ML20041A360
ML20041A360 | |
Person / Time | |
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Site: | Millstone |
Issue date: | 02/16/1982 |
From: | EG&G, INC. |
To: | Office of Nuclear Reactor Regulation |
References | |
CON-FIN-A-6429 EGG-EA-5481-ERR, EGG-EA-5481-R02, EGG-EA-5481-R2, NUDOCS 8202220031 | |
Download: ML20041A360 (2) | |
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Category:CONTRACTED REPORT - RTA
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[Table view]Technical Evaluation Rept on Third 10-Year Interval ISI Program Plan:Nneco Millstone Nuclear Power Station,Unit 2, Dtd Mar 1998 ML20140G5901997-03-27027 March 1997 Rev 0 to, Review of Millstone Nuclear Power Station Response to USNRC RAI of 960812 on Fire Barrier Ampacity Derating ML20117D0801995-11-30030 November 1995 TER on IPE - Back-End Analysis ML20117D0741995-11-30030 November 1995 Unit 2-TER on IPE Submittal Human Reliability Analysis - Final Rept ML20117D0681995-11-27027 November 1995 NPP TER on IPE Front End Analysis L-94-021, Evaluation of Util Response to Suppl 1 to NRC Bulletin 90-01:Millstone-2/-31994-11-30030 November 1994 Evaluation of Util Response to Suppl 1 to NRC Bulletin 90-01:Millstone-2/-3 ML20126M4231992-07-31031 July 1992 TER on Third 10-Yr Interval ISI Program Plan:Northeast Utils,Millstone Nuclear Power Station,Unit 1 ML20071A6371991-01-31031 January 1991 Trip Rept: Onsite Analysis of Human Factors of Event at Millstone 3 on 901231 (Turbine Bldg Pipe Break) ML20063P9331990-07-18018 July 1990 Technical Evaluation Rept Millstone Nuclear Power Station Unit 3 Station Blackout Evaluation, Final Rept ML20058K9731990-07-18018 July 1990 Technical Evaluation Rept - 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Storage of Consolidated Spent Fuel Tech Spec Change ML20205E3711986-07-31031 July 1986 Conformance to Generic Ltr 83-28,Item 2.1 (Part 1), Equipment Classification (Reactor Trip Sys Components) Fort Calhoun,Millstone Unit 2,Nine Mile Point 2 & Fort St Vrain, Technical Evaluation Rept ML20205E3991986-07-31031 July 1986 Conformance to Generic Ltr 83-28,Item 2.1 (Part 1), Equipment Classification (Reactor Trip Sys Components) Ginna,Haddam Neck,Millstone 3 & Harris 1 ML20244E1901986-07-31031 July 1986 Conformance to Generic Ltr 83-28,Item 2.1 (Part 1) Equipment Classification (Reactor Trip Sys Components), Fort Calhoun,Millstone Unit 2,Nine Mile Point Unit 2 & Fort St Vrain ML20205T5611986-06-11011 June 1986 Review of Licensee Responses to SEP Topic III-7.B,'Design Codes,Design Criteria & Loading Combinations,' Technical Evaluation Rept ML20197G5931986-04-30030 April 1986 a Review of the Millstone 3 Probabilistic Safety Study ML20211F0301986-03-31031 March 1986 Conformance to Generic Ltr 83-28,Item 2.1 (Part 1) Equipment Classification (RTS Components) Selected GE BWR Plants (Grand Gulf 1 & 2,Hatch 1 & 2,LaSalle 1 & 2 & Millstone 1) ML20214G9591986-03-31031 March 1986 Conformance to Generic Ltr 83-28,Item 2.1 (Part 2) Equipment Qualification (Reactor Trip Sys Components), Selected GE BWR Plants ML20214C4281986-01-15015 January 1986 Site Survey of Millstone Unit 1 Maint Program & Practices, Technical Ltr Rept ML20140A9851986-01-0606 January 1986 Review of Millstone Unit 3 Tech Specs, Technical Review Rept for Onsite Activities Conducted 851111-22 ML20137A6291985-12-31031 December 1985 Review of Risk Based Evaluation of Integrated Safety Assessment Program Issues for Millstone Unit 1, Final Rept ML20210K6451985-11-30030 November 1985 PRA Insights ML20138R6321985-11-0606 November 1985 Draft Review of Licensee & Applicant Responses to NRC Generic Ltr 83-28,(Required Actions Based on Generic Implications of Salem ATWS Events),Item 1.2..., Technical Evaluation Rept ML20133A6481985-09-30030 