Letter Sequence Other |
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Results
Other: A01155, Forwards Nonproprietary & Proprietary Versions of Test Rept, Hydraulic Flow Test of Model C Prototype Fuel Assembly. Application & Affidavit for Withholding Encl.Proprietary Rept Withheld (Ref 10CFR2.790), A01183, Submits Info Re Justification of Measurement Uncertainty Values for Axial Shape Index,Pressure,Temp,Flow & Power,In Response to NRC 801006 Request, A01184, Submits Resolution of Cycle 4 Startup Commitments,Re Effect of Predicted Bundle Deformation on Heat Transfer from Fuel Rods During Reflooding Stage of LOCA, A01848, Advises That Licensee Will Not Propose License Amend to Tech Specs,Section 5 to Include Guide Tube Sleeving Requirements for Fuel Assemblies Located Under Control Element Assemblies.Current Fixes Adequate, B10342, Part 21 Rept Re Resistance Temp Detectors (RTD) & Associated Signal Processing Equipment Scheduled for Installation During Refueling Outage in Early 1983.Steps Taken to Ensure Reliable RTD Operation in Interim Listed, B10408, Informs of Status of Transient & Accident Analyses Review to Determine Steam Generator Operability W/Approx 1,500 Plugged Tubes.All non-LOCA & Small Break Analyses Remain Valid. Analysis of Large Break Scenario Will Be Docketed by 820212, B10425, Forwards Large Break Loca/Eccs Performance Results W/Addl Plugged Steam Generator Tubes, B10427, Advises That Evaluations of Clad Collapse & Fission Gas Pressure Have Been Performed for C-E Fuel to Be Utilized During Cycle 5, B10433, Submits Addl Info Supporting 820204 Cycle 5 non-LOCA Transient Analyses Results for Addl Plugged Steam Generator Tubes,Per Request.Increasing Number of Tubes Do Not Require Tech Spec Mods, ML19350A511, ML20031C479, ML20040A520, ML20041C396, ML20042C153, ML20042C157
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MONTHYEARA01183, Submits Info Re Justification of Measurement Uncertainty Values for Axial Shape Index,Pressure,Temp,Flow & Power,In Response to NRC 801006 Request1981-01-0808 January 1981 Submits Info Re Justification of Measurement Uncertainty Values for Axial Shape Index,Pressure,Temp,Flow & Power,In Response to NRC 801006 Request Project stage: Other A01155, Forwards Nonproprietary & Proprietary Versions of Test Rept, Hydraulic Flow Test of Model C Prototype Fuel Assembly. Application & Affidavit for Withholding Encl.Proprietary Rept Withheld (Ref 10CFR2.790)1981-03-0606 March 1981 Forwards Nonproprietary & Proprietary Versions of Test Rept, Hydraulic Flow Test of Model C Prototype Fuel Assembly. Application & Affidavit for Withholding Encl.Proprietary Rept Withheld (Ref 10CFR2.790) Project stage: Other ML19350A5111981-03-31031 March 1981 Nonproprietary Version of Hydraulic Flow Test of Model C Prototype Fuel Assembly Project stage: Other A01184, Submits Resolution of Cycle 4 Startup Commitments,Re Effect of Predicted Bundle Deformation on Heat Transfer from Fuel Rods During Reflooding Stage of LOCA1981-06-0808 June 1981 Submits Resolution of Cycle 4 Startup Commitments,Re Effect of Predicted Bundle Deformation on Heat Transfer from Fuel Rods During Reflooding Stage of LOCA Project stage: Other ML20005A9541981-06-22022 June 1981 Submits Physics Review of 800306 Basic Safety Rept.Rept Intended to Serve as Ref Fuel Assembly & Safety Analysis Rept.Rept Acceptable for Ref in Licensing Actions.Review Will Be Completed by 810901 Project stage: Approval A01848, Advises That Licensee Will Not Propose License Amend to Tech Specs,Section 5 to Include Guide Tube Sleeving Requirements for Fuel Assemblies Located Under Control Element Assemblies.Current Fixes Adequate1981-09-11011 September 1981 Advises That Licensee Will Not Propose License Amend to Tech Specs,Section 5 to Include Guide Tube Sleeving Requirements for Fuel Assemblies Located Under Control Element Assemblies.Current Fixes Adequate Project stage: Other ML20031C4791981-09-28028 September 1981 Provides Info Re Guide Tube Wear Experienced in Sleeved C-E, Sleeved Westinghouse,Low Flow C-E & Inset Westinghouse Fuels,Per 801006 Commitment,In Support of Continued Operation W/Modified Guide Tubes in Cycle 5 Project stage: Other ML20031G3521981-10-15015 October 1981 Forwards Supplementary Steam Generator Insp Program - Cycle 5 Reload,Per Amend 61 to License DPR-65 Project stage: Supplement ML20031G3561981-10-31031 October 1981 Supplementary Steam Generator Insp Program - Cycle 5 Reload Project stage: Supplement B10348, Application to Amend Tech Specs for License DPR-56,revising Section 3/4.9.8 Re Shutdown Cooling & Coolant Circulation During Refueling Operations to Increase Flexibility During Leak Testing1981-12-0202 December 1981 Application to Amend Tech Specs for License DPR-56,revising Section 3/4.9.8 Re Shutdown Cooling & Coolant Circulation During Refueling Operations to Increase