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| {{#Wiki_filter:CATEGORY j.REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)A CCESSION NBR:9801290057 DOC.DATE: 98/01/19 NOTARIZED: | | {{#Wiki_filter:CATEGORY j. |
| NO DOCKET FACIL:50-397 WPPSS Nuclear Project, Unit 2, Washington Public Powe 05000397 AUTH.NAME AUTHOR AFFILIATION BEMIS,P.R. | | REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS) |
| Washington Public Power Supply System RECIP.NAME RECIPIENT AFFILIATION Document Control Branch (Document Control Desk) | | ACCESSION NBR:9801290057 DOC.DATE: 98/01/19 NOTARIZED: NO DOCKET FACIL:50-397 WPPSS Nuclear Project, Unit 2, Washington Public Powe 05000397 AUTH. NAME AUTHOR AFFILIATION BEMIS,P.R. Washington Public Power Supply System RECIP.NAME RECIPIENT AFFILIATION Document Control Branch (Document Control Desk) |
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| ==SUBJECT:== | | ==SUBJECT:== |
| Responds to NRC 971218 ltr re violations noted in insp rept 50-397/97-17.Corrective actions: technician visually verified area to be clear of personnel&immediately locked gate&performed walkdown to verify locked status of similar are s.DISTRIBUTION CODE: IEOID COPIES RECEIVED:LTR (ENCL t SIZE: TITLE: General (50 Dkt)-Insp Rept/Notice of Violation Response NOTES: E RECIPIENT ID CODE/NAME PD4-2 PD INTERNAL: ACRS AEOD ILE CENTER NRR DRPM/PECB NUDOCS-ABSTRACT OGC/HDS3 TERNAL: LITCO BRYCE,J H NRC PDR COPIES LTTR ENCL 1 1 2 2 1 1 1 1 1 1 1 1 1 1 1 1 1 1 RECIPIENT ID CODE/NAME POSLUSNY,C AEOD/SPD/RAB DEDRO NRR/DRCH/HHFB NRR/DRPM/PERB OE DIR RGN4 FILE 01 NOAC NUDOCS FULLTEXT COPIES LTTR ENCL 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 R D 0 U N NOTE TO ALL"RIDS" RECIPIENTS: | | Responds to NRC 971218 ltr re violations noted in insp rept 50-397/97-17.Corrective actions: technician visually verified area to be clear of personnel & immediately locked gate & |
| PLEASE HELP US TO REDUCE WASTE.TO HAVE YOUR NAME OR ORGANIZATION REMOVED FROM DISTRIBUTION LISTS OR REDUCE THE NUMBER OF COPIES RECEIVED BY YOU OR YOUR ORGANIZATION, CONTACT THE DOCUMENT CONTROL DESK (DCD)ON EXTENSION 415-2083 TOTAL NUMBER OF COPIES REQUIRED: LTTR 19 ENCL 19 WASHIV>GTON PUBLIC POWER SUPPI.Y SYSTElvf I?O.Iiox 968~Ri~%hniil, 11'ashiiigtow 99352-0968 January 19, 1998 G02-98-011 Docket No.50-397 U.S.Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 Gentlemen: | | performed walkdown to verify locked status of similar are s. |
| Subjec't: WNP-2, OPERATING LICENSE NPF-21 NRC INSPECTION REPORT 97-19, RESPONSE TO NOTICE OF VIOLATION | | DISTRIBUTION CODE: IEOID COPIES RECEIVED:LTR ( ENCL t SIZE: |
| | TITLE: General (50 Dkt)-Insp Rept/Notice of Violation Response E |
| | NOTES: |
| | RECIPIENT COPIES RECIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL PD4-2 PD 1 1 POSLUSNY,C 1 1 R |
| | INTERNAL: ACRS 2 2 AEOD/SPD/RAB 1 1 AEOD 1 1 DEDRO 1 1 ILE CENTER 1 1 NRR/DRCH/HHFB 1 1 NRR DRPM/PECB 1 1 NRR/DRPM/PERB 1 1 NUDOCS-ABSTRACT 1 1 OE DIR 1 1 OGC/HDS3 1 1 RGN4 FILE 01 1 1 TERNAL: LITCO BRYCE,J H 1 1 NOAC 1 1 NRC PDR 1 1 NUDOCS FULLTEXT 1 1 D 0 |
| | U N |
| | NOTE TO ALL "RIDS" RECIPIENTS: |
| | PLEASE HELP US TO REDUCE WASTE. TO HAVE YOUR NAME OR ORGANIZATION REMOVED FROM DISTRIBUTION LISTS OR REDUCE THE NUMBER OF COPIES RECEIVED BY YOU OR YOUR ORGANIZATION, CONTACT THE DOCUMENT CONTROL DESK (DCD) ON EXTENSION 415-2083 TOTAL NUMBER OF COPIES REQUIRED: LTTR 19 ENCL 19 |
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| | WASHIV>GTON PUBLIC POWER SUPPI.Y SYSTElvf I? O. Iiox 968 ~ Ri~%hniil, 11'ashiiigtow 99352-0968 January 19, 1998 G02-98-011 Docket No. 50-397 U.S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 Gentlemen: |
| | Subjec't: WNP-2, OPERATING LICENSE NPF-21 NRC INSPECTION REPORT 97-19, RESPONSE TO NOTICE OF VIOLATION |
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| ==Reference:== | | ==Reference:== |