September 1985 Review and Evaluation of the Millstone Unit 3 Probabilistic Safety Study.Containment Failure Modes,Radiological Source- Terms and Offsite Consequences ML20133A9101985-09-16016 September 1985 Draft Review of Risk Based Evaluation of Integrated Safety Assessment Program (Isap) Issues for Millstone Unit 1 ML20134G4521985-08-30030 August 1985 Draft Review of Operating Experience History Through 1984 of Millstone 1 for NRC Integrated Safety Assessment Program ML20135D2561985-08-15015 August 1985 Review of Risk Based Evaluation of Integrated Safety Assessment (Isap) Issues for Millstone Unit 1 - 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[Table view]Technical Evaluation Rept on Third 10-Year Interval ISI Program Plan:Nneco Millstone Nuclear Power Station,Unit 2, Dtd Mar 1998 ML20140G5901997-03-27027 March 1997 Rev 0 to, Review of Millstone Nuclear Power Station Response to USNRC RAI of 960812 on Fire Barrier Ampacity Derating ML20117D0801995-11-30030 November 1995 TER on IPE - Back-End Analysis ML20117D0741995-11-30030 November 1995 Unit 2-TER on IPE Submittal Human Reliability Analysis - Final Rept ML20117D0681995-11-27027 November 1995 NPP TER on IPE Front End Analysis L-94-021, Evaluation of Util Response to Suppl 1 to NRC Bulletin 90-01:Millstone-2/-31994-11-30030 November 1994 Evaluation of Util Response to Suppl 1 to NRC Bulletin 90-01:Millstone-2/-3 ML20126M4231992-07-31031 July 1992 TER on Third 10-Yr Interval ISI Program Plan:Northeast Utils,Millstone Nuclear Power Station,Unit 1 ML20071A6371991-01-31031 January 1991 Trip Rept: Onsite Analysis of Human Factors of Event at Millstone 3 on 901231 (Turbine Bldg Pipe Break) ML20063P9331990-07-18018 July 1990 Technical Evaluation Rept Millstone Nuclear Power Station Unit 3 Station Blackout Evaluation, Final Rept ML20058K9731990-07-18018 July 1990 Technical Evaluation Rept - Millstone Nuclear Power Station Unit 1,Station Blackout Evaluation, Final Rept ML19332B5821989-09-30030 September 1989 Conformance to Reg Guide 1.97:Millstone-2, Technical Evaluation Rept ML20246B8151989-04-30030 April 1989 Rev 1 to Conformance to Item 4.5.2 of Generic Ltr 83-28, Duane Arnold,Enrico Fermi-2,Hope Creek,Lasalle County 1 & 2, Limerick 1 & 2,Millstone 1,Monticello,Nine Mile Point 1 & 2 & Oyster Creek, Technical Evaluation Rept ML20067E7161989-03-31031 March 1989 First Interval ISI Program Millstone Nuclear Power Station Unit 3, Technical Evaluation Rept ML20070Q4561989-01-31031 January 1989 Nuclear Power Plant Sys Sourcebook,Millstone 2 ML20070Q4331989-01-31031 January 1989 Nuclear Power Plant Sys Sourcebook,Millstone 3 ML20205N9431988-10-31031 October 1988 Conformance to Generic Ltr 83-28,Item 2.2.1 - Equipment Classification for All Other Safety-Related Components: Millstone-1 ML20154B8311988-04-30030 April 1988 Rev 1 to EGG-NTA-7895, TMI Action-NUREG-0737 (II.D.1), Technical Evaluation Rept ML20205N9531988-01-31031 January 1988 Conformance to Generic Ltr 83-28,Item 2.2.1 - Equipment Classification for All Other Safety-Related Components: Millstone-3 ML20205N9481988-01-31031 January 1988 Conformance to Generic Ltr 83-28,Item 2.2.1 - Equipment Classification for All Other Safety-Related Components - Millstone-2 ML20195G5271987-10-0202 October 1987 Technical Evaluation Rept:Millstone Nuclear Power Station, Unit 1,Post-Fire Shutdown Evaluation,App R ML20237J1411987-08-17017 August 1987 Facility Sys Analysis Support, Progress Rept 23 for 870713 -0807 ML18052B1931987-06-30030 June 1987 Conformance to Item 2.1 (Part 2) of Generic Ltr 83-28, Reactor Trip Sys Vendor Interface,Calvert Cliffs-1 & -2, Millstone-2 & Palisades, Final Informal Rept ML20214Q8981987-04-30030 April 1987 Conformance to Item 2.1 (Part 2) of Generic Ltr 83-28, Reactor Trip Sys Vendor