Flexibility During Leak Testing Project stage: Request B10342, Part 21 Rept Re Resistance Temp Detectors (RTD) & Associated Signal Processing Equipment Scheduled for Installation During Refueling Outage in Early 1983.Steps Taken to Ensure Reliable RTD Operation in Interim Listed1981-12-0808 December 1981 Part 21 Rept Re Resistance Temp Detectors (RTD) & Associated Signal Processing Equipment Scheduled for Installation During Refueling Outage in Early 1983.Steps Taken to Ensure Reliable RTD Operation in Interim Listed Project stage: Other ML20040A3471981-12-24024 December 1981 Forwards Request for Addl Info Necessary to Complete Review of Reload Safety Analysis for Cycle 5 Operation.Info Should Be Submitted by 820111 Project stage: RAI ML20040E2041982-01-12012 January 1982 Forwards Safety Evaluation of Westinghouse Basic Safety Rept.Transient Analysis for Startup of Inactive Reactor Coolant Pump,Excess Load & Loss of Normal Feedwater Acceptable Project stage: Approval B10382, Application to Amend License DPR-65,revising Tech Spec Section 3/4.1.1 Re Shutdown Margin Required in Modes 1-41982-01-14014 January 1982 Application to Amend License DPR-65,revising Tech Spec Section 3/4.1.1 Re Shutdown Margin Required in Modes 1-4 Project stage: Request ML20040A5201982-01-30030 January 1982 Proposed Revision to Tech Spec Section 3/4.1.1,changing Limiting Condition for Operation,Surveillance Requirements & Bases for Shutdown Margin Required in Modes 1-4 Project stage: Other B10408, Informs of Status of Transient & Accident Analyses Review to Determine Steam Generator Operability W/Approx 1,500 Plugged Tubes.All non-LOCA & Small Break Analyses Remain Valid. Analysis of Large Break Scenario Will Be Docketed by 8202121982-02-0404 February 1982 Informs of Status of Transient & Accident Analyses Review to Determine Steam Generator Operability W/Approx 1,500 Plugged Tubes.All non-LOCA & Small Break Analyses Remain Valid. Analysis of Large Break Scenario Will Be Docketed by 820212 Project stage: Other ML20041E1141982-02-18018 February 1982 Forwards Safety Evaluation Re Reactor Fuels & Thermal Hydraulic Sections of Basic Safety Rept (Bsr).Reactor Fuel Design & Thermohydraulic Characteristics Including Transient & Accident Analyses Addressed in Bsr Acceptable Project stage: Approval A02239, Forwards Requested Addl Info Re Response to TMI Action Item I.A.1.1., Shift Technical Advisor.Info Consists of Name,Nuclear Experience,College Courses Completed & Training for Each Nondegreed Shift Technical Advisor1982-02-19019 February 1982 Forwards Requested Addl Info Re Response to TMI Action Item I.A.1.1., Shift Technical Advisor.Info Consists of Name,Nuclear Experience,College Courses Completed & Training for Each Nondegreed Shift Technical Advisor Project stage: Request B10425, Forwards Large Break Loca/Eccs Performance Results W/Addl Plugged Steam Generator Tubes1982-02-19019 February 1982 Forwards Large Break Loca/Eccs Performance Results W/Addl Plugged Steam Generator Tubes Project stage: Other B10433, Submits Addl Info Supporting 820204 Cycle 5 non-LOCA Transient Analyses Results for Addl Plugged Steam Generator Tubes,Per Request.Increasing Number of Tubes Do Not Require Tech Spec Mods1982-02-23023 February 1982 Submits Addl Info Supporting 820204 Cycle 5 non-LOCA Transient Analyses Results for Addl Plugged Steam Generator Tubes,Per Request.Increasing Number of Tubes Do Not Require Tech Spec Mods Project stage: Other B10427, Advises That Evaluations of Clad Collapse & Fission Gas Pressure Have Been Performed for C-E Fuel to Be Utilized During Cycle 51982-02-23023 February 1982 Advises That Evaluations of Clad Collapse & Fission Gas Pressure Have Been Performed for C-E Fuel to Be Utilized During Cycle 5 Project stage: Other ML20041C3961982-02-28028 February 1982 Large Break Loca/Eccs Performance Results W/Addl Plugged Steam Generator Tubes Project stage: Other ML20042C1561982-03-0505 March 1982 Safety Evaluation Supporting Amend 74 to License DPR-65 Project stage: Approval ML20042C1571982-03-0505 March 1982 Notice of Issuance & Availability of Amend 74 to License DPR-65 Project stage: Other ML20042C1531982-03-0505 March 1982 Amend 74 to License DPR-65,authorizing Cycle 5 Operation & Amending App a Tech Specs Project stage: Other 1981-09-11
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General of 6ces e 5.iden Street, Berlin, Connecticut gg g
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m 6589" QL 2 ::T;OZ"%'Cl September 28, 1981 Docket No. 50-336
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W Director of Nuclear Reactor Regulation
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Mr. Robert A. Clark, Chief p 3, raxuAn ncutAton Operating Reactors Branch #3 cc m '555>1 U. S. Nuclear Regulatory Commission T
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Washington, D.C.
