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Results
Other: A01061, Forwards Info Re Design Basis Transient & Accident Conditions Providing Basis for Auxiliary Feedwater Sys Flow Requirements,In Response to NRC 791022 Request.Based on Analyses,Auxiliary Feedwater Sys Complies W/Section 1.4, B10116, Advises of Discrepancy Between Delays Cited in Util 800520 Analysis Re Use of Two Electrically Driven Auxiliary Feedwater Pumps in Automatic Initiation Scheme.Multiple Conservatisms Justify Validity of Analysis, ML19210E670, ML19211A900, ML19211C160, ML19253C587, ML19257C081, ML19257C288, ML19257D549, ML19260B517, ML19305A972, ML19305D956, ML19309B223, ML19322E381, ML19338C766, ML20125D098
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MONTHYEARML19256E2921979-10-22022 October 1979 Fowards Generic Request for Addl Info & Requirements for Auxiliary Feedwater Sys Project stage: RAI ML19210E6701979-11-28028 November 1979 Responds to NRC 791018,22 & 1121 Requests Re short- & long- Term Recommendations for Auxiliary Feedwater Sys Requirements Project stage: Other ML19253C5871979-11-30030 November 1979 Forwards Calculations Re Automatic Initiation of Auxiliary Feedwater & Supporting Statement That Longer Time Is Available for Haddem Neck Steam Generator Dryout than for Millstone-2 Project stage: Other ML19260B5111979-12-0606 December 1979 Forwards Proposed Automatic Initiation Scheme for Auxiliary Feedwater Sys, in Response to NRC Request for Specific Design Details & Demonstration of Compliance W/Hr Denton Project stage: Request ML19211A9001979-12-17017 December 1979 Forwards Design Drawings Re Automatic Initiation of Auxiliary Feedwater,In Response to NRC Request.W/O Encl. List of Drawings Encl Project stage: Other ML19211C1601979-12-21021 December 1979 Requests Tech Specs for Auxiliary Feedwater Sys Mods & Revision of Normal & Emergency Operating Procedures. Sample Tech Spec Pages Encl Project stage: Other ML20125D0981979-12-27027 December 1979 Responds to to Hendrie Re Concerns About Requirement for Automatically Initiated Auxiliary Feedwater Sys at Facilities.Requests Analysis of Effect of Failure to Isolate Feedwater Flow to Affected Steam Generator Project stage: Other ML19260B5171979-12-31031 December 1979 Proposed Automatic Initiation Scheme for Auxiliary Feedwater Sys Project stage: Other ML19257C0811980-01-0303 January 1980 Forwards Summary of Bulletins & Orders Task Force 791218-19 Audit of Small Break LOCA Emergency Procedure & Operator Retraining.List of Exit Interview Attendees & List of Instrument Power Supplies Encl Project stage: Other ML19257C2881980-01-17017 January 1980 Submits Results of Review of Operating Records of 48-h Endurance Test on Auxiliary Feedwater Pumps,In Response to short-term Recommendations of NRC 791011 & 22 Ltrs.Intent of Recommendation Fulfilled Project stage: Other ML19257D5491980-01-25025 January 1980 Forwards Info Re Automatic Initiation of Auxiliary Feedwater.No Conclusion Reached Re Acceptability of Implementation Project stage: Other ML19273D1251980-02-14014 February 1980 Forwards Licensee Accident Analysis Re Main Steam Line Break Inside Containment.Requests Safety Evaluation.Licensee Plans to Submit Auxiliary Feedwater Sys auto-initiation Sys Which Delays Auxiliary Feedwater Flow for Three Minutes Project stage: Approval ML19322E3811980-03-0505 March 1980 Responds to IE Bulletin 80-04 Re Analysis of PWR Main Steam Line Break W/Continued Feedwater Addition.Details of Control Grade Automatic Initiation of Auxiliary Feedwater Scheme Are Being Finalized.Necessity of Installation Is Questionable Project stage: Other ML19305A9721980-03-10010 March 1980 Advises That Util Response to NRC 791022 Request Re Auxiliary Feedwater Sys Flow Design Info Is Scheduled for Submittal on or About 800616 Project stage: Other ML19309B2231980-03-31031 March 1980 Proposed Revisions to Tech Specs 3.7.1.2 & 4.7.1.2,adding Surveillance Requirement for Auxiliary Feedwater Flow Test After Cold Shutdown Exceeding One Month Project stage: Other ML19309B1741980-03-31031 March 1980 Application to Amend License DPR-65,in Response to Concerns Expressed in NRC .Revisions Add Surveillance Requirement for Auxiliary Feedwater Flow Test After Cold Shutdown Exceeding One Month.Affidavit Encl Project stage: Request ML19305D9561980-04-11011 April 1980 Discusses Problems W/Implementation of Lessons Learned Task Force Recommendation Re Automatic Initiation of Auxiliary Feedwaters Sys.Requests NRC Concurrence W/Plan for Implementing Requirement During 1980 Refueling Outage Project stage: Other ML19275E7271980-05-0909 May 1980 Suppl to Safety Evaluation Supporting Licensee 800125 Response.Peak Containment Pressure Will Remain Below Design Pressure Even W/Addition of Auxiliary Feedwater at run-out Flow Project stage: Approval ML19275E7241980-05-0909 May 1980 Forwards Supplemental Safety Evaluation Supporting Licensee 800125 Response.Peak Containment Pressure Will