Letter Sequence Other |
|---|
TAC:44491, (Approved, Closed) TAC:44830, (Approved, Closed) TAC:44901, (Open) TAC:45114, (Open) TAC:45275, (Approved, Closed) TAC:45323, (Approved, Closed) TAC:45609, (Open) TAC:46355, () TAC:46426, (Approved, Closed) |
Initiation
- Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request
- Acceptance...
Results
Other: B12630, Proposed Tech Specs,Adding New Surveillance Requirement Re Control Room Habitability, ML19241B419, ML19241B427, ML19254D272, ML19263C802, ML19310A426, ML19321A695, ML19330B754, ML19339A509, ML19339A598, ML19343A382, ML19345E132, ML19347C739, ML20049H553, ML20050C507, ML20052A948, ML20053D721, ML20066D300, ML20071G129
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MONTHYEARML19256A1121978-10-27027 October 1978 Application for Amend to License DPR-35,changing Tech Specs to Accomodate New Steamline Break Protection Sys Scheduled for Installation in Spring of 1979.Fee Paid Project stage: Request ML20071G1291978-12-14014 December 1978 Forwards Addl Info Re Lic Amend Appl Covering Eval of Low Feedwater Flow Reactor Trip Setpoint Change Project stage: Other ML19263C8021979-02-0505 February 1979 Lists Individual Fee Classes for 781027 Application for Tech Spec Changes.Requests Submittal of Addl $13,500 Fee. Any Overcharges Will Be Refunded Project stage: Other ML19261B1761979-02-0808 February 1979 Responds to NRC Re Containment Purging During Normal Operation.Reviewed Design of Safety Actuation Signals to Ensure That Overriding of One Signal Does Not Inhibit Other Signals.Maintains Subatmospheric Conditions Project stage: Other ML19276E2751979-03-0707 March 1979 Forwards Addl Info Requested at 790223 Meeting Re Proposed Steam Break Protection Sys Project stage: Meeting ML19270F9971979-03-12012 March 1979 Summary of 790223 Meeting W/Westinghouse & Duquesne Light Re Steamline Break Protection Sys.W/Supporting Documentation Project stage: Meeting ML19241B4271979-07-13013 July 1979 Tech Spec Change Requests 42 & 47 Re Mod to ECCS Project stage: Other ML19241B4191979-07-13013 July 1979 Forwards Tech Spec Change Requests 42 & 47 Re Amend to App a of DPR-72.Change Is Required Prior to Startup After Completion of Planned ECCS Mod,Which Could Be Accomplished as Early as 790722 Project stage: Other ML19274G1021979-07-31031 July 1979 Forwards Request for Addl Info to Util Proposed Steam Break Protection Sys & N-1 Loop Operation Project stage: RAI ML19208B5691979-08-21021 August 1979 Forwards Safety Evaluation Re Electrical,Instrumentation & Control Aspects of Deletion of Reactor Trip on Turbine Trip Below 50% Power Project stage: Approval ML19259D6001979-10-18018 October 1979 Summary of 791009 Meeting W/Util Re Proposed Steamline Break Protection Project stage: Meeting ML19254D2721979-10-18018 October 1979 Forwards Addl Info Re Proposed Steam Break Protection Sys Per Tech Spec Change Request 35.Proposed Tech Spec Re Maint of Required Shutdown Margin & Revised Reactivity Control Sys Tech Specs Encl Project stage: Other ML19260B5841979-10-29029 October 1979 Discusses NRC Concern Re Containment Purging & Venting During Normal Operation.Includes Licensee Override of Safety Actuation Isolation Signals to Containment Isolation Valves & Valve Ability to Shut W/O Degrading Containment Project stage: Other ML19210C6291979-11-0202 November 1979 Requests Addl Info Re Containment Purge Sys Project stage: Other ML19260B5231979-12-0505 December 1979 Forwards Proposed Tech Spec 3/4.6.5,deleting Option to Utilize Steam Jet Air Ejector During Mode 4.Class II Amend Fee Encl Project stage: Other ML19309A8581980-03-28028 March 1980 Forwards Documents Re Investigation Into Extended Outages