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| {{#Wiki_filter:ACCEI.ERATED DOCUMENT DISTRIBUTION SYSTEM REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)ACCESSION NBRF'9303300040 DOC.DATE: 93/03/22 NOTARIZED: | | {{#Wiki_filter:ACCEI.ERATED DOCUMENT DISTRIBUTION SYSTEM REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS) |
| NO DOCKET CIL:50-397 WPPSS Nuclear Project, Unit 2, Washington Public Powe 05000397 TH.NAME AUTHOR AFFILIATION ,ARRISH,J.V. | | ACCESSION NBRF'9303300040 DOC.DATE: 93/03/22 NOTARIZED: NO DOCKET CIL:50-397 WPPSS Nuclear Project, Unit 2, Washington Public Powe 05000397 TH.NAME AUTHOR AFFILIATION |
| Washington Public Power Supply System RECIP.NAME RECIPIENT AFFILIATION Document Control Branch (Document Control Desk) | | ,ARRISH,J.V. Washington Public Power Supply System RECIP.NAME RECIPIENT AFFILIATION Document Control Branch (Document Control Desk) |
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| ==SUBJECT:== | | ==SUBJECT:== |
| Responds to NRC 921203 ltr re violations noted in insp of facility training rept 50-397/92-27.C/As:requalification instructors,mgt 6 Operations Liaison have participated in training&evaluation of initial license candidates. | | Responds to NRC 921203 ltr re violations noted in insp of facility training rept 50-397/92-27.C/As:requalification instructors,mgt 6 Operations Liaison have participated in training & evaluation of initial license candidates. |
| DISTRIBUTION CODE: IE01D COPIES RECEIVED:LTR ENCL SIZE: TITLE: General (50 Dkt)-Insp Rept/Notice of Violation Response NOTES: RECIPIENT ID CODE/NAME PD5 PD INTERNAL: ACRS AEOD/DSP/TPAB DEDRO NRR/DRCH/HHFBPT NRR/DRSS/PEPB NRR/PMAS/ILPB2 OE C FILE 02 ILE 01 EXTERNAL EGGG/BRYCE i J~H~NSIC;COPIES LTTR ENCL 1 1 2 2 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 RECIPIENT ID CODE/NAME CLIFFORD,J AEOD/DEIB AEOD/TTC NRR/DORS/OEAB NRR/DRIL/RPEB NRR/PMAS/ILPB1 NUDOCS-ABSTRACT OGC/HDS1 RES MORISSEAUiD NRC PDR COPIES LTTR ENCL 1 1 1 1 1 1 1 1 1 1 1 1'1 1 1 1.1 1 1 NOTE TO ALL"RIDS" RECIPIENTS: | | DISTRIBUTION CODE: IE01D COPIES RECEIVED:LTR ENCL SIZE: |
| PLEASE HELP US TO REDUCE WASTE!CONTACT THE DOCUMENT CONTROL DESK, ROOM PI-37 (EXT.504-2065)TO ELIMINATE YOUR NAME FROM DISTRIBUTION LISTS FOR DOCUMENTS YOU DON'T NEEDI TOTAL NUMBER OF COPIES REQUIRED: LTTR 23 ENCL 23 WASHINGTON PUBLIC POWER SUPPLY SYSTEM P.O.Box 968~3000 George Washington Way~Rfchland, Wasbfngton 993524968~(509)372-5000 March 22, 1993 G02-93-067 Docket No.50-397 U.S.Nuclear Regulatory Commission Attn: Document Control Desk'ashington, D.C.20555 Gentlemen: | | TITLE: General (50 Dkt)-Insp Rept/Notice of Violation Response NOTES: |
| | RECIPIENT ;COPIES RECIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL PD5 PD 1 1 CLIFFORD,J 1 1 INTERNAL: ACRS 2 2 AEOD/DEIB 1 1 AEOD/DSP/TPAB 1 1 AEOD/TTC 1 1 DEDRO 1 1 NRR/DORS/OEAB 1 1 NRR/DRCH/HHFBPT 1 1 NRR/DRIL/RPEB 1 1 NRR/PMAS/ILPB1 1 1' NRR/DRSS/PEPB 1 1 NRR/PMAS/ILPB2 1 1 NUDOCS-ABSTRACT 1 OE 1 1 OGC/HDS1 1 1 C FILE 02 1 1 RES MORISSEAUiD 1 . 1 ILE 01 1 1 EXTERNAL EGGG/BRYCE iJ ~ H~ 1 1 NRC PDR 1 1 NSIC 1 1 NOTE TO ALL"RIDS" RECIPIENTS: |
| | PLEASE HELP US TO REDUCE WASTE! CONTACT THE DOCUMENT CONTROL DESK, ROOM PI-37 (EXT. 504-2065) TO ELIMINATEYOUR NAME FROM DISTRIBUTION LISTS FOR DOCUMENTS YOU DON'T NEEDI TOTAL NUMBER OF COPIES REQUIRED: LTTR 23 ENCL 23 |
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| | WASHINGTON PUBLIC POWER SUPPLY SYSTEM P.O. Box 968 ~ 3000 George Washington Way ~ Rfchland, Wasbfngton 993524968 ~ (509) 372-5000 March 22, 1993 G02-93-067 Docket No. 50-397 U.S. Nuclear Regulatory Commission Attn: Document Control Desk D.C. 20555 'ashington, Gentlemen: |
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| ==Subject:== | | ==Subject:== |
| WNP-2, OPERATING LICENSE NPF-21 NRC INSPECTION OF FACILITY TRAINING (REPORT NO.50-397/92-27) | | WNP-2, OPERATING LICENSE NPF-21 NRC INSPECTION OF FACILITYTRAINING (REPORT NO. 50-397/92-27) ACTION STATUS |
| ACTION STATUS | |
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| ==References:== | | ==References:== |
| | : 1) Letter G02-92-255 dated November 19, 1992, J,V. Parrish (SS) to U.S. |
| | Nuclear Regulatory Commission, "WNP-2 Operating License NPF-21 NRC Inspection of Facility Training (Report No. 50-397/92-27)" |
| | : 2) Letter dated December 3, 1992, L.F. Miller (NRC) to A.L. Oxsen (SS), |
| | "WNP-2 Response to NRC Inspection Report No. 50-397/92-27" The subject inspection was an evaluation of various aspects of facility training. Three weaknesses were identified in this inspection which required a response detailing the planned actions to be taken to address them. The WNP-2 response to these issues was forwarded by my letter of November 19, 1992 (Reference 1), |
| | The committed actions are in progress and we have completed evaluation of all of the issues addressed in the inspection report weaknesses. This letter is intended to provide an interim status update to apprise you of our progress in this area of extreme importance to the continued improvement of the Supply System. |
| | Commitment Modify the operations liaison responsibility instruction (LTI 7.4) to formally define the necessary qualification level by March 1, 1993, and qualify the incumb'ent accordingly by July 1, 1993. |
