Letter Sequence Other |
|---|
|
Results
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 820212, B10420, Forwards Addl Info Supporting Amend to Ol,To Limit Steam Generator Inservice Insps During Cycle 5 Refueling Outage, B10425, Forwards Large Break Loca/Eccs Performance Results W/Addl Plugged Steam Generator Tubes, B10581, Describes Activities Currently Planned for 1983 Refueling Outage to Assure Continued Operability of Steam Generators. Any Licensing Action Will Be Initiated in Time to Support Scheduled 830416 Outage, ML20040A554, ML20040A557, ML20040C965, ML20041C396, ML20042C036, ML20042C042, ML20049J152, ML20054F221
|
MONTHYEARML20040A5541982-01-12012 January 1982
Steam Generator Eddy-Current Test Results,Jan 10,1982
Project stage: Other
ML20040A5501982-01-12012 January 1982
Application to Amend License DPR-65,changing Tech Spec Table 4.4-6 to Delete Category C-3 Tubes from Steam Generator Tube
Project stage: Request
ML20040C9651982-01-22022 January 1982
Forwards Revised Figures 1-4 Which Define Affected Areas of Steam Generator Tube Bundle to Which Util Proposed to Limit Cycle 5 Refueling Outage Steam Generator eddy-current Exams. Revised Figures Part of Proposal to Limit Inservice Insp
Project stage: Other
ML20040A5571982-01-31031 January 1982
Proposed Revision to Tech Spec Table 4.4-6,deleting Category C-3 Tubes from Steam Generator Tube Insp
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
B10384, Forwards Addl Info in Support of Util 820112 Application to Amend OL to Limit Steam Generator Tube Inservice Insps Conducted During Cycle 5 Refueling Outage.Revised Tube Maps of Defects Found During Eddy Current Exams Encl1982-02-0505 February 1982
Forwards Addl Info in Support of Util 820112 Application to Amend OL to Limit Steam Generator Tube Inservice Insps Conducted During Cycle 5 Refueling Outage.Revised Tube Maps of Defects Found During Eddy Current Exams Encl
Project stage: Request
ML20041B6101982-02-10010 February 1982
Notification of 820216 Meeting W/Util in Bethesda,Md to Discuss Encl Meeting Agenda Re Steam Generator Review
Project stage: Meeting
B10420, Forwards Addl Info Supporting Amend to Ol,To Limit Steam Generator Inservice Insps During Cycle 5 Refueling Outage1982-02-12012 February 1982
Forwards Addl Info Supporting Amend to Ol,To Limit Steam Generator Inservice Insps During Cycle 5 Refueling Outage
Project stage: Other
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
ML20041C3961982-02-28028 February 1982
Large Break Loca/Eccs Performance Results W/Addl Plugged Steam Generator Tubes
Project stage: Other
B10448, Application for Amend to License DPR-65,providing Daily Sampling for Gross Activity in Each Steam Generator During Cycle 5 Operation to Assure Prompt Detection & Monitoring of Primary to Secondary Leakage1982-03-0404 March 1982
Application for Amend to License DPR-65,providing Daily Sampling for Gross Activity in Each Steam Generator During Cycle 5 Operation to Assure Prompt Detection & Monitoring of Primary to Secondary Leakage
Project stage: Request
ML20042C0361982-03-0505 March 1982
Amend 73 to License DPR-65,changing Tech Specs to Allow Reactor Heatup for Cycle 5 Operation W/Less than 100% Insp of Tubes in Each Steam Generator
Project stage: Other
ML20042C0421982-03-0505 March 1982
Notice of Issuance & Availability of Amend 73 to License DPR-65
Project stage: Other
ML20042C0381982-03-0505 March 1982
Safety Evaluation Supporting Amend 73 to License DPR-65
Project stage: Approval
ML20049J1521982-03-31031 March 1982
Proposed Tech Spec Page 3/4 7-8,providing Daily Sampling for Gross Activity in Each Steam Generator During Cycle 5 Operation to Assure Prompt Detection & Monitoring of Primary to Secondary Leakage
Project stage: Other
ML20054F2211982-06-0202 June 1982
Forwards Cycle 5 Refueling Outage Steam Generator Profilometry Insp Results,Per Util .Results Confirm Integrity of Steam Generator Tubes & Supports & Assure Continued Applicability of Design Basis Analyses
Project stage: Other
B10581, Describes Activities Currently Planned for 1983 Refueling Outage to Assure Continued Operability of Steam Generators. Any Licensing Action Will Be Initiated in Time to Support Scheduled 830416 Outage1982-11-19019 November 1982
Describes Activities Currently Planned for 1983 Refueling Outage to Assure Continued Operability of Steam Generators. Any Licensing Action Will Be Initiated in Time to Support Scheduled 830416 Outage
Project stage: Other
B10724, Application for Amend to License DPR-65,revising Tech Specs Re Steam Generator Inservice Insp1983-03-14014 March 1983
Application for Amend to License DPR-65,revising Tech Specs Re Steam Generator Inservice Insp
Project stage: Request
1982-02-28
[Table View] |
Text
.
Docket No. 50-336 Millstone Nuclear Power Station, Unit No. 2 Proposed Revisions to Technical Specifications Primary-to-Secondary Leakage Monitoring and Reporting During Cycle 5 March, 1982 8203120161 820304 PDR ADOCK 05000336 p
PDR
TABLE 4.7-2 55CONDARYCCOLANTSYSTEMSPECIFICACTIVITY
~
SAMPLE AND ANALYSIS PROGRAM TYPE OF MEASUREMENT AND ANALYSIS MINIMUM
_FREGUENCY 1.
Gross Activity Determination
with a maximum time of 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> between
~
samples
~
2.
Isotocic Anal'ysis for DOSE EQUIVALENT I-131 Concentration a) 1 per 31 days, when-ever the gross activity
~
determination indicates iodine concentrations greater than 10% of the allowable limit.
J b) 1 per 6 months, when-ever the gross activity determination indicates iodine concentrations below 10% of the allcwable limit.
- During Cycle 5, the gross activity of each steam generator shall be determined daily to monitor the extent, if any, of primary-to-secondary leakage.
The following reports shall be provided to the assigned NRC Project Manager in the event of primary-to-secondary leakage:
1.
The baseline primary-to-secondary leakage in each steam generator shall be determined within two weeks after reaching equilibrium operation in MODE 1, and 2.
Any subsequent incremental increase of 0.05 gpm in the equilibrium primary-to-secondary leak rate per steam generator shall be reported verbally within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> with a written followup within 14 working days.
Whenever possible, all leak rate determinations shall be made at steady
-; tate operating conditions.
MILLI!CSE - UNIT 2 2/47.S
{
