ML20213A571
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Letter Sequence Other | |
|---|---|
TAC:62942, (Open) | |
Results
Other: ML20136A525, ML20154H062, ML20205T087, ML20209B179, ML20209H460, ML20209J071, ML20210S931, ML20212N168, ML20212P923, ML20213A571, ML20213F835, ML20214K127, ML20214K485, ML20214K986, ML20214W789, ML20235H950, NUREG-1259, Forwards Corrected Pages VI,3/4 4-40,3/4 7-17,3/4 7-18 & 3/4 7-19 to Facility Tech Specs | |
MONTHYEARML20136A5251985-12-20020 December 1985
[Table View]Forwards Preissue Rev 1 to Proposed Tech Specs in Accordance w/10CFR50.36.Rev Incorporates Recent Plant Design Changes Project stage: Other ML20154H0621986-02-27027 February 1986 Forwards Beaver Valley Deletion of Reactor Trip on Turbine Trip Below 70% Power. Analysis Justifies Increase of Setpoint from 50 to 70% Power Level for Reactor Trip Upon Turbine Trip Project stage: Other ML20141F7021986-04-0909 April 1986 Forwards Request for Addl Info to Continue Review of 851220 Draft Tech Specs.Response Should Be Submitted within 45 Days of Ltr Receipt Project stage: Draft RAI ML20204A0161986-05-0606 May 1986 Forwards Responses to 860409 Request for Addl Info Re Draft Tech Specs.Future Unit 1 Amends & Changes to Draft Tech Specs Will Be Addressed as Needed.Revised Tech Specs Also Encl Project stage: Draft Request ML20214K1271986-08-12012 August 1986 Requests Rev to Section 2.4.3.1 of SER (NUREG-1057) to Delete Requirement for Tech Spec Mandate to Issue Flood Alert When Ohio River Exceeds 695 Mean Sea Level.Proposed Tech Specs Encl Project stage: Other ML20213H1861986-11-0606 November 1986 Forwards marked-up Draft Tech Specs,Based on Unit 1 Tech Specs Up to Amend 105,consistent W/Policy Stated in & Ser.Markups Reflect Changes Proposed in & Design Differences Between Units.W/Proposed Review Schedule Project stage: Draft Other IR 05000412/19860281986-11-0606 November 1986 Insp Rept 50-412/86-28 on 860930-1003.Violations Noted:Sys Changes Not Properly Reflected in Preoperational Tests & Failure to Assure That All Sys Prerequisites Satisfied Prior to Performance of Testing Project stage: Request ML20214Q0561986-11-20020 November 1986 Notification of 861209-11 Meetings W/Util in Shippingport,Pa to Develop Tech Specs for Facility.Applicants Response to NRC 861106 Draft Tech Specs Expected in Late Nov.Meeting Called to Resolve Differences Between NRC & Applicant ML20214R1911986-11-21021 November 1986 Forwards Typed Draft Tech Specs.Pen & Ink Version,W/Tech Spec Review Schedule,Transmitted on 861106 Project stage: Draft Other ML20214R4621986-11-28028 November 1986 Forwards Comments & Justifications on Draft Tech Specs Submitted on 861106,per Review.Addl Justification Will Be Provided During 861209-11 Tech Spec Review Meetings,If Requested ML20207J8991986-12-31031 December 1986 Notification of 870108-09 Meeting W/Util in Bethesda,Md to Discuss Issues Re Draft Tech Specs ML20212F3931987-01-0707 January 1987 Summary of 861209-11 Site Meeting W/Applicant & Consultants Re Tech Spec Review,Proposed Requirements Described in SER & Ssers & Differences Between Draft Tech Specs & Current Regulatory Requirements ML20209B1791987-01-26026 January 1987 Forwards Proprietary WCAP-11366 & Nonproprietary WCAP-11367, Westinghouse Setpoint for Protection Sys,Beaver Valley Unit 2, Per SER Section 7.2.2.4 (NUREG-1057).Related Info Also Encl.W/O WCAP-11367 Project stage: Other ML20213A5711987-01-28028 January 1987 Forwards Proof & Review Tech Specs for Comment by 870211 Project stage: Other ML20210S9311987-02-10010 February 1987 Forwards Assessment of SER Sections 6.4,9.2.1.2,9.5.4.2,10.2 & 10.4.9 Re Acceptability of plant-specific Tech Specs Project stage: Other ML20210T3521987-02-10010 February 1987 Notification of Meetings W/Util to Discuss & Prepare Final Version of Tech Specs.Meetings Will Take Place from Notice Date Through Apr 1987 Project stage: Meeting ML20212N1681987-03-0606 March 1987 Requests Exemption from Requirements of 10CFR50,App J, Section III.D.2(b)(ii) Re Testing Air Locks Opened During Periods When Containment Integrity Not Required by Tech Spec.Tech Spec 4.6.1.3.b Deviates from Requirement Project stage: Other ML20212P9231987-03-0606 March 1987 Forwards Revised Tech Specs Re Pressure Isolation Valve Testing,Per 870206 Telcon.Proposed Tech Specs Do Not Include Rev 5 of STS Item 4.4.6.2.2.