| | <<Stat a: The enclosed department instruction defining the responsibilities of the Operations Liaison (LTI 7.4) has been revised to formally define the necessary qualification level for this position. Actions to qualify the incumbent accordingly are in progress. This training is planned to be complete by the original date specified, July 1, 1993. |
| | 9303300040 930322 PDR 6 |
| | ADQCK 05000397 Qpo PDR I |
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| 1)Letter G02-92-255 dated November 19, 1992, J,V.Parrish (SS)to U.S.Nuclear Regulatory Commission,"WNP-2 Operating License NPF-21 NRC Inspection of Facility Training (Report No.50-397/92-27)" 2)Letter dated December 3, 1992, L.F.Miller (NRC)to A.L.Oxsen (SS),"WNP-2 Response to NRC Inspection Report No.50-397/92-27" The subject inspection was an evaluation of various aspects of facility training.Three weaknesses were identified in this inspection which required a response detailing the planned actions to be taken to address them.The WNP-2 response to these issues was forwarded by my letter of November 19, 1992 (Reference 1), The committed actions are in progress and we have completed evaluation of all of the issues addressed in the inspection report weaknesses.
| | K Page Two NRC INSPECTION OF FACILITYTRAINING (REPORT NO. 50-397/92-27I ACTION STATUS t |
| This letter is intended to provide an interim status update to apprise you of our progress in this area of extreme importance to the continued improvement of the Supply System.Commitment Modify the operations liaison responsibility instruction (LTI 7.4)to formally define the necessary qualification level by March 1, 1993, and qualify the incumb'ent accordingly by July 1, 1993.<<Stat a: Qpo I)9303300040 930322 PDR ADQCK 05000397 6 PDR The enclosed department instruction defining the responsibilities of the Operations Liaison (LTI 7.4)has been revised to formally define the necessary qualification level for this position.Actions to qualify the incumbent accordingly are in progress.This training is planned to be complete by the original date specified, July 1, 1993.
| | Commitment: Incorporate a formal means of assuring an ongoing sharing of skills and knowledge between the requalification and initial license training programs within our applicable department instructions by March 1, 1993. |
| K Page Two NRC INSPECTION OF FACILITY TRAINING (REPORT NO.50-397/92-27I ACTION STATUS t Commitment: | | tatus: We have chosen to not implement this commitment as stated. Instead, our efforts to ensure the sharing of skills from the requalification training area to the initial license area have taken the form of: |
| Incorporate a formal means of assuring an ongoing sharing of skills and knowledge between the requalification and initial license training programs within our applicable department instructions by March 1, 1993.tatus: We have chosen to not implement this commitment as stated.Instead, our efforts to ensure the sharing of skills from the requalification training area to the initial license area have taken the form of: Initial license instructors attend requalification train-the-trainer sessions.Requalification instructors, management, and the Operations Liaison have participated in the training and evaluation of the initial license candidates to a significant degree.Further review indicates that formalizing this sharing of instructional resource will add little benefit if organizational constraints preclude effective implementation. | | Initial license instructors attend requalification train-the-trainer sessions. |
| Therefore, we are evaluating our organizational structure and intend to implement appropriate changes to accomplish this objective by June 1, 1993.f i R i i Ip<<h h ff i*<<l'id<<~training by July 1, 1993.Status: The enclosed letter defines an assessment process which will commence in April, 1993.The results of this process will be used to enhance industry events training which should create effective responsiveness to industry lessons learned and improve overall performance at WNP-2.Additional actions are being taken beyond those previously committed to provide a better focus on injecting lessons learned into our training programs.The training staff has been informed through the enclosed letter of their critical role in establishing a culture that believes"it can happen here" with an urgency to prevent recurrence. | | Requalification instructors, management, and the Operations Liaison have participated in the training and evaluation of the initial license candidates to a significant degree. |
| We intend to enhance the visibility of related industry experience in our training materials. | | Further review indicates that formalizing this sharing of instructional resource will add little benefit if organizational constraints preclude effective implementation. Therefore, we are evaluating our organizational structure and intend to implement appropriate changes to accomplish this objective by June 1, 1993. |
| In addition, we plan to conduct instructor skills training on the INPO"case study approach" as an enhancement technique for effective industry events training.All actions are scheduled for completion by the original schedule of July 1, 1993. | | f i R i i Ip training by July 1, 1993. |
