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MONTHYEARML20080G8541983-09-14014 September 1983
Advises That Actions Required by 830708 Generic Ltr 83-28, Items 2.2.2,4.2.3,4.2.4 & 4.3 Re Reactor Trip Breakers Currently Being Reviewed.Response Will Be Provided Upon Completion
Project stage: Other
ML20086A8401983-11-0404 November 1983
Forwards Response to Generic Ltr 83-28, Required Actions Based on Generic Implications of Salem ATWS Events. Proprietary List Rules Will Be Forwarded Separately
Project stage: Other
ML20093G5671984-07-16016 July 1984
Forwards Responses to NRC Questions Re Preliminary Design for Automatic Shunt Trip Feature Per Generic Ltr 83-28.Shunt Trip Mod Will Be Installed During Fifth Refueling Outage
Project stage: Other
ML20094A3731984-10-30030 October 1984
Responds to 840913 Request for Addl Info Re Generic Ltr 83-28,Items 4.2.1 & 4.2.2.Westinghouse Owners Group Maint Program Reviewed & Pertinent Insps Incorporated Into plant-specific Preventive Maint Program
Project stage: Request
ML20113A5021985-01-14014 January 1985
Forwards Current List,As of 850111,for 58 Outstanding SER Issues.Specific Description of Unresolved Issue,Safety Evaluation for Issues Identified in Generic Ltr 82-33,SER, Safety Implementation Rept for SPDS & ACRS Items Requested
Project stage: Request
ML20113D6941985-01-14014 January 1985
Forwards Response to Conditional Items Per 841108 SER on Generic Ltr 83-28,Item 4.3 Reactor Trip Breaker Automatic Shunt Trip. Addl Info Justifying Addition of Status Lights for Bypass Breakers Also Encl
Project stage: Other
ML20100B1091985-03-20020 March 1985
Forwards Addl Info Re Six Backfit Requirements,As Discussed in Util .Meetings Re Resolution of Items Requested.Agenda Should Include Major Points of NRC Basis (Improvement to Safety)
Project stage: Request
ML20116N2611985-04-24024 April 1985
Amend 92 to License DPR-66,revising Tech Specs to Require Two Reactor Coolant Pumps to Be Operating When Reactor Trip Breakers Closed in Mode 3
Project stage: Request
ML20117L9181985-05-10010 May 1985
Forwards Revised Response to Generic Ltr 83-28,Item 4.3 Re Bypass Breaker Status Indication.Rev to Design Concept for Shunt Trip Attachment Automatic Actuation Includes Status Indication for Reactor Trip Bypass Breaker
Project stage: Other
ML20127K6121985-06-17017 June 1985
Forwards Tables & Figures Summarizing History of Reactor Trip Breakers in Response to Requirement for Addl Justification Contained in 850424 Preliminary Safety Evaluation Per Generic Ltr 83-28,Item 4.2.1
Project stage: Other
ML20127G8141985-06-17017 June 1985
Forwards Application for Amend to License DPR-66,removing Iodine Sampler Cartridges from Radioactive Gaseous Effluent Monitoring Instrumentation
Project stage: Request
ML20135A7951985-09-0303 September 1985
Responds to 850816 Telcon Request for Addl Info on Generic Ltr 83-28,Item 4.3 Re Bypass Breaker Status Lights & Seismic Qualification of Shunt Trip Attachment.Diagram of Revised Design of Control Room Status Lights Encl
Project stage: Request
ML20138H2181985-09-30030 September 1985
Conformance to Generic Ltr 83-28,Items 3.1.3 & 3.2.3, Beaver Valley Unit 1,North Anna Units 1 & 2 & Surry Units 1 & 2
Project stage: Other
ML20138K9301985-10-0808 October 1985
Forwards Safety Evaluation Accepting 850617 Response to Salem ATWS Items 4.2.1 & 4.2.2 Re 18-month Surveillance Frequency for Reactor Trip Breakers
Project stage: Approval
ML20138K9041985-10-0909 October 1985
Forwards Supplemental Safety Evaluation Accepting 850114 & 0510 Responses to Generic Ltr 83-28,Item 4.3 on Proposed Design Mods for Automatic Shunt Trip.Tech Spec Changes Should Be Submitted
Project stage: Approval
ML20138S0531985-10-31031 October 1985
Forwards SER Re Util 831104 Response to Generic Ltr 83-28 Concerning Items 3.1.3 & 3.2.3, Post-Maint Testing. Response Acceptable
Project stage: Approval
ML20137S0291985-11-21021 November 1985
Advises That Response to Generic Ltr 83-28,ATWS Action Items 3.1.1,3.1.2,3.2.1,3.2.2,4.1 & 4.5.1 Acceptable.Ser Encl