| | Letter dated December 18, 1997, B Murray (NRC) to JV Parrish (SS), "NRC Inspection Report 50-397/97-19" The Supply System's response to the Notice Of Violation, pursuant to the provisions of Section 2.201, Title 10, Code of Federal Regulations, is enclosed as Attachment A. |
| | We acknowledge the additional concerns that were identified in the inspection report and the Supply System is taking steps to address the issues. |
| | Should you have any questions or desire additional information regarding this matter, please call Mr. PJ Inserra at (509) 377-4147. |
| | PR is Vi resident, Nuclear Operations Mail Drop PE23 Attachment cc: EW Merschoff - NRC RIV NRC Sr. Resident Inspector - 927N KE Perkins, Jr. - NRC RIV, WCFO DL Williams - BPA/399 C Poslusny, Jr. - NRR PD Robinson - Winston & Strawn 980i290057 980ii9 IIIIIIIIIIIIIIIIIIIIIIIIIIIIIIIIIIIIIIII PDR ADGCK 05000397 8 PDR |
| | |
| | RESPONSE TO NOTICE OF VIOLATIONIN INSPECTION REPORT 50-397/97-19 Appendix A Page 1 of 3 RESTATEMENT F VI LATIONA Technical Specification 5.7.2.a requires, in part, that each entryway to high radiation areas with dose rates greater than 1.0 rem/hour (at 30 centimeters from the radiation source or from any surface penetrated by the radiation) be provided with a locked door, gate, or guard that prevents unauthorized entry. |
| | Contrary to the above, on October 6, 1997, an entryway to the radwaste liner storage room on the 437-foot elevation of the radwaste building, an area with dose rates greater than 1.0 rem/hour (at 30 centimeters from the radiation source or from any surface penetrated by the radiation) was not provided with a locked door, gate, or guard that prevented unauthorized entry. |
| | This is a Severity Level IV violation (Supplement IV) (50-397/9719-01). |
| | R P N ET VI LATI N The Supply System accepts the violation. |
| | REA N F RVI LATI N The Supply System agrees with the staff's characterization of the reason for this event given in the Report Details section of Inspection Report 50-397/97-19. |
| | The failure to properly secure a chain link gate to a high high radiation area (HHRA) was caused by human error on the part of a health physics technician. One condition that contributed to the event was the failure to perform a timely independent verification of the door's locked status. A second contributing condition was the use of a chain to secure the gate, rather than permanently installed padeyes. |
| | RRE A N TAKEN AND R TS A HIEVED Upon identification of the event a health physics technician responded, visually verified the area to be clear of personnel and immediately locked the gate. A walk-down was performed to verify the locked status of all other similar areas. No other doors were found to be improperly secured. |
| | An additional walk-down was performed by Health Physics to identify any other HHRA or high radiation areas that were secured by means of chain and padlocks. One additional door (access hatch to the wetwell) was found to be secured in this manner. Supply System staff determined that this hatch did not require a padeye as it is bolted and secured with a heavy chain and padlock. |
| | |
| | RESPONSE TO NOTICE OF VIOLATIONIN INSPECTION REPORT 50-397/97-19 Appendix A Page 2 of 3 A work request was issued to install lockable padeyes on the gate to the radwaste liner storage room on the 437'levation of the radwaste building. Work was completed December 10, 1997, Lessons learned from the event were discussed and documented in Health Physics Technician Continuing Training. This training was completed December 22, 1997. |
| | The appropriate plant procedure was revised on December 15, 1997 to require performance of independent verification in a timely manner. |
| | Appropriate personnel actions were taken with the health physics technician who failed to properly secure the gate. |
| | RRE TEP T BETAKENT AV IDF EVI LATI N All corrective actions have been completed. |