| 'I Page Three NRC INSPECTION OF FACILITY TRAINING (REPORT NO.50-397/92-27I ACTION STATUS A recent example, the Supply System response to the recent issue concerning BWR reactor vessel level anomalies during transients, demonstrates our training process for industry feedback.Also included in the following are the actions taken based upon a review of our plant experience with this issue.Requalification cycle 92-6 contained classroom training covering rapid depressurization and notching indications. | | <<h h ff i* << l'id<<~ |
| BWROG source documents transmitted to all licensed operators via required reading.Operations night orders required the Shift Managers to train their crews on this information. | | Status: The enclosed letter defines an assessment process which will commence in April, 1993. The results of this process willbe used to enhance industry events training which should create effective responsiveness to industry lessons learned and improve overall performance at WNP-2. |
| A Maintenance and Operations bulletin was prepared and distributed detailing how this industry experience could impact WNP-2.Requalification cycle 93-1, which concluded on 2/19/93, contained classroom training and dynamic simulator scenarios containing rapid depressurization indications. | | Additional actions are being taken beyond those previously committed to provide a better focus on injecting lessons learned into our training programs. The training staff has been informed through the enclosed letter of their critical role in establishing a culture that believes "it can happen here" with an urgency to prevent recurrence. We intend to enhance the visibility of related industry experience in our training materials. In addition, we plan to conduct instructor skills training on the INPO "case study approach" as an enhancement technique for effective industry events training. All actions are scheduled for completion by the original schedule of July 1, 1993. |
| This also included viewing a GE video tape on RPV level determination following rapid depressurization. | | |
| The initial licensed operator class, examined the week of 3/8/93, has had training on depressurization and notching indications included in EOP training.The recent WNP-2 Problem Evaluation Request concerning observed notching was distributed as required reading prior to assuming licensed duties.Formal training on this event was conducted during the last week of February, 1993, for all licensed personnel. | | 'I Page Three NRC INSPECTION OF FACILITYTRAINING (REPORT NO. 50-397/92-27I ACTION STATUS A recent example, the Supply System response to the recent issue concerning BWR reactor vessel level anomalies during transients, demonstrates our training process for industry feedback. Also included in the following are the actions taken based upon a review of our plant experience with this issue. |
| | Requalification cycle 92-6 contained classroom training covering rapid depressurization and notching indications. |
| | BWROG source documents transmitted to all licensed operators via required reading. Operations night orders required the Shift Managers to train their crews on this information. |
| | A Maintenance and Operations bulletin was prepared and distributed detailing how this industry experience could impact WNP-2. |
| | Requalification cycle 93-1, which concluded on 2/19/93, contained classroom training and dynamic simulator scenarios containing rapid depressurization indications. This also included viewing a GE video tape on RPV level determination following rapid depressurization. |
| | The initial licensed operator class, examined the week of 3/8/93, has had training on depressurization and notching indications included in EOP training. |
| | The recent WNP-2 Problem Evaluation Request concerning observed notching was distributed as required reading prior to assuming licensed duties. |
| | Formal training on this event was conducted during the last week of February, 1993, for all licensed personnel. |
| A follow-up quiz is planned for the subsequent requalification cycle. | | A follow-up quiz is planned for the subsequent requalification cycle. |
| e Page Four NRC INSPECTION OF FACILITY TRAINING (REPORT NO.50-397/92-27) | | |
| ACTION STATUS If you have any questions or require any additional information, please contact Mr.Myron Baird, Manager, Licensed Operator Requalification Training, at (509)377-8266./Sincerely, J+rvr~V Parrish (Mail Drop 1023)Assistant Managing Director, Operations DRK/bk cc: JB Martin-NRC RV NS Reynolds-Winston&Strawn JW Clifford-NRC DL Williams-BPA/399 NRC Site Inspector-901A}} | | e Page Four NRC INSPECTION OF FACILITYTRAINING (REPORT NO. 50-397/92-27) ACTION STATUS If you have any questions or require any additional information, please contact Mr. Myron Baird, Manager, Licensed Operator Requalification Training, at (509) 377-8266. |
| | / |
| | Sincerely, J +rvr~ |
| | V Parrish (Mail Drop 1023) |
| | Assistant Managing Director, Operations DRK/bk cc: JB Martin - NRC RV NS Reynolds - Winston & Strawn JW Clifford - NRC DL Williams - BPA/399 NRC Site Inspector - 901A}} |
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Category:CORRESPONDENCE-LETTERS
MONTHYEARML20217K9681999-10-19019 October 1999
Ack Receipt of Transmitting Rev 40 to Physical Security Plan for Washington Nuclear Plant 2.Based on Determination That Changes Do Not Decrease Effectiveness of Plan,No NRC Approval Required
ML17284A8981999-10-14014 October 1999
