Letter Sequence Request |
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Results
Other: A02357, Ro:On 820629,primary to Secondary Leakage Rate Increased. Caused by Erosion & Thermal Cycling.Prompt Corrective Action Initiated for Leakage in Excess of 0.5 Gpm Per Steam Generator, 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, B10672, Ro:On 830131,increased Primary to Secondary Leakage Rate Noted in Steam Generator 1.Caused by Expected Erosion in Leakage Area & Thermal Cycling Due to Power Transients & Plant Trips.Leakage Rate Measurements on 830202 Listed, ML20054C168, ML20054F221, ML20072H501
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MONTHYEARML20054C1681982-04-0707 April 1982
Ro:On 820323,during Reactor Trip from Full Power Operating Conditions,Baseline primary-to-secondary Leakage Rates Increased.Caused by Increased Steam Generator Activity Due to Trip.Equilibrium Operation in Mode 1 Achieved on 820326
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
A02357, Ro:On 820629,primary to Secondary Leakage Rate Increased. Caused by Erosion & Thermal Cycling.Prompt Corrective Action Initiated for Leakage in Excess of 0.5 Gpm Per Steam Generator1982-07-0909 July 1982
Ro:On 820629,primary to Secondary Leakage Rate Increased. Caused by Erosion & Thermal Cycling.Prompt Corrective Action Initiated for Leakage in Excess of 0.5 Gpm Per Steam Generator
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
B10672, Ro:On 830131,increased Primary to Secondary Leakage Rate Noted in Steam Generator 1.Caused by Expected Erosion in Leakage Area & Thermal Cycling Due to Power Transients & Plant Trips.Leakage Rate Measurements on 830202 Listed1983-02-10010 February 1983
Ro:On 830131,increased Primary to Secondary Leakage Rate Noted in Steam Generator 1.Caused by Expected Erosion in Leakage Area & Thermal Cycling Due to Power Transients & Plant Trips.Leakage Rate Measurements on 830202 Listed
Project stage: Other
ML20072H5011983-03-0101 March 1983
Proposed Tech Spec Revs Re Frequency of Steam Generator Inservice Insp
Project stage: Other
ML20071D7771983-03-0101 March 1983
Proposed Changes to Tech Spec 3.4.6.2.b,extending Time Period Which Plant Must Be in Cold Shutdown Following Determination That Unidentified RCS Leakage Exceeded 1.0 Gpm Limit
Project stage: Request
B10712, Application for Amend to License DPR-65,changing Tech Spec 3.4.6.2.b to Extend Time Period Which Plant Must Be in Cold Shutdown Following Determination That Unidentified RCS Leakage Exceeded 1.0 Gpm Limit1983-03-0101 March 1983
Application for Amend to License DPR-65,changing Tech Spec 3.4.6.2.b to Extend Time Period Which Plant Must Be in Cold Shutdown Following Determination That Unidentified RCS Leakage Exceeded 1.0 Gpm Limit
Project stage: Request
ML20069F7121983-03-11011 March 1983
Safety Evaluation Supporting Amend 82 to License DPR-65
Project stage: Approval
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
1982-07-09
[Table View] |
Text
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Docket No. 50-336 ATTACHMENT 1 MILLSTONE NUCLEAR POWER STATION, UNIT NO. 2 PROPOSED REVISIONS TO TECHNICAL SPECIFICATIONS MARCH, 1983 8303110322 830301 i
PDR ADOCK 05000336 i
P PDR.
REACTOR COOLANT SYSTEM REACT 03 COOLANT SYSTEM LEAKAGE LIMITING CONDITION FOR OPERATION 1
3.4.6.2 Reactor Coolant System leakage shall be limited to:
a.
No PRESSURE BDUNDARY LEAKAGE, b.
1 GPM UNIDENTIFIED LEAKAGE, c.
1 GPM total prinary-to-secondary leakage through both steam generators and 0.5 GPM through any one steam generator, and d.
10 GPM IDENTIFIED LEAKAGE from the Reactor Coolant System.
APPLICABILITY: MODES 1, 2, 3 and 4.
ACTION:
a.
With any PRES 5URE BOUNDARY LEAKAGE, be in COLD SHUTDOWN with-in 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />.
b.
With any Reactor Coolant System leakage greater than any one of the above limits, excluding PRESSURE BOUNDARY LEAKAGE, reduce the leakage rate to within limits within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> or be in COLD SHUTDOWN within the next 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />.**
SURVEILLANCE REQUIREMENTS 4.4.6.2 Reactor Coolant System leakages shall be demonstrated to be within each of the above limits by:
Monitoring the containment atmosphere particulate radioactivity a.
at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
b.
Monitoring the containment sump inventory at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, i
Perforr.ance of a Reactor Coolant System water inventory l
c.
balance at least once per 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> during steady state opera-tion except when operating in the shutdown cooling mode.
For the shutdown commencing on March 1,1983, the unit shall be placed in HOT l
STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and COLD SHUTDOWN within the next 54 hours6.25e-4 days <br />0.015 hours <br />8.928571e-5 weeks <br />2.0547e-5 months <br />.
MILLSTONE - UNIT 2 3/4 4-9 l
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