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MONTHYEARML19225B2461979-07-13013 July 1979
Forwards Application for Amend to License NPF-3 Revising Tech Specs to Reflect Changes Re Interim Anticipatory Reactor Trip Sys & Auxiliary Feedwater Flow Indications. Class IV Amend Fee Encl
Project stage: Request
ML15223A5321979-09-0707 September 1979
Requests Addl Info Re Upgrade of Anticipatory Reactor Trip
Project stage: Other
ML19256C7381979-10-0303 October 1979
Forwards Addl Info Re Upgrading of safety-grade Anticipatory Reactor Trip Sys (Arts),In Response to 790907 Request.One Oversize Drawing Available in Central Files
Project stage: Other
ML20213D0761979-12-20020 December 1979
Forwards Safety Evaluation Re Preliminary Design for safety- Grade Anticipatory Reactor Trips on Loss of Main Feedwater &/Or Main Turbine Generator
Project stage: Approval
ML19257B4161979-12-20020 December 1979
Forwards Safety Evaluation Re Preliminary Design for safety- Grade Anticipatory Reactor Trips on Loss of Main Feedwater &/Or Main Turbine Generator
Project stage: Approval
ML19320C0351980-07-10010 July 1980
Forwards Suppl to 800211 Reload Rept Describing Info Supporting Repairs Made to Failed Springs in Fuel Assemblies
Project stage: Other
ML20009G0981981-07-24024 July 1981
Informs That During Next Refueling Outage in Feb 1982, Anticipatory Reactor Trip Sys Will Be Replaced W/Upgraded Sys.Revised Application Will Be Submitted
Project stage: Other
ML20032A6501981-10-21021 October 1981
Ack Receipt of 810908 Rept Re safety-grade Anticipatory Reactor Sys.Requests That Addl Info Per Encl List Be Forwarded within 14 Days
Project stage: Other
ML20033C8541981-11-25025 November 1981
Forwards Application to Amend License NPF-3
Project stage: Request
ML20033C8651981-11-25025 November 1981
Proposed Tech Specs 6.8.4,3.3.2.3,4.3.2.3 & Tables 3.3-15 & 4.3-15 Re Administrative Controls & Anticipatory Reactor Trip Sys Instrumentation.Safety Evaluation & Bases Encl
Project stage: Other
ML20033C8621981-11-25025 November 1981
Application to Amend License NPF-3,revising Tech Specs to Reflect Proposed Changes to Sys Integrity Measurements & Improved Iodine Monitoring Programs & Anticipatory Reactor Trip Sys
Project stage: Request
ML20039F5871982-01-0505 January 1982
Responds to Questions Raised at 811208 Meeting W/Nrc & Consultants Re Anticipatory Reactor Trip Sys.Proposed Channel Functional Test Will Include Pressure Switch.Light Indicating Level Bypass Will Clear When Level Bypass Clears
Project stage: Meeting
ML20041G3831982-02-28028 February 1982
Cycle 3 - Reload Rept
Project stage: Other
ML20041G3811982-03-0505 March 1982
Application to Amend License NPF-3,allowing Rector Startup W/O Trip & Changing Tech Specs for safety-grade Anticipatory Reactor Trip Sys
Project stage: Request
ML20041E7421982-03-0505 March 1982
Advises That Inclusion of Emergency Diesel Generator Fuel Oil in QA Program Should Be Completed by 820415
Project stage: Request
ML20041G3821982-03-0505 March 1982
Proposed Tech Spec Tables 4.3-15 & 3.3-15 Re Anticipatory Reactor Trip Sys Instrumentation
Project stage: Other
ML20041G3791982-03-0505 March 1982
Transmits Application for Amend to License NPF-3,extending Length of Fuel Cycle 3
Project stage: Request
IR 05000346/19820101982-03-23023 March 1982
IE Insp Rept 50-346/82-10 on 820301-04.No Noncompliance Noted.Major Areas Inspected:Collection of Samples,Qa & QC of Analytical Measurements
Project stage: Request
ML20050A5131982-03-23023 March 1982
Application for Amend to License NPF-3 Consisting of Changes to Tech Specs Figures 3.1-2a & 3.1-3a of Cycle 3 Reload Rept BAW-1707 (Figures 8-5 & 8-10 of Rept)
Project stage: Request
ML20050A5081982-03-23023 March 1982
Forwards Revised Application for Amend to License NPF-3 Consisting of Changes to Tech Specs Figures 3.1-2a & 3.1-3a of Cycle 3 Reload Rept BAW-1707 (Figures 8-5 & 8-10 of Rept)