Forwards Rev 0 to WNP-2 Cycle 15,COLR 99-15, IAW Requirements of TS 5.6.5
ML17284A9061999-09-24024 September 1999
Forwards Final Rept for 990812 out-of-sequence Drills for Energy Northwest Washington Nuclear Power Project 2 (Lab, Food Control Point & Milk Sampling).No Deficiences & No Areas Requiring C/A Identified in Three Drills
ML17284A8881999-09-24024 September 1999
Informs NRC of Change in Schedule Pertaining to Final Implementation of Reactor Stability long-term Solution for WNP-2
ML17292B7591999-09-24024 September 1999
Forwards Rev 24 to WNP-2 Emergency Plan,Iaw 10CFR50.4(b), 50.54(q) & 10CFR50 App E.Detailed Synopsis of Changes,Encl
ML17292B7581999-09-22022 September 1999
Forwards NRC Forms 396 & 398 for Nl Hancock,License SOP-50027-3,AR Herrington,License OP-50013-3,WH Sawyer, License SOP-50023-3 & Dl Strote,License SOP-50031-3,for Renewal of Licenses.Without NRC Forms 396 & 398
ML17284A8811999-09-0909 September 1999
Forwards Response to NRC 990623 RAI to Support Review of Pending Request for Amend to Reactor pressure-temp Limit Curve TS
GO2-99-168, Forwards Rev 40 to Physical Security Plan.Rev Withheld,Per 10CFR2.790(a)(3)1999-09-0808 September 1999
Forwards Rev 40 to Physical Security Plan.Rev Withheld,Per 10CFR2.790(a)(3)
ML17284A8711999-08-30030 August 1999
Informs Staff of Errors in world-wide-web Database Related to WNP-2 Reactor Vessel Structural integrity.Marked-up Pages Containing Errors or Omissions Will Be Forwarded by 991201
ML17284A8751999-08-30030 August 1999
Provides Correct Page from License NPF-21 Marked to Show Rev Addressed in 990729 Application for Amend,Which Included Page That Was Inadvertently Included as Attachment 4.Replace Attachment 4 with Attached Page & Disregard Attachment 5
ML17284A8721999-08-30030 August 1999
Forwards Proprietary Info to Support Review of Request for Amend to License NPF-21,re Min Critical Power Ratio Safety Limits Tss,As Requested During 990816 Conversation. Proprietary Encl Withheld
ML17292B7531999-08-24024 August 1999
Requests That Eleven Individuals Listed Below Take BWR Generic Fundamentals Examination to Be Administered on 991006
ML17292B7511999-08-24024 August 1999
Forwards Fitness for Duty (FFD) Semiannual Performance Data Rept for Jan-June 1999,per 10CFR26.71(d)
ML17284A8701999-08-19019 August 1999
Forwards NRC Form 396, Certification of Medical Exam by Facility Licensee & NRC Form 398, Personal Qualification Statement - Licensee, for Jd Prescott (License SOP-50262-1).Without Encls
ML17292B7501999-08-19019 August 1999
Informs Staff That Licensee Has Completed Review of NRC SER for B&Wog Util Resolution Guidance Document Addressing ECCS Suction Strainer Blockage
ML17284A8681999-08-12012 August 1999
Submits Two ISI Program Plan Relief Requests for NRC Review & Approval,Per 10CFR50.55a(a)(3)(i).Proposed Alternatives Provide Acceptable Level of Quality & Safety
ML20211A9501999-08-12012 August 1999
Discusses 990720-21 Workshop Conducted in Region IV Ofc,Re Exchange of Info in Area of Use of Risk Insights in Regulatory Activities.List of Attendees,Summary of Topic & Issues,Agenda & Copies of Handouts Encl
ML20210L1461999-08-0303 August 1999
Informs That NRC Plans to Administer Gfes of Written Operator Licensing Exam on 991006.Requests Submittal of Ltr Identifying Individuals Taking Exam,Personnel Allowed Access to Exams & Mailing Address for Exams
ML17284A8541999-08-0202 August 1999
Forwards Proprietary Addl Info to Support Review of Pending Request for Amend to MCPR Safety Limit Ts.Info Consists of Proprietary Ltr from Abb Combustion Engineering,Inc.Encl Withheld
ML17284A8531999-07-30030 July 1999
Forwards Estimate of Number of Licensing Action Requests Planned for Submittal in Future,As Requested in Administrative Ltr 99-02.Twenty-nine Submittals Scheduled for Fy 2000 & Four for Fy 2001
ML17284A8301999-07-22022 July 1999
Clarifies Change of Licensee Name from Wpps to Energy Northwest & Change of Facility Name from Wppss Nuclear Project Number 2 to WNP-2,as Requested in 990719 Telcon with Js Cushing of NRC.Marked-up OL Pages,Encl
ML17292B7451999-07-20020 July 1999
Forwards Rev 23 to WNP-2 Emergency Plan,Iaw 10CFR50.4(b) & 50.54(q) & 10CFR50 App E.Rev 23 Provides Updated Description Re Establishment of Separate Emergency Operation Centers for Benton & Franklin Counties
ML17292B7391999-07-16016 July 1999
Submits Withdrawal of Request for Amend to Secondary Containment & Standby Gas Treatment Sys Ts.Util Currently Plan to re-submit Amend Request in Entirety by 991112
ML17292B7381999-07-12012 July 1999
Forwards NRC Form 396 & NRC Form 398,for If Sumsion,License OP-50487 & Ga Westergard,License SOP-50415 for Renewal of Operator Licenses.Without Encls
ML17292B7171999-07-0606 July 1999
Provides Notification of Early Completion on 990630 of Exception Noted in 990629 Ltr.Equipment within Scope of GL 98-01,Suppl 1, Y2K Readiness of Computer Sys at Nuclear Power Plants, Evaluated & Y2K Ready
ML17292B7181999-07-0202 July 1999
Responds to 990623 RAI to Support Review of Evaluation of Planar Indication Found on Weld Number 24RRC(2)A-1 During 1998 RO
ML17292B7161999-06-30030 June 1999
Forwards Addl Info Requested in 990513 Ltr to Support Review of Pending Response to GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power Operated Gate Valves.
ML17292B7131999-06-29029 June 1999
Forwards Response to NRC GL 98-01,Suppl 1, Y2K Readiness of Computer Sys at Npps.
