Letter Sequence Other |
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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 ML19253C9351979-12-0606 December 1979 Forwards Rept Re Proposed Automatic Initiation of Auxiliary Feedwater Sys in Response to NRC Request for Sepcific Design Details & for Demonstration of Compliance W/Nrc to All Operating Nuclear Power Plants 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 ML17208B0701979-12-18018 December 1979 Provides Info on Compliance W/Tmi Lessons Learned Task Force short-term Item Re Auxiliary Feedwater Sys Flow Indication, in Response to NRC 791211 Request.Util Installing Single Control Grade Flow Indication Channel Per Feedline 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 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 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 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 A01060, Responds to IE Bulletin 80-06, Engineered Safety Feature (ESF) Reset Controls. Three Facilities Will Have Completed Mods Per IE Bulletin 80-06 by 810101.List of Equipment & Status of Criteria Encl1980-06-13013 June 1980 Responds to IE Bulletin 80-06, Engineered Safety Feature (ESF) Reset Controls. Three Facilities Will Have Completed Mods Per IE Bulletin 80-06 by 810101.List of Equipment & Status of Criteria Encl Project stage: 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 1.41980-06-16016 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 ML19338C7661980-08-29029 August 1980 Proposed Revisions to Tech Specs Required to Support Plant Operation During Cycle 4 Reload 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 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 A00921, Forwards Addl Response to IE Bulletin 80-06, Engineered Safety Feature Reset Controls. Reset Logic Associated W/Certain Components Did Not Require Mods.Items & Justification for Deletions Described1981-02-13013 February 1981 Forwards Addl Response to IE Bulletin 80-06, Engineered Safety Feature Reset Controls. Reset Logic Associated W/Certain Components Did Not Require Mods.Items & Justification for Deletions Described Project stage: Other A01488, Responds to NRC Requesting Auxiliary Feedwater Pump Endurance Test & Compliance W/Requirement to Automate Steam Driven Auxiliary Feedwater Pump.Test Confirmed Pump Vibrations Did Not Exceed Allowable Limits1981-02-19019 February 1981 Responds to NRC Requesting Auxiliary Feedwater Pump Endurance Test & Compliance W/Requirement to Automate Steam Driven Auxiliary Feedwater Pump.Test Confirmed Pump Vibrations Did Not Exceed Allowable Limits Project stage: Other ML19347D4851981-03-19019 March 1981 Discusses Review of Util Providing Info Re 48-h Auxiliary Feedwater Pump Endurance Test & Compliance W/Nrc Requirement to Automate Start of steam-driven Pump.Item Re Pump Test Resolved Project stage: Approval ML19343D0051981-03-20020 March 1981 Suppls 810213 Response to IE Bulletin 80-06, Engineered Safety Feature (ESF) Reset Controls. Low Pressure Safety Injection Pumps P-42A & B Are Secured Upon Receipt of Sump Recirculation Actuation Signal Project stage: Other ML20005A8731981-06-26026 June 1981 Informs That Control Board Mounting Hardware for Auxiliary Feedwater Flow Indicators Will Not Arrive Prior to Required 810701 Inservice Date,Per NUREG-0737,Item II.E.1.2.Vendor Failed to Order Equipment.Foxboro Co Encl Project stage: Other ML20054E1841982-04-16016 April 1982 Forwards Responses to Generic Ltr 82-05 Re post-TMI Requirements Implementation.Continued Safe Operation Assured W/Existing Implementation Status Project stage: Other 1980-03-10
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DOCKET NO. 50-336 ATTACHMENT 2 MILLSTONE NUCLEAR F0WER STATION, UNIT NO. 2 PROPOSED AUIDMATIC INITIATION SCHEME FOR AUXILIARY FEEDWATER SYSTDIS DECDIBER, 1979 1521 324
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Introduction The AFW system at MP-2 consists of two half capacity motor driven AFW pumps and one full capacity turbine driven pump. Each motor driven pump is powered from a separate and redundant emergency bus. The turbine is supplied with steam from either main steam header. Each AFW turbine steam supply header isolation valve is normally open. The combined header steam admission valve is normally closed.
The auxiliary feedwater valves will be lef t in their operating position so that only the check valves have to change position to commence feeding.
The AFW feed regulating valves will be prepositioned to provide 300 GPM flow to each SG at normal isolated SG pressure. The pump discharge crossconnect valve will be normally open. This allows feeding either steam generator with, two motor driven AFW pumps or with the turbine driven AFW pump. The pump suction crossconnect valve will be normally closed thus the turbine driven pump will receive water from the condensate storage tank from one suction line while the motor driven pumps will receive water from the condensate storage tank from another suction line. The attached diagram is provided to illustrate the above description.
AFW Initiation Steam generator level will be the only parameter sensed to initiate AFW automatically. The system will consist of two trains, Facility Z1 and Facility Z2.
