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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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- TECHNICAL SPECIFICATIONS Rhode Island Nuclear Science Center Docket 50193, License R 95 P.evision 1 reactor operation, fuel movement and handling of radioactive materials in the reactor building.
Objective:
To assure that radiation monitoring equipment is-available 'for evaluation of radiation conditions and that the release of airborne radioactive material is - maintained below the limits established in 10CFR20. -)
Specification:
- 1. -When the reactor. is operating, gaseous and I
particulate sampling of the stack effluent shall be monitored by a stack monitor with a readout in the control room.
The particulate activity monitor and the l
gaseous activity ' monitor for the facility j exhaust stack shall. be operating. . If either unit is out of service for more than one shift (6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />), either. the reactor. shall be shut down or the _ unit . shall .be replaced by one of 3 comparable monitoring capability.
- 2. - When the reactor : is operating, at- least one ,
constant air monitoring unit (Table 3.2.11) located in the confinement building shall be operating. Temporary shutdown of- this unit shall be limited as in 3.7.1 above.
i j 3. The reactor shall not be continuously *
- operated without a minimum of one area
- s. radiation monitor (Table - 3.2.8) on the experimental- level of the reactor building and -
one area monitor (Table 3.2.6) over the L reactor pool (reactor bridge) operating and capable of warning personnel of high
- radiation levels.
1.
-9710070283 971002 I Page 29 Admendment 24 PDR ADOCK 05000193:
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