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Category:CORRESPONDENCE-LETTERS
MONTHYEARML20217M8851999-10-0808 October 1999 Informs of Staff Determination That Listed Calculations Should Be Withheld from Public Disclosure,Per 10CFR2.790, as Requested in 990909 Affidavit ML20211J7731999-08-31031 August 1999 Forwards Insp Rept 50-312/99-03 on 990802-06.No Violations Noted.Insp Included Decommissioning & Dismantlement Activities,Verification of Compliance with Selected TS & Review of Completed SEs ML20211H7481999-08-13013 August 1999 Forwards Amend 126 to License DPR-54 & Safety Evaluation. Amend Changes Permanently Defueled Technical Specification (PDTS) D3/4.1, Spent Fuel Pool Level, to Replace Specific Reference to SFP Level Alarm Switches with Generic Ref 3F0799-22, Provides Update & Rev to Submittal Made by Util Ltr with Regard to EAL Classification Methodology for Unit 3.Reponses to NRC Staff Questions Provided as Attachment D to Ltr & Reflects Discussions Held1999-07-13013 July 1999 Provides Update & Rev to Submittal Made by Util Ltr with Regard to EAL Classification Methodology for Unit 3.Reponses to NRC Staff Questions Provided as Attachment D to Ltr & Reflects Discussions Held ML20210H9541999-07-0707 July 1999 Informs NRC of Change to Rancho Seco Decommissioning Schedule,As Described in Licensee Post Shutdown Decommissioning Activities Rept ML20209D2501999-06-24024 June 1999 Informs That Util Has Revised All Sections of Rancho Seco Emergency Plan (Rsep),Change 4,effective 990624 ML20196G0431999-06-22022 June 1999 Forwards Certified Copies of Listed Nuclear Liability Endorsements for Smud Rancho Seco Nuclear Generating Station ML20195D1851999-05-27027 May 1999 Forwards Rancho Seco Annual Rept, IAW Plant Permanently Defueled TS D6.9.4 & D6.9.6b.Rept Contains Shutdown Statistics,Narrative Summary of Shutdown Experience,Er Info & Tabulation of Facility Changes,Tests & Experiments ML20195B8511999-05-27027 May 1999 Forwards Change 4 to Rancho Seco Emergency Plan, Incorporating Commitments Made to NRC as Outlined in NRC .Emergency Plan Includes Two Listed Supporting Documents ML20207E9181999-05-27027 May 1999 Informs That Effective 990328,NRR Underwent Reorganization. within Framework of Reorganization,Div of Licensing Project Mgt Created.Reorganization Chart Encl ML20206U7411999-05-18018 May 1999 Provides Summary of 990217-18 Visit to Rancho Seco Facility to Become Familar with Facility,Including Onsite ISFSI & Meeting with Representatives of Smud to Discuss Issues Re Revised Rancho Seco Ep,Submitted to NRC on 960429 ML20206M1611999-05-10010 May 1999 Forwards Listed Proprietary Calculations to Support Review of Rancho Seco ISFSI Sar.Proprietary Encls Withheld ML20206E8591999-04-12012 April 1999 Provides Info Re High Total Coliform Result in Plant Domestic Sewage Effluent Prior to Confluence with Combined Effluent.Cause of High Total Coliform Result Was Broken Flow Rate Instrument.Instrument Was Repaired on 990318 ML20204H6751999-03-19019 March 1999 Forwards Insp Rept 50-312/99-02 on 990309-11.No Violations Noted.Portions of Physical Security & Access Authorization Programs Were Inspected ML20204E4031999-03-16016 March 1999 Submits Rept of Status of Decommissioning Funding for Rancho Seco,As Required by 10CFR50.75(f)(1).Plant Is Currently in Safstor, with Operating License Scheduled to Expire in Oct 2008 ML20204E6661999-03-11011 March 1999 Forwards Rancho Seco Exposure Rept for Individuals That Received Greater than 100 Mrem During 1998,IAW TS D6.9.2.2 & NRC Regulatory Guide 1.16 ML20204E6441999-03-11011 March 1999 Forwards Individual Monitoring Repts for Personnel That Required Radiation Exposure Monitoring During 1998 ML20207L1711999-03-10010 March 1999 Informs of Staff Determination That Supporting Calculations & Drawings Contained in Rev 2 of Sar, Should Be Withheld from Public Disclosure,Per 10CFR2.790 NL-99-002, Submits Info About Property Insurance for Rancho Seco Nuclear Generating Station,Iaw 10CFR50.54(w)(3)1999-03-10010 