Letter Sequence Other |
---|
|
|
MONTHYEARML20195E4071998-11-16016 November 1998 Discusses 970522 Request That NRC Reconsider Conclusions in SE ,on EP Change 28.001.95 for Plant,Unit 1.Board Affirmation of Findings of NRC SE in EP Change 28.001-95 Decreased Effectiveness of Plan Project stage: Other 1998-11-16
[Table View] |
|
---|
Category:CORRESPONDENCE-LETTERS
MONTHYEARML20217F8911999-10-13013 October 1999 Forwards Copy of FEMA Region IV Final Rept for 990623-24, Grand Gulf Nuclear Station Exercise.Rept Indicates No Deficiencies or Areas Requiring Corrective Action Identified During Exercise ML20216J8891999-10-0404 October 1999 Forwards Details of Existing Procedural Guidance & Planned Administrative Controls.Util Respectfully Requests NRC Review & Approval of Changes by 991020.Date Will Permit to Implement Changes & Realize Full Benefit During Refueling ML20217B0361999-10-0404 October 1999 Refers to Investigation Conducted by NRC OI Re Activities at Grand Gulf Nuclear Station.Investigation Conducted to deter- Mine Whether Security Supervisor Deliberately Falsified Unescorted Access Authorizations.Allegation Unsubstantiated ML20212J8151999-09-29029 September 1999 Forwards Insp Rept 50-416/99-12 on 990725-0904.One Violation Noted & Being Treated as Noncited Violation.Licensee Conduct of Activities at Grand Gulf Facility Characterized by Safety Conscious Operations,Sound Engineering & Maint Practices ML20216J6811999-09-28028 September 1999 Ack Receipt of ,Transmitting Rev 31 to Physical Security Plan for GGNS Under Provisions of 10CFR50.54(p). NRC Approval Not Required,Based on Determination That Changes Do Not Decrease Effectiveness & Limited Review ML20212J7361999-09-28028 September 1999 Forwards Insp Rept 50-416/99-11 on 990830-0903.No Violations Noted.Purpose of Insp to Review Solid Radioactive Waste Management & Radioactive Matl Transportation Programs ML20212J5321999-09-27027 September 1999 Forwards Insp Rept 50-416/99-14 on 990830-0903.No Violations Noted.Inspectors Determined That Radioactive Waste Effluent Releases Properly Controlled,Monitored & Quantified ML20216J7101999-09-26026 September 1999 Forwards NRC Form 536,in Response to NRC Administrative Ltr 99-03, Preparation & Scheduling of Operator License Examinations ML20216J8141999-09-26026 September 1999 Forwards Proprietary Renewal Applications for Licensed Operators for Wk Gordon & SA Elliott at Grand Gulf Nuclear Station.Proprietary Info Withheld ML20212F5521999-09-23023 September 1999 Forwards SER Accepting Util Analytical Approach for Ampacity Derating Determinations at Grand Gulf Nuclear Station,Unit 1 & That No Outstanding Ampacity Derating Issues as Identified in GL 92-08 Noted ML20212D9211999-09-16016 September 1999 Informs That NRC Staff Completed Midcycle PPR of GGNS on 990818 & Identified No Areas in Which Licensee Performance Warranted Insp Beyond Core Insp Program.Details of Insp Plan Through March 2000 Encl ML20212A9331999-09-13013 September 1999 Forwards Partially Withheld Insp Rept 50-416/99-15 on 990816-20 (Ref 10CFR73.21).One Violation of NRC Requirements Occurred & Being Treated as Ncv,Consistent with App C of Enforcement Policy ML20211P7631999-09-10010 September 1999 Discusses Staff Issuance of SECY-99-204, Kaowool & FP-60 Fire Barriers at Plant.Proposed Meeting to Discuss Subj Issues Will Take Place in Oct or Nov 1999 ML20212A6951999-09-0909 September 1999 Requests That Licensees Affected by Kaowool Fire Barriers Take Issue on Voluntary Initiative & Propose Approach for Resolving Subj Issues.Staff Plans to Meet with Licensees to Discuss Listed Topics ML20212A8341999-09-0909 September 1999 Requests That Licensees Affected by Kaowool Fire Barriers Take Issue on Voluntary Initiative & Propose Approach for Resolving Subj Issues.Staff Plans to Meet with Licensees to Discuss Listed Topics ML20211Q3471999-09-0909 September 1999 Forwards Federal Emergency Mgt Agency Final Rept for 990623 Plant Emergency Preparedness Exercise.No Deficiencies Noted & One Area Requiring Corrective Action Identified ML20211Q3091999-09-0909 September 1999 Forwards Safety Evaluation Accepting