Letter Sequence Other |
|---|
|
Results
Other: ML20008G315, ML20023B690, ML20023B693, ML20064D127, ML20064G097, ML20064K897, ML20064N491, ML20070W125, ML20070W130, ML20071A617, ML20079N907, ML20083N032, ML20083N079
|
MONTHYEARML20008G3151981-06-29029 June 1981
Responds to Generic Ltr 81-04 Re Implementation of NUREG-0313,Revision 1, Technical Rept on Matl Selection & Processing Guidelines for BWR Coolant Pressure Boundary Piping, Per NRC 810226 Request
Project stage: Other
ML20064D1271982-12-15015 December 1982
Responds to Items 1 & 4 of IE Bulletin 82-03 Re Stress Corrosion Cracking in Austenitic Stainless Steel Recirculation Sys Piping.Total of 51 Circumferential & Branch Connection Welds & 6 Longitudinal Welds Examined
Project stage: Other
ML20064G0971983-01-0606 January 1983
Forwards Documentation of 821207,13 & 14 Telcons Re Inservice Insp Findings & Resultant Repair Activities Conducted During Maint/Refueling Outage Presently in Progress
Project stage: Other
ML20064K8971983-01-26026 January 1983
Responds to IE Bulletin 82-03 Re Stress Corrosion Cracking in Austenitic Stainless Steel in BWR Recirculation Sys Piping.Info Re Items 1 & 4 Submitted 821215.Info Completes Response
Project stage: Other
ML20083N0321983-01-26026 January 1983
Responds to Items 2 & 3 of IE Bulletin 82-03 Re Stress Corrosion Cracking in Austenitic Stainless Steel BWR Recirculation Sys Piping.Responses to Items 1 & 4 Provided in Util .Recirculation Sys Welds Will Be Repaired
Project stage: Other
ML20083M9661983-01-27027 January 1983
Forwards Info Re Analyses & Repairs of Recirculation & RHR Sys Piping Welds.Details of Inservice Insp Discussed.Util Intends to Return Unit to Power Operation Upon Completion of Current Outage.Meeting Scheduled for 830201 to Discuss Subj
Project stage: Meeting
ML20083N0791983-01-31031 January 1983
Rev 0 to Design Rept for Recirculation Sys & RHR Sys Weld Overlay Repairs & Flaw Evaluation at Ei Hatch Nuclear Power Plant Unit 1
Project stage: Other
ML20064N4771983-02-10010 February 1983
Application for Amend to License DPR-57,revising Tech Specs on Reactor Coolant Leakage Limiting Conditions for Operation & Surveillance Requirements
Project stage: Request
ML20064N4911983-02-10010 February 1983
Proposed Tech Specs Re Reactor Coolant Leakage Limiting Conditions for Operation & Surveillance Requirements
Project stage: Other
ML20070W1251983-02-11011 February 1983
Forwards Corrected Proposed Tech Specs Re Recirculation & RHR Sys Piping Repairs Submitted on 830210.Typographical Errors Contained in Paragraphs 2.a & 2.b of Page 3.6-8
Project stage: Other
ML20071A6171983-02-11011 February 1983
Notice of Issuance & Availability of Amend 93 to License DPR-57
Project stage: Other
ML20070W1301983-02-11011 February 1983
Corrected Proposed Tech Spec Page 3.6-8 Re Reactor Coolant Leakage
Project stage: Other
ML20071A6061983-02-11011 February 1983
Safety Evaluation Supporting Amend 93 to License DPR-57
Project stage: Approval
ML20079N9071983-02-18018 February 1983
Documents 830124 Telcon Re Replacement of Selected Portion of Stainless Steel 4-inch Diameter Reactor Water Cleanup Return Line Piping
Project stage: Other
ML20023B6931983-03-0404 March 1983
Rev 1 to Design Rept for Recirculation Sys & RHR Sys Weld Overlay Repairs & Flaw Evaluation at Ei Hatch Nuclear Power Plant,Unit 1
Project stage: Other
ML20023B6901983-04-28028 April 1983
Forwards Rev 1 to Design Rept for Recirculation Sys & RHR Sys Weld Overlay Repairs & Flaw Evaluation at Ei Hatch Nuclear Power Plant,Unit 1
Project stage: Other
1983-01-06
[Table View] |
Similar Documents at Hatch |
|---|
|
Text
LIMIIING CONDIIIONS F0H OPEHAfION buRVdILLANCE rtEQuinti4ENfa G. _ Reactor Coolant Leakace
- 2. Leakace Detection Systems (Cont'd)
- a. (Continued) in the reactor vessel and reactor coolant temperature is above 2120F Further, the primary containment atmosphere particulate radioactlyity monitoring system shall be among these t'.-d operable j"O systems, or samples shall be octained and analyzed at least once each 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.
D.
From and after the date that any two of the four systems identified in Table 3.2-10, note c are made or found to be inoperaale but with the primary con,tainment atmosphere particulate radioactivity /
-- 8/' W y
- monitoring system i.. w llo, reactor power operation may continue for the succeeding 30 days provided the primary containment atmosphere particulate radioactivity monitoring system reading is checked and recorded at least once each 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.
From and after the date that c.
any two of the four systms, including the primary containment atmosphere particulate radioactivity monitoring syst s, identified in Table 3.2-10, note c are made or found to be inoperable, reactor power operation may continue for the succeeding 30 days provided samples of the containment atmosphere are obtained and analyzed at least once each 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.
pa82;gg2pagggg; P
Amendment No.
- 3. 6-8
LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREENTS G. Reactor Coolant Leakage
- 2. Leakage Detection Systems (Cont'd)
- a. (Continued) fn the reactor vessel and reactor coolant temperature is 0
above 212 F.
Further, the primary containment atmosphere particulate radioactivity monitoring system shall be among these two operable cystems, or samples shall be obtained and analyzed at least once each 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.
b.
From and after the date that any two of the four systems identified in Table 3.2-10, note c are made or found to be inoperable, but with the primary containment atmosphere particulate radioactivity monitoring system operable, l
reactor power operation may continue for the succeeding 30 days provided the primary containment atmosphere particulate radioactivity monitoring systen reading is checked and recorded at least once each 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.
c.
From and after the date that any two of the four systems, including the primary containment atmosphere particulate radioactivity monitoring system, identified in Table 3.2-10, note c are made or found to be inoperable, reactor power operation may continue for the succeeding 30 days provided samples of the containment atmosphere are obtained and analyzed at least once each 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.
Amendment No.
3.6-8
