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MONTHYEARML0530502922005-10-18018 October 2005 Draft RAI on Proposed Amendment Re. Oyster Creek RWCU HELB Isolation Project stage: Draft RAI ML0602604072006-02-0101 February 2006 Oyster Creek Generating Station - Facsimile Transmission, Draft Request for Additional Information to Be Discussed in an Upcoming Conference Call Project stage: Draft RAI ML0606704632006-03-0909 March 2006 Request for Additional Information Revision of Appendix B, Environmental Technical Specifications Project stage: RAI ML0606904192006-03-20020 March 2006 Correction to RAI Reactor Water Clean-Up High Energy Line Break Detection and Isolation License Amendment Request Project stage: RAI ML0623704752006-08-25025 August 2006 Technical Specifications - Deletion of Reporting Requirement in Facility Operating License Project stage: Other ML0620901592006-08-25025 August 2006 Issuance of Amendment Deletion of Reporting Requirement in Facility Operating License Project stage: Approval 2006-03-20
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Category:Technical Specifications
MONTHYEARML21119A0642021-06-25025 June 2021 License Amendment 299 ML18221A4002018-10-17017 October 2018 Issuance of Amendment No. 294, Revise the Site Emergency Plan and Emergency Action Level Scheme for the Permanently Defueled Condition (CAC No. MG0160; L-2017-LLA-0307) ML15141A0582015-07-28028 July 2015 Issuance of Amendments Regarding Emergency Action Level Schemes (TAC Nos. MF4232-MF4251) RA-15-030, Submittal of Changes to Technical Specifications Bases2015-04-14014 April 2015 Submittal of Changes to Technical Specifications Bases ML14329A6252015-03-30030 March 2015 Issuance of Amendment Regarding Reactor Building Vital Area Access Control ML1019301722010-09-27027 September 2010 Issuance of Amendment Relocation of Surveillance Requirement Frequencies to a Licensee Controlled Document Based on TSTF-425, Revision 3 RA-10-028, Response to Request for Additional Information, License Amendment Request Regarding Relocation of Selected Technical Specification Surveillance Frequencies to a Licensee Controlled Document2010-04-16016 April 2010 Response to Request for Additional Information, License Amendment Request Regarding Relocation of Selected Technical Specification Surveillance Frequencies to a Licensee Controlled Document RA-09-029, Supplement to License Amendment Request Application for Technical Specification Change Regarding Revision of Control Rod Notch Surveillance Test Frequency, Clarification of SRM Insert Control Rod Action, and Clarification of A..2009-03-30030 March 2009 Supplement to License Amendment Request Application for Technical Specification Change Regarding Revision of Control Rod Notch Surveillance Test Frequency, Clarification of SRM Insert Control Rod Action, and Clarification of A.. RA-08-100, Special Report for Inoperability of Turbine Building High Range Radioactive Noble Gas Monitor2008-11-18018 November 2008 Special Report for Inoperability of Turbine Building High Range Radioactive Noble Gas Monitor ML0824703052008-08-28028 August 2008 Technical Specifications, TSTF Change Traveler TSTF-479 & TSTF-497 ML0823907072008-08-21021 August 2008 Revised T.S. Pages Oyster Creek Nuclear Generating Station and Peach Bottom Atomic Power Station, Unit 3-Correction to Facility Operating Licenses ML0821301362008-07-25025 July 2008 Braidwood/Byron/Clinton/Dresden/Lasalle/Oyster Creek/Peach Bottom/Quad Cities/Three Mile Island - Tech Spec Pages for Amds to Change TS Unit Staff Qualifications Education and Experience Eligibility Requirements for Licensed Operators ML0812303462008-05-30030 May 2008 Tec Specs to Amd 266/License DPF-16/Oyster Creek ML0810505452008-04-30030 April 2008 Technical Specification Pages for License Amendment No. 265 the Incorporation of TSTF-448, Revision 3, Control Room Habitability. (Tac MD5281) RA-08-024, Amergen, Energy LLC, License Amendment Request to Remove References to NRC Generic Letter 82-12, Nuclear Power Plant Staff Working Hours.2008-04-21021 April 2008 Amergen, Energy LLC, License Amendment Request to Remove References to NRC Generic Letter 82-12, Nuclear Power Plant Staff Working Hours. RA-08-004, Technical Specification Change Request No. 348 - Relocation of Pressure and Temperature (P-T) Curves to the Pressure and Temperature Limits Report (PTLR)2008-03-10010 March 2008 Technical Specification Change Request No. 348 - Relocation of Pressure and Temperature (P-T) Curves to the Pressure and Temperature Limits Report (PTLR) RS-08-012, Amergen Company, Request for Amendment to Administrative Controls Section of Technical Specifications2008-02-28028 February 2008 Amergen Company, Request for Amendment to Administrative Controls Section of Technical Specifications ML0802901792008-02-0101 February 2008 Oyster Creek,Technical Specifications, Corrected, Revised Pages of Facility Operating License No. DPR-16 RA-08-011, Response to Request for Additional Information - Exelon/Amergen Application to Revise Technical Specifications Control Room Envelope Habitability in Accordance with TSTF-448, Revision 3, Using the Consolidated Line Item Improvement..2008-01-23023 January 2008 Response to Request for Additional Information - Exelon/Amergen Application to Revise Technical Specifications Control Room Envelope