BWROG Rept, Prediction of Onset of Fission Gas Release from Fuel in Generic BWR, Dtd July 1996 ML20211Q4861999-09-0808 September 1999 Informs That Util Has Discovered Dose Calculation Utilized non-conservative Geometry Factor for Parameter.Calculation Error Being Evaluated in Accordance with Corrective Action Program ML20211Q0091999-09-0808 September 1999 Forwards Request for Addl Info Re Individual Plant Exam of External Events for Grand Gulf Nuclear Station,Unit 1. Response Requested by 000615 ML20211N4301999-09-0808 September 1999 Discusses Proposed Meeting to Discuss Kaowool Fire Barriers. Staff Requesting That Affected Licensees Take Issue on Voluntary Initative & Propose Approach for Resolving Issues ML20211P4171999-09-0707 September 1999 Ack Receipt of ,Which Transmitted Addendum to Rev 30 to Physical Security Plan for Ggns,Per 10CFR50.54(p).NRC Approval Is Not Required,Since Util Determined That Changes Do Not Decrease Effectiveness of Plan ML20211P4121999-09-0707 September 1999 Requests NRC Staff Review & Approval of Integrated Nuclear Security Plan (Insp) & Integrated Security Training & Qualification Plan (Ist&Q), for Use by All Entergy Operations,Inc.Encl Withheld,Per 10CFR2.790(d) ML20211K6061999-08-31031 August 1999 Informs That Plant Has No Candidates to Take 991006 Generic Fundamentals Exam ML20211K5641999-08-31031 August 1999 Forwards Rev 39 to Grand Gulf Nuclear Station Emergency Plan Non-Safety Related, IAW 10CFR50,App E,Section V. Changes Do Not Decrease Effectiveness of Plan & Continues to Meets Stds of 10CFR50.47(b) & Requirements of App E ML20211J2321999-08-26026 August 1999 Advises That Info Contained in to Support NRC Review of GE Rept, Prediction of Onset of Fission Gas Release from Fuel in Generic BWR, Will Be Withheld from Public Disclosure ML20211J3761999-08-25025 August 1999 Corrected Ltr Informing That Info Provided (on Computer Disk & in Ltr to Ineel ) Marked as Proprietary Will Be Withheld from Public Disclosure Per 10CFR2.790(b)(5) & Section 103(b) of AEA of 1954,as Amended.Corrected 990827 ML20211F4881999-08-25025 August 1999 Advises That Info Submitted by 990716 Application & Affidavit Containing Diskette & to Ineel Mareked Proprietary Will Be Withheld from Public Disclosure,Per 10CFR2.790(b)(5) & Section 103(b) of AEA of 1954 ML20211F7751999-08-24024 August 1999 Forwards Insp Rept 50-416/99-10 on 990809-13.No Violations Noted.Insp Covered Licensed Operator Requalification Program & Observations of Requalification Activities ML20211C4381999-08-20020 August 1999 Forwards Rev 31 to Physical Security Plan for Protection of Grand Gulf Nuclear Station,Iaw 10CFR50.54(p).Util Has Determined That Rev Does Not Decrease Effectiveness of Plan. Encl Withheld,Per 10CFR73.21 ML20211C5101999-08-19019 August 1999 Forwards Certified Copies of Liability Insurance Policy Endorsements Issued in First Half of 1999 for Each Entergy Operations,Inc Nuclear Unit,Per 10CFR140.15 ML20211B3761999-08-16016 August 1999 Submits Voluntary Response to NRC AL 99-02, Operating Reactor Licensing Actions Estimates, for Fys 2000 & 2001, 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 ML20211A9481999-08-12012 August 1999 Informs of Completion of Analysis of Heat Transfer in Cooler During Fan Coast Down & Concludes That Potential Exists for Steam Foundation,Under Conditions Where Dcw Sys Flow Is Lost Prior to Full Isolation Valve Closure ML20210P8411999-08-0909 August 1999 Forwards Insp Rept 50-416/99-09 on 990613-0724.No Violations Noted.Activities at Facility Generally Characterized by safety-conscious Operations,Sound Engineering & Maint Practices & Careful Radiological Work Controls ML20210N6401999-08-0303 August 1999 Informs That Eighteeen Identified Penetrations Will Be Restored to Conformance with Licensing Requirements Prior to Restart from RFO10,scheduled for Fall 1999,per GL 96-06. Example of Piping Analysis Being Performed,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 ML20210K1951999-07-30030 July 1999 Forwards Insp Rept 50-416/99-03 on 990405-08 & 0510-11.No Violations Identified ML20211K7491999-07-30030 July 1999 Forwards Ltr Rept