Remain Below Design Pressure Even W/Addition of Auxiliary Feedwater at Run Out Flow Project stage: Approval A00803, Application to Amend License DPR-65,submitted as Proposed Revision to Tech Specs,In Response to NRC . Summarizes Status of Implementation of Automatic Initiation of Auxiliary Feedwater.One Pump Sufficient1980-05-20020 May 1980 Application to Amend License DPR-65,submitted as Proposed Revision to Tech Specs,In Response to NRC . Summarizes Status of Implementation of Automatic Initiation of Auxiliary Feedwater.One Pump Sufficient Project stage: Request ML19323F2551980-05-20020 May 1980 Tech Spec Change Request for Tables 3.3-3,3.3-4,3.3-5 & 4.3-2,for Engineered Safety Features Actuation Sys Instrumentation,Trip Values,Response Times & Surveillance Requirements Project stage: Request A01061, Forwards Info Re Design Basis Transient & Accident Conditions Providing Basis for Auxiliary Feedwater Sys Flow Requirements,In Response to NRC 791022 Request.Based on Analyses,Auxiliary Feedwater Sys Complies W/Section 1.41980-06-16016 June 1980 Forwards Info Re Design Basis Transient & Accident Conditions Providing Basis for Auxiliary Feedwater Sys Flow Requirements,In Response to NRC 791022 Request.Based on Analyses,Auxiliary Feedwater Sys Complies W/Section 1.4 Project stage: Other B10061, Application for Amend to License DPR-65,incorporating Proposed Revisions to Tech Specs Required to Support Plant Operation During Cycle 4 Reload1980-08-29029 August 1980 Application for Amend to License DPR-65,incorporating Proposed Revisions to Tech Specs Required to Support Plant Operation During Cycle 4 Reload Project stage: Request ML19338C7661980-08-29029 August 1980 Proposed Revisions to Tech Specs Required to Support Plant Operation During Cycle 4 Reload Project stage: Other ML19338D1421980-09-0202 September 1980 Requests Class III Fee for Review of 800520 Application for Proposed Tech Spec Changes Re Automatic Initiation of Auxiliary Feedwater Sys.Application Involves Consideration of Single Safety Issue Project stage: Approval B10116, Advises of Discrepancy Between Delays Cited in Util 800520 Analysis Re Use of Two Electrically Driven Auxiliary Feedwater Pumps in Automatic Initiation Scheme.Multiple Conservatisms Justify Validity of Analysis1980-10-31031 October 1980 Advises of Discrepancy Between Delays Cited in Util 800520 Analysis Re Use of Two Electrically Driven Auxiliary Feedwater Pumps in Automatic Initiation Scheme.Multiple Conservatisms Justify Validity of Analysis Project stage: Other B10127, Advises of Error in Sgn 111 Code Used for Feedline Break Analysis Submitted 800616 in Response to NRC 791022 Request for Addl Info Re Auxiliary Feedwater Sys Flow Requirements. Forwards Reanalysis Using Sgn 111 Code1980-11-20020 November 1980 Advises of Error in Sgn 111 Code Used for Feedline Break Analysis Submitted 800616 in Response to NRC 791022 Request for Addl Info Re Auxiliary Feedwater Sys Flow Requirements. Forwards Reanalysis Using Sgn 111 Code Project stage: Request 1980-10-31
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MILLSTONE NUCLEAR POWER PLANT, UNIT 2 SER Supplement Docket No. 50-336 CONTAINMENT OVERPRESSURIZATION POTENTIAL DUE TO AUXILIARY FEEDWATER PUMP RUN-0UT FLOW FOLLOWING A MAIN STEAM LINE BREAK By letter dated December 21, 1979, the staff requested Northeast Utilities, the licensee for the Millstone Nuclear Plant, Unit 2 to provide certain additional information.
Specifically, the licensee was to assess the potential for contain-ment overpressurization due to the anticipated continuous additon, at pump run-out flow, of auxiliary feedwater to the.affected steam generator following a postulated main steam line break (MSLB) accident.
The staff's interest in this issue resulted from the recommendation of the Three Mile Island, Unit 2 (TMI-2) Lessons Learned Task Force to automat'esinitiation of the auxiliary feedwater systems. Automating the auxiliary feedwater system would cause an increase in energy released to containment after a MSLB; thereby, increasina the containm/ent pressure response to a MS' B.
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By letter dated January 25, 1980, Northeast Utilities responded to the staff's letter cited above.
In the orf pinal MSLB analysis by Northeast Utilities, no consideration was given to auxiliary feedwater pump run-out. The licensee has since performed an analy-sis that demonstrates that the addition of auxiliary feedwater at the run-out flow condition (2000 gpm) will not cause containment pressure to rise above the initial blowdov4 peak. The auxiliary feedwater pump run-out flow was conserva-tively based on a backpressure of one atmosphere.
The staff concurs with the licensee's conclusion that the peak containment pres-sure will remain below the containment design pressure with the addition of auxiliary feedwater at the run-out flow rate.
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