March 1999 Submits Info About Property Insurance for Rancho Seco Nuclear Generating Station,Iaw 10CFR50.54(w)(3) ML20207D4431999-03-0101 March 1999 Forwards Annual Radioactive Effluent Release Rept, for Rancho Seco Nuclear Generating Station for 1998 ML20207H6181999-02-18018 February 1999 Provides Attached Metrix & Two Copies of Rancho Seco ISFSI Sar,Rev 2 on Compact Disc,As Requested in 990209 Meeting. First Rounds of RAIs Dealt Primarily with Use of Cask as Storage Cask.Without Compact Disc ML20203D0761999-02-10010 February 1999 Ltr Contract:Task Order 37 Entitled, Technical Assistance in Review of New Safety Analysis Rept for Rancho Seco Spent Fuel Storage Facility, Under Contract NRC-02-95-003 ML20155D4431998-10-27027 October 1998 Forwards Amend 3 to Rancho Seco Dsar,Representing Updated Licensing Basis for Operation of Permanently Shutdown & Defueled Rancho Seco Nuclear Facility During Permanently Defueled Mode.With Instructions & List of Effective Pages NL-98-032, Forwards Certified Copies of Listed Nuclear Liability Endorsements for Util1998-09-30030 September 1998 Forwards Certified Copies of Listed Nuclear Liability Endorsements for Util ML20237A6031998-08-0707 August 1998 Forwards Insp Rept 50-312/98-03 on 980706-09.No Violations Noted ML20237A9481998-08-0303 August 1998 Forwards Smud 1997 Annual Rept, IAW 10CFR50.71(b),which Includes Certified Financial Statements ML20236Q9461998-07-15015 July 1998 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Rept 50-312/98-02 ML20236J6331998-06-30030 June 1998 Forwards Response to Violations Noted in Insp Rept 50-312/98-02.Corrective Actions:Util Revised RSAP-1003 to Clarify District Security Staff Responsibilities Re Handling & Review of Criminal History Info ML20236E8211998-06-0303 June 1998 Forwards Insp Rept 50-312/98-02 on 980519-21 & NOV Re Failure to Review & Consider All Info Obtained During Background Investigation.Areas Examined During Insp Also Included Portions of Physical Security Program ML20217G8391998-04-20020 April 1998 Forwards Copy of Rancho Seco Monthly Discharger Self-Monitoring Rept for Mar 1998 IR 05000312/19980011998-03-25025 March 1998 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Rept 50-312/98-01 on 980205 ML20217F1891998-03-18018 March 1998 Forwards Signed Original & Amend 7 to Rancho Seco Long Term Defueled Condition Physical Security Plan & Rev 4 to Long Term Defueled Condition Training & Qualification Plan.Encls Withheld,Per 10CFR2.790 ML20217G6661998-03-18018 March 1998 Forwards Discharge Self Monitoring Rept for Feb 1998, Which Makes Note of One Wastewater Discharge Permit Violation ML20217H0451998-03-18018 March 1998 Submits Rancho Seco Exposure Rept for Individuals Receiving Greater than 100 Mrem During 1997,per TS D6.9.2.2 & Guidance Contained in Reg Guide 1.16.No One Exposed to Greater than 100 Mrem in 1997 ML20216K1091998-03-11011 March 1998 Forwards NRC Form 5 Individual Monitoring Repts for Personnel Who Required Radiation Exposure Monitoring,Per 10CFR20.1502 During 1997.W/o Encl ML20217N9531998-03-0505 March 1998 Responds to Violations Noted in Insp Rept 50-312/98-01. Corrective Actions:Radiation Protection Group Wrote Potential Deviation from Quality (Pdq) 97-0082 & Assigned Radiation Protection Action to Determine Cause & CAs ML20203H7001998-02-25025 February 1998 Forwards Annual Radioactive Effluent Release Rept for Jan- Dec 1997, IAW 10CFR50.36a(a)(2) & TS D6.9.3.Revs to Radiological Environ Monitoring Manual & off-site Dose Calculation Manual,Encl ML20202G0131998-02-12012 February 1998 Forwards Certified Copies of Listed Nuclear Liability Endorsements & Master Worker Policy Certificate of Insurace for Facility NL-98-006, Submits Annual Rept of Property Insurance Levels for Rsngs, IAW 10CFR50.54(w)(3)1998-02-12012 February 1998 Submits Annual Rept of Property Insurance Levels for Rsngs, IAW 10CFR50.54(w)(3) ML20202C4641998-02-0505 February 1998 Forwards Insp Rept 50-312/98-01 on 980105-08 & Notice of Violation.Insp