| | DATE F L MPLIAN E The gate was immediately locked on October 6, 1997 upon identification of the event. |
| | R TATEMENT F VI LATI NB 10 CFR 20. 1501(a) requires, in part, that each licensee make or cause to be made surveys that may be necessary for the licensee to comply with the regulations in 10 CFR Part 20 and are reasonable to evaluate the quantities of radioactive material and the potential radiological hazards that could be present. |
| | 10 CFR 20. 1003 defines a survey as an evaluation of radiological conditions and potential hazards incident to the production, use, transfer, release, disposal, or presence of radioactive material or other sources of radiation. |
| | 10 CFR 20.1201 requires, in part, each licensee to control the occupational dose to individual adults to 5 rems for the total effective dose equivalent or (to) 50 rems for the sum of the deep-dose equivalent and the committed dose equivalent to any individual organ or tissue other than the lens of the eye. |
| | Contrary to the above, the licensee did not make or cause to be made surveys necessary to comply with 10 CFR 20.1201. Specifically, on April 30, May 30, and July 2, 1997, the licensee failed to perform evaluations of the radiological hazards that could have been present when four individuals were identified to have potentially taken radioactive material internally. |
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| Letter dated December 18, 1997, B Murray (NRC)to JV Parrish (SS),"NRC Inspection Report 50-397/97-19" The Supply System's response to the Notice Of Violation, pursuant to the provisions of Section 2.201, Title 10, Code of Federal Regulations, is enclosed as Attachment A.We acknowledge the additional concerns that were identified in the inspection report and the Supply System is taking steps to address the issues.Should you have any questions or desire additional information regarding this matter, please call Mr.PJ Inserra at (509)377-4147.PR is Vi resident, Nuclear Operations Mail Drop PE23 Attachment cc: EW Merschoff-NRC RIV KE Perkins, Jr.-NRC RIV, WCFO C Poslusny, Jr.-NRR 980i290057 980ii9 PDR ADGCK 05000397 8 PDR NRC Sr.Resident Inspector-927N DL Williams-BPA/399 PD Robinson-Winston&Strawn IIIIIIIIIIIIIIIIIIIIIIIIIIIIIIIIIIIIIIII RESPONSE TO NOTICE OF VIOLATION IN INSPECTION REPORT 50-397/97-19 Appendix A Page 1 of 3 RESTATEMENT F VI LATION A Technical Specification 5.7.2.a requires, in part, that each entryway to high radiation areas with dose rates greater than 1.0 rem/hour (at 30 centimeters from the radiation source or from any surface penetrated by the radiation) be provided with a locked door, gate, or guard that prevents unauthorized entry.Contrary to the above, on October 6, 1997, an entryway to the radwaste liner storage room on the 437-foot elevation of the radwaste building, an area with dose rates greater than 1.0 rem/hour (at 30 centimeters from the radiation source or from any surface penetrated by the radiation) was not provided with a locked door, gate, or guard that prevented unauthorized entry.This is a Severity Level IV violation (Supplement IV)(50-397/9719-01).
| | RESPONSE TO NOTICE OF VIOLATIONIN INSPECTION REPORT 50-397/97-19 Appendix A Page3 of 3 This is a Severity Level IV violation (Supplement IV) (50-397/971942). |
| R P N ET VI LATI N The Supply System accepts the violation.
| | R P NET VI LATI N The Supply System accepts the violation. |
| REA N F RVI LATI N The Supply System agrees with the staff's characterization of the reason for this event given in the Report Details section of Inspection Report 50-397/97-19.
| | REA N F RVI LATI N The Supply System agrees with the staff's characterization of the reason for this event given in the Report Details section of Inspection Report 50-397/97-19. |
| The failure to properly secure a chain link gate to a high high radiation area (HHRA)was caused by human error on the part of a health physics technician.