Interface,Hatch-1 & 2,Millstone-1, Final Rept ML20214R2161987-03-31031 March 1987 Conformance to Generic Ltr 83-28,Item 2.2.2 - Vendor Interface Programs for All Other Safety-Related Components, Haddam Neck & Millstone 1,2 &3, Informal Rept ML20214R7431987-03-31031 March 1987 Rev 1 to Conformance to Item 4.5.2 of Generic Ltr 83-28, Arkansas Nuclear One-2,Calvert Cliffs 1 & 2,Fort Calhoun, Main Yankee,Millstone 2,Palisades,Palo Verde 1,2 & 3,San Onofre 2 & 3,St Lucie 1 & 2,Waterford 3 & WNP 3 ML20212H3711987-01-14014 January 1987 Technical Evaluation of Dcrdr for Millstone Nuclear Power Station,Unit 2 ML20210Q4481987-01-0909 January 1987 Reactor Trip Sys Reliability Conformance to Item 4.5.2 of Generic Ltr 83-28,Arkansas Nuclear One Unit 2,Calvert Cliffs Units 1 & 2,Fort Calhoun,Maine Yankee,Millstone Unit 2, Palisades,Palo Verde Units..., Technical Evaluation Rept ML20211K5101986-11-30030 November 1986 Input for Ser,Mcguire Nuclear Station Units 1 & 2,Millstone Nuclear Power Station Unit 3,Seabrook Station Units 1 & 2, VC Summer Nuclear Station,Vogtle Electric...Reactor Trip Sys Reliability,Item 4.5.2 of Generic Ltr 83-28 ML20206Q3321986-08-31031 August 1986 Draft Technical Evaluation Rept,Millstone 2 - Storage of Consolidated Spent Fuel Tech Spec Change ML20205E3711986-07-31031 July 1986 Conformance to Generic Ltr 83-28,Item 2.1 (Part 1), Equipment Classification (Reactor Trip Sys Components) Fort Calhoun,Millstone Unit 2,Nine Mile Point 2 & Fort St Vrain, Technical Evaluation Rept ML20205E3991986-07-31031 July 1986 Conformance to Generic Ltr 83-28,Item 2.1 (Part 1), Equipment Classification (Reactor Trip Sys Components) Ginna,Haddam Neck,Millstone 3 & Harris 1 ML20244E1901986-07-31031 July 1986 Conformance to Generic Ltr 83-28,Item 2.1 (Part 1) Equipment Classification (Reactor Trip Sys Components), Fort Calhoun,Millstone Unit 2,Nine Mile Point Unit 2 & Fort St Vrain ML20205T5611986-06-11011 June 1986 Review of Licensee Responses to SEP Topic III-7.B,'Design Codes,Design Criteria & Loading Combinations,' Technical Evaluation Rept ML20197G5931986-04-30030 April 1986 a Review of the Millstone 3 Probabilistic Safety Study ML20211F0301986-03-31031 March 1986 Conformance to Generic Ltr 83-28,Item 2.1 (Part 1) Equipment Classification (RTS Components) Selected GE BWR Plants (Grand Gulf 1 & 2,Hatch 1 & 2,LaSalle 1 & 2 & Millstone 1) ML20214G9591986-03-31031 March 1986 Conformance to Generic Ltr 83-28,Item 2.1 (Part 2) Equipment Qualification (Reactor Trip Sys Components), Selected GE BWR Plants ML20214C4281986-01-15015 January 1986 Site Survey of Millstone Unit 1 Maint Program & Practices, Technical Ltr Rept ML20140A9851986-01-0606 January 1986 Review of Millstone Unit 3 Tech Specs, Technical Review Rept for Onsite Activities Conducted 851111-22 ML20137A6291985-12-31031 December 1985 Review of Risk Based Evaluation of Integrated Safety Assessment Program Issues for Millstone Unit 1, Final Rept ML20210K6451985-11-30030 November 1985 PRA Insights ML20138R6321985-11-0606 November 1985 Draft Review of Licensee & Applicant Responses to NRC Generic Ltr 83-28,(Required Actions Based on Generic Implications of Salem ATWS Events),Item 1.2..., Technical Evaluation Rept ML20133A6481985-09-30030 September 1985 Review and Evaluation of the Millstone Unit 3 Probabilistic Safety Study.Containment Failure Modes,Radiological Source- Terms and Offsite Consequences ML20133A9101985-09-16016 September 1985 Draft Review of Risk Based Evaluation of Integrated Safety Assessment Program (Isap) Issues for Millstone Unit 1 ML20134G4521985-08-30030 August 1985 Draft Review of Operating Experience History Through 1984 of Millstone 1 for NRC Integrated Safety Assessment Program ML20135D2561985-08-15015 August 1985 Review of Risk