ML17292B7091999-06-21021 June 1999
Forwards Proprietary Response to NRC 990603 RAI Re Licensee Request for Amend to MCPR Safety Limit Tss.Proprietary Info Withheld IAW Requirements of 10CFR2.790
ML17292B7041999-06-17017 June 1999
Forwards NRC Forms 396 & 398 for Three Individuals Listed Below for Renewal of Operator Licenses.Without Encls
ML17292B7031999-06-10010 June 1999
Forwards Response to NRC 990511 RAI Re License Request for Amend to Secondary Containment & SGTS Tss.Results of Addl Benchmark of Gothic Computer Code Performed to Demonstrate Modeling Capability of Drawdown Response,Encl
ML17292B6841999-06-0404 June 1999
Forwards Response to NRC 990326 RAI Re WNP-2 GL 96-05 Program for Periodic Verification of design-basis Capability of MOVs
ML17292B6851999-06-0101 June 1999
Forwards 1999 Quality Audit of WNP-2 Emergency Preparedness Program, Per NUREG-0654,Section Ii,Criteria P.9.Seven Problem Evaluation Requests & Nine Recommendations for Improvement Were Issued as Result of Audit Activities
ML17292B6831999-05-25025 May 1999
Informs That Request for NRC Approval of Changes to Emergency Plan Requesting Reduction in on-shift HP Staffing, Is Retracted.Util Will Resubmit Request with Required Addl Info at Later Date
ML17292B6751999-05-25025 May 1999
Forwards Proprietary ABB-CE Ltr Re WNP-2 Cycle 15 SLMCPR & Core Reload Design Rept,Per Util Request for Amend Re MCPR Safety Limits.Proprietary Info Withheld,Per 10CFR2.790
ML20206U4501999-05-19019 May 1999
Ack Receipt of Which Transmitted Rev 39 to Physical Security Plan,Per 10CFR50.54(p).No NRC Approval Is Required,Since Changes Do Not Decrease Effectiveness of Security Plan
ML17292B6661999-05-0707 May 1999
Requests Exemption to Requirement in 10CFR55.59(a)(2) Re Annual Operating Test requirements.One-time Exemption from Requirement to Period Not to Exceed 15-months from Last Date of Passing Operating Exam for Licensee at Facility
ML17292B6531999-05-0303 May 1999
Forwards Response to NRC 990402 RAI Re Licensed Operator Positive Drug Test.Encl Withheld,Per 10CFR2.790
ML17292B6561999-04-29029 April 1999
Forwards Rev 0 to Calculation ME-02-98-04, Fracture Mechanics Evaluation of N1 Safe End & Calculation Mod Record CMR-98-0243, Fracture Mechanics Evaluation of N1A Nozzle Safe End, as Suppl Info to ISI Exam
ML17292B6421999-04-19019 April 1999
Responds to NRC 990319 Ltr Re Violations Noted in Insp Rept 50-397/99-01.Corrective Actions:Provisions Are Presently in Place to Maintain Adequate Level of Security
GO2-99-073, Forwards Rev 39 to WNP-2 Physical Security Plan,Per 10CFR50.54(p).Changes Do Not Decrease Effectiveness of Approved Plan.Encl Withheld IAW 10CFR73.21 & 10CFR2.7901999-04-19019 April 1999
Forwards Rev 39 to WNP-2 Physical Security Plan,Per 10CFR50.54(p).Changes Do Not Decrease Effectiveness of Approved Plan.Encl Withheld IAW 10CFR73.21 & 10CFR2.790
ML17292B6401999-04-13013 April 1999
Requests That WNP-2 Operator Requalification Program Be Granted one-time Extension Beyond Requirement in 10CFR55.59(a)(2) for Annual Operating Tests
ML17292B6371999-04-12012 April 1999
Forwards Response to NRC 990211 RAI Re Util Request for Amend to Secondary Containment & SBGTS TS
ML17292B6281999-04-0606 April 1999
Informs NRC That Insp Interval Ending Date for ISI Program Plan Has Been Extended by One Year to Dec 12,2005 Due to Changes in Plant Refueling Outage Schedule
ML20196K6961999-03-30030 March 1999
Ack Receipt of ,Transmitting Rev 38 to Physical Security Plan for Plant.No NRC Approval Is Required,In Accordance with 10CFR50.54(p)
GO2-99-060, Submits Rept of Status of WNP-2 Decommissioning Fund as of 981231,IAW 10CFR50.75(f)(1)1999-03-26026 March 1999
Submits Rept of Status of WNP-2 Decommissioning Fund as of 981231,IAW 10CFR50.75(f)(1)
ML17292B6131999-03-24024 March 1999
Forwards Rev 0 to Calculation ME-02-98-04, Fracture Mechanics Evaluation of N1 Nozzle Safe End. Info Will Be Used to Assist NRC in Review of WNP-2 ISI Activities Associated with Evaluation of Planar Indication
ML20204F0261999-03-19019 March 1999
Forwards Insp Rept 50-397/99-01 on 990201-04 & 0303-05.No Violations Noted.Areas of Physical Security Plan Effectively Implemented with Listed Exceptions
ML17292B6001999-03-16016 March 1999
Responds to Weakness Noted in Insp Rept 50-397/98-24. Corrective Actions:Developed Document to Identify Areas Needing Improvement,Assigned Responsibility for Actions & Provided Milestones for Achievement
ML17292B5941999-03-16016 March 1999
Forwards NRC Form 396, Certification of Medical Exam by Facility Licensee, & NRC Form 398, Personal Qualification Statement - Licensee, for MD Comstock,Mc Naulty & RR Nelson.Without Encls
1999-09-09
[Table view]
Category:INCOMING CORRESPONDENCE
MONTHYEARML17284A8981999-10-14014 October 1999
Forwards Rev 0 to WNP-2 Cycle 15,COLR 99-15, IAW Requirements of TS 5.6.5
ML17284A9061999-09-24024 September 1999
Forwards Final Rept for 990812 out-of-sequence Drills for Energy Northwest Washington Nuclear Power Project 2 (Lab, Food Control Point & Milk Sampling).No Deficiences & No Areas Requiring C/A Identified in Three Drills
ML17292B7591999-09-24024 September 1999
Forwards Rev 24 to WNP-2 Emergency Plan,Iaw 10CFR50.4(b), 50.54(q) & 10CFR50 App E.Detailed Synopsis of Changes,Encl