Documenting Work Completed Under JCN-W6095,analyses Performed at Ineel to Calculate Minimum Time to Fuel Pin Failure in Boiling Water Reactors (BWR) ML20210K6661999-07-29029 July 1999 Forwards Fitness for Duty Program Performance six-month Rept for Period Covering Jan-June 1999,per 10CFR26.71 ML20210F3591999-07-26026 July 1999 Forwards Proprietary Version & Redacted Version of Wyle Test Rept M-J5.08-Q1-45161-0-8.0-1-0,re Pressure Locking & Thermal Binding Test Program.Proprietary Version Withheld ML20210E3251999-07-23023 July 1999 Forwards Insp Rept 50-416/99-07 on 990622-25.No Violations Noted.Emergency Plan & Procedures During Biennial Emergency Preparedness Exercise Was Conducted ML20210D2401999-07-21021 July 1999 Informs of Resignation of Operator WE Griffith,License OP-20806-1,from Entergy Operations,Inc ML20209J0311999-07-16016 July 1999 Forwards Proprietary Info Supporting Review of Generic Alternate Source Term Request.Proprietary Info Withheld Per 10CFR2.790 ML20209G4791999-07-15015 July 1999 Forwards Proposed Emergency Plan Change as Addendum to Changes Previously Submitted Via GNRO-98/00028 & GNRO-99/00007,for NRC Review & Approval ML20210B1031999-07-15015 July 1999 Forwards Insp Rept 50-416/99-08 on 990502-0612.Determined That Three Severity Level IV Violations Occurred & Being Treated as Noncited Violations ML20210H3211999-07-14014 July 1999 Forwards Proprietary Info Supporting Review of 970506 Submittal of BWROG Rept, Prediction of Onset of Fission Gas Release from Fuel in Generic Bwr. Proprietary Info Withheld Per 10CFR2.790 ML20209D7511999-07-0909 July 1999 Responds to RAI on GL 92-01,rev 1,suppl 1, Rv Structural Integrity. as Result of NRC Review of Util Responses,Info Revised in Rvid & Rvid Version 2 Will Be Released ML20209D7671999-07-0101 July 1999 Submits Response to Violations Noted in Insp Rept 50-416/99-02 on 990222-26 & 0308-12.Corrective Actions: Contractor Performance Has Been re-evaluated in Regards to UFSAR Reviews ML20196K4901999-07-0101 July 1999 Discusses Relief Requests PRR-E12-01,PRR-E21-01,PRR-E22-01, PRR-P75-01,PRR-P81-01,VRR-B21-01,VRR-B21-02,VRR-E38-01 & VRR-E51-01 Submitted by EOI on 971126 & 990218.SE Accepting Alternatives Proposed by Util Encl ML20196J5711999-06-30030 June 1999 Advises That Versions of Submitted Info in 990506 Application & Affidavit, Re Proposed Amend to Revise Ts,Marked Proprietary Will Be Withheld from Public Disclosure,Per 10CFR2.790(b)(5) & Section 103(b) of AEA 1999-09-09
[Table view] Category:OUTGOING CORRESPONDENCE
MONTHYEARML20217F8911999-10-13013 October 1999 Forwards Copy of FEMA Region IV Final Rept for 990623-24, Grand Gulf Nuclear Station Exercise.Rept Indicates No Deficiencies or Areas Requiring Corrective Action Identified During Exercise ML20217B0361999-10-0404 October 1999 Refers to Investigation Conducted by NRC OI Re Activities at Grand Gulf Nuclear Station.Investigation Conducted to deter- Mine Whether Security Supervisor Deliberately Falsified Unescorted Access Authorizations.Allegation Unsubstantiated ML20212J8151999-09-29029 September 1999 Forwards Insp Rept 50-416/99-12 on 990725-0904.One Violation Noted & Being Treated as Noncited Violation.Licensee Conduct of Activities at Grand Gulf Facility Characterized by Safety Conscious Operations,Sound Engineering & Maint Practices ML20216J6811999-09-28028 September 1999 Ack Receipt of ,Transmitting Rev 31 to Physical Security Plan for GGNS Under Provisions of 10CFR50.54(p). NRC Approval Not Required,Based on Determination That Changes Do Not Decrease Effectiveness & Limited Review ML20212J7361999-09-28028 September 1999 Forwards Insp Rept 50-416/99-11 on 990830-0903.No Violations Noted.Purpose of Insp to Review Solid Radioactive Waste Management & Radioactive Matl Transportation Programs ML20212J5321999-09-27027 September 1999 Forwards Insp Rept 50-416/99-14 on 990830-0903.No Violations Noted.Inspectors Determined That Radioactive Waste Effluent Releases Properly Controlled,Monitored & Quantified ML20212F5521999-09-23023 September 1999 Forwards SER Accepting Util Analytical Approach for Ampacity Derating Determinations at