Project stage: Request
ML20050A5151982-03-23023 March 1982
Tech Spec Changes to Figures 3.1-2a & 3.1-3a of Cycle 3 Reload Rept BAW-1707 (Figures 8-5 & 8-10 of Rept).Safety Evaluation Encl
Project stage: Other
ML20053B0061982-05-11011 May 1982
Forwards Request for Addl Info in Order to Complete Application for License Amend Re Cycle 3 Reload.Response Needed by 820528
Project stage: RAI
ML20052H4931982-05-14014 May 1982
Safety Evaluation Re Final Design & Implementation of safety-grade Anticipatory Reactor Trip on Turbine Trip or Loss of Main Feedwater.Design Satisfies Reactor Protection Sys Safety Requirements & Criteria
Project stage: Approval
ML20053D5841982-06-0101 June 1982
Forwards Application for Amend to License NPF-3 Re Reactor Protection Sys Trip Setpoints Contained in Cycle 3 Reload Rept
Project stage: Request
ML20053D9731982-06-0101 June 1982
Tech Specs,App A,Reflecting Changes Contained in Cycle 3 Reload Rept
Project stage: Other
ML20053D9701982-06-0101 June 1982
Application for Amend to License NPF-3,revising Reactor Protection Sys Trip Setpoints
Project stage: Request
ML20054H2231982-06-15015 June 1982
Notifies That Seismic & Environ Qualification Summary Rept for Anticipatory Reactor Trip Sys Complete & Will Be Submitted by 820709
Project stage: Other
ML20054J6581982-06-21021 June 1982
Proposed Tech Spec Table 3.3.2 Re Reactor Protection Instrumentation Response Times
Project stage: Other
ML20054J6571982-06-21021 June 1982
Application to Amend License NPF-3,revising Tech Specs to Reflect Proposed Changes Re Reactor Protection Sys Response Time Omitted in Cycle 3 Reload rept,BAW-1707,Feb 1982
Project stage: Request
ML20054J6501982-06-21021 June 1982
Forwards Application for Amend to License NPF-3,revising Tech Specs to Reflect Proposed Changes Re Reactor Protection Sys Response Time Omitted in Cycle 3 Reload rept,BAW-1707
Project stage: Request
ML20054L1841982-06-28028 June 1982
Informs That Util 820305 Submittal Contained Table 6-2, Including Basis for Determining Worst Case Rod Bow Penalty, Per NRC Request Re License Amend Application
Project stage: Other
ML20054M2011982-07-0707 July 1982
Revises 791003 Response to Request for Addl Info Re Operating Bypasses & Bypass Indications,In Support of 811125 Request for Amend to License NPF-3
Project stage: Request
ML20063E2211982-07-0808 July 1982
Forwards Seismic Qualification Rept 3394-1..., Anticipatory Reactor Trip Sys Seismic Qualification Test Plan, Seismic Simulation Test Program... & Environ Qualification Rept..., in Response to NRC 820514 Request
Project stage: Other
ML20062F2651982-07-27027 July 1982
Concludes That Anticipatory Reactor Trip Sys Bypasses Classification as Operating Bypass Is Unacceptable Unless Addl Features to Alert Operator to Remove Bypasses Are Added
Project stage: Other
IR 05000346/19820191982-07-27027 July 1982
IE Insp Rept 50-346/82-19 on 820713.No Noncompliance Noted. Major Areas Inspected:Followup of Prompt Public Notification/Warning Sys
Project stage: Request
ML20062D5001982-07-28028 July 1982
Safety Evaluation Supporting Amend 45 to License NPF-3
Project stage: Approval
ML20065H9181982-09-29029 September 1982
Responds to Re NUREG-0737,Item II.K.2.10, Anticipatory Reactor Trip Sys (Arts). Adequate Features Available to Alert Operator to Remove Bypass When Automatic Bypass Removal Not Required
Project stage: Other
1982-03-05
[Table View] |
Text
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APPLICATION FOR MIEND: LENT t
TO 1
FACILITY OPERATING LICENSE NO NPF-3 l
FOR DAVIS-BESSE NUCLEAR POWER STATION UNIT NO. 1 Enclosed are forty-three (43) copics of the requested changes to the Davis-Besse Nuclear Power Station Unit No. 1 Facility Operating License No. NPF-3, together with the Safety Evaluation for the requested change.