at Facility.Documents Include Trial Staff Statement Before PA Public Util Commission,Consumer Advocate Statement & CN Dunn Testimony Project stage: Request ML19309H2151980-04-15015 April 1980 Notification of 800422 Meeting W/Util in Bethesda,Md to Discuss & Review Decay Heat Exchanger Sys Integrity & Operation Project stage: Request IR 05000334/19800081980-05-0707 May 1980 IE Insp Rept 50-334/80-08 on 800324-28.No Noncompliance Noted.Major Areas Inspected:Qa Program Review,Qa/Qc Administrative Design Change & Mod Control,Measurement & Test & Previous Insp Items Project stage: Request IR 05000302/19800181980-05-0707 May 1980 IE Insp Rept 50-302/80-18 on 800331-0411.No Noncompliance Noted.Major Areas Inspected:Previous Insp Findings,Fuel Receipt,Refueling Activities,Maint Activities & IE Bulletin 79-01B Project stage: Request ML19305E7811980-05-16016 May 1980 Submits Addl Info & Schedules for Uncompleted Items Re Bypass & Reset of Engineered Safety Features Per 800404 Request Project stage: Other ML19310A4261980-06-0909 June 1980 Responds to & Schedule for Implementation of TMI-2-related Requirements.Discusses Shift Manning,Scope & Criteria for Licensing Exam,Procedures for Feedback of Operating Experience & Control Room Habitability Project stage: Other IR 05000412/19800061980-07-0303 July 1980 IE Insp Rept 50-412/80-06 on 800602-06.Noncompliance Noted: Failure to Return Used or Damaged Welding Electrodes to Issue Station & Failure to Provide Adequate Protection for Equipment in Temporary Storage Project stage: Request ML19321A6951980-07-21021 July 1980 Forwards Schedule for Commitments to TMI-2 Related Requirements,Per NRC 800507 Request.Affidavit Encl Project stage: Other ML19330B7541980-07-31031 July 1980 Informs of Intentions to Withdraw Commitment to Adopt Guidance of IE Circular 80-02,due to Wording of IE Circular 80-02 & Application of Circular Re Work Situations Project stage: Other ML19343A3821980-09-15015 September 1980 Tech Specs 3/4 3-38,requesting Changes Re Model License Conditions,Emergency Feedwater Initiation & Flow Monitoring, Diverse Containment Isolation & Emergency Power Supply to Pressurizer Heaters Project stage: Other ML19343A3791980-09-15015 September 1980 Application to Amend App a to Ol,Changing Aspects of NUREG-0578 Including Model License Conditions & Emergency Feedwater Initiation & Flow Monitoring.Affidavit & Certificate of Svc Encl Project stage: Request ML19338D6391980-09-17017 September 1980 Confirms 800919 Telcon Re Clarification of Util Position W/Respect to NRC Questions Concerning 800628 Submittal on TMI Short-Term Lessons Learned Requirements Project stage: Other ML19339A5091980-10-24024 October 1980 Withdraws Tech Specs Change Request 47,implementing Items Contained in NRC 790516 Confirmatory Order.Util Considers Specs Requested in Eisenhut & Provided in Change Request 64,Revision 1,as Representing Latest Position Project stage: Other ML19339A5981980-10-29029 October 1980 Advises of Status Re Shift Staffing,In Response to Interim Criteria in NRC Project stage: Other ML19339B2141980-10-31031 October 1980 Advises That Util Has Not Made Plans to Conduct Any Qualification Tests During Next 2 Yrs.Nrc Will Be Notified in Event of Decision to Conduct Tests Project stage: Request ML19345E1321980-12-17017 December 1980 Responds to Re Confirmation of Commitment to Meet Implementation Dates Contained in NUREG-0737.Requests Extension for Proposed Mods Re Auto Trip of Reactor Coolant Pumps Project stage: Other ML19340D7831980-12-23023 December 1980 Requests Summary Rept,Westinghouse Reactor Vessel Level Instrumentation Sys for Monitoring Inadequate Core Cooling, (7300 Sys), Dtd Dec 