Grand Gulf Nuclear Station,Unit 1 & That No Outstanding Ampacity Derating Issues as Identified in GL 92-08 Noted ML20212D9211999-09-16016 September 1999 Informs That NRC Staff Completed Midcycle PPR of GGNS on 990818 & Identified No Areas in Which Licensee Performance Warranted Insp Beyond Core Insp Program.Details of Insp Plan Through March 2000 Encl ML20212A9331999-09-13013 September 1999 Forwards Partially Withheld Insp Rept 50-416/99-15 on 990816-20 (Ref 10CFR73.21).One Violation of NRC Requirements Occurred & Being Treated as Ncv,Consistent with App C of Enforcement Policy ML20211P7631999-09-10010 September 1999 Discusses Staff Issuance of SECY-99-204, Kaowool & FP-60 Fire Barriers at Plant.Proposed Meeting to Discuss Subj Issues Will Take Place in Oct or Nov 1999 ML20212A8341999-09-0909 September 1999 Requests That Licensees Affected by Kaowool Fire Barriers Take Issue on Voluntary Initiative & Propose Approach for Resolving Subj Issues.Staff Plans to Meet with Licensees to Discuss Listed Topics ML20211Q3471999-09-0909 September 1999 Forwards Federal Emergency Mgt Agency Final Rept for 990623 Plant Emergency Preparedness Exercise.No Deficiencies Noted & One Area Requiring Corrective Action Identified ML20211Q3091999-09-0909 September 1999 Forwards Safety Evaluation Accepting BWROG Rept, Prediction of Onset of Fission Gas Release from Fuel in Generic BWR, Dtd July 1996 ML20212A6951999-09-0909 September 1999 Requests That Licensees Affected by Kaowool Fire Barriers Take Issue on Voluntary Initiative & Propose Approach for Resolving Subj Issues.Staff Plans to Meet with Licensees to Discuss Listed Topics ML20211Q0091999-09-0808 September 1999 Forwards Request for Addl Info Re Individual Plant Exam of External Events for Grand Gulf Nuclear Station,Unit 1. Response Requested by 000615 ML20211N4301999-09-0808 September 1999 Discusses Proposed Meeting to Discuss Kaowool Fire Barriers. Staff Requesting That Affected Licensees Take Issue on Voluntary Initative & Propose Approach for Resolving Issues ML20211P4171999-09-0707 September 1999 Ack Receipt of ,Which Transmitted Addendum to Rev 30 to Physical Security Plan for Ggns,Per 10CFR50.54(p).NRC Approval Is Not Required,Since Util Determined That Changes Do Not Decrease Effectiveness of Plan ML20211J2321999-08-26026 August 1999 Advises That Info Contained in to Support NRC Review of GE Rept, Prediction of Onset of Fission Gas Release from Fuel in Generic BWR, Will Be Withheld from Public Disclosure ML20211J3761999-08-25025 August 1999 Corrected Ltr Informing That Info Provided (on Computer Disk & in Ltr to Ineel ) Marked as Proprietary Will Be Withheld from Public Disclosure Per 10CFR2.790(b)(5) & Section 103(b) of AEA of 1954,as Amended.Corrected 990827 ML20211F4881999-08-25025 August 1999 Advises That Info Submitted by 990716 Application & Affidavit Containing Diskette & to Ineel Mareked Proprietary Will Be Withheld from Public Disclosure,Per 10CFR2.790(b)(5) & Section 103(b) of AEA of 1954 ML20211F7751999-08-24024 August 1999 Forwards Insp Rept 50-416/99-10 on 990809-13.No Violations Noted.Insp Covered Licensed Operator Requalification Program & Observations of Requalification Activities 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 ML20210P8411999-08-0909 August 1999 Forwards Insp Rept 50-416/99-09 on 990613-0724.No Violations Noted.Activities at Facility Generally Characterized by safety-conscious Operations,Sound Engineering & Maint Practices & Careful Radiological Work Controls 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 ML20210K1951999-07-30030 July 1999 Forwards Insp Rept 50-416/99-03 on 990405-08 & 0510-11.No Violations Identified ML20210E3251999-07-23023 July 1999 Forwards Insp Rept 50-416/99-07 on 990622-25.No Violations Noted.Emergency Plan & Procedures During Biennial Emergency Preparedness Exercise Was Conducted ML20210B1031999-07-15015 July 1999 Forwards Insp Rept 50-416/99-08 on 990502-0612.Determined That Three Severity Level IV Violations Occurred & Being Treated as Noncited Violations ML20209D7511999-07-0909 July 1999 Responds to RAI on GL 92-01,rev 1,suppl 1, Rv