Based Evaluation of Integrated Safety Assessment (Isap) Issues for Millstone Unit 1 - Phase 2 ML20213F4161985-07-31031 July 1985 Conformance to Reg Guide 1.97,Millstone Nuclear Power Station,Unit 3 ML20136G1881985-07-23023 July 1985 Radiological Effluent Tech Spec Implementation,Millstone Point Nuclear Power Station Unit 1, Technical Evaluation Rept ML20135A6611985-07-19019 July 1985 Review of Millstone Unit 3 Tech Specs,Northeast Nuclear Energy Co, Technical Review Rept ML20244D3871985-07-10010 July 1985 Review of Licensee & Applicant Responses to NRC Generic Ltr 83-28 (Required Actions Based on Generic Implications of Salem ATWS Events),Item 1.2, `Post-Trip Review:Data & Info Capabilities' for Bellefonte Nuclear Plant. ML20134P9851985-06-30030 June 1985 Conformance to Generic Ltr 83-28 Items 3.1.3 & 3.2.3 for Dresden Units 2 & 3,Millstone Unit 1,Monticello,Pilgrim & Quad-Cities Units 1 & 2 1998-03-31 |
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ABSTRACT e sg;1 9
(4 g This report reviews the Millstone Unit No. 2 Technical Soecification ,
requirements for redundancy in decay heat removal capability in all modes of operation.
FOREWORD This report is supplied as part cf the " Selected Operating Reactor Issues Program (III)" being conducted for the U.S. Nuclear Regulatory Commission, Office of Nuclear Reactor Regulation, Division of Licensing, by EG&G Idaho, Inc., Reliability and Statistics Branch.
The U.S. Nuclear Regulatory Commission funded the work under the
! authorization, B&R 20 19 01 06, FIN No. A6429.
I ii 8202220031 820216 PDR RES I o PDR. J
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Hot Standby (made 3) 3.4.1.2 Limiting Conditions. for Operation 4.4.1.2.1 Surveillance Requirement 4.4.1.2.2 Surveillance Requirement Shutdown (modes 4 & 5) 3.4.1.3 Limiting Conditions for Operation 4.4.1.3.1 Surveillance Requirement X 4.4.1.3.2 Surveillance Requirement 4.4.1.3.3 Surveillance Requirement 4.4.1.3.4 Surveillance Requirement Refueling Operations (mode 6) 3.9.8.1 Limiting Condition for Operation 3.9.8.2 Limiting Condition for Operation 4.9.8.1 Surveillance Requirement 4.9.8.2 Surveillance Requirement 3.0 DISCUSSION AND EVALUATION Millstone Unit No. 2, is a two loop Combustion Engineering (CE) PWR plant. The following discussion presents an evaluation of the proposed technical specifications submitted by Northeast Utilities for redundant decay heat removal as requested by the NRC.
3.1 Startup and Power Operation--Modes 1 and 2 The proposed TS require that both reactor coolant loops and coolant pumps are to be operational. If these conditions are not met, the reactor is to be in Hot Standby (Mode 3) within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />. The proposed TS require verification that the required reactor coolant loops are in operation at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
The above described proposed TS are in agreement with the MTS since two coolant loops are required and the periodic surveillance assures the operability of the systems.
3.2 Hot Standby--Mode 3 The proposed TS require two coolant loops and at least one associated coolant pump for each loop shall be operable and at least one of the coolant loops shall be in operation during this operating mode;a and the proposed TS require the plant to be in Hot Shutdown (Mode 4 & 5) in 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> if the two coolant loops are not operable and cannot be restored to operable status
- a. All reactor coolant pumps may be de-energized for up to I hour provided (1) no operations are permitted that would cause dilution of the reactor coolant system baron concentration, and (2) core outlet temperature is maintained at least 10 0F below saturation temperature.
2
,