1980 Be Withheld (Ref 10CFR2.790) Per Previously Submitted Application AW-77-18 Approved 771028 Project stage: Other IR 05000334/19800291980-12-31031 December 1980 IE Insp Rept 50-334/80-29 on 801103-07.Noncompliance Noted: Failure to Control Vital Area,To Follow Access Control Procedures & to Follow Search Procedures.Details Withheld (Ref 10CFR2.790) Project stage: Request ML19347C7391980-12-31031 December 1980 Forwards Nonproprietary & Proprietary Versions of Response to NUREG-0737. Proprietary Version Available in Central Files Only Project stage: Other ML19341C6391981-02-23023 February 1981 Informs That Licensee Agreed to Actions Re Resetting of Main Feedwater & Bypass Valves After Feedwater Isolation Signal. Control Circuitry Revised to Prevent Valves from Returning to Pretrip Position on Resetting ESF Signal Project stage: Other ML20003G1191981-04-15015 April 1981 Forwards Evaluation Rept of Inadequate Core Cooling Instrument Sys Conformance to NUREG-0737 Item II.F.2,per .Evaluation of Core Exit Thermocouples to Be Submitted by 810701 Project stage: Other ML20009E3001981-07-15015 July 1981 Forwards Safety Evaluation Accepting Containment Purge & Venting Sys Design & Operating Practices.Proposal for Tech Spec Change Incorporating Test Requirements for Butterfly Isolation Valves Requested within 45 Days Project stage: Approval ML20010A3821981-08-0606 August 1981 Submits Justification of Licensing/Engineering Dept Determination That Mod of Main Feedwater Valve Circuits Is Not Necessary.Diagrams Encl Project stage: Other ML20010F0021981-09-0202 September 1981 Forwards Responses to NRC Requesting Addl Info on NUREG-0737,Item II.F.2.3 Re Reactor Vessel Level Instrumentation Sys for Monitoring Inadequate Core Cooling. Response Withheld (Ref 10CFR2.790) Project stage: Other ML20031C0401981-09-30030 September 1981 Forwards Supplemental Response to NRC Re NUREG-0737,Item II.F.2.3 on Reactor Vessel Instrumentation Sys.Application for Withholding & Affidavit Encl Project stage: Supplement ML20032D5701981-11-0909 November 1981 Responds to NRC Re NUREG-0737 Items II.F.1.1 & II.F.1.2,re Installation of High Range Noble Gas Effluent Monitors & Effluent Monitoring of Radioiodines.Requests Permission to Defer Installation Until 820101 Outage Project stage: Other ML20039D5731981-12-30030 December 1981 Provides Info Re NUREG-0737 Items Scheduled for Implementation on 820101.Mods Requiring Station Shutdown Will Be Completed During Second Refueling Outage Scheduled 821225 Project stage: Other ML20049H5531982-02-24024 February 1982 Provides Info on Item II.K.3.5 Re Automatic Trip of Reactor Coolant Pumps During Loca,Per NUREG-0737 Requirements. Status Submitted in Has Not Changed Project stage: Other ML20042B9261982-03-16016 March 1982 Forwards Request for Addl Info for Review of TMI Action Items 2.A.2.1,upgrading Senior Reactor Operator & Reactor Operator Training & II.B.4,training for Mitigating Core Damage Project stage: RAI ML20050C5071982-03-24024 March 1982 Ack Commitment in to Meet Reporting Requirement Provided in NRC Re Relief & Safety Valve Failures.Info Missing from 1981 Annual Rept.Requests That Rept Be Updated W/Errata Sheet to Correct Discrepancy Project stage: Other ML20054D6381982-04-16016 April 1982 Responds to 820317 Generic Ltr 82-05, Post-TMI Requirements Re Scheduling of Specific NUREG-0737 Items Project stage: Other ML20052A9481982-04-23023 April 1982 Requests Addl Info Re TMI Action Plan Item II.K.3.3, Reporting Relief Valve & Safety Valve Failures.Response within 30 Days Requested Project stage: Other ML20052E2371982-04-28028 April 1982 Submits Addl Info Re TMI Action Plan Items II.F.2 & II.B.2. Installation