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References:
(1)
R. A. Clark letter to W. G. Counsil, dated October 6, 1080.
(2)
W. G. Counsil letter to R. A. Clark, dated September 30, 1980.
Gentlemen:
Millstone NucAear Power Station, Unit No. 2 Resolution of Cycle 4 Startup Commitments In Reference (1), the NRC Staff issued License Amendment No. 61 and the supporting Safety Evaluation to Facility Operating License No.
DPR-65, for Millstone Unit No. 2.
Included in Reference (1) was a commitment by Northeast Nuclear Energy Company (NNECO) to provide an evaluation program to determi e the amount of guide tube wear experienced in each type of fuel (sleeved Combustion Engineering (CE),
'deeved Westinghouse, low flow CE and inset Westinghouse).
Accordingly, NNECO hereby provides the following information in support of continued operation with modified guide tubes in Cycle 5.
Following Cycle 3 operation, NNECO performed eddy current examinations on the guide tube sleeves in six (6) fuel assemblies that were located under control element assemblies (CEA) during Cycle 3.
Eddy current examinations were also performed on the guide tubes of two (2) of the CE demonstration "small-flow-hole" assemblies which were located under CEA's during Cycle 3.
The results of these examinations revealed no indication of guide tube wear.
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Eddy cur /ent examinations of two CEA's indicated no significant wear after thl'e (3) cycles of operation.
During Cycle 4 operation, all fuel assemblies located under CEA's were sleeved except eight (8) test assemblies. The eight (8) test assemblies consist of four (4) CE-reduced flow guide tubes and four (4) Westinghouse assemblies utilizing guide tube insets.
The planned inspection program following Cycle 4 operation hra been designed to address the pertinent operational aspects of guide tube wear prevention methods consisting of CE and Westinghouse guide tube sleeves, reduced flow guide tubes and insets.
In addition, the program will confirm satisfactory performance of the guide tube wear prevention hardwear as well as the acceptability of continued use of the modified guide tubes durir-Cycle 5.
The guide tube inspection program utilizes a combination of eddy current tests, profilometry and visual exas.inations to confirm the acceptability of sleeves, reduced flow guide tubes or insets as methods of mitigating guide tube wear.
(1) Fuel Assembly Guide Tube Inspections Eddy current tests will be performed on 6 to 16 fuel assemblies that were located under CEA's during Cycle 4.
These e:xaminations will include both CE and Westinghouse assemblies, several of which are scheduled to be returned to locations under CEAs during Cycle 5.
The assemblies to be examined include sleeved and reduced flow CE assemblies residing under CEAs for a second cycle and sleeved Westinghouse assemblies residing under CEAs for one cycle.
Visual examinations of several ancemblies will be performed, in-cluding the four Westinghouse inset design assemblics.
v NNECO does not intend to examine any sleeved assemblies not located under CEAs during Cycle 4 since the examinations or assemblies located in non-CEA locations after Cycle 1 revealed no indication of wear.
(2) Control Element Assembly Inspections Eddy current tests will be performed on 2 to 6 CEAs.
The,CEAs to be inspected include several located over fuel assemblies scheduled for the eddy current tests described above. Limited profilometry is also plarned for at least one CEA.
The examinations are in-tended to provide benchmark performance data in an effort to determine life Ihniting effects such as wear and irradiation growth.
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{ I Based on the results of the guide tube. sleeve inspection' programs j
conducted following Cycle 2 and 3 operation, NNECO anticipates that negligible guide tube sleeve wear will be measured. NNECO does 3
not. anticipate any wear of the guide tubes thelpselves in sleeved assemblies of either CE or Westinghouse design. These considerations l
are reflected in the determination of the number of bundles planned y
j for inspection.
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Should NNECO identify any non-conformances or significe.nt deviations during the inspections, a more extensive examination program involving additional assemblies will be undertaken.
1 The above inspection progi.t has been designed to address all aspects of sleeved, reduced flow guide tube and inset operation. The successful i
completion of this program will confirm satisfactory performance of j
operation with modified guide tubes during Cycle 4 and demonstrate the.
1 acceptability of continued use of the guide tubes.during Cycle 5.
L NNECO trusts you find this information responsive to the Reference *(l) commitment.
Very truly yours, NORTHEAST NUCLEAR ENERGY COMPANY I
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a W./U. Couhdil Senior Vice President rs
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