ML17284A8881999-09-24024 September 1999
Informs NRC of Change in Schedule Pertaining to Final Implementation of Reactor Stability long-term Solution for WNP-2
ML17292B7581999-09-22022 September 1999
Forwards NRC Forms 396 & 398 for Nl Hancock,License SOP-50027-3,AR Herrington,License OP-50013-3,WH Sawyer, License SOP-50023-3 & Dl Strote,License SOP-50031-3,for Renewal of Licenses.Without NRC Forms 396 & 398
ML17284A8811999-09-0909 September 1999
Forwards Response to NRC 990623 RAI to Support Review of Pending Request for Amend to Reactor pressure-temp Limit Curve TS
GO2-99-168, Forwards Rev 40 to Physical Security Plan.Rev Withheld,Per 10CFR2.790(a)(3)1999-09-0808 September 1999
Forwards Rev 40 to Physical Security Plan.Rev Withheld,Per 10CFR2.790(a)(3)
ML17284A8751999-08-30030 August 1999
Provides Correct Page from License NPF-21 Marked to Show Rev Addressed in 990729 Application for Amend,Which Included Page That Was Inadvertently Included as Attachment 4.Replace Attachment 4 with Attached Page & Disregard Attachment 5
ML17284A8721999-08-30030 August 1999
Forwards Proprietary Info to Support Review of Request for Amend to License NPF-21,re Min Critical Power Ratio Safety Limits Tss,As Requested During 990816 Conversation. Proprietary Encl Withheld
ML17284A8711999-08-30030 August 1999
Informs Staff of Errors in world-wide-web Database Related to WNP-2 Reactor Vessel Structural integrity.Marked-up Pages Containing Errors or Omissions Will Be Forwarded by 991201
ML17292B7531999-08-24024 August 1999
Requests That Eleven Individuals Listed Below Take BWR Generic Fundamentals Examination to Be Administered on 991006
ML17292B7511999-08-24024 August 1999
Forwards Fitness for Duty (FFD) Semiannual Performance Data Rept for Jan-June 1999,per 10CFR26.71(d)
ML17284A8701999-08-19019 August 1999
Forwards NRC Form 396, Certification of Medical Exam by Facility Licensee & NRC Form 398, Personal Qualification Statement - Licensee, for Jd Prescott (License SOP-50262-1).Without Encls
ML17292B7501999-08-19019 August 1999
Informs Staff That Licensee Has Completed Review of NRC SER for B&Wog Util Resolution Guidance Document Addressing ECCS Suction Strainer Blockage
ML17284A8681999-08-12012 August 1999
Submits Two ISI Program Plan Relief Requests for NRC Review & Approval,Per 10CFR50.55a(a)(3)(i).Proposed Alternatives Provide Acceptable Level of Quality & Safety
ML17284A8541999-08-0202 August 1999
Forwards Proprietary Addl Info to Support Review of Pending Request for Amend to MCPR Safety Limit Ts.Info Consists of Proprietary Ltr from Abb Combustion Engineering,Inc.Encl Withheld
ML17284A8531999-07-30030 July 1999
Forwards Estimate of Number of Licensing Action Requests Planned for Submittal in Future,As Requested in Administrative Ltr 99-02.Twenty-nine Submittals Scheduled for Fy 2000 & Four for Fy 2001
ML17284A8301999-07-22022 July 1999
Clarifies Change of Licensee Name from Wpps to Energy Northwest & Change of Facility Name from Wppss Nuclear Project Number 2 to WNP-2,as Requested in 990719 Telcon with Js Cushing of NRC.Marked-up OL Pages,Encl
ML17292B7451999-07-20020 July 1999
Forwards Rev 23 to WNP-2 Emergency Plan,Iaw 10CFR50.4(b) & 50.54(q) & 10CFR50 App E.Rev 23 Provides Updated Description Re Establishment of Separate Emergency Operation Centers for Benton & Franklin Counties
ML17292B7391999-07-16016 July 1999
Submits Withdrawal of Request for Amend to Secondary Containment & Standby Gas Treatment Sys Ts.Util Currently Plan to re-submit Amend Request in Entirety by 991112
ML17292B7381999-07-12012 July 1999
Forwards NRC Form 396 & NRC Form 398,for If Sumsion,License OP-50487 & Ga Westergard,License SOP-50415 for Renewal of Operator Licenses.Without Encls
ML17292B7171999-07-0606 July 1999
Provides Notification of Early Completion on 990630 of Exception Noted in 990629 Ltr.Equipment within Scope of GL 98-01,Suppl 1, Y2K Readiness of Computer Sys at Nuclear Power Plants, Evaluated & Y2K Ready
ML17292B7181999-07-0202 July 1999
Responds to 990623 RAI to Support Review of Evaluation of Planar Indication Found on Weld Number 24RRC(2)A-1 During 1998 RO
ML17292B7161999-06-30030 June 1999
Forwards Addl Info Requested in 990513 Ltr to Support Review of Pending Response to GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power Operated Gate Valves.
ML17292B7131999-06-29029 June 1999
Forwards Response to NRC GL 98-01,Suppl 1, Y2K Readiness of Computer Sys at Npps.
ML17292B7091999-06-21021 June 1999
Forwards Proprietary Response to NRC 990603 RAI Re Licensee Request for Amend to MCPR Safety Limit Tss.Proprietary Info Withheld IAW Requirements of 10CFR2.790
ML17292B7041999-06-17017 June 1999
Forwards NRC Forms 396 & 398 for Three Individuals Listed Below for Renewal of Operator Licenses.Without Encls
ML17292B7031999-06-10010 June 1999
Forwards Response to NRC 990511 RAI Re License Request for Amend to Secondary Containment & SGTS Tss.Results of Addl Benchmark of Gothic Computer Code Performed to Demonstrate Modeling Capability of Drawdown Response,Encl
ML17292B6841999-06-0404 June 1999
Forwards Response to NRC 990326 RAI Re WNP-2 GL 96-05 Program for Periodic Verification of design-basis Capability of MOVs
ML17292B6851999-06-0101 June 1999
