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Category:TECHNICAL SPECIFICATIONS
MONTHYEARML20217M4721999-10-14014 October 1999 Proposed Tech Specs Pages,Upgrading Position of RSO to Assistant Director for Radiation & Reactor Safety ML20211J0231997-10-0202 October 1997 Corrected Page 29 to Amend 24 of Ts,Including Change Made by Amend 20 ML20217R3601997-08-20020 August 1997 Proposed Tech Specs,Incorporating Addl Changes in Page 29,Section 3.7.1,page 62,Section 6.8 & Page 66, Section 6.9 ML20198F1871997-07-31031 July 1997 Rev 1 to Proposed Ts,Changing Page 7 Section 1.25.5 & 6 RO, Page 14 Section 2.2.1 Limiting Safety Sys Settings in Forced Convection Mode & Page 16 Section 2.2.2.1 Limiting Safety Sys Settings in Natural Convection Mode ML20148D9651997-05-20020 May 1997 Proposed Tech Specs for License R-95,incorporating NRC Changes ML20078R5941994-12-14014 December 1994 Proposed Tech Specs Requiring Sampling of Secondary Coolant Sys for Radioactivity on Weekly Basis & Deletion of Requirement for Secondary Radiation Detector ML20063G1131994-01-31031 January 1994 Rev 1 to Tech Specs ML20058A6621993-11-17017 November 1993 Proposed TSs for License R-95,incorporating NRC Questions ML20151U9081988-08-0505 August 1988 Proposed Tech Specs,Revising Page 3 to Change Flow Rate in 115 Ft High Stack from Approx 4,000 Cfm to Approx 14,000 Cfm ML20214T0431987-06-0202 June 1987 Proposed Tech Specs,Revising Pages 1 & 2 Re New Const on Portion of Narragansett Bay Campus of Univ of Rhode Island 1999-10-14
[Table view] Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML20217M4721999-10-14014 October 1999 Proposed Tech Specs Pages,Upgrading Position of RSO to Assistant Director for Radiation & Reactor Safety ML20211J0231997-10-0202 October 1997 Corrected Page 29 to Amend 24 of Ts,Including Change Made by Amend 20 ML20217R3601997-08-20020 August 1997 Proposed Tech Specs,Incorporating Addl Changes in Page 29,Section 3.7.1,page 62,Section 6.8 & Page 66, Section 6.9 ML20198F1871997-07-31031 July 1997 Rev 1 to Proposed Ts,Changing Page 7 Section 1.25.5 & 6 RO, Page 14 Section 2.2.1 Limiting Safety Sys Settings in Forced Convection Mode & Page 16 Section 2.2.2.1 Limiting Safety Sys Settings in Natural Convection Mode ML20148D9651997-05-20020 May 1997 Proposed Tech Specs for License R-95,incorporating NRC Changes ML20078R5941994-12-14014 December 1994 Proposed Tech Specs Requiring Sampling of Secondary Coolant Sys for Radioactivity on Weekly Basis & Deletion of Requirement for Secondary Radiation Detector ML20078B6341994-10-0707 October 1994 Ri Nuclear Science Ctr Proposed 3 MW or Higher ECCS Plan ML20069H4781994-06-0101 June 1994 Rhode Island Nuclear Science Ctr Proposed 3 MW or Higher Emergency Core Cooling Sys Plan. W/Three Oversize Drawings ML20063G1131994-01-31031 January 1994 Rev 1 to Tech Specs ML20058A6621993-11-17017 November 1993 Proposed TSs for License R-95,incorporating NRC Questions ML20151U9081988-08-0505 August 1988 Proposed Tech Specs,Revising Page 3 to Change Flow Rate in 115 Ft High Stack from Approx 4,000 Cfm to Approx 14,000 Cfm ML20214T0431987-06-0202 June 1987 Proposed Tech Specs,Revising Pages 1 & 2 Re New Const on Portion of Narragansett Bay Campus of Univ of Rhode Island 1999-10-14
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-e' TECHNICAL SPECIFICATIONS
'Rhode Island Nuclear Science Center Docket 50-193, License R-95
, Revision 1 I
- Annual pool . system inspections are made to provide assurance that other cooling system components (eg. gate valves, gasketing etc.) are functioning properly.
- b. Secondary Coolant System ;
Applicability: ,
This specification applies to the surveillance of the secondary coolant water.
Objective:
To assure the conditions of the coolant meet specification 3.3.(b) and to detect a primary to secondary water leak.
Specification:
- 1. The pH shall be measured weekly during reactor operation.
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- 2. A sample shall be drawn weekly and analyzed for sodium-24 activity, during reactor operation.
Bases:
Proper secondary coolant conditions - are obtained by blowdown and makeup water systems which maintain the proper water quality pH. Radioactive concentrations are measured in accordance with written procedures.
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l Page 42 Auendment No. 19 9412270113 941214 PDR ADOCK 05000193 1 p PDR