Project stage: Other
ML20138A2941986-03-0404 March 1986
Advises That Shunt Trip Attachment & Automatic Shunt Trip Panel Seismically Qualified Per 840716 Commitment Re Generic Ltr 83-28,Item 4.3 & Listed Responses to 841108 Safety Evaluation.Qualification Based on Westinghouse Tests
Project stage: Other
ML20202C5541986-04-0303 April 1986
Forwards Sser Accepting Util 860304 Response to Generic Ltr 83-28,Item 4.3, Seismic Qualification of Shunt Trip Components
Project stage: Other
ML20211Q1081986-12-10010 December 1986
Informs That Contact Pressure Will Be Removed from Reactor Trip Breaker Trending Program.Westinghouse Indicated That Test for Contact Pressure Should Be Go no-go Test Instead of Obtaining Actual Reading.List of Trended Parameters Encl
Project stage: Other
ML20207P6441987-01-12012 January 1987
Forwards SER Accepting Util 831104 Info Needed for Compliance W/Generic Ltr 83-28,Item 2.1,Part 2 Re Vendor Interface Program for Reactor Trip Sys (RTS) Components & Item 4.5.2 Concerning RTS Online Reliability Testing
Project stage: Approval
1985-03-20
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'Af Telephone (412) 393-6000 Nuclear Division P.O. Box 4 Stilppingport, PA 15077-0004 September 14, 1983 Director of ?!uclear Reactor Regulation U. S. Nuclear Regulatory Commission Attn:
D. G. Eisenhut, Director Division of Licensing Washington, DC 20555
Reference:
Beaver Valley Power Station, Unit No.1 Docket No. 50-334, License No. DPR-66 Deviations to Generic Letter 83-28 dated July 8,1983 Gentlemen:
The actions required by the above referenced letter are currently being reviewed to identify where improvements are needed.
No schedule can be given at this time for a response to action items 2.2.2 Vendor Interface, 4.2.3 Life Testing of Reactor Trip Breakers, 4.2.4 Periodic Replacement of Reactor Trip Breakers, and 4.3 Automatic Reactor Trip System Actuation.
DLC is a participating member of INP0's Nuclear Utility Task Action Committee (NUTAC) on Generic Letter 83-28, Item 2.2.2.
The NUTAC was fomed for the specific purpose of defining an appropriate vendor inter-face program. Upon completion of NUTAC efforts, and internal review for applicability, a response to Item F...2 will be provided.
The Westinghouse Owner's Group has funded a program to determine the service life of shunt and undervoltage reactor trip attachments. The results of this program will be reviewed and a response to action items 4.2.3 and 4.2.4 will be provided following internal review after the issuance of their report.
In regard to action item 4.3 Reactor Trip System Reliability, 1.'estinghouse has prepared a generic design for incorporation of the shunt trip feature into the automatic reactor protection function. However, plans for implementation of, and deviations from tha generic design will not te forthcoming until the final ATWS ruling is received. This must be done to ensure that the design modifications proposed, address all regulatory concerns of this system.
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Beaver Valley Power Station, Unit No.1
' Docket N3. 50-334, License No.-DPR-66 Deviations to Generic Letter 83-28 dated July 8,1983 Page 2 Item 3.2.2 requires a check of vendor and engineering recommendations to ensure that the appropriate test guidance is included in the applicatile maintenance procedures. We are reviewing a portion of the safety related pumps, breakers, motors and valve technical nanuals to comply with this part.
We expect that we will demonstrate that our existing and proposed programs are equivalent in the other areas described in the Generic Letter.
Very truly yours,
. J. Carey Vice President, Nuclear cc: Nr. W. M. Troskoski, Resident Inspector U. S. fluclear Regulatory Commission Beaver Valley Power Station Shippingport, PA 15077 U. S. Nuclear Regulatory Commission c/o Document Managment Branch Washington, DC 20555
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