For each train two level signals from each steam generator will be applied to bistables. The dry contact outputs of the bistables will be m.trixed to two out of four. The matrix will control two lockout relays per train. Two control selector switches between the bistables and the lockout relays will be used to pass or block the auto start signal, trip the lockout relays, or reset the lockout relays. One switch will be located on the control room panel i521 325
(C05) the other on the hot shutdown control panel (C21). The block is accomplished by moving either switch to a " pull or lock" position. The pull to lock operation requires an extra step from normal switch operation, and once accomplished the switch is in a visually abnormal position, making it distinct from other switches on the control board, The block position will also be annunciated in the control room and an amber light will be lit at panel C21.
One lockout relay per train supplies a contact to start a motor driven AFW pump. The start signal to the mo tor driven pump will be blocked if the emergency diesel generator is required to start and sequentially accept loads from its emergency bus.
In this mode (and with SO level low) the AFW pump will be sequenced onto the diesel in load group four, twenty seconds after sequencing commences. Another contact from the first lockout relay causes an alarm in the control room and lights a red light at C05 and C21 indicating pickup of the lockout relay and automatic AFW system initiation. The second lockout relay in the train provides a contact to the circuit for the motor operated AFW regulating valve associated with the train, and a contact to open the combined steam admission valve for the turbine driven AFW pump. The open signal to the AFW regulating valve will be interrupted by a valve position limit switch.
The AFW regulating valve will be prepositioned as mentioned before and the open signal is provided to guarantee that a flow path is available.
One lockout relay in each train starts its respective motor driven AFW pump.
A second lockout relay in each train provides start signals to the turbine and guarantees a flow path for its respective train.
1521 326 NUREG 0578 Design Requirements 1.
The design provides for the automatic initiation of the auxiliary feedwater system by sensing a low steam generator level, starting the three AFW pu=ps and assuring an adequate flow path.
2.
The signals and circuits have been designed so that a single failure will not result in the loss of auxiliary feedwater system function. The signals and circuits will be arranged in trains.
Separation of signals and circuits will be maintained in accordance with established plant separation criteria for safeguard systems. Two level signals from each steam generator will be used per train. The level signals will be grouped according to their power source either Z1 or 22.
Two separate two out of four matrices will be extablished to operate four relays (twc per train). The loss of one complete power train would still provide a minimum of one AFW flow path and one motor driven pump. The turbine driven pump would not star' automatically if pcwer for the steam admission valve was aligned to the unavailable power facility. The operator has turbine RPM, inlet steam pressure, and steam admission valve position indicating lights displayed on control room panel C05. For the assumed case where the turbine driven pump has failed to start because power to the selected emergency bus has been lost, turbine speed and inlet steam pressure would be zero, indicating the turbine driven pump has failed to start.
Both the open and the closed indicating lights for the steam admission valve would be out indicating a loss of power to the valve control circuit, thus indicating the cause for the failure of the turbine driven pump to start. The operator would have ample time to proceed to the Hot Shutdown 1521 327
Control Panel (C21), about fif ty feet away, and select the known available power source. This will be identified because one of the motor driven pumps will have started, and be providing fifty percent of the required auxiliary feedwater flow. Loss of one complete power train would still permit responding to a low steam generator level in either steam generator as two level detectors for each steam generator would still be operable and powered from the redundant train.
3.
Testability of the level signals will be included in the design engineering of the proposed change. The entire system can be tested by inserting signals in the level current loops. This method may also be employed in testing one current loop and associated histable at a time. The lockout relays and actuated equipment can be tested by placing either of the switches between the bistables and the relays in the start position. The entire system can be tested as a whole or the signal portion and the relay and actuated equipment portion can be tested separately.
4.
The initiating signals and circuits are powered from the emergency buses, from the vital buses via the inverters, or from the battery buses.
Power to operate the combined steam admission valve to the turbine driven AFW pu=p may come from a Z1 motor control center or a 22 motor control center.
Cable separation will be verified before upgrading its classification from facility 5 to facility Z5.
5.
Manual capability to initiate the auxiliary feedwater system from the control room will be retained. The AFW system may be started either by operating individual switches for each component or by going to the start position with the two new switches on C05. A single failure in the manual circuit will affect only one of the two redundant trains.
1521 328 6.
The AC motor dri - 7 umps and valves in the auxiliary feedwater system have been included in the automatic actuation of the loads to the emergency buses. The valves receive open signals regardless of the emergency bus conditions since the motors involved are less than two horsepower total.
The motor driven pumps are sequenced onto the emergency bus as previously discussed.
7.
The automatic initiating signals and circuits have been designed so that their falure will not result in the loss of manual capability to initiate the AFW system from the control room. The automatic signals and circuits have been designed to supplement but not interrupt the manual control of the AFW system. Failure by short circuit could start one train but would not affect the other train. Failure by open circuit would still permit normal manual control.
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