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Category:Legal-Exhibit
MONTHYEARML1116406212011-06-13013 June 2011 Commonwealth of Massachusetts Supplemental Attachment to the Declaration of Dr. Gordon R. Thompson ML1115304492011-06-0101 June 2011 Exhibit 12 in Support of Pilgrim Watch Request for Hearing on a New Contention Re Inadequacy of Environmental Report, Post Fukushima ML1115304462011-06-0101 June 2011 Exhibit 3C in Support of Pilgrim Watch Request for Hearing on a New Contention Re Inadequacy of Environmental Report, Post Fukushima ML1115303392011-06-0101 June 2011 New and Significant Information from the Fukushima Daiichi Accident in the Context of Future Operation of the Pilgrim Nuclear Power Plant ML1115303452011-06-0101 June 2011 Declaration of Dr. Gordon R. Thompson in Support of Commonwealth of Massachusetts' Contention and Related Petitions and Motions ML1115304432011-06-0101 June 2011 Exhibit 3B in Support of Pilgrim Watch Request for Hearing on a New Contention Re Inadequacy of Environmental Report, Post Fukushima ML1115304452011-06-0101 June 2011 Exhibit 11 in Support of Pilgrim Watch Request for Hearing on a New Contention Re Inadequacy of Environmental Report, Post Fukushima ML1115304442011-06-0101 June 2011 Exhibit 3A in Support of Pilgrim Watch Request for Hearing on a New Contention Re Inadequacy of Environmental Report, Post Fukushima ML1115304412011-06-0101 June 2011 Exhibit 5 in Support of Pilgrim Watch Request for Hearing on a New Contention Re Inadequacy of Environmental Report, Post Fukushima ML1113905652011-05-12012 May 2011 Fukushima Fallout Regulatory Loopholes at U.S. Nuclear Plants ML1113905712011-04-28028 April 2011 Transcript of Briefing on the Status of NRC Response to Events in Japan and Briefing on Station Blackout ML1106009342011-02-0202 February 2011 Official Exhibit - NRC000015-00-BD01 - NRC Staff Testimony of James V. Ramsdell Jr., Concerning the Impact of Specific Meteorological Conditions on the Severe Accident Mitigation Analysis ML1106009352011-02-0202 February 2011 Official Exhibit - NRC000016-00-BD01 - NRC Staff Rebuttal Testimony of S. Tina Ghosh Concerning Pilgrim Watch'S Application of NUREG-1150 and NUREG-1465 ML1106009322011-02-0202 February 2011 Official Exhibit - NRC000014-00-BD01 - NRC Staff Testimony of Nathan E. Bixler and S. Tina Ghosh Concerning the Impact of Alternative Meteorological Models on the Severe Accident Mitigation Alternatives Analysis ML1106008802011-02-0101 February 2011 Official Exhibit - ENT000013-00-BD01 - Rebuttal Testimony of Dr. Kevin R. O'Kula and Dr. Steven R. Hanna on Meteorological Matters Pertaining to Pilgrim Watch Contention 3 ML1106008822011-02-0101 February 2011 Official Exhibit - ENT000014-00-BD01 - Rebuttal Testimony of Dr. Kevin R. O'Kula on Source Term Used in the Pilgrim Nuclear Power Station SAMA Analysis ML1106008782011-01-31031 January 2011 Official Exhibit - ENT000011-00-BD01 - URS-TR-10-0003, Rev. 1, ENT-Exposure Index Calculation - Exposure Index Analysis Using MACCS2 and Calmet: Sensitivity Study Supporting the Pilgrim Station SAMA Analysis. ML1106009382011-01-30030 January 2011 Official Exhibit - PWA000023-00-BD01 - Statement by Bruce A. Egan, Sc.D., Cmm, in the Matter of Entergy Corporation, Pilgrim Nuclear Power Station License Renewal Application ML1106009372011-01-30030 January 2011 Official Exhibit - PWA000022-00-BD01 - Declaration of Bruce A. Egan, Sc.D., Cmm, in Support of Pilgrim Watch'S Response Opposing Entergy'S Initial Statement of Position on Pilgrim Watch Contention 3 ML1106008982011-01-0303 January 2011 Official Exhibit - PWA000016-00-BD01 - NUREG/CR-6853, Comparison of Average Transport and Dispersion Among a Gaussian, a Two-Dimensional, and a Three-Dimensional Model ML1106008972011-01-0303 January 2011 Official Exhibit - PWA000015-00-BD01 - Revisiting Goiania - 1987 Radiological Accident in Goiania, Brazil ML1106009282011-01-0303 January 2011 Official Exhibit - NRC000011-00-BD01 - Statement of Qualifications for Nathan E. Bixler ML1106008962011-01-0303 January 2011 Official Exhibit - PWA000014-00-BD01 - Kamiar Jamali, Use of Risk Measures in Design