(b) & (D) for Listed Reasons Project stage: Other ML20206J9501987-04-10010 April 1987 Forwards Final Draft Tech Specs to Be Issued as App a to License.Discussions Re Adequacy of Reactor Trip Sys,Esf Actuation Sys & Control Room Habitability May Alter Tech Specs.Proof of Consistency W/Fsar Requested by 870511 Project stage: Draft Other ML20215H4821987-04-13013 April 1987 Forwards Comments Re Preliminary Draft of Proposed Low Power License Transmitted by NRC .Util Will Work W/Nrc Project Manager to Resolve Comments Project stage: Draft Other ML20209H4601987-04-24024 April 1987 Provides Basis for Operating Bypass of ATWS Mitigation Sys Actuation Circuitry Below 40% Turbine Load,Per 870227 Commitment Project stage: Other ML20209J0711987-04-24024 April 1987 Submits Info to Finalize Facility Tech Specs.Fsar Table 6.2-60 for Containment Isolation Valves Revised to Change All Air Operated Valve Stroke Times from 10 to 60 S.Tech Spec Table 3.6-1 Should Be Revised Accordingly Project stage: Other ML20213F8351987-05-0707 May 1987 Forwards Safety Evaluation Justifying Use of Pressurizer pressure-high Reactor Trip Setpoint of 2,375 Psig & Supporting Required Tech Spec Change Concern Re Calculation of ESF Response Time for Safety Injection Function Project stage: Other ML20214H2761987-05-15015 May 1987 Application for Amend to License DPR-66,deleting Applicability Requirements for Modes 2 & 3 & Replacing 7-day Test Frequency w/120-day Test Frequency Project stage: Request ML20205T0871987-05-19019 May 1987 Advises That Amend to FSAR Chapter 16 to Encompass Surveillance & Operability Requirements Would Resolve NRC Concerns Project stage: Other ML20214K9251987-05-22022 May 1987 Forwards Addl Info Requested by NRC in 870514 Meeting Re Operability & Testing of Control Room Isolation on High Radiation & High Chlorine to Be Added to Fsar.Tech Spec Discussion Considered Closed by Submittal Project stage: Meeting ML20214K4851987-05-26026 May 1987 Forwards Westinghouse Describing Essence of 870522 Discussion W/Util & NRC Re Turbine Overspeed Open Item.Info Justifies & Supports Util Position That Monthly Surveillance Testing Appropriate for Turbine Project stage: Other ML20214K9861987-05-27027 May 1987 Informs That Util Will Provide Safety Evaluation Justifying Utilization of Equal or Greater than 7% Target Band Core Delta Flux & Fq & Fh Multiplier Values as Provided in Fsar. Formal Evaluation Will Be Provided by 870610 Project stage: Other ML20214L6211987-05-27027 May 1987 Attests to Accuracy of 870418 Final Draft Tech Specs & Addl Page Changes to 870527 Final Draft,In Response to Request. Final Draft Tech Specs Accurately Reflect as-built Plant & Current FSAR Project stage: Draft Other ML20214W7891987-06-0808 June 1987 Submits Addl Info Re Several Values Previously Revised in FSAR & Incorporated in Tech Specs.Encl Westinghouse Ltr DMW-D-6020 Documents That Revised Values Used in Safety Analysis for Facility & Justifies Use in Tech Specs Project stage: Other NUREG-1259, Forwards Corrected Pages VI,3/4 4-40,3/4 7-17,3/4 7-18 & 3/4 7-19 to Facility Tech Specs1987-06-10010 June 1987 Forwards Corrected Pages VI,3/4 4-40,3/4 7-17,3/4 7-18 & 3/4 7-19 to Facility Tech Specs Project stage: Other ML20235H9501987-07-0808 July 1987 Forwards Proposed Tech Specs 3.7.7 Re Control Room Habitability,Authorizing Emergency Backup Power for One Train of Dampers & Fans to Not Be Available in Modes 5 & 6, Per Request Project stage: Other ML20205T0221988-05-27027 May 1988 Forwards Replacement Pages for 870410 Tech Spec Final Draft. W/O Encl Project stage: Draft Other 1987-02-10 |
| ML20213A571 | |
| Person / Time | |
|---|---|
| Site: | Beaver Valley |
| Issue date: | 01/28/1987 |
| From: | Tam P Office of Nuclear Reactor Regulation |
| To: | Carey J DUQUESNE LIGHT CO. |
| References | |
| TAC-62942, NUDOCS 8702030361 | |
| Download: ML20213A571 (419) | |
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