Structural Integrity. as Result of NRC Review of Util Responses,Info Revised in Rvid & Rvid Version 2 Will Be Released ML20196K4901999-07-0101 July 1999 Discusses Relief Requests PRR-E12-01,PRR-E21-01,PRR-E22-01, PRR-P75-01,PRR-P81-01,VRR-B21-01,VRR-B21-02,VRR-E38-01 & VRR-E51-01 Submitted by EOI on 971126 & 990218.SE Accepting Alternatives Proposed by Util Encl ML20196J5811999-06-30030 June 1999 Advises That Version of Info Submitted in 990504 Application & Affidavit Re Engineering Rept ME-98-001-00,marked Proprietary Will Be Withheld from Public Disclosure,Per 10CFR2.790(b)(5) & Section 103(b) of AEA of 1954 as Amended ML20196J5711999-06-30030 June 1999 Advises That Versions of Submitted Info in 990506 Application & Affidavit, Re Proposed Amend to Revise Ts,Marked Proprietary Will Be Withheld from Public Disclosure,Per 10CFR2.790(b)(5) & Section 103(b) of AEA ML20195G3811999-06-0909 June 1999 Ack Receipt of ,Which Transmitted Emergency Plan Procedure 10-S-01-1,Rev 103,under Provisions of 10CFR50, App E,Section V ML20195G2971999-06-0909 June 1999 Ack Receipt of Re Emergency Plan Procedure 10-S-01-1,rev 104.No Violations Identified & Changes Subject to Insp to Confirm Effectiveness ML20195G3511999-06-0909 June 1999 Ack Receipt of 980831 & 1022 Ltrs,Which Transmitted Changes to Grand Gulf Emergency Plan,Rev 36 & 37,under Provisions of 10CFR50,App E,Section V ML20207D3351999-05-27027 May 1999 Forwards Insp Rept 50-416/99-05 on 990321-0501.Three Violations of NRC Requirements Occurred & Being Treated as non-cited Violations,Consistent with App C of Enforcement Policy ML20207A6961999-05-21021 May 1999 Forwards Insp Rept 50-416/99-06 on 990419-23.No Violations Noted.Determined That Fire Protection Program Was Implemented IAW Requirements of License & GL 86-10.One Unresolved Item Noted Re fire-induced Failures on Equipment ML20206U3851999-05-18018 May 1999 Forwards Insp Rept 50-416/99-02 on 990222-26 & 0308-12.Two Violations of NRC Requirements Identified & Being Treated as non-cited Violations,Consistent with App C of Enforcement Policy ML20207A7561999-05-17017 May 1999 Ack Receipt of Which Transmitted Exercise Scenario for Emergency Plan Exercise Scheduled for 990623. Some Parts of Exercise Scenario Package Not Submitted & Being Developed ML20206N3921999-05-11011 May 1999 Informs of Reorganization in NRR Ofc,Effective 990328. Organization Chart Encl ML20206K1261999-05-0707 May 1999 Informs That on 990407 NRC Administered Gfes of Written Operator Licensing Exam.Facility Did Not Participate in Exam.Copy of Master Exam with Answer Key Encl.Without Encl ML20206E0571999-04-29029 April 1999 Discusses EOI 960418 Request for License Amend for GGNS That Would Permit Addl Method of Fuel Movement & Loading in Core When Control Rods Removed.Determined That Insufficient Info Provided to Permit Completion of Review ML20206B0951999-04-23023 April 1999 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Rept 50-416/99-01 & NOV .Reply Found to Be Responsive to Concerns Raised in Nov.Implementation of C/As Will Be Reviewed in Future Insps ML20206B3601999-04-23023 April 1999 Forwards Insp Rept 50-416/99-04 on 990131-0320.Three Violations of NRC Requirements Identified & Being Treated as non-cited Violations Consistent with App C of Enforcement Policy ML20206E7661999-04-19019 April 1999 Submits Summary of 990415 Meeting Conducted in Port Gibson, Mi Re Results of Plant Performance Review Completed on 990211 & Transmitted on 990319.List of Attendees Encl ML20205N7251999-04-13013 April 1999 Forwards Summary of 990408 Meeting with EOI in Jackson, Mississippi Re EOI Annual Performance Assessment of Facilities & Other Issues of Mutual Interest.List of Meeting Attendees & Licensee Presentation Slides Encl ML20205M9421999-04-13013 April 1999 Forwards Emergency Response Data System Implementation Documents.Data Point Library Updates for Kewaunee (271), San Onofre (272) & Clinton (273) Encl.Also Encl Plant Attribute Library Update for Grand Gulf (274).Without Encls IR 05000416/19980131999-04-0606 April 1999 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Rept 50-416/98-13 .Discussions