Letter Sequence RAI |
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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 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 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 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 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 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 ML19338G0941980-09-0202 September 1980 Forwards Revised Operator Training Program 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 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 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 ML19347C7391980-12-31031 December 1980 Forwards Nonproprietary & Proprietary Versions of Response to NUREG-0737. Proprietary Version Available in Central Files Only 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 ML20071K0321982-04-21021 April 1982 Forwards Addl Info Requested 820316 Re TMI Action Items I.A.2.1, Upgraded Senior Reactor Operator & Reactor Operator Training & II.B.4, Training for Mitigating Core Damage 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 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 ML20199F1421982-10-28028 October 1982 Forwards SER Accepting Science Applications,Inc Technical Evaluation Rept on Listed TMI Action Plan Items Concerning Upgrading of Reactor Operator/Senior Reactor Operator Training & Training for Mitigating Core Damage Project stage: Approval ML20066D3001982-11-0303 November 1982 Informs That Since Unit 1 Anticipatory Trip Mod Is Enveloped by Unit 2 Analysis Basis,Analysis May Be Applied to Unit 1 Per Requirements of TMI Item II.K.3.10, Proposed Anticipatory Trip Mod Project stage: Other ML20084C5841984-04-24024 April 1984 Discusses 830808 Program Plan Rept for Detailed Control Room Design Review Containing Section Entitled, Mgt & Staffing, Outlining Min Qualification for Team Members.Resumes Encl Project stage: Request A06182, Responds to 861029 Request for util-proposed Tech Spec Changes Re Reporting of Safety Valve & Relief Valve Failure & Challenges,Control Room Habitability & Secondary Water Chemistry.Schedule for Submittal of Amend Requests Encl1986-12-10010 December 1986 Responds to 861029 Request for util-proposed Tech Spec Changes Re Reporting of Safety Valve & Relief Valve Failure & Challenges,Control Room Habitability & Secondary Water Chemistry.Schedule for Submittal of Amend Requests Encl Project stage: Request ML20236N0591987-08-0303 August 1987 Application for Amend to License DPR-65,adding New Surveillance Requirement Re Control Room Habitability.Fee Paid Project stage: Request B12630, Proposed Tech Specs,Adding New Surveillance Requirement Re Control Room Habitability1987-08-0303 August 1987 Proposed Tech Specs,Adding New Surveillance Requirement Re Control Room Habitability Project stage: Other 1980-06-09
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DISTRIBUTION Docket NRC PDR L PDR MAR 161982 NSIC Docket No. 50-334 ORB #1 Rdg y
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Hr. J. J. Carey, Vice President ilECDVF:D
'l ACRS-10 Duquesne Light Company 2
DChaney Nuclear Division MAR l ! !3,gg gi. L__
DWigginton M nF m ry%,_, fN$
CParrish Post Office Box 4 9
"3W Went AE00 Shippingport, Pennsylvania 15077
Dear Mr. Carey:
SSa ah
SUBJECT:
UPGRADED ST:0 AND R0 TRAINIllG AND TRAINING FOR ff!TIGATING CORE DAMAGE - PEQUEST FOR ADDITIONAL INFORMATION In our review of NUREG-0737 Item Nos. I.A.2.1 and II.B.4 for Beaver Valley Power Station, Unit No.1, we have identified additional information which we will need in order to complete our review. Science Applications, Inc.
ander contract to the NRC has developed the attached request for additional information. Ife request that you respond within 30 days of receipt of this letter.
Please send a copy of your sutnittal directly to Dr. R. T. Liner, Science Applications, Inc.,1710 Goodridge Drive, Mc!.ean, Virginia 22102.
Sincerely.
Original signed by:
S. A. Varga Steven A. Varga, Chief Operating Reactors Branch fl Division of Licensing
Enclosure:
As stated cc w/ enclosure:
See next page 8203260288 820316 DR ADOCK 05000334 PDR O
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4 Mr. J. J. Carey Duquesne Light Company cc: Mr. H. P. Williams Mr. J. D. Sieber, Manager Station Superintendent Nuclear Safety and Licensing Duquesne Light Company Duquesne Light, Company Beaver Valley Power Station Nuclear Division Post Office Box 4 Post Office Box 4 Shippingport, Pennsylvania 15077 Shippingport, Pennsylvania 15077 Mr. T. D. Jones, Manager Resident Inspector Nuclear Operatinns U. S. Nuclear Regulatory Commission Duquesne Light Company Post Office Box 298 Post Office Box 4 Shippingport, Pennsylvania 15077 Shippingport, Pennsylvania 15077 Ronald C. Haynes B. F. Jones Memorial Library Regional Administrator - Region I 663 Franklin Avenue U. S. Nuclear Regulatory Commission Aliquippa, Pennsylvania 15001 631 Park Avenue King of Prussia, Pennsylvania 19406 Gerald Charnoff, Esquire Jay E. Silberg, Esquire Shaw, Pittman, Potts and Trowbridge 1800 M Street, N.W.