| |
| One condition that contributed to the event was the failure to perform a timely independent verification of the door's locked status.A second contributing condition was the use of a chain to secure the gate, rather than permanently installed padeyes.RRE A N TAKEN AND R TS A HIEVED Upon identification of the event a health physics technician responded, visually verified the area to be clear of personnel and immediately locked the gate.A walk-down was performed to verify the locked status of all other similar areas.No other doors were found to be improperly secured.An additional walk-down was performed by Health Physics to identify any other HHRA or high radiation areas that were secured by means of chain and padlocks.One additional door (access hatch to the wetwell)was found to be secured in this manner.Supply System staff determined that this hatch did not require a padeye as it is bolted and secured with a heavy chain and padlock.
| |
| RESPONSE TO NOTICE OF VIOLATION IN INSPECTION REPORT 50-397/97-19 Appendix A Page 2 of 3 A work request was issued to install lockable padeyes on the gate to the radwaste liner storage room on the 437'levation of the radwaste building.Work was completed December 10, 1997, Lessons learned from the event were discussed and documented in Health Physics Technician Continuing Training.This training was completed December 22, 1997.The appropriate plant procedure was revised on December 15, 1997 to require performance of independent verification in a timely manner.Appropriate personnel actions were taken with the health physics technician who failed to properly secure the gate.RRE TEP T BETAKENT AV IDF EVI LATI N All corrective actions have been completed.
| |
| DATE F L MPLIAN E The gate was immediately locked on October 6, 1997 upon identification of the event.R TATEMENT F VI LATI NB 10 CFR 20.1501(a)requires, in part, that each licensee make or cause to be made surveys that may be necessary for the licensee to comply with the regulations in 10 CFR Part 20 and are reasonable to evaluate the quantities of radioactive material and the potential radiological hazards that could be present.10 CFR 20.1003 defines a survey as an evaluation of radiological conditions and potential hazards incident to the production, use, transfer, release, disposal, or presence of radioactive material or other sources of radiation.
| |
| 10 CFR 20.1201 requires, in part, each licensee to control the occupational dose to individual adults to 5 rems for the total effective dose equivalent or (to)50 rems for the sum of the deep-dose equivalent and the committed dose equivalent to any individual organ or tissue other than the lens of the eye.Contrary to the above, the licensee did not make or cause to be made surveys necessary to comply with 10 CFR 20.1201.Specifically, on April 30, May 30, and July 2, 1997, the licensee failed to perform evaluations of the radiological hazards that could have been present when four individuals were identified to have potentially taken radioactive material internally.
| |
| RESPONSE TO NOTICE OF VIOLATION IN INSPECTION REPORT 50-397/97-19 Appendix A Page3 of 3 This is a Severity Level IV violation (Supplement IV)(50-397/971942). | |
| R P NET VI LATI N The Supply System accepts the violation. | |
| REA N F RVI LATI N The Supply System agrees with the staff's characterization of the reason for this event given in the Report Details section of Inspection Report 50-397/97-19. | |
| Briefly restated, the requirement to provide whole-body counts to personnel found with facial contamination was not clearly stated in the appropriate plant procedure. | | Briefly restated, the requirement to provide whole-body counts to personnel found with facial contamination was not clearly stated in the appropriate plant procedure. |
| RR A N TAKEN AND R T A HIEVED Health Physics performed a comprehensive review of 1997 logs and determined that a total of six individuals with facial contamination were not immediately given whole-body counts.These individuals were contacted and whole-body counts were performed. | | RR A N TAKEN AND R T A HIEVED Health Physics performed a comprehensive review of 1997 logs and determined that a total of six individuals with facial contamination were not immediately given whole-body counts. These individuals were contacted and whole-body counts were performed. No internal contamination was identified. |
| No internal contamination was identified. | | The appropriate plant procedure was revised January 8, 1998 to clearly state the requirement that personnel found with facial contamination will receive a whole-body count. |
| The appropriate plant procedure was revised January 8, 1998 to clearly state the requirement that personnel found with facial contamination will receive a whole-body count.TEP T BETAKENTOAV IDF EVI LATI N A review of the procedure will be incorporated into the Health Physics Quarterly Continuing Training to be completed by February 20, 1998.DATE F F L MPLIAN E Full compliance was achieved by December 5, 1997 when affected personnel received whole-body counts.}} | | TEP T BETAKENTOAV IDF EVI LATI N A review of the procedure will be incorporated into the Health Physics Quarterly Continuing Training to be completed by February 20, 1998. |
| | DATE F F L MPLIAN E Full compliance was achieved by December 5, 1997 when affected personnel received whole-body counts.}} |
|
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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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CATEGORY j.
REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)
ACCESSION NBR:9801290057 DOC.DATE: 98/01/19 NOTARIZED: NO DOCKET FACIL:50-397 WPPSS Nuclear Project, Unit 2, Washington Public Powe 05000397 AUTH. NAME AUTHOR AFFILIATION BEMIS,P.R. Washington Public Power Supply System RECIP.NAME RECIPIENT AFFILIATION Document Control Branch (Document Control Desk)
SUBJECT:
Responds to NRC 971218 ltr re violations noted in insp rept 50-397/97-17.Corrective actions: technician visually verified area to be clear of personnel & immediately locked gate &
performed walkdown to verify locked status of similar are s.
DISTRIBUTION CODE: IEOID COPIES RECEIVED:LTR ( ENCL t SIZE:
TITLE: General (50 Dkt)-Insp Rept/Notice of Violation Response E
NOTES:
RECIPIENT COPIES RECIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL PD4-2 PD 1 1 POSLUSNY,C 1 1 R
INTERNAL: ACRS 2 2 AEOD/SPD/RAB 1 1 AEOD 1 1 DEDRO 1 1 ILE CENTER 1 1 NRR/DRCH/HHFB 1 1 NRR DRPM/PECB 1 1 NRR/DRPM/PERB 1 1 NUDOCS-ABSTRACT 1 1 OE DIR 1 1 OGC/HDS3 1 1 RGN4 FILE 01 1 1 TERNAL: LITCO BRYCE,J H 1 1 NOAC 1 1 NRC PDR 1 1 NUDOCS FULLTEXT 1 1 D 0
U N
NOTE TO ALL "RIDS" RECIPIENTS:
PLEASE HELP US TO REDUCE WASTE. TO HAVE YOUR NAME OR ORGANIZATION REMOVED FROM DISTRIBUTION LISTS OR REDUCE THE NUMBER OF COPIES RECEIVED BY YOU OR YOUR ORGANIZATION, CONTACT THE DOCUMENT CONTROL DESK (DCD) ON EXTENSION 415-2083 TOTAL NUMBER OF COPIES REQUIRED: LTTR 19 ENCL 19
WASHIV>GTON PUBLIC POWER SUPPI.Y SYSTElvf I? O. Iiox 968 ~ Ri~%hniil, 11'ashiiigtow 99352-0968 January 19, 1998 G02-98-011 Docket No. 50-397 U.S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 Gentlemen:
Subjec't: WNP-2, OPERATING LICENSE NPF-21 NRC INSPECTION REPORT 97-19, RESPONSE TO NOTICE OF VIOLATION
Reference:
Letter dated December 18, 1997, B Murray (NRC) to JV Parrish (SS), "NRC Inspection Report 50-397/97-19" The Supply System's response to the Notice Of Violation, pursuant to the provisions of Section 2.201, Title 10, Code of Federal Regulations, is enclosed as Attachment A.
We acknowledge the additional concerns that were identified in the inspection report and the Supply System is taking steps to address the issues.
Should you have any questions or desire additional information regarding this matter, please call Mr. PJ Inserra at (509) 377-4147.
PR is Vi resident, Nuclear Operations Mail Drop PE23 Attachment cc: EW Merschoff - NRC RIV NRC Sr. Resident Inspector - 927N KE Perkins, Jr. - NRC RIV, WCFO DL Williams - BPA/399 C Poslusny, Jr. - NRR PD Robinson - Winston & Strawn 980i290057 980ii9 IIIIIIIIIIIIIIIIIIIIIIIIIIIIIIIIIIIIIIII PDR ADGCK 05000397 8 PDR
RESPONSE TO NOTICE OF VIOLATIONIN INSPECTION REPORT 50-397/97-19 Appendix A Page 1 of 3 RESTATEMENT F VI LATIONA Technical Specification 5.7.2.a requires, in part, that each entryway to high radiation areas with dose rates greater than 1.0 rem/hour (at 30 centimeters from the radiation source or from any surface penetrated by the radiation) be provided with a locked door, gate, or guard that prevents unauthorized entry.