Forwards 1999 Quality Audit of WNP-2 Emergency Preparedness Program, Per NUREG-0654,Section Ii,Criteria P.9.Seven Problem Evaluation Requests & Nine Recommendations for Improvement Were Issued as Result of Audit Activities
ML17292B6751999-05-25025 May 1999
Forwards Proprietary ABB-CE Ltr Re WNP-2 Cycle 15 SLMCPR & Core Reload Design Rept,Per Util Request for Amend Re MCPR Safety Limits.Proprietary Info Withheld,Per 10CFR2.790
ML17292B6831999-05-25025 May 1999
Informs That Request for NRC Approval of Changes to Emergency Plan Requesting Reduction in on-shift HP Staffing, Is Retracted.Util Will Resubmit Request with Required Addl Info at Later Date
ML17292B6661999-05-0707 May 1999
Requests Exemption to Requirement in 10CFR55.59(a)(2) Re Annual Operating Test requirements.One-time Exemption from Requirement to Period Not to Exceed 15-months from Last Date of Passing Operating Exam for Licensee at Facility
ML17292B6531999-05-0303 May 1999
Forwards Response to NRC 990402 RAI Re Licensed Operator Positive Drug Test.Encl Withheld,Per 10CFR2.790
ML17292B6561999-04-29029 April 1999
Forwards Rev 0 to Calculation ME-02-98-04, Fracture Mechanics Evaluation of N1 Safe End & Calculation Mod Record CMR-98-0243, Fracture Mechanics Evaluation of N1A Nozzle Safe End, as Suppl Info to ISI Exam
ML17292B6421999-04-19019 April 1999
Responds to NRC 990319 Ltr Re Violations Noted in Insp Rept 50-397/99-01.Corrective Actions:Provisions Are Presently in Place to Maintain Adequate Level of Security
GO2-99-073, Forwards Rev 39 to WNP-2 Physical Security Plan,Per 10CFR50.54(p).Changes Do Not Decrease Effectiveness of Approved Plan.Encl Withheld IAW 10CFR73.21 & 10CFR2.7901999-04-19019 April 1999
Forwards Rev 39 to WNP-2 Physical Security Plan,Per 10CFR50.54(p).Changes Do Not Decrease Effectiveness of Approved Plan.Encl Withheld IAW 10CFR73.21 & 10CFR2.790
ML17292B6401999-04-13013 April 1999
Requests That WNP-2 Operator Requalification Program Be Granted one-time Extension Beyond Requirement in 10CFR55.59(a)(2) for Annual Operating Tests
ML17292B6371999-04-12012 April 1999
Forwards Response to NRC 990211 RAI Re Util Request for Amend to Secondary Containment & SBGTS TS
ML17292B6281999-04-0606 April 1999
Informs NRC That Insp Interval Ending Date for ISI Program Plan Has Been Extended by One Year to Dec 12,2005 Due to Changes in Plant Refueling Outage Schedule
GO2-99-060, Submits Rept of Status of WNP-2 Decommissioning Fund as of 981231,IAW 10CFR50.75(f)(1)1999-03-26026 March 1999
Submits Rept of Status of WNP-2 Decommissioning Fund as of 981231,IAW 10CFR50.75(f)(1)
ML17292B6131999-03-24024 March 1999
Forwards Rev 0 to Calculation ME-02-98-04, Fracture Mechanics Evaluation of N1 Nozzle Safe End. Info Will Be Used to Assist NRC in Review of WNP-2 ISI Activities Associated with Evaluation of Planar Indication
ML17292B5991999-03-16016 March 1999
Informs That Listed Property & Liability Insurance Coverage for WNP-2 Is in Force,In Compliance with Licensing Responsibilities Delineated in 10CFR50.54(w)(3)
ML17292B5911999-03-16016 March 1999
Forwards 1998 Environ Operating Rept, Per Reporting Requirements of Section 5.4.1 of WNP-2 Epp.No Design or Operational Changes or Tests in 1998 Involved Unreviewed Environ Question
ML17292B5941999-03-16016 March 1999
Forwards NRC Form 396, Certification of Medical Exam by Facility Licensee, & NRC Form 398, Personal Qualification Statement - Licensee, for MD Comstock,Mc Naulty & RR Nelson.Without Encls
ML17292B6001999-03-16016 March 1999
Responds to Weakness Noted in Insp Rept 50-397/98-24. Corrective Actions:Developed Document to Identify Areas Needing Improvement,Assigned Responsibility for Actions & Provided Milestones for Achievement
ML17292B5901999-03-11011 March 1999
Forwards Hard Copy of Addl Occupational Exposure Data Requested in GL 94-04,per 990303 e-mail.Original Electronic Version Was Corrupted
ML17292B5681999-03-0101 March 1999
Forwards Radioactive Effluent Release Rept for 1998, IAW 10CFR50.36a(a)(2) & TS 5.6.3 & Complete Copy of WNP-2 ODCM Per TS 5.5.1
ML17292B5651999-02-22022 February 1999
Forwards Relief Request 2ISI-20,proposing Alternate Exam Expected to Reduce Dose Significantly & Still Provide Adequate Safety & Quality.Attached Relief Request Will Be Used to Support ALARA Dose Reduction Efforts During Maint
ML17292B5581999-02-0404 February 1999
Requests Change to Co Which Modified WNP-2 OL to Reflect Schedule for Implementing Thermo-Lag 330-1 Fire Barrier C/As.Change Requested to Reflect That Final Implementation of C/As Will Be Completed During Fall 1999 Not Spring 1999
1999-09-09
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Text
ACCEI.ERATED DOCUMENT DISTRIBUTION SYSTEM REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)
ACCESSION NBRF'9303300040 DOC.DATE: 93/03/22 NOTARIZED: NO DOCKET CIL:50-397 WPPSS Nuclear Project, Unit 2, Washington Public Powe 05000397 TH.NAME AUTHOR AFFILIATION
,ARRISH,J.V. Washington Public Power Supply System RECIP.NAME RECIPIENT AFFILIATION Document Control Branch (Document Control Desk)
SUBJECT:
Responds to NRC 921203 ltr re violations noted in insp of facility training rept 50-397/92-27.C/As:requalification instructors,mgt 6 Operations Liaison have participated in training & evaluation of initial license candidates.