of Reactor Vessel Level Instrumentation Will Be Completed During Third Refueling Outage Project stage: Other ML20052G1951982-05-10010 May 1982 Informs of No Relief or Safety Valve Failures or Challenges During Apr-Dec 1980 in Response to 820423 Request for Documentation & Commitment to NUREG-0737,Item II.K.3.3, Reporting Relief & Safety Valve Failures & Challenges Project stage: Request ML20053D7211982-05-27027 May 1982 Forwards Westinghouse Transmitting SAR for Deletion of Reactor Trip Following Turbine Trip Below 50% Power.Review Requested Against NUREG-0737,Item II.K.3.10 Concerns Project stage: Other 1980-05-07
[Table View] |
Forwards Nonproprietary & Proprietary Versions of Response to NUREG-0737. Proprietary Version Available in Central Files Only| ML19347C739 |
| Person / Time |
|---|
| Site: |
Beaver Valley |
|---|
| Issue date: |
12/31/1980 |
|---|
| From: |
Dunn C DUQUESNE LIGHT CO. |
|---|
| To: |
Eisenhut D Office of Nuclear Reactor Regulation |
|---|
| Shared Package |
|---|
| ML19262F356 |
List: |
|---|
| References |
|---|
| RTR-NUREG-0737, RTR-NUREG-737 44212, TAC-44491, TAC-44830, TAC-44901, TAC-45114, TAC-45275, TAC-45323, TAC-45609, TAC-46355, TAC-46426, NUDOCS 8101050321 |
| Download: ML19347C739 (2) |
|
Text
.
'Af 44m 4ss.6 coo y,5g^p+
December 31, 1980 m
United States Nuclear Regulatory Cocsission Atta:
Mr. Darrell G. Eisenhut, Director Division of Licensing Washington, DC 20555
Reference:
3eaver Valley Power Station - Unit No. 1 Docket No. 50-334; License No. DPR-66 Response to NUREG-0737
Dear Mr. Eisenhut:
Forwarded herewith are responses to various items in NUREG-0737 applicable to our facility required to be submitted by January 1,1981.
We have endeavored to submit complete responses to each of the required items but we have requested additional time to respond to one require-ment in Item II.F.2 requiring evaluation of instruments for compliance with a specified list of codes, standards and guides, Item II.E.3.1 and Item II.E.1.2 which required a comparison similar to the above plus a complete design description. This additional information will be compiled and submitted by the dates specified.
This submittal contains information considered by Westinghouse Electric Corporation, the owner of the informatioa, to be proprietarv to it.
An affidavit, signed by Westinghouse, is furnished herewith and this affidavit sets forth the basis on which the information may be withheld from public disclosure by the Commission and specifically addresses the considerations listed in paragraph (b)(4) of 10 CFR 2.790.
Accordingly, it is requested that information which is proprietary to Westinghouse be withheld from public disclosure in accordance with 10 CFR 1.790.
Correspondence relating to proprietary aspects of this application for withholding or the supporting Westinghouse affidavit should be addressed to R. A. Wiesmann, Manager, Regulatory and Legislative Af fairs, Westinghouse Electric Corporation, P.O. Box 355, Pittsburgh, Pennsylvania 15230.
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Seaver Valley Power Station - Unit No. 1 Docket No. 50-334; License No. DPR-66 Response to NUREG-0737 Page 2 A non-proprietary copy of this submittal has been included for your use.
If you have any questions concerning this submittal, please contact my office.
Very truly yours,
,Y*
- n ~,x g C. N. Dunn Vice President, Operations cc:
Mr. D. A. Beckman U.S Nuclear Regulatory Commission Beaver Valley Power Station Shippingport, PA 15077 U.S. Nuclear Regulatory Co= mission (non-proprietary only) c/o Document Management Branch Washington, DC 20555 r
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