on 990330 Resulted in Addl C/A Commitments to Address Violation Re Onsite Investigation ML20205J1051999-03-29029 March 1999 Forwards Objectives for Plant,Unit 1 1999 FEMA Emergency Plan Exercise Scheduled for 990623 ML20205E8701999-03-19019 March 1999 Advises of Completion of Plant Performance Review on 990211 to Develop Integrated Understanding of Safety Performance. Overall Performance Acceptable.Isolated Examples of Failure to Follow Procedures Noted ML20207L3621999-03-0303 March 1999 Advises That Effective 990217,NRC Project Mgt Responsibilities for Grand Gulf Nuclear Station Transferred to Sp Sekerak 1999-09-09
[Table view] |
Text
- . _ . _ . _ _ . . . _ _ _ _ _ .
a..g l t UNITED STATES s* ; NUCLEAR REGULATORY COMMISSION
. WASHINGTON, D.C. ace 86 00M j g
- November 16, 1998 Mr. William A. Eaton -
Vice President, Operations GGNS Entergy Operations, Inc.
! P. O. Box 756 Port Gibson, MS 39150
SUBJECT:
APPEAL MEETING FOR EMERGENCY PLAN CHANGE 28.001-95 FOR GRAND GULF NUCLEAR STATION, UNIT 1 (TAC NO. M99124)
Dear Mr. Eaton:
i i
! In a letter dated May 22,1997 (GNRO-97/00048), Entergy Operations, Incorporated (the l licensee) requested that the Nuclear Regulatory Commission (NRC) reconsider its conclusions l In its Safety Evaluation (SE), dated December 11,1996, on Emergency Plan (EP) change
- 28.001.95 for the Grand Gulf Nuclear Station, Unit 1, (GGNS). The NRC staff concluded in the SE that change 28.001.95 decreased the effectiveness of the GGNS Emergency Plan, and, in l- accordance with 10 CFR 50.54(q), should not have been implemented without prior staff review and approval. This SE was transmitted to GGNS in a letter dated April 24,1997. The licensee's May 22,1997, letter also contained information to justify its position.
L The' NRC convened an appeal board (the Board) on July 10,1997, to hear the licensee's position to determine whether reconsideration was warranted; a summary of the Board meeting was issued on July 17,1997. In letters dated September 5, and December 9,1997 (GNRO-97/00086 and GNRO-97/00118, respectively), the licensee provided additional information to address issues raised by the Board and, subsequently thereafter, in response to staff concems.
l This transmits the Board's affirmation of the findings of the NRC safety evaluation in that EP change 28.001-95 decreased the effectiveness of the plan. The bases and the events leading up to this conclusion are described below.
l The Board meeting with the licensee revealed certain ambiguities in the staffing of the EP that the licensee addressed in its letters of September 5 and December 9,1997. These ambiguities
- prevented the resolution of the technicalissues raised by the licensee in its letter of May 22, l 1997, and during the meeting of July 10,1997, and these issues were discussed at a meeting of the Board with the staff when the staff reported back to the Board on the letters of September 5 and December 9,1997. This Board-staff meeting focused on the technicalissues involving the use of technology to replace two (2) 30-minute health physics (HP) technician responders as described in the emergency plan. At that meeting, the Board requested that a l survey be made of the radiation protection and emergency preparedness staffs in headquarters and the regions to establish a consensus to determine whether the replacement of HP technicians by the use of technology in the early phase of an accident is an adequate attemative approach. The Board sought to determine whether technological advances and experience in the use of the technology were sufficient to warrant a change to the NRC position. The conclusion derived from that sun /ey is that the use of electronic dosimeters (EDs) and area radiation monitors (ARMS) cannot replace the two 30-minute HP technician I l
' g responders. In providing its position to the Board, the staff also evaluated the information ,
n
, e s P [.*;
9811180334 981116
[. .No h
. -(
. William A. Eaton 2 presented by the licensee to assure that the rationale used by the licensee was considered before the staff finalized its recommendation to the Board.
