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MONTHYEARML20004E4991981-06-0404 June 1981
Provides Assessment of Existing & Planned Procedures & Training for Station Blackout Events,In Response to Generic Ltr 81-04.Westinghouse Owners Group Has Program for Emergency Operating Guidelines Per NUREG-0737,Item I.C.1
Project stage: Other
ML20073M2231983-04-15015 April 1983
Forwards Response to 821217 Generic Ltr 82-33 Re Schedule for Addressing Each Element of Emergency Response Capability.Schedule Developed Following Guidelines Contained in Suppl 1 to NUREG-0737
Project stage: Other
ML20023B3571983-04-15015 April 1983
Forwards Response to Generic Ltr 82-33, Suppl 1 to NUREG-0737,Requirements for Emergency Response Capability. Safety Parameter Display Sys Will Operate from Emergency Response Facilities Computer Sys.W/One Oversize Drawing
Project stage: Request
ML20154J3951983-05-0303 May 1983
Discusses Negotiations Re Util 830415 Response to Generic Ltr 82-33.Licensee Proposed Implementation Dates,Summarized in Encl,Acceptable.Record of 820806 Telcon Encl
Project stage: Other
ML20024D1091983-07-25025 July 1983
Clarifies Scheduled Completion of Tasks Identified in Suppl 1 to NUREG-0737,per 830502 Meeting
Project stage: Meeting
ML20078D5831983-09-27027 September 1983
Forwards Program Plan for Implementation of Control Room Design Review of Beaver Valley Power Station, Following Guidelines in Suppl 1 to NUREG-0737,per Generic Ltr 82-33
Project stage: Other
ML20087L4571984-03-14014 March 1984
Provides Followup to 840228 Telcon Re Suppl 1 to NUREG-0737, Development of Emergency Operating Procedures, from Generic Westinghouse Emergency Response Guidelines. Development Will Continue as Described
Project stage: Other
ML20084H5191984-04-30030 April 1984
Provides Approx Starting Dates & Summaries of Each Review Phase of Control Room Design Review,In Response to NRC .Summary Rept Expected to Be Submitted in Nov 1985
Project stage: Other
ML20091H9491984-05-30030 May 1984
Requests Rev to Procedures Generation Package Submittal Date to 840701 Due to Need for Addl Review of Revised Package Incorporating Addl Concerns Re Emergency Operating Procedure Task Analysis,Per Suppl 1 to NUREG-0737
Project stage: Other
ML20092N5791984-06-28028 June 1984
Forwards Procedures Generation Package Re Methods for Developing & Implementing function-oriented Emergency Operating Procedures,Per Generic Ltr 82-33
Project stage: Other
ML20198D2521986-05-0909 May 1986
Forwards Responses to Items 1 Through 3 from Generic Ltr 86-04, Policy Statement on Engineering Expertise on Shift. Util Currently Utilizes Dedicated Shift Technical Advisor (STA) at Unit 1 & Plans to Use STA at Unit 2
Project stage: Request
ML20206H4931986-06-19019 June 1986
Safety Evaluation on Generic Ltr 83-28,Item 4.2.3 & 4.2.4, Preventive Maint Program for Reactor Trip Breakers/Life Testing. Licensee Position Unacceptable
Project stage: Request
ML20206G2351986-09-30030 September 1986
Rev 4 to ASME Code Baseline Document
Project stage: Request
ML20214C9841986-11-0303 November 1986
Provides Required Info & Describes Compensatory Measures Presently in Place to Ensure Easy Access Between Control Room & Emergency Response Facility
Project stage: Other
ML20214J6501987-05-12012 May 1987
Responds to NRC Re Interim Review Results on Abnormal Transient Guidelines Procedures Generation Package for Facility.Response Refs Util 870408 Submittal Re Unit 2 SER Confirmatory Item 47 Procedures Generation Package
Project stage: Other
ML16223A6531988-01-0606 January 1988
Confirms Planned Insp of Emergency Operating Procedures (Eops) on 880201,per 880104 Telcon.Requests Simulator Be Available for Evaluation of EOPs Effectiveness & Controlled Copy of EOPs Be Provided to NRC Prior to Insp
Project stage: Other
ML20235T2491989-02-21021 February 1989
Advises That Action Plan Schedule for Corrective Action Re Deviations Identified in Insp Rept 50-334/88-02 Revised. Tasks for Emergency Operating Procedures Will Be Completed by May 1989
Project stage: Other
1984-05-30
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snippingpon. PA 15077 @ 04 Director of Nuclear Reactor Regulation Unite.d States Nuclear Regulatory Commission Attn: Mr. Darrell 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 Supplement 1 to NUREG-0737 Gentlemen:
This submittal is being provided as clarification for the scheduled completion of the tasks identified in Supplement 1 to NUREG-0737.
Our submittal of April 15, 1983 provided the information requested in Generic Letter 82-33.
On May 2,1983, a meeting was held at this site as a follow-up to that submittal to negotiate the schedule in accordance with the direction provided in the Generic Letter. At this meeting and in sub-sequent telephone conversations, senral dates for completion of certain tasks and for the submittal of additional infonnation were established.
The information below represents the most recent conversation between our NRC I'roject Manager and members of my staff with regard to the SPDS, CRDR, Regulatory Guide 1.97 and E0Ps.
SPDS 1
Full implementation of the SPDS will be accomplished follow-ing the fifth refueling outage tentatively scheduled for July of 1986.
CRDR 1.
The Program Plan will be submitted in September 1983.
2.
The Summary Report will be submitted in November 1985.
R(g. Guide 1.97 1.
This work activity and development of the final report will be accomplished concurrent with the CRDR.
The final report will be submitted in November 1985.
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l 8308030170 830725
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PDR ADOCK 05000334 F
PDR
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B:: aver Valley Power Station, Unit flo.1 Docket tio. 50-334, License No. DPR-66 Supplement 1 to NUREG-0737 Page 2 2.
The schedule for full implementation of R.G.1.97 will be provided in the final report. This is consistent with the request of Supplement 1 to NUREG-0737 of pro-viding a schedule for plant modifications, if any, in the final report.
.EOPs 1.
Full implementation of the E0Ps will be accomplished following the fifth refueling outage tentatively scheduled for July of 1986.
Should you have any questions regarding this submittal, please contact myself or members of my staff.
Very trul you rs,
3
. Carey Vice President, Nuclear cc: Dr. Thomas E. Murley, Regional Administrator U. S. Nuclear Regulatory Commission Office of Inspection & Enforcement Region I 631 Park Avenue King of Prussia, PA 19406 Mr. Steven A. Varga, Chief U. S. Nuclear Regulatory Commission Operating Reactors Branch No.1 Division of Licensing Washington, DC 20555 l
Mr. W. M. Troskoski, Resident Inspector U. S. Nuclear Regulatory Commission Beaver Valley Power Station Shippingport, PA 15077 l
U. S. Nuclear Regulatory Commission c/o Document Management Branch Washington, DC 20555