ML031070088
ML031070088 | |
Person / Time | |
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Site: | Hope Creek |
Issue date: | 04/16/2003 |
From: | Office of Nuclear Reactor Regulation |
To: | |
References | |
Download: ML031070088 (1) | |
Similar Documents at Hope Creek | |
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Category:Technical Specification
MONTHYEARLR-N23-0024, Submittal of Hope Creek Generating Station Technical Specification Bases Changes2023-03-29029 March 2023
[Table view]Submittal of Hope Creek Generating Station Technical Specification Bases Changes LR-N21-0078, Hope and Creek Generating Station, Supplement to License Amendment Request to Revise Technical Specifications (TS) to Delete Definitions Found in 10 CFR Part 20 and Delete Figures of the Site and Surrounding Areas from TS2021-11-18018 November 2021 Hope and Creek Generating Station, Supplement to License Amendment Request to Revise Technical Specifications (TS) to Delete Definitions Found in 10 CFR Part 20 and Delete Figures of the Site and Surrounding Areas from TS LR-N21-0079, Submittal of Hope Creek Generating Station Technical Specification Bases Changes2021-11-0303 November 2021 Submittal of Hope Creek Generating Station Technical Specification Bases Changes LR-N21-0025, License Amendment Request to Revise Technical Specification Limits for Ultimate Heat Sink2021-05-0707 May 2021 License Amendment Request to Revise Technical Specification Limits for Ultimate Heat Sink LR-N20-0060, Application to Revise Technical Specifications to Adopt TSTF-582, Reactor Pressure Vessel Water Inventory Control (RPV WIC) Enhancements2020-09-29029 September 2020 Application to Revise Technical Specifications to Adopt TSTF-582, Reactor Pressure Vessel Water Inventory Control (RPV WIC) Enhancements ML20142A5412020-05-21021 May 2020 4 to Updated Final Safety Analysis Report, Section 16, Technical Specifications LR-N20-0033, Submittal of Hope Creek Generating Station Technical Specification Bases Changes2020-05-15015 May 2020 Submittal of Hope Creek Generating Station Technical Specification Bases Changes LR-N20-0015, License Amendment Request to Revise Technical Specification Actions for Suppression Pool Cooling2020-05-0707 May 2020 License Amendment Request to Revise Technical Specification Actions for Suppression Pool Cooling LR-N18-0127, Application to Revise Technical Specifications to Adopt TSTF-546, Revise APRM Channel Adjustment Surveillance Requirement.2019-02-27027 February 2019 Application to Revise Technical Specifications to Adopt TSTF-546, Revise APRM Channel Adjustment Surveillance Requirement. ML19058A2212019-02-27027 February 2019 Application to Revise Technical Specifications to Adopt TSTF-546, Revise APRM Channel Adjustment Surveillance Requirement. LR-N18-0013, License Amendment Request (LAR) to Amend the Hope Creek Technical Specifications (TS) to Revise Action for Inoperable Emergency Diesel Generator (EDG) a or B2018-03-28028 March 2018 License Amendment Request (LAR) to Amend the Hope Creek Technical Specifications (TS) to Revise Action for Inoperable Emergency Diesel Generator (EDG) a or B LR-N18-0011, Supplement to License Amendment Request- Safety Limit Minimum Critical Power Ratio Change. Includes GNF-004N5379-R1-NP, Gnf Additional Information Regarding the Requested Changes to the Technical Specification SLMCPR2018-01-22022 January 2018 Supplement to License Amendment Request- Safety Limit Minimum Critical Power Ratio Change. 