Habitability in Accordance with TSTF-448, Revision 3, Using the Consolidated Line Item Improvement.. ML0729202902007-10-18018 October 2007 Technical Specification Change Request No. 374 - Revision to Mechanical Snubber Functional Testing Requirements ML0722501972007-08-0808 August 2007 Technical Specifications Pages Re Annual Radioactive Effluent Release Report Submittal Date ML0721302932007-07-27027 July 2007 Technical Specifications, Issuance of Amendment Request to Change Technical Specification Definition of Channel Calibration, Channel Check, and Channel Test RS-07-078, Amergen - License Amendment Request to Change Technical Specification Unit Staff Qualifications Education and Experience Eligibility Requirements for Licensed Operators2007-07-19019 July 2007 Amergen - License Amendment Request to Change Technical Specification Unit Staff Qualifications Education and Experience Eligibility Requirements for Licensed Operators ML0713603392007-05-16016 May 2007 Technical Specification Change Request No. 327 - Modify Technical Specifications for Primary Containment Oxygen Concentration ML0711703892007-04-26026 April 2007 Technical Specifications Application of Alternate Source Term Methodology ML0633201962006-11-27027 November 2006 Technical Specification Change Request No. 341 - Revision to Required Submittal Date for Annual Radioactive Effluent Release Report ML0626101962006-09-13013 September 2006 Technical Specification Pages Re Increase Safety Valve As-Found Setpoint Tolerance from 1 Percent to 3 Percent ML0624404112006-09-0101 September 2006 Tech Spec Pages for Amendment 260 Regarding Revision to Electromatic Relief Valve Surveillance Requirement ML0623704752006-08-25025 August 2006 Technical Specifications - Deletion of Reporting Requirement in Facility Operating License ML0605500582006-02-22022 February 2006 Tech Spec Page for Amendment 258 Regarding Deletion of Reporting Requirement in Facility Operating License ML0600600152006-01-0404 January 2006 Technical Specifications, 1.0 Environmental Monitoring ML0529701902005-10-18018 October 2005 Technical Specification Change Request No. 328 - Modify Surveillance Requirements for Testing of Main Steam Line Electromatic Relief Valves ML0520000612005-07-14014 July 2005 Tech Spec Pages for Amendment 256 Capability Upgrade of a 69-KV Offsite Power Line to 230-KV ML0517802562005-06-23023 June 2005 Tech Spec Pages for Amendment, Reactor Building Closed Cooling Water Pump and Service Water Pump Trip Conditions ML0516002532005-06-0808 June 2005 Tech Spec Page for Amendment 254 Delete the TS Requirements to Submit Monthly Operating Reports and Annual Occupational Radiation Exposure Reports RS-05-006, Nuclear/Amergen, Proposed Changes to Delete the Reporting Requirement Section of the Facility Operating License2005-02-25025 February 2005 Nuclear/Amergen, Proposed Changes to Delete the Reporting Requirement Section of the Facility Operating License ML0505900852005-02-24024 February 2005 Technical Specification Change Request No. 319 - Revision to Table 3.1.1 Notes Aa and Bb Regarding Reactor Building Closed Cooling Water Pump and Service Water Pump Trip Conditions RS-04-157, Proposed Revision to Appendix B, Environmental Protection Plan (Non-Radiological) of the Facility Operating License2004-12-17017 December 2004 Proposed Revision to Appendix B, Environmental Protection Plan (Non-Radiological) of the Facility Operating License ML0430803562004-11-0202 November 2004 Tech Spec Pages for Amendment 250 Main Steam Line Isolation Valve Leakage Testing ML0433100362004-10-20020 October 2004 Technical Specification, Control Rod Scram Time Testing Requirements ML0429203072004-10-13013 October 2004 Table, Run or Startup Mode (Except for Low Power Physics Testing) ML0427902182004-10-0404 October 2004 Technical Specifications, Modify Control Rod Scram Time Testing Surveillance Requirements ML0425301502004-08-27027 August 2004 Station,Technical Specification Change Request No. 331 - Safety Limit Minimum Critical Power Ratio ML0423604742004-08-19019 August 2004 Technical Specification for Oyster Creek ML0422301962004-08-0909 August 2004 Tech Spec for Oyster Creek, License Amendment No. 246, Elimination of Requirements for Hydrogen Monitors ML0421703712004-07-30030 July 2004 Technical Specifications, Sections 3.7 and 4.7, Auxiliary Electrical Power, and Added a New Section 6.8.5, Station Battery Monitoring and Maintenance Program ML0415600412004-07-13013 July 2004 Unit, 1, License Amendments 244 and 250 Re.: Amendments to Delete a License Condition Regarding the Long Range Planning Program ML0415305902004-05-27027 May 2004 Unit 1, Technical Specifications, Reflect Ownership Change ML0409002892004-03-29029 March 2004 Tech Spec Pages for Amendment 241 Regarding Increasing Flexibility in Mode Restraints ML0333201312003-11-24024 November 2003 Tech Spec Pages for Amendment 239 Regarding Startup Transformer and Emergency Diesel Generator Unavailability 2021-06-25
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The drywell high radiation setpoint will ensure a timely closure of the large vent and purge isolation valves to prevent releases from exceeding ten percent of the dose guideline values allowed by 10 CFR 100. The containment vent and purge isolation function is provided in response to NUREG 0737 Item II E.4.2.7.
