Letter Sequence Other |
|---|
|
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
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
[Table View] |
Text
~.
2NRC-7-173 JULY 8,1987 Telephone (412) 393-6000 OE x4 Shippingport. PA 15077 4004 United States Nuclear Regulatory Commission i
ATTN:
Document Control Desk Washington, DC 20555
SUBJECT:
Beaver Valley Power Station Unit No. 2 l
Docket No. 50-412 Technical Specification Changes Gentlemen:
During discussions concerning changes to the Technical Specifications for the Full Power License the Staff requested additional information and justification for a requested change to Specification 3.7.7 on control room habitability.
The requested change is attached.
The proposed change would allow emergency backup power for one train of dampers and fans to not be available in modes 5 and 6.
As currently written this specification would require entering an action statement in modes 5
and 6 to remove an Emergency Diesel Generator from service for maintenance.
This is not consistent with past Technical Specification practice.
This is also not consistent with Specification 3.8.1.2 which allows one diesel to be inoperable in modes 5
and 6.
It should be noted that while emergency-backup power may not be available the dampers and fans will still-be operable and powered from their normal power source similar to the philosophy used in Specification 3.0.5 for modes 1, 2, 3 and 4.
This approach for specifications which require two trains of equipment to be available in modes 5
and 6 has been applied to Technical Specification 3.9.8.2 and is consistent with the recently approved Beaver Valley Unit 1 amendment on control room habitability which contains a similar footnote.
I DUQUESNE LIGHT COMPANY f
I M
8707150330 07070s PDR ADOCK 05000412 By
//
P PDR JL/ (./ Carey f/ )
Senior Wce President RTZ/slp Attachment AR/NAR l
cc: Mr.
P. Tam, Project Manager (w/a) l l
l Mr. J. Beall, NRC Sr. Resident Inspector (w/a)
Ill Mr.
L. Prividy, NRC Resident Inspector (w/a)
INPO Records Center-(w/a)
_____ _ -