Included Decommissioning & Dismantlement Work Underway,Verification of Compliance W/Selected TS & Main & Surveillance Activities Associated W/Sfp ML20199A5881997-11-10010 November 1997 Responds to NRC Re Violations Noted in Insp Rept 50-312/97-01.Corrective Actions:Reviewed SFP Water Temp & Instrument Calibr Records,Generated Otr 97-001 to Document out-of-tolerance Instrument & Generated Pdq 97-0064 ML20198R9501997-11-0505 November 1997 Requests Interpretation of or Rev to NUREG-1536, Std Review Plan for Dry Cask Storage Sys, Re Compliance W/ 10CFR72.236(e) & 10CFR72.122(h)(4) for Dry Fuel Storage Casks ML20198K5391997-10-21021 October 1997 Forwards Insp Rept 50-312/97-04 on 970922-25 & Notice of Violation.Response Required & Will Be Used to Determine If Further Action Will Be Necessary ML20217D3101997-09-25025 September 1997 Forwards Update of 1995 Decommissioning Evaluation, for Rancho Seco Nuclear Generation Station & Annual Review of Nuclear Decommissioning Trust Fund for Adequacy Re Assumptions for Inflation & Rate of Return ML20211F0991997-09-23023 September 1997 Forwards One Certified Copy of Mutual Atomic Energy Liability Underwriters Nuclear Energy Liability Insurance Endorsement 120 for Policy MF-0075 for Smud Rancho Seco Nuclear Facility ML20198G8141997-08-22022 August 1997 Forwards Amend 125 to License DPR-54 & Safety Evaluation. Amend Permits Smud to Change TS to Incorporate Revised 10CFR20.Amend Also Revises References from NRC Region V to NRC Region IV ML20151L0281997-07-29029 July 1997 Provides Response to NRC Request for Addl Info Re TS Change,Relocating Administrative Controls Related to QA to Ufsar,Per NUREG-0737 ML20149E5031997-07-10010 July 1997 Second Partial Response to FOIA Request for Documents. Forwards Records Listed in App C Being Made Available in Pdr.Records in App D Already Available in PDR ML20148P5161997-06-30030 June 1997 Second Partial Response to FOIA Request for Documents.App B Records Being Made Available in PDR ML20141A1721997-06-17017 June 1997 Forwards Insp Rept 50-312/97-03 on 970603-05.No Violations Noted.Areas Examined During Insp Included Portions of Physical Security Program 1999-08-31
[Table view] Category:NRC TO UTILITY
MONTHYEARML20059N3331990-10-0202 October 1990 Forwards Notice of Consideration of Issuance of Amend to OL & Proposed NSHC Re 900426 Application for Possession Only License ML20059M6871990-09-14014 September 1990 Forwards Notice of Consideration of Issuance of Amend & Proposed NSHC Re Plant Physical Security Plan for Long Term Defueled Condition ML20059G9421990-09-10010 September 1990 Forwards Amend 115 to License DPR-54 & Safety Evaluation. Amend Revises License Condition Re Fire Protection Plan,Adds Administrative Controls to Tech Specs in Support of Fire Protection Plan & Relocates Fire Protection Requirements ML20056B4621990-08-22022 August 1990 Forwards Environ Assessment & Finding of No Significant Impact Re 900724 Request for Exemption to 10CFR50.47 ML20058N6461990-07-31031 July 1990 Forwards Insp Rept 50-312/90-11 on 900527-0706.No Violations Indentified ML20055E5151990-07-0303 July 1990 Requests Listed Addl Info on Licensee 900606 Plans Re Diesel Generator Operation as Peaking Power Supplies to Assure That Generators Will Be Maintained in Nondegraded Status IR 05000312/19900101990-07-0303 July 1990 Forwards Security Insp Rept 50-312/90-10 on 900611-22.No Violations Noted.Major Areas Inspected:Physical Protection. Rept Withheld (Ref 10CFR2.790 & 73.21) ML20055D5441990-06-28028 June 1990 Forwards Request for Addl Info Re 891129,900221 & 0327 Ltrs Concerning Computerized Commitment Tracking Sys,Long Range Scope List & Effluents & Water Mgt Project Action Plan Items Needing Deferral ML20248D3411989-09-25025 September 1989 Forwards Amend 8 to Indemnity Agreement B-66,reflecting Changes to 10CFR140,effective 890701 ML20248G7031989-09-21021 September 1989 Forwards Enforcement Conference Rept 50-312/89-16 on 890915 ML20248G5731989-09-21021 September 1989 Forwards Insp Rept 