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Creek Generating Station, Emergency Action Level Technical Bases Document (Strike-out Version)2010-10-14014 October 2010 Attachment 1 to LR-N10-0355, Hope Creek Generating Station, Emergency Action Level Technical Bases Document (Strike-out Version) ML1100503982010-10-14014 October 2010 Attachment 3 to LR-N10-0355, Hope Creek Generating Station, Emergency Action Level Comparison Matrix LR-N10-0355, Hope Creek, CY-AA-170-500, Revision 0, Meteorological Monitoring System Calibration and Maintenance2010-10-14014 October 2010 Hope Creek, CY-AA-170-500, Revision 0, Meteorological Monitoring System Calibration and Maintenance ML1100504152010-10-14014 October 2010 Hope Creek, CY-AA-170-500, Revision 0, Meteorological Monitoring System Calibration and Maintenance LR-N10-0355, Attachment 2 to LR-N10-0355, Hope Creek Generating Station, Emergency Action Level Technical Bases Document (Clean Version)2010-10-14014 October 2010 Attachment 2 to LR-N10-0355, Hope Creek Generating Station, Emergency 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2010 Attachment 2 to LR-N10-0355, Hope Creek Generating Station, Emergency Action Level Technical Bases Document (Clean Version) ML1025802422010-09-0808 September 2010 License Amendment Request H10-01:, Application for Technical Specification Change Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program LR-N10-0355, Hope Creek, HC.OP-AB.ZZ-0150(Q), Rev. 6, 125VDC System Malfunction2010-08-24024 August 2010 Hope Creek, HC.OP-AB.ZZ-0150(Q), Rev. 6, 125VDC System Malfunction ML1100505182010-08-24024 August 2010 Hope Creek, HC.OP-AB.ZZ-0150(Q), Rev. 6, 125VDC System Malfunction ML1100505002010-07-13013 July 2010 Hope Creek, HC.OP-AB.HVAC-0002(Q), Rev. 7, Control Room Environment LR-N10-0355, Hope Creek, HC.OP-AB.HVAC-0002(Q), Rev. 7, Control Room Environment2010-07-13013 July 2010 Hope Creek, HC.OP-AB.HVAC-0002(Q), Rev. 7, Control Room Environment LR-N10-0355, Hope Creek, HC.OP-AB.RPV-0009(Q), Rev. 7, 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Creek, HC.OP-AB.MISC-0002(Q), Rev. 10, Crids/Overhead Annunciators/Ppc Computer LR-N10-0355, Hope Creek, Offsite Dose Calculation Manual, Revision 252010-04-16016 April 2010 Hope Creek, Offsite Dose Calculation Manual, Revision 25 ML1100504172010-04-16016 April 2010 Hope Creek, Offsite Dose Calculation Manual, Revision 25 ML1100504742010-03-17017 March 2010 Hope Creek, HC.IC-GP.BB-0003(Q) - Rev. 17, Nuclear Boiler - Nondivisional Channel L-11683/B21-N027 Rx Cavity Flood Up Level/Rx Shutdown Range Level Setup LR-N10-0355, Hope Creek, HC.IC-GP.BB-0003(Q) - Rev. 17, Nuclear Boiler - Nondivisional Channel L-11683/B21-N027 Rx Cavity Flood Up Level/Rx Shutdown Range Level Setup2010-03-17017 March 2010 Hope Creek, HC.IC-GP.BB-0003(Q) - Rev. 17, Nuclear Boiler - Nondivisional Channel L-11683/B21-N027 Rx Cavity Flood Up Level/Rx Shutdown Range Level Setup LR-N10-0355, Hope Creek, HC.OP-AB.MISC-0001(Q), Rev. 15, Acts of Nature2010-03-0505 March 2010 Hope Creek, HC.OP-AB.MISC-0001(Q), Rev. 15, Acts of Nature 2023-03-29 Category:Amendment MONTHYEARLR-N21-0025, License Amendment Request to Revise Technical Specification Limits for Ultimate Heat Sink2021-05-0707 May 2021
[Table view]License Amendment Request to Revise Technical Specification Limits for Ultimate Heat Sink LR-N20-0015, License Amendment Request to Revise Technical Specification Actions for Suppression Pool Cooling2020-05-0707 May 2020 License Amendment Request to Revise Technical Specification Actions for Suppression Pool Cooling LR-N17-0124, Application to Revise Technical Specifications to Adopt TSTF-542, Reactor Pressure Vessel Water Inventory Control2017-09-21021 September 2017 Application to Revise Technical Specifications to Adopt TSTF-542, Reactor Pressure Vessel Water Inventory Control ML1118615602011-07-28028 July 2011 and Salem Nuclear Generating Station, Unit Nos. 1 and 2, License Amendment, Issuance of Amendments Approval of Cyber Security Plan LR-N09-0290, Hope Creek Generating Station - License Amendment Request Supporting the Use of Co-60 Isotope Test Assemblies (Isotope Generation Pilot Project)2009-12-21021 December 2009 Hope Creek Generating Station - License Amendment Request Supporting the Use of Co-60 Isotope