The proposed changes include:
1.
Cycle 3 Reload Report (BAW-1707 February, 1982),
2.
Tables 3.3-15 and 4.3-15 and By fs/__ R. P. Crouse Vice President, Nuclear Sworn and subscribed before me this 5th day of March, 1982.
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Notary Public LAURIE A. ERUDZlNSKI IWry Miic. State cf Chio lay Ccanimen E 1res Itay 16.1935 9
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Docket No. 50-346 License No. NPF-3 Serial No. 787 March 5, 1982 I.
Change to Davis-Besse Nuclear Power Station Unit 1, Appendix A Technical Specifications to reflect Cycle 3 reload report.
A.
Time required to Implement This change is to be effective upon NRC approval B.
Reason for Change (Facility Change Request 80-268 Supplement 1) to reflect changes in the Cycle 3 core.
C.
Safety Evaluation i
See Attached I
Safety Evaluation The proposed reloading of new fuel and shuffling of fuel and control elements to facilitate nuclear power generation for Cycle 3 is in accordance with the limits and analysis proposed in the attached reload report. The safety function of the reload report and affected Technical Specifications is to ensure operation of the core within safety limits.
Per Section 7 of the attached reload report, each FSAR accident analysis has been reexamined with respect to changes in Cycle 3 parameters. This examination has concluded that thermal performance during hypothetical transients is not degraded.
In addition, thermal-hydraulic and kinetics properties have been evaluated and it has been determined that this core reload will not adversely affect the ability of DB-1 to operate safely.
The transient evaluation of Cycle 3 is also bounded by previous analyses.
Based on the above, it is concluded that the changes proposed as outlined in the reload report do not involve an unreviewed safety question.
l
Docket No. 50-346 License No. NPF-3 Serial No. 787 March 5, 1982 l
Attachment II I.
Change to Davis-Besse Nuclear Power Station Unit 1, Appendix A Technical Specifications Tables 3.3-15 and 4.3.15 i
A.
Time required to Implement This change is to be effective upon NRC approval and installa-tion of the Anticipatory Reactor Trip System.
B.
Reason for Change (Facility Change Request 79-283) The previously proposed Amendment Request requires operability of the main feed pump turbine (MFPT) trip in Modes 1 and 2 for the ARTS system.
MFPT cannot be started until sufficient steam is available (approximately 1% full power in Mode 2) to run the turbine. A revision is required to allow reactor start up without trip.
l C.
Safety Evaluation See Attached i
l s
i
Safety Evaluation This amendment request proposes changes to the previously proposed Technical Specifications for the safety grade Auticipatory Reactor Trip System (ARTS). The changes relate to the main feed pump turbine trip input to this system. The safety function of this input to ARTS is to trip the reactor on a loss of main feedwater (trip of main feedwater pump turbines) so as to reduce the likelihood of primary system pressure transients and challenges to the reactor protection system.
At Davis-Besse 1, the main feed pump turbines (MFPT) cannot be started up to a power level of approximately 1% (Mode 2) to supply feedwater to steam generators since sufficient steam is not available (by running reactor coolant pumps alone) to run the main feed pump turbine.
In that event, the electric motor driven startup feedwater pump acts as a normal supply of feedwater. However, since the MFPTs cannot be started, normal startup of the unit cannot progress owing to the ARTS trip of control rod drive breaker on " loss" of both main feed pump turbines. Therefore, the changes attached herewith propose that operability of MFPT trip functional unit and its associated surveillance requirements not be applicable during those times in Mode 2 when the main feed pumps are not running.
It is noted that with the ARTS-MFPT trip unavailable during these condi-tions in Mode 2, if a loss of feedwater (loss of startup pump) were to occur, the safety grade SFRCS will be actuated on low steam generator level or high steam generator-feedwater reverse differential pressure.
This will initiate the auxiliary feedwater system, one train of which provides more than twice the secondary side cooling as that provided by the startup pump. Thus, adequate heat removal capability will be main-tained at all times.
Based on the above, it is concluded that changes proposed herewith do not involve an unreviewed safety question.
bt d/3 l
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