In its May 22,1997, letter, the licensee identified the following reasons for eliminating the two 30-minute HP technician responders:
. Automated access control
. On-shift personnel provide HP coverage
. Minimal HP involvement required for personnel monitoring
. Dosimetry self-issued by workers
. - Additional on-shift staff available for HP support.
Network of area radiation monitors Access control involves safety decisions to permit personnel into radiological areas, managing the activities of personnel in radiological areas, establishing control areas to prevent the spread of contamination, and providing appropriate dosimetry for personnel. Under normal plant operating conditions, access control may be automated because radiological conditicas are established before permitting personnel into a hazardous environment and conditions are monitored before releasing personnel. Issuing radiation work permits, establist ing barriers, step off pads, etc. are essential to an effective access control program; these s etivities require personnel even during normal operating conditions. Under accident conditions, where conditions may not be well established, HP staff are required to ensure that persannel are not subject to undue risk. Access controlis substantively more than just logging persennelinto radiological areas and providing dosimetrv Staffing was discussed in great depth with the licensee at the Board meeting and in subsequent phone calls; the licensee stated that the contingent of on-shift personnel exceeded minimum requirements. Nevertheless, the staff identified discrepancies in the emergency organization described in the GGNS EP. The staff determhed that a number of emergency workers were double-counted and given collateral responsibilities for handling several assignments simultaneously. The staffing scheme outlined in the emergency plan was confusing and ambiguous regarding the number of emergency responders; the licensee did not resolve this issue at the Board meeting. In subsequent discussions and in the submittals of September 5 and December 9,1997, the proposed licensee staffing-level changes were implemented and the staffing issues were resolved for the GGNS EP. The EP staffing levels in Table 5-1, EP shift staffing and augmentation capabilities, dated October 20,1997, that was submitted in the
~ December 9,1997, letter removed the double counting of emergency workers that had been incorporated in earlier versions of Table 5-1, and thus was an augmentation of previous staffing levels.
ARMS have been part of radiation protection programs for a long time and their use was
' considered when the minimum HP emergency organization staffing standard was developed initially. Recognition of the presence of these monitors does not provide a sufficient basis to
. Justify the reduction in the number of 30 minute HP technician responders. Unlike normal operations, where there is likely to be good correlation between ARMS and radiological conditions there may be an inappropriate reliance on ARMS under accidert conditions because
Wdliam A. Eaton 3 the magnitude and mix of radionuclides may be unknown and the spatial distribution of radioactive material may be highly variable.
The underlying principles associated with as low as is reasonably achievable (ALARA) for occupational exposure, even under accident conditions, would not permit workers to enter into a hazardous environment without recognition of the risk and an appropriate justification for worker exposure. The use of EDs to monitor and control radiation exposure provides additional advantages over thermoluminescent dosimeters and pocket dosimeters, however, EDs cannot 1 replace appropriate HP coverage where judgement is required for personnel safety. Only j recently have licensees relied on EDs as the primary dosimeter. Notwithstading improvements in the design, performance and fabrication of these devices, EDs have limitations. Reliance on EDs as the primary information source to preclude unnecessary worker exposure under accident conditions is not consistent with ALARA.
The licensee expected that there would be a human resource savings provided by workers obtaining their own dosimetry and performing their own monitoring as is evidenced under the current practice for normal operations. In addition to the foregoing discussion as the bases for the denial of reconsideration of the staff's conclusion in its SE dated December 11,1996, the licensee's practice in this specific area is a problem area. For example, in the letter dated October 9,1997, the Plant Support area of the latest SALP Report found a decrease in the SALP score from a "1" to a "2." The NRC noted that problems were identified in the radiation protection area: radiation workers were not wearing EDs and were not following established radiation protection procedures. These inspection findings alone do not advance the licensee's position that HPs are not needed because radiation workers can use electronic dosimeters and are trained in their use.
The Board affirms the findings of the NRC safety evaluation, issued to the licensee in the NRC letter dated April 24,1997, that EP change 28.001-95 decreased the effectiveness of the plan.