Test Assemblies (Isotope Generation Pilot Project) ML0936401982009-12-21021 December 2009 Hope Creek Generating Station - License Amendment Request Supporting the Use of Co-60 Isotope Test Assemblies (Isotope Generation Pilot Project) LR-N09-0237, License Amendment Request H09-05 Revision to Technical Specification 4.0.5, Surveillance Requirements for Inservice Inspection and Testing of ASME Code Components2009-11-0404 November 2009 License Amendment Request H09-05 Revision to Technical Specification 4.0.5, Surveillance Requirements for Inservice Inspection and Testing of ASME Code Components ML0836501692008-12-30030 December 2008 Correction to Amendment No. 175 Regarding Technical Specification Requirements for Inoperable Inverters ML0834601362008-12-0303 December 2008 New Jersey Department of Environmental Protection'S Bureau of Nuclear Engineering Comment on PSEG Nuclear Llc'S License Amendment Request to Remove Restrictions on Operation of the Hydrogen Water Chemistry System at Low Power. 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LR-N02-0069, Request for License Amendment A.C. Sources - Operating2002-08-20020 August 2002 Request for License Amendment A.C. Sources - Operating ML0222606802002-08-13013 August 2002 Technical Specifications for Amendment 139 Use of Existing Pressure-Temperature Curves Through Cycle 12 (Tac No. MB4685) ML0210504542002-04-0303 April 2002 Request for Change to Technical Specifications Reactor Coolant Chemistry 2021-05-07 |
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ADMINISTRATIVE CONTROLS 6.8.4.f Primary Containment Leakaae Rate Testing Proaram A program shall be established, implemented, and maintained to comply with the leakage rate testing of the containment as required by 10CFR50.54(o) and 10CFR50, Appendix J, Option B, as modified by approved exemptions. This program shall be in accordance with the guidelines contained in Regulatory Guide 1.163, "Performance-Based Containment Leak-Test Program', dated September 1995, as modified by the following exception:
- a. NEI 94-01-1995, Section 9.2.3: The first Type A test performed after April 12, 1994 shall be performed no later than April 12, 2009.
The peak calculated containment internal pressure for the design basis loss of coolant accident, P., is 48.1 psig.
The maximum allowable primary containment leakage rate, L., at P.,
shall be 0.5% of primary containment air weight per day.
Leakage Rate Acceptance Criteria are:
- a. Primary containment leakage rate acceptance criterion is less than or equal to 1.0 L.. During the first unit startup following testing in accordance with this program, the leakage rate acceptance criteria are less than or equal to 0.6 L. for Type B and Type C tests and less than or equal to 0.75 L. for Type A tests;
- b. Air lock testing acceptance criteria are:
- 1) overall air lock leakage rate is less than or equal to 0.05 L. when tested at greater than or equal to P.,
- 2) Door seal leakage rate less than or equal to 5 scf per hour when the gap between the door seals is pressurized to greater than or equal to 10.0 psig.
The provisions of Specification 4.0.2 do not apply to the test frequencies specified in the Primary Containment Leakage Rate Testing Program.
The provisions of Specification 4.0.3 are applicable to the Primary Containment Leakage Rate Testing Program.
6.8.4.g. Radioactive Effluent Controls Proaram A program shall be provided conforming with 10 CFR 50.36a for the control of radioactive effluents and for maintaining the doses to MEMBER(S) OF THE PUBLIC from radioactive effluents as low as reasonably achievable. The program (1) shall be contained in the ODCM, (2) shall be implemented by operating procedures, and (3) shall include remedial actions to be taken whenever the program limits are exceeded. The program shall include the following elements:
HOPE CREEK 6-16b Amendment No.147