Temperature switches are provided at the entrance of the RWCU Pump Room to detect a line break downstream of the RWCU isolation valves. A line break will raise room temperature. Before the room temperature exceeds 1800F, the switches will trip and close the RWCU isolation valves.
This ensures that a high energy line break will automatically be detected and isolated, even if an RWCU System isolation is not initiated by a LO-LO reactor water level signal. System isolation at this temperature will minimize the impact on off-site releases and the environmental qualification profiles for the Reactor Building.
References:
(1) NEDC-30851 P-A, "Technical Specification Improvement Analyses for BWR Reactor Protection System."
(2) NEDC-30936P-A, "BWR Owners' Group Technical Specification Improvement Methodology (With Demonstration for BWR ECCS Actuation Instrumentation)," Parts 1 and 2.
(3) NEDC-30851 P-A, Supplement 1, "Technical Specification Improvement Analysis for BWR Control Rod Block Instrumentation."
(4) NEDC-30851 P-A, Supplement 2, "Technical Specification Improvement Analysis for BWR Isolation Instrumentation Common to RPS and ECCS Instrumentation."
(5) NEDC-31677P-A, "Technical Specification Improvement Analysis for BWR Isolation Actuation Instrumentation.'
(6) GENE-770-06-1 -A, "Bases for Changes to Surveillance Test Intervals and Allowed Out-of-Service Times for Selected Instrumentation Technical Specifications."
OYSTER CREEK 3.1-8 Amendment No.: 146, 4;1, 259
TABLE 3.1.1 PROTECTIVE INSTRUMENTATION REQUIREMENTS Sheet 7 of 13 Reactor Modes Minimum Number of Minimum Number of in which Function OPERABLE or Instrument Channels Must Be OPERABLE OPERATING [tripped] Per OPERABLE Function Trip Setting Shutdown Refuel Startu Run u Trip Systems Trip System Action Required*
M. Diesel Generator Load Sequence Timers (Cont'd.)
- 2. Service Water Pump (aa) 120 sec +/- 15% x x x x 2(o) 2(p)(kk) Consider the (SKIA) pump inoperable (SK2A) and comply 10 sec. +/- 15% within 7 days (SK7A) (See note q)
(SK8A)
- 3. Reactor Building Closed 166 sec
- 15% x x x x 2(m) 1(n)(kk) Consider the Cooling Water Pump pump inoperable (bb) and comply within 7 days (See note q)
N. Loss of Power
- a. 4.16 KV Emergency Bus ** X(ff) X(ff) X(f0 X(ff) 2 1(kk)
Undervoltage (Loss of Voltage)
- b. 4.16 KV Emergency Bus X(ff) X(ff) X(ff) X(ff) 2 3(kk) See note cc Undervoltage (Degraded Voltage)
- 0. Containment Vent and Purge Isolation
- 1. Drywell High Radiation S 74.6 R/hr X(u) X(u) X(u) x 1 1 Isolate vent &
Purge pathways or PLACE IN COLD SHUTDOWN CONDITION P. RWCU HELB Isolation
- 1. RWCU Pump Room High Temperature S1800 F X(s) X(s) x x 2 2(oo) Close isolation valves V-16-1, V-16-2, V-16-14, &V-16-61.
OYSTER CREEK 3.1-15 Corrected Letter dated 10/28/99 Amendment No.: 15,414,60,89,160,17"4,195, , 259
TABLE 4.1.1 Page 5 of 6 MINIMUM CHECK, CALIBRATION AND TEST FREQUENCY FOR PROTECTIVE INSTRUMENTATION Instrument Channel Check Calibrate Test Remarks (Applies to Test &Calibration)
- 32. LPRM Level a) Electronics N/A 1/12 mo. 1/12 mo.
b) Detectors N/A Note 4 N/A
- 33. RWCU HELB High Temperature N/A Each refueling 1/3 mo. Perform Channel Tests using the test outage switches.
Calibrate prior to startup and normal shutdown and thereafter check 1/s and test 1/wk until no longer required.
Legend: N/A = Not Applicable 1/s Once per shift lid = Once per day 1/3d = Once per 3 days; 1/wk = Once per week 1/mo. = Once per month 1/3 mo. = Once every 3 months; 1/12 mo. = Once every 12 months 1/24 mo. = Once every 24 months OYSTER CREEK 4.1-8 Change: 5, 7, Amendment No.: w7 l, 2O9, 259