and Licensing of Future Reactors ML1106009102011-01-0303 January 2011 Official Exhibit - NRC000001-00-BD01 - Applicant'S Environmental Report, Attachment E, Severe Accident Mitigation Alternatives Analysis. ML1106008792011-01-0303 January 2011 Official Exhibit - ENT000012-00-BD01 - Testimony of Dr. Kevin R. O'Kula on Source Term Used in the Pilgrim Nuclear Power Station Severe Accident Mitigation Alternatives (SAMA) Analysis ML1106008722011-01-0303 January 2011 Official Exhibit - ENT000006-00-BD01 - Er Attachment E, Severe Accident Mitigation Alternatives Analysis ML1106008712011-01-0303 January 2011 Official Exhibit - ENT000005-00-BD01 - LRA Er Section 4.21 ML1106009002011-01-0303 January 2011 Official Exhibit - PWA000018-00-BD01 - NRC Staff'S Response in Opposition to State of New York'S Motion for Partial Summary Disposition of NYS Contention 16/16A ML1106009292011-01-0303 January 2011 Official Exhibit - NRC000012-00-BD01 - Statement of Qualifications for S. Tina Ghosh ML1106008662011-01-0303 January 2011 Official Exhibit - ENT000001-00-BD01 - Testimony of Dr. Kevin R. O'Kula and Dr. Steven R. Hanna on Meteorological Matters Pertaining to Pilgrim Watch Contention 3 ML1106009302011-01-0303 January 2011 Official Exhibit - NRC000013-00-BD01 - Statement of Qualifications for James V. Ramsdell, Jr ML1106008692010-12-31031 December 2010 Official Exhibit - ENT000004-00-BD01 - Analysis of Annual Wind Roses and Precipitation within About 50 Miles of the Pilgrim Nuclear Power Station, and Use of Calmet to Calculate the Annual Distribution of Trajectories from the Pilgrim Stati ML1106008672010-12-30030 December 2010 Official Exhibit - ENT000002-00-BD01 - Declaration of Kevin R. O'Kula in Support of Entergy'S Pre-filed Testimony on Pilgrim Watch Contention 3 ML1106008682010-12-22022 December 2010 Official Exhibit - ENT000003-00-BD01 - Declaration of Steven R. Hanna in Support of Entergy'S Pre-filed Testimony on Pilgrim Watch Contention 3 ML1013304352010-05-12012 May 2010 NRC Staff'S Initial Brief in Response to the Board'S Order (Regarding Deadlines for Submission of Parties) ML1106009022009-12-31031 December 2009 Official Exhibit - PWA000019-00-BD01 - What'S in the Black Box Known as Emergency Dose Assessment ML1106008912009-05-31031 May 2009 Official Exhibit - PWA000010-00-BD01 - Jennifer E. Thorp, the Eastern Massachusetts Sea Breeze Study ML1106009262009-05-31031 May 2009 Official Exhibit - NRC000010-00-BD01 - the Eastern Massachusetts Sea Breeze Study NRC-2007-0019, FRN the Attorney General of Commonwealth of Massachusetts, the Attorney General of California; Denial of Petitions for Rulemaking2008-08-0808 August 2008 FRN the Attorney General of Commonwealth of Massachusetts, the Attorney General of California; Denial of Petitions for Rulemaking ML1112203542008-08-0808 August 2008 FRN the Attorney General of Commonwealth of Massachusetts, the Attorney General of California; Denial of Petitions for Rulemaking ML0810904402008-04-15015 April 2008 Pilgrim April 2008 Evidentiary Hearing - Staff Exhibit 11, NUREG-1891 (Sept. 2007, Published Nov. 2007) Excerpt - 3.0.3.1.13 Water Chemistry Control BWR Program ML0810904752008-04-15015 April 2008 2008/04/15-Pilgrim April 2008 Evidentiary Hearing - Applicant Exhibit 8, License Renewal Application, Appendix B.0.3 ML0810905332008-04-15015 April 2008 Pilgrim April 2008 Evidentiary Hearing - Staff Exhibit 14, Amendment No. 176 Excerpt (3/4.5-7 - 3/4.5-8) ML0810902922008-04-15015 April 2008 Pilgrim April 2008 Evidentiary Hearing - Intervenor Exhibit 17, Bptip: NUREG-1891, Rev. 1, X I M32, 3.0.3.2.1, Buried Pipes and Tanks Inspection Program, 3-35 to 3-38 ML0810902462008-04-15015 April 2008 2008/04/15-Pilgrim April 2008 Evidentiary Hearing - Applicant Exhibit 2, Pilgrim License Renewal Application, Pages from Appendix B ML0811202612008-04-15015 April 2008 Pilgrim April 2008 Evidentiary Hearing - Staff Exhibit 23, NUREG-1891 (Sept. 2007, Published Nov. 2007) Excerpt - 3.0.2 Staff'S Review Process ML0810904382008-04-15015 April 2008 Pilgrim April 2008 Evidentiary Hearing - Staff Exhibit 9, NUREG-1891 (Sept. 2007, Published Nov. 2007) Excerpt - 