proposed License Amend1986-08-29029 August 1986
Forwards Item II.K.3.31,NUREG-0737,Small-Break LOCA Evaluation,Large-Break LOCA Evaluation, Per Wg Counsil to DG Eisenhut & EP Rahe to Co Thomas. Analyses Will Be Ref in Proposed License Amend
Project stage: Other
ML20209E8511986-08-31031 August 1986
Item II.K.3.31,NUREG-0737,Small-Break LOCA Evaluation, Large-Break LOCA Evaluation
Project stage: Other
ML20215N8271986-09-30030 September 1986
Rev 2 to Reload Safety Evaluation,Millstone Nuclear Power Station,Unit 2 Cycle 8
Project stage: Other
B12224, Application for Amend to License DPR-65,changing Tech Specs to Revise pressure-temp Limits & Max heat-up & cool-down Rates for Rcs.Fee Paid1986-10-20020 October 1986
Application for Amend to License DPR-65,changing Tech Specs to Revise pressure-temp Limits & Max heat-up & cool-down Rates for Rcs.Fee Paid
Project stage: Request
ML20215K2411986-10-20020 October 1986
Proposed Tech Specs Revising pressure-temp Limits & Max heat-up & cool-down Rates for RCS
Project stage: Other
B12240, Application to Amend License DPR-65,revising Tech Specs to Reduce Frequency of Surveillance Requirement for Determining Reactor Coolant Flow Rate.Fee Paid1986-10-24024 October 1986
Application to Amend License DPR-65,revising Tech Specs to Reduce Frequency of Surveillance Requirement for Determining Reactor Coolant Flow Rate.Fee Paid
Project stage: Request
ML20215N8131986-10-27027 October 1986
Application for Amend to License DPR-65,allowing Reduction in RCS Flow Rate & Reducing Total Integrated Radial Peaking Factor.Forwards Westinghouse Rev 2 to Reload Safety Evaluation Millstone...Unit 2 Cycle 8. Fee Paid
Project stage: Request
B12310, Proposed Tech Specs Allowing Reduction in RCS Flow Rate from Current Value of 350,000 to 340,000 Gpm & Reducing Total Integrated Radial Peaking Factor1986-10-27027 October 1986
Proposed Tech Specs Allowing Reduction in RCS Flow Rate from Current Value of 350,000 to 340,000 Gpm & Reducing Total Integrated Radial Peaking Factor
Project stage: Other
ML20215N7961986-10-29029 October 1986
Notice of Consideration of Issuance of Amend to License DPR-65 & Proposed NSHC Determination & Opportunity for Hearing on 861020,24 & 27 Requests to Revise Tech Specs Re Temp Pressure Limits,Surveillance Frequency & RCS Flow
Project stage: Other
05000336/LER-1986-010-02, :on 861006,inconsistency Identified Between Safety Analysis for Control Element Assembly (CEA) & Tech Specs for Modes 3,4 & 5.Caused by Assumption That Hot Zero Power Results for CEA Withdrawn1986-11-0404 November 1986
- on 861006,inconsistency Identified Between Safety Analysis for Control Element Assembly (CEA) & Tech Specs for Modes 3,4 & 5.Caused by Assumption That Hot Zero Power Results for CEA Withdrawn
Project stage: Other
A06096, Forwards Addl Justification for 861020 Application to Amend License DPR-65 to Facilitate NRC Review of Small & Large Break Locas.Amend Incorporates Changes Relative to Revised pressure-temp Limit Curves1986-12-0101 December 1986
Forwards Addl Justification for 861020 Application to Amend License DPR-65 to Facilitate NRC Review of Small & Large Break Locas.Amend Incorporates Changes Relative to Revised pressure-temp Limit Curves
Project stage: Request
ML20211M2841986-12-0808 December 1986
Safety Evaluation Supporting Amend 113 to License DPR-65
Project stage: Approval
ML20211M2651986-12-0808 December 1986
Amend 113 to DPR-65,changing Tech Specs to Provide for Revised Temp/Pressure Limits in Tech Spec 3/4.4.9, Pressure /Temp Limits & Tech Spec Figure 3.4-2, RCS Pressure Temp Limitations for 12 Full Power Yrs
Project stage: Other
ML20207S9811987-03-16016 March 1987
Forwards Millstone Nuclear Power Station Unit 2 Startup Test Rept Cycle 8. Plant Achieved Criticality on 861214 & Reached 100% Power on 870101
Project stage: Other
B12473, Submits Addl Info in Support of 870206 Application for Amend to License DPR-65,revising Tech Specs Re Operability of CRD Mechanisms.High Power Reactor Trip Required Only Under Listed Conditions1987-03-20020 March 1987
Submits Addl Info in Support of 870206 Application for Amend to License DPR-65,revising Tech Specs Re Operability of CRD Mechanisms.High Power Reactor Trip Required Only Under Listed Conditions
Project stage: Request
B12440, Startup Test Rept Cycle 81987-03-31031 March 1987
Startup Test Rept Cycle 8
Project stage: Other
ML20209F7271987-04-21021 April 1987
Safety Evaluation Supporting Amend 116 to License DPR-65
Project stage: Approval
ML20209F7211987-04-21021 April 1987
Amend 116 to License DPR-65,creating Tech Spec 3/4.1.7, CRD Mechanisms & Changing Tech Spec 3/4.3.1 to Extend Operability & Surveillance Requirements for Reactor Protection Sys Power level-high Trip Function to Mode 3
Project stage: Other
1986-12-08
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March 16,1987 Docket No. 50-336 B12440 Re: Technical Specifications U.S. Nuclear Regulatory Commission Attn:
Document Control Desk Washington, D.C. 20555 Gentlemen:
Millstone Nuclear Power Station, Unit No. 2 Start-Up Test Report for Cycle 8 Millstone Unit No. 2 achieved criticality on December 14, 1986 and reached 100% power on January 1,1987 following its refueling outage. As required by the Millstone Nuclear Power Station Unit No. 2 Technical Specifications, Section 6.9, Northeast Nuclear Energy Company hereby submits the attached Millstone Unit No. 2 Cycle 8 Start-Up Test Report.
We trust you will find this information satisfactory.
Very truly yours, NORTHEAST NUCLEAR ENERGY COMPANY W !W E. 33 foczka f
Senior)Vice President cc:
Dr. T. E. Murley, Region I Administrator D. H. Jaffe, NRC Project Manager, Millstone Unit No. 2 T. Rebelowski, Resident Inspector, Millstone Unit Nos. I and 2 8703230017 870316 PDR ADOCK 05000336 P
PDR