The Board considered the licensee's position outlined in its May 22,1997, letter and the representations made at the Board meeting on July 10,1997. The summary of the Board meeting dated July 17,1997, indicated that a limited number of issues required clarification to i be acceptable; the summary did not reflect the concern of the Board regarding the ambiguity in the emergency organization described in the cmergency plan and the assignment of collateral l duties. Nevertheless, in letters dated September 5, and December 9,1997, the licensee provided additional information to respond to the isst es covered in the summary of the meeting l and, subsequently thereafter, in response to staff cornerns. While the Board finds that i reconsideration of the staff's conclusion in its SE dateJ December 11,1996, is not warranted, it i is apparent to the Board that the licensee attempted to resolve the issues promptly and in good !
faith. The Board has directed the staff to proceed with closure of this proceeding and '
disposition of findings; however, the Board is receptive to the reconsidernon by the licensee of l its EP staffing commitments in its correspondence dated September 5, and December 9,1997, l had the staffing commitments been made under the presumption that the licensee would have prevailed on its position or that the licensee would have prevailed on appeal.
In the absence of an action by the licensee to continue this matter, the Board plans to dissolve within 30 days of the date of this letter.
4
i e l William A. Eaton 4
, This closes out the appeal meeting and your appeal of the staff's decision in its letter of April 24,1997, on EP change 28.001-95. This also closes out TAC M99124 on the appeal l
meeting. If you have any questions, contact me at 301-415-1307, or by "JND@NRC. GOV" on l the intemet.
Sincerely, l
i 13 4 h id Jack N. Donohew, Senior Project Manager
! Project Directorate IV-1 Division of Reactor Projects lil/IV Office of Nuclear Reactor Regulation Docket No. 50-416 i
cc: See next page l
l l
4 l
William A. Eaton 4 This closes out the appeal meeting and your appeal of the staff's decision in its letter of April 24,1997, on EP change 28.001-95. This also closes out TAC M99124 on the appeal meeting. If you have any questions, contact me at 301-415-1307, or by "JND@NRC. GOV" on the internet.
Sincerely, 1
N ND Jack N. Donohew, Senior Project Manager Project Directorate IV-1 Division of Reactor Projects Ill/IV Office of Nuclear Reactor Regulation Docket No. 50-416 cc: See next page DISTRIBUTION:
DechetfUi] PUBLIC PD4-1 r/f E. Adensam (EGA1) J.Donohew T. Gwynn, RIV ACRS OGC (15B18) C.Hawes J.Hannon C. Miller B. Zaleman L. Cohen J. Roe B. Murray, RIV Document Name: GG99124. APP *SEE PREVIOUS CONQURRENCE OFC PM/kD4h LA/PD4-1' BC/PERB* RIV\PSB D/ OS[ DD/DRPM NAME JDdeN CHaN CMiller SkuNaf JHannon f Jh DATE 19Y/98 /0/ k /98 10/07/98 II 2/ /98 h/N/98 ) h /98 II/ /98 COPY YES/NO YES/NO YES/NO - YES/NON YES/NO YES/NO OFFICIAL RECORD COPY q e-ns 6h llf 2- fd N
1
, ,.7 __._ _ .
i .
I l- Mr.' William A. Eaton
! Entergy Operations, Inc. Grand Gulf Nuclear Station cc:
Executive Vice President General Manager, GGNS
& Chief Operating Officer Entergy Operations, Inc.
Entergy Operations, Inc. P. O. Box 756 -
- P. O. Box 31995 Port Gibson, MS 39150
- Jackson, MS 39286-1995 Attorney General L Wise, Carter, Child & Caraway Department of Justice L P. O. Box 651 State of Louisiana Jackson, MS 39205 P. O. Box 94005 Baton Rouge, LA 70804-9005 Winston & Strawn 1400 L Street, N.W. - 12th Floor State Health Officer ;
l Washington, DC 20005-3502 State Board of Health P. O. Box 1700 Director Jackson, MS 39205 Division of Solid Waste Management Mississippi Department of Natural Office of the Govemor Resources State of Mississippi P. O. Box 10385 Jackson, MS 39201 Jackson, MS 39209 Attomey General l: Fresident, Asst. Attorney General l Claibome County Board of Supervisors State of Mississippi P. O. Box 339 P. O. Box 22947 Port Gibson, MS 39150 Jackson, MS 39225 Regional Administrator, Region IV Vice President, Operations Support l U.S. Nuclear Regulatory Commission Entergy Operations, Inc.
611 Ryan Plaza Drive, Suite 1000 P.O. Box 31995 Arlington,TX 76011 Jackson, MS 39286-1995 Senior Resident inspector Director, Nuclear Safety U. S. Nuclear Regulatory Commission and Regulatory Affairs l P. O. Box 399 Entergy Operations, Inc.
Port Gibson, MS 39150 P.O. Box 756 l- Port Gibson, MS 39150 i
l l
l i
i
. - -- . ..