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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
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
ML20041G3791982-03-0505 March 1982
Transmits Application for Amend to License NPF-3,extending Length of Fuel Cycle 3
Project stage: Request
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
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
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
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
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
ML20066G7271982-11-15015 November 1982
Responds to Re NUREG-0737 Tech Specs (Generic Ltr 82-16)
Project stage: Other
ML20071B4701983-02-22022 February 1983
Proposed Revs to Tech Spec Re Anticipatory Reactor Trip Sys,Boration Sys Temp & Corrections to Typographical Errors in Administrative Section
Project stage: Other
ML20071B4681983-02-22022 February 1983
Forwards Proposed Tech Spec Changes Re Anticipatory Reactor Trip Sys,Boration Sys Temp & Corrections to Typographical Errors in Administration Section
Project stage: Other
ML20076F3381983-08-18018 August 1983
Forwards Application for Amend to License NPF-3 to Include Special Leak Rate Requirement for Containment Purge & Exhaust Isolation Valves
Project stage: Request
ML20076F3601983-08-18018 August 1983
Application for Amend to License NPF-3 to Include Special Leakage Test Requirement for Containment Purge & Exhaust Isolation Valves.Safety Evaluation & Significant Hazards Consideration Encl
Project stage: Request
ML20094H1521984-07-25025 July 1984
Amend 73 to License NPF-3,adding New Tech Spec Sections 3.3.2.3 & 4.3.2.3 & Tables 3.3-15 & 4.3-15 to Reflect Addition of Final Anticipatory Reactor Trip Sys
Project stage: Other
1982-03-05
[Table View] |
Text
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APPLICATION FOR AMENDMENT TO FACILITY OPERATING LICENSE NO..NPF-3 FOR DAVIS-BESSE NUCLEAR POWER STATION UNIT NO. 1 Enclosed are forty-three (43) copies 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.
Changes in Section 6.8.4 2.
Changes in Sections 3.3.2.3, 4.3.2.3, Table 3.3-15, 4.3-15 and bases By 3 9 C m D Vice Presid'ent, Nuclear Sworn and subscribed before me this O 6 day of November, 1981.
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Notary Public 1.AURIE A. GRUDZINSKI bry IWic. State of h My Commissa E 1res May 161906 9
8112040428 811125 t
PDR ADOCK 05000346 P
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Docket No. 50-346 License No. NPF-3 Serial No. 757 November 25, 1981 4
Attachment I I.
Change to Davis-Besse Nuclear Power Station Unit 1, Appendix A Technical Specifications Section 6.8.4.
A.
Time required to Implement This change is to be effective upon NRC approval 4
B.
Reason for Change (Facility Change Request 81-124)
To comply with Mr. J. F. Stolz' letter of March 24, 1981 (Log 681)
C.
Safety Evaluation Technical Specification 6.8.4 of Section 6 of Administrative Controls establishes requirements for preventive maintenance and periodic visual inspection and in-plant radiation monitor-ing.
The safety function provided by this requirement is the minimization of possible exposure and off-site release, under accident conditions. Additionally,' measurement of airborne iodine concentrations would allow for assessment of personnel exposure during accident conditions.
The leak reduction program reduces possible exposure by identifying the leaks within a potentially radioactive system allowing for corrective maintenance action.
The in-plant radiation monitoring system identifies iodine concentration in areas under accident conditions, providing the capability to determine appropriate stay times and personnel exposures in the event of an accident After Three Mile Island NUREG-0578 (Short-Term Lessons Learned) was issued and recommended a leak reduction and in-plant radiation monitoring program.
Davis-Besse has implemented these programs which are currently in effect.
These programs will not alter existing plant systems such as to defeat 4ny system safety
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functions.
There is no unreviewed safety question involved.
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