Contrary to the above, on October 6, 1997, an entryway to the radwaste liner storage room on the 437-foot elevation of the radwaste building, an area with dose rates greater than 1.0 rem/hour (at 30 centimeters from the radiation source or from any surface penetrated by the radiation) was not provided with a locked door, gate, or guard that prevented unauthorized entry.
This is a Severity Level IV violation (Supplement IV) (50-397/9719-01).
R P N ET VI LATI N The Supply System accepts the violation.
REA N F RVI LATI N The Supply System agrees with the staff's characterization of the reason for this event given in the Report Details section of Inspection Report 50-397/97-19.
The failure to properly secure a chain link gate to a high high radiation area (HHRA) was caused by human error on the part of a health physics technician. One condition that contributed to the event was the failure to perform a timely independent verification of the door's locked status. A second contributing condition was the use of a chain to secure the gate, rather than permanently installed padeyes.
RRE A N TAKEN AND R TS A HIEVED Upon identification of the event a health physics technician responded, visually verified the area to be clear of personnel and immediately locked the gate. A walk-down was performed to verify the locked status of all other similar areas. No other doors were found to be improperly secured.
An additional walk-down was performed by Health Physics to identify any other HHRA or high radiation areas that were secured by means of chain and padlocks. One additional door (access hatch to the wetwell) was found to be secured in this manner. Supply System staff determined that this hatch did not require a padeye as it is bolted and secured with a heavy chain and padlock.
RESPONSE TO NOTICE OF VIOLATIONIN INSPECTION REPORT 50-397/97-19 Appendix A Page 2 of 3 A work request was issued to install lockable padeyes on the gate to the radwaste liner storage room on the 437'levation of the radwaste building. Work was completed December 10, 1997, Lessons learned from the event were discussed and documented in Health Physics Technician Continuing Training. This training was completed December 22, 1997.
The appropriate plant procedure was revised on December 15, 1997 to require performance of independent verification in a timely manner.
Appropriate personnel actions were taken with the health physics technician who failed to properly secure the gate.
RRE TEP T BETAKENT AV IDF EVI LATI N All corrective actions have been completed.
DATE F L MPLIAN E The gate was immediately locked on October 6, 1997 upon identification of the event.
R TATEMENT F VI LATI NB 10 CFR 20. 1501(a) requires, in part, that each licensee make or cause to be made surveys that may be necessary for the licensee to comply with the regulations in 10 CFR Part 20 and are reasonable to evaluate the quantities of radioactive material and the potential radiological hazards that could be present.
10 CFR 20. 1003 defines a survey as an evaluation of radiological conditions and potential hazards incident to the production, use, transfer, release, disposal, or presence of radioactive material or other sources of radiation.
10 CFR 20.1201 requires, in part, each licensee to control the occupational dose to individual adults to 5 rems for the total effective dose equivalent or (to) 50 rems for the sum of the deep-dose equivalent and the committed dose equivalent to any individual organ or tissue other than the lens of the eye.
Contrary to the above, the licensee did not make or cause to be made surveys necessary to comply with 10 CFR 20.1201. Specifically, on April 30, May 30, and July 2, 1997, the licensee failed to perform evaluations of the radiological hazards that could have been present when four individuals were identified to have potentially taken radioactive material internally.
RESPONSE TO NOTICE OF VIOLATIONIN INSPECTION REPORT 50-397/97-19 Appendix A Page3 of 3 This is a Severity Level IV violation (Supplement IV) (50-397/971942).
R P NET VI LATI N The Supply System accepts the violation.
REA N F RVI LATI N The Supply System agrees with the staff's characterization of the reason for this event given in the Report Details section of Inspection Report 50-397/97-19.
Briefly restated, the requirement to provide whole-body counts to personnel found with facial contamination was not clearly stated in the appropriate plant procedure.
RR A N TAKEN AND R T A HIEVED Health Physics performed a comprehensive review of 1997 logs and determined that a total of six individuals with facial contamination were not immediately given whole-body counts. These individuals were contacted and whole-body counts were performed. No internal contamination was identified.
The appropriate plant procedure was revised January 8, 1998 to clearly state the requirement that personnel found with facial contamination will receive a whole-body count.
TEP T BETAKENTOAV IDF EVI LATI N A review of the procedure will be incorporated into the Health Physics Quarterly Continuing Training to be completed by February 20, 1998.
DATE F F L MPLIAN E Full compliance was achieved by December 5, 1997 when affected personnel received whole-body counts.