3.0.3.2.16 Service Water Integrity Program ML0810905242008-04-15015 April 2008 Pilgrim April 2008 Evidentiary Hearing - Intervenor Exhibit 8, Nureg/Cr 6876, Risk Informed Assessment of Degraded Buried Piping Systems in Nuclear Power Plants; Brookhaven National Laboratory; Us NRC, June 2005. from Sections.. ML0810906152008-04-15015 April 2008 Pilgrim April 2008 Evidentiary Hearing - Staff Exhibit 28, NRC Region III Report Excerpt - Service Water (SX) System ML0810906162008-04-15015 April 2008 Pilgrim April 2008 Evidentiary Hearing - Intervenor Exhibit 53, 2-Photographs of Corrosion on Pipes at Pilgrim Nuclear Power Station 2011-06-13
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9/+-S LIMITING CONDITIONS FOR OPERATION SURVEILLANCE* REQUIREMENTS 4.5 CORE AND CONTAINMENT COOLING 3.5 CORE AND CONTAINMENT COOLING SYSTEMS SYSTEMS C. HPCI System C. HPCI System W 1. The HPCI system shall be 1. HPCI system testing shall be as operable whenever there is follows:
irradiated fuel in the reactor vessel, reactor pressure is greater than a. Simulated Once/
150 psig., and reactor coolant Automatic Operating temperature is greater than 365"F, Actuation Cycle except as specified in 3.5.C.2 Test below,
- b. Pump When tested
- 2. From and after the date that the Operability as specified in HPCI system is made or found to 3.13, verify be inoperable for any reason, that the HPCI continued reactor operation is pump delivers permissible only during the at least 4250 succeeding 14 days unless such GPM for a system is sooner made operable, system head providing that during such 14 days corresponding all active components of the ADS to a system, the RCIC system, the reactor LPCI system and both core spray pressure of systems are operable, 1000 psig.
- 3. If the requirements of 3.5.C cannot c. Motor As Specified in
- 0 be met, an orderly shutdown of the Operated 3.13 reactor shall be initiated and the Valve reactor shall be in the Cold Operability Shutdown Condition within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. d. Flow Rate at Once!
150 psig. operating cycle, verify U.. NUCLEAR REGUMATORY CONISSI0N that the HPCt pump deliver awnor ""Im DOCKETED at least mdo No L - gtN , . 4250 GPM fca.
Aoril 15. 2008 (10:00am) yst hel correspoindir .9 OFFICE OF SECRETARY" to a reactor I Pill F-IMAkIN. ANi Afi'.1 1rl'lATinN.J qTAFFI pressure of 150 psig.
The HPCI pump shall deliver at least 4250 GPM fcor a system head corresponding to a reactor pressure of 1000 to 150 psig.
Amendment No. 176 3/4.5-7 5~~C42-o 0 27 D503
LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS 3.5 CORE AND CONTAINMENT COOLING 4.5 CORE AND CONTAINMENT COOLING SYSTEMS SYSTEMS w D. Reactor Core Isolation Cooling (RCIC) System D. Reactor Core Isolation Cooling (RCIC)
System
- 1. The RCIC system shall be 1. HPCI system testing shall be as operable whenever there is follows:
irradiated fuel in the reactor vessel, reactor pressure is greater than a. Simulated Once/
150 psig, and reactor coolant Automatic Operating temperature is greater than 355'F, Actuation Test Cycle except as specified in 3.5.D.2 below. b. Pump When tested as Operability specified in
- 2. From and after the date that the 3.13, verify that RCIC system is made or found to the RCIC pump be inoperable for any reason, delivers at least continued reactor operation is 400 GPM at a permissible only during the system head succeeding 14 days unless such corresponding system is sooner made operable, to a reactor providing that during such 14 days pressure of the HPCIS is operable. 1000 psig.
Ifthe requirements of 3.5.D cannot c. Motor As Specified 3.
be mete an orderly shutdown of the Operated in 3.13 reactor shall be initiated and the Valve reactor shall be in the Cold Operability Shutdown Condition within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. d. Flow Rate at Once/
150 psig. operating cycle verify that the RCIC pump delivers at least 400 GPM at a system head corresponding to a reactor pressure of
'50 psig.
The'RCIC pump shall deliver at least.
400 GPM for a system head.
corresponding to a reactor pressure of 1000 to 150 psig.
Amendment No. 1753 3/4.5-8