Washington, D.C.
20036 Karin Carter, Esquire Special Assistant Attorney General Bureau of Administrative Enforcement 5th Floor, Executive House Harrisburg, Pennsylvania 17120 Marvin Fein Utility Counsel City of Pittsburgh 313 City-County Building Pittsburgh, Pennsylvania 15219 Mr. John A. Levin Public Utility Commission P.O. Box 3265 Harrisburg, Pennsylvania 17120 Irwin A. Popowsky, Esquire Office of Consumer Advocate 1425 Strawberry Square Harrisburg, Pennsylvania 17120 Charles A. Thomas, Esquire Thomas and Thomas 212 Locust Street Box 999 Harrisburg, Pennsylvania 17108 i
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Subject:
Improvements in Operator Training and Requalificati*n Programs Plant:
Beaver Valley Date:
23 February 1982 LICENSING ACTION REQUEST FOR ADDITIONAL INFORMATION The U.S.
Nuclear Regul atory Commission and its technical assistance contractor, Science Applications, Inc.
(SAI), are performing a review to ascertain the acceptability of your response to certain requirements contained in post-TMI Action Items set forth in NUREG-0660 and NUREG-0737:
I.A.2.1 Immediate Upgrading of Reactor Operator and Senior Reactor Operator Training and Qualifications II.B.4 Training for Mitigating Core Damage Specifically, this. review addresses the following items from Enclosure 1 of Harold Denton's letter of March 28, 1980, contained in NUREG-0737.
Item A.2.c which addresses operator training requirements, item A.2.e which addresses instructor requalification, and Section C which addresses operator requalification.
Some of these items are further elaborated in Enclosures 2, 3, and 4 of the Denton letter and in post-TMI Action Item II.B.4 (also in NUREG-0737).
Our review is presently based on your submittal of September 2, 1980, which incudes the following:
1.
Letter dated 2 September,1980, J. A. Werling to Harold R. Denton.
2.
Duquesne Light Company, Beaver Valley Power Station Training Manual Section 2.0, Operations Training, Issue 2, Rev.1, (3 subsections, no date).
We have assumed in our review that these submittals reflect your current training program. We need answers to the following questions before we can complete our evaluation:
1.
The training programs for licensed operating personnel consists of two options.
Under what conditiont has Option I been exercised? Under what conditions has Option II been exercised? Are both options in effect now?
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..i Beaver Vc11er TAC No. 44141 page 2 2.
The training progrants for reactor operators (Option I and Option II) and the requalification program for reactor operators (Section 2.2) include lectures which appear to have the potential for covering the subjects of heat transfer, fluid flow and thermodynamics as called out in enclosure 1 of Denton's March 28, 1980, l etter. Do these lectures in f act cover these materials and is the coverage to the level spelled out in enclosure 2 of the Denton letter?
3.
The training program for licensed operating personnel Option I appears to contain no training in the area of accident mitigation and training in dealing with transients as called out in enclosure 1 of Denton's letter. Does your training program Option I cover these areas and is the coverage to the level spelled out in enclosure 3 of Denton's letter?
4.
The training program for licensed operating personnel Option II appears to have some potential for covering the training in the area of accident mitigation and training in dealing with transients as called out in enclosure 1 of Denton's letter.
Does your training program Option II cover these areas and is the coverage to the level spelled out in enclosure 3 of Denton's letter?
5.
Do the training programs for Options I and II each involve 80 contact hours under the subjects of heat transf er, fluid
- flow, thermodynamics and accident mitigation? Are there similarly 80 contact hours of heat transf er, fluid
- flow, thermodynamics and accident mitigation in the requalification program (Section 2.2)?
( A contact hour of instruction is a one-hour period in which the course instructor is present or available for instructing or assisting students; lectures, seminars, discussions, problen-solving sessions, and examinations are considered contact periods under this definition.)
6.
T9e reactor operator requalification program, Section 2.2.4.3, identi fies nine reactor manipul ations (Items (a) to (h) and (j)) along with ambiguous item (i), plant and reactor operation, that involve emergency or transient procedures where reactivity is changing.
Do these ten items cover all the twenty-seven manipulations identified in enclosure 4 of the Denton letter?
7.
Are your instructors enrolled in appropriate requalification programs to assure they are cognizant of current operating history, problens, and changes to procedures and administrative limitations?
[
1 For item II.B.4 provide an outline of the training program for mitigating core damage, including the number of training hours involved.
Your outline can include any training program which relates to the training for mitigating core damage.
Follow the guidelines given in the enclosure 3 of H. R. Denton's letter dated March 28, 1980 and INPO Guidelines for Training to Recognize and Mitigate the Consecuences of Core Damage (Document Number STG-01, Rev. l. January 15,1981).
NRC requires minimum of 80 contact hours of training for mitigating core damage.
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