DISTRIBUTION CODE: IE01D COPIES RECEIVED:LTR ENCL SIZE:
TITLE: General (50 Dkt)-Insp Rept/Notice of Violation Response NOTES:
RECIPIENT ;COPIES RECIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL PD5 PD 1 1 CLIFFORD,J 1 1 INTERNAL: ACRS 2 2 AEOD/DEIB 1 1 AEOD/DSP/TPAB 1 1 AEOD/TTC 1 1 DEDRO 1 1 NRR/DORS/OEAB 1 1 NRR/DRCH/HHFBPT 1 1 NRR/DRIL/RPEB 1 1 NRR/PMAS/ILPB1 1 1' NRR/DRSS/PEPB 1 1 NRR/PMAS/ILPB2 1 1 NUDOCS-ABSTRACT 1 OE 1 1 OGC/HDS1 1 1 C FILE 02 1 1 RES MORISSEAUiD 1 . 1 ILE 01 1 1 EXTERNAL EGGG/BRYCE iJ ~ H~ 1 1 NRC PDR 1 1 NSIC 1 1 NOTE TO ALL"RIDS" RECIPIENTS:
PLEASE HELP US TO REDUCE WASTE! CONTACT THE DOCUMENT CONTROL DESK, ROOM PI-37 (EXT. 504-2065) TO ELIMINATEYOUR NAME FROM DISTRIBUTION LISTS FOR DOCUMENTS YOU DON'T NEEDI TOTAL NUMBER OF COPIES REQUIRED: LTTR 23 ENCL 23
WASHINGTON PUBLIC POWER SUPPLY SYSTEM P.O. Box 968 ~ 3000 George Washington Way ~ Rfchland, Wasbfngton 993524968 ~ (509) 372-5000 March 22, 1993 G02-93-067 Docket No. 50-397 U.S. Nuclear Regulatory Commission Attn: Document Control Desk D.C. 20555 'ashington, Gentlemen:
Subject:
WNP-2, OPERATING LICENSE NPF-21 NRC INSPECTION OF FACILITYTRAINING (REPORT NO. 50-397/92-27) ACTION STATUS
References:
- 1) Letter G02-92-255 dated November 19, 1992, J,V. Parrish (SS) to U.S.
Nuclear Regulatory Commission, "WNP-2 Operating License NPF-21 NRC Inspection of Facility Training (Report No. 50-397/92-27)"
- 2) Letter dated December 3, 1992, L.F. Miller (NRC) to A.L. Oxsen (SS),
"WNP-2 Response to NRC Inspection Report No. 50-397/92-27" The subject inspection was an evaluation of various aspects of facility training. Three weaknesses were identified in this inspection which required a response detailing the planned actions to be taken to address them. The WNP-2 response to these issues was forwarded by my letter of November 19, 1992 (Reference 1),
The committed actions are in progress and we have completed evaluation of all of the issues addressed in the inspection report weaknesses. This letter is intended to provide an interim status update to apprise you of our progress in this area of extreme importance to the continued improvement of the Supply System.
Commitment Modify the operations liaison responsibility instruction (LTI 7.4) to formally define the necessary qualification level by March 1, 1993, and qualify the incumb'ent accordingly by July 1, 1993.
<<Stat a: The enclosed department instruction defining the responsibilities of the Operations Liaison (LTI 7.4) has been revised to formally define the necessary qualification level for this position. Actions to qualify the incumbent accordingly are in progress. This training is planned to be complete by the original date specified, July 1, 1993.
9303300040 930322 PDR 6
ADQCK 05000397 Qpo PDR I
)
K Page Two NRC INSPECTION OF FACILITYTRAINING (REPORT NO. 50-397/92-27I ACTION STATUS t
Commitment: Incorporate a formal means of assuring an ongoing sharing of skills and knowledge between the requalification and initial license training programs within our applicable department instructions by March 1, 1993.
tatus: We have chosen to not implement this commitment as stated. Instead, our efforts to ensure the sharing of skills from the requalification training area to the initial license area have taken the form of:
Initial license instructors attend requalification train-the-trainer sessions.
Requalification instructors, management, and the Operations Liaison have participated in the training and evaluation of the initial license candidates to a significant degree.
Further review indicates that formalizing this sharing of instructional resource will add little benefit if organizational constraints preclude effective implementation. Therefore, we are evaluating our organizational structure and intend to implement appropriate changes to accomplish this objective by June 1, 1993.
f i R i i Ip training by July 1, 1993.
<<h h ff i* << l'id<<~
Status: The enclosed letter defines an assessment process which will commence in April, 1993. The results of this process willbe used to enhance industry events training which should create effective responsiveness to industry lessons learned and improve overall performance at WNP-2.
Additional actions are being taken beyond those previously committed to provide a better focus on injecting lessons learned into our training programs. The training staff has been informed through the enclosed letter of their critical role in establishing a culture that believes "it can happen here" with an urgency to prevent recurrence. We intend to enhance the visibility of related industry experience in our training materials. In addition, we plan to conduct instructor skills training on the INPO "case study approach" as an enhancement technique for effective industry events training. All actions are scheduled for completion by the original schedule of July 1, 1993.
'I Page Three NRC INSPECTION OF FACILITYTRAINING (REPORT NO. 50-397/92-27I ACTION STATUS A recent example, the Supply System response to the recent issue concerning BWR reactor vessel level anomalies during transients, demonstrates our training process for industry feedback. Also included in the following are the actions taken based upon a review of our plant experience with this issue.
Requalification cycle 92-6 contained classroom training covering rapid depressurization and notching indications.
BWROG source documents transmitted to all licensed operators via required reading. Operations night orders required the Shift Managers to train their crews on this information.
A Maintenance and Operations bulletin was prepared and distributed detailing how this industry experience could impact WNP-2.
Requalification cycle 93-1, which concluded on 2/19/93, contained classroom training and dynamic simulator scenarios containing rapid depressurization indications. This also included viewing a GE video tape on RPV level determination following rapid depressurization.
The initial licensed operator class, examined the week of 3/8/93, has had training on depressurization and notching indications included in EOP training.
The recent WNP-2 Problem Evaluation Request concerning observed notching was distributed as required reading prior to assuming licensed duties.
Formal training on this event was conducted during the last week of February, 1993, for all licensed personnel.
A follow-up quiz is planned for the subsequent requalification cycle.
e Page Four NRC INSPECTION OF FACILITYTRAINING (REPORT NO. 50-397/92-27) ACTION STATUS If you have any questions or require any additional information, please contact Mr. Myron Baird, Manager, Licensed Operator Requalification Training, at (509) 377-8266.
/
Sincerely, J +rvr~
V Parrish (Mail Drop 1023)
Assistant Managing Director, Operations DRK/bk cc: JB Martin - NRC RV NS Reynolds - Winston & Strawn JW Clifford - NRC DL Williams - BPA/399 NRC Site Inspector - 901A