50-312/89-12 on 890801-04,21-25 & 30.No Violations or Deviations Noted.Concerns Raised Re Contamination Control Practices,Instrumentation Control & Informal Use of Vendor Data for Liquid Effluent Release ML20248B4131989-09-19019 September 1989 Provides Info Re Generic Fundamentals Exam Section of Operator Licensing Written Exam to Be Administered on 891004.Map of Area,List of Lodging in Immediate Area & Preliminary Instructions for Taking Exam Encl ML20248C8401989-09-11011 September 1989 Forwards Insp Rept 50-312/89-14 on 890828-0901.Concern Raised Re Apparent Decrease in Level of Emergency Preparedness.Enforcement Action Will Be Subj of Separate Correspondence ML20247C4931989-09-0606 September 1989 Informs That 890901 Insp Determined That Preparedness to Respond to Emergency Was Degraded.Violation Involved Failure to Assign Individuals Qualified Per EPIP to Critical Emergency Response Position ML20247B7561989-09-0606 September 1989 Advises That Response to Generic Ltr 88-17 Re Expeditious Actions for Loss of DHR Acceptable.Training Program Should State That Maint Personnel Included in Program & Daily Walkdowns of Tygon Tube Areas Should Be Performed ML20246K4581989-08-18018 August 1989 Forwards Insp Rept 50-312/89-10 on 890603-0721.No Violations Noted ML20247H5551989-07-21021 July 1989 Advises That Util 890511 Response to SALP Meeting Rept 50-312/88-39 Appropriate & No Changes to 890328 SALP Board Rept Deemed Necessary ML20247F0291989-07-20020 July 1989 Redistributed Forwarding Amend 112 to License DPR-54.Amend Revises Tech Specs Re Increasing Max Closure Time for Selected Containment Isolation Valves & Addition of 12 Valves to Table 3.6-1 ML20247B4031989-07-19019 July 1989 Forwards Errata to Amends 109,110 & 111 to License DPR-54, Correcting Omission of Language from Revised Pages ML20247B2961989-07-17017 July 1989 Forwards Amend 112 to License DPR-54 & Safety Evaluation. Amend Revises Tech Specs to Increase Max Closure Time for Selected Containment Isolation Valves & Add 12 Valves to Table 3.6-1 ML20247J0581989-07-12012 July 1989 Forwards Insp Rept 50-312/89-08 on 890422-0602.No Violations or Deviations Noted ML20246D5241989-07-0707 July 1989 Forwards Request for Addl Info Re 10-yr Internal Inservice Insp Program Plan.Response Requested within 45 Days of Ltr Receipt ML20247A0471989-07-0606 July 1989 Forwards Insp Rept 50-312/89-11 on 890629-30.No Items of Noncompliance Noted IR 05000312/19890011989-06-30030 June 1989 Ack Receipt of Responding to Violations Noted in Insp Rept 50-312/89-01.Reasons for Denial of Violations a & B.2 Will Be Reviewed During Future Insp ML20246B0911989-06-28028 June 1989 Forwards Exemption from Requirements of 10CFR20,App a, Footnote d-2(c) to Allow Use of Radioiodine Protection Factor of 50 for MSA GMR-I Canisters at Plant,Per 881117 Request.Notice of Environ Assessment Also Encl ML20245J3301989-06-22022 June 1989 Provides Background Info on Regulatory Analysis Supplementing NRC Proposed Backfit,Per 890413 Request.Util Expected to Provide Schedule for Implementation of Required Improvements ML20245E0961989-06-20020 June 1989 Forwards Amend 111 to License DPR-54 & Safety Evaluation. Amend Revises Section 2.C.(4) of License Re Fire Doors & Dampers Based on Reevaluation of Fire Areas in Uitl 1985 Updated Fire Hazards Analysis ML20245F5731989-06-20020 June 1989 Advises That Senior Reactor Operator Licensing Writtem Exams & Operating Exams Scheduled for 890905 & 06-19,respectively. Encl Ref Matl Requested by 890710 in Order to Meet Schedule ML20245A1831989-06-0909 June 1989 Forwards Amend 110 to License DPR-54 & Safety Evaluation. Amend Removes Tabular Listing of Snubbers from Tech Specs as Suggested by Generic Ltr 84-13 NUREG-0460, Forwards Safety Evaluation & Inel Rept EGG-NTA 8341, Providing Details & Basis for Concluding That Existing Intervals for on-line Functional Testing at Plant Should Result in High Reactor Trip Sys Availability.W/O Inel Rept1989-06-0606 June 1989 Forwards Safety Evaluation & Inel Rept EGG-NTA 8341, Providing Details & Basis for Concluding That Existing Intervals for on-line Functional Testing at Plant Should Result in High Reactor Trip Sys Availability.W/O Inel Rept ML20248B9451989-06-0505 June 1989 Forwards Amend 109 to License DPR-54 & Safety Evaluation. Amend Revises Tech Spec 4.17, Steam Generators & Associated Bases & Tables 4.17-2A & 417-2B to Permit Repairs of Steam Generator Tubes by Means of Tube Sleeves ML20248B9191989-06-0505 June 1989 Forwards Amend 107 to License DPR-54 & Safety Evaluation. Amend Removes Requirements for Fire Suppression Sys in Fire Zones 75-80 from Tech Spec 3.14 ML20248B6091989-06-0505 June 1989 Forwards Amend 108 to License DPR-54 & Safety Evaluation. Amend Modifies Paragraph 2.C.(3) to Require Compliance W/ Amended Physical Security Plan ML20248B6611989-06-0202 June 1989 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Rept 50-312/89-04 ML20247P1571989-05-30030 May 1989 Forwards Safety Evaluation Accepting Util 831104 Response to Item 4.5.2 of Generic Ltr 83-28, Reactor Trip Sys Reliability ML20247J1831989-05-25025 May 1989 Forwards Notice of Withdrawal of 860613 Application for Amend to License DPR-54 to Modify Tech Specs Pertaining to Deletion of Nonradiological Items Contained within App B Tech Specs & LER Clarifications ML20247K7061989-05-23023 May 1989 Forwards Amend 105 to License DPR-54 & Safety Evaluation. Amend Clarifies Operational Mode of Applicability of Tech Spec 3.4 & Definition of Auxiliary Feedwater Train & Revises Frequency for Verifying Auxiliary Feedwater Sys Flow Path ML20247M9001989-05-23023 May 1989 Forwards Amend 106 to License DPR-54 & Safety Evaluation. Amend Revises Tech Spec 4.17, Steam Generators, to Provide for More Extensive Insp of Steam Generator Tubes by Defining Tube Areas to Complete 100% Insp Where Degradation Expected IR 05000312/19890051989-05-17017 May 1989 Forwards Insp Rept 50-312/89-05 on 890304-0421.Two Noncited Violations Noted ML20247K6621989-05-16016 May 1989 Forwards Amend 104 to License DPR-54 & Safety Evaluation. Amend Deletes Tech Specs Re Reactor Vessel Matl Surveillance.Approval to Use B&W Integrated Reactor Vessel Matl Surveillance Program,Per 851014 & s,Approved IR 05000312/19880021989-05-12012 May 1989 Discusses Insp Rept 50-312/88-02 on 880104-14,0210-12 & 0307-09.Violations Noted.Advises That Violations Demonstrated Lack of Mgt Control Over Certain Aspects of Procurement Program.Enforcement Action Not Necessary ML20247B1341989-05-12012 May 1989 Forwards State of CA 1987 Environ Radiological Measurements Rept,Per Cooperative Agreement NRC-32-83-684.No Outstanding Concerns Identified in Data Comparisions Between Util & State Measurements ML20246M6271989-05-11011 May 1989 Advises That plant-specific Reactor Coolant Pump Trip Setpoint Development,Per TMI Action Item II.K.3.5, Acceptable,Based on Methodology Contained in Generic Ltr 86-05 IR 05000312/19890061989-05-11011 May 1989 Forwards Safeguards Insp Rept 50-312/89-06 on 890424-28.No Violations Noted.Evaluation of Plant Security Sys Conducted Through Extended Augmented Sys Review Requested.Rept Withheld (Ref 10CFR2.790(d)) ML20246P4801989-05-10010 May 1989 Advises of Locations & Features That Geologists Need to Inspect for Completion of Review of Sept 1987 Response to NRC Questions on Geologic & Seismologic Conditions ML20246M1741989-05-0808 May 1989 Submits Addendum to Safety Evaluation Supporting Amend 92 to License DPR-54,per Util 881129 Request to Revise Safety Evaluation.Approval to Extend Refueling Interval as Applies to Reactor Vessel Vent Valve Granted ML20246F4631989-05-0404 May 1989 Forwards Safety Evaluation & Technical Evaluation Rept Supporting Util Inservice Testing Program for Pumps & Valves.Certain Relief Requests Denied Where Proposed Alternative Testing Unacceptable ML20246H9151989-04-28028 April 1989 Forwards Insp Rept 50-312/89-07 on 890417-21.No Violations Noted ML20245J9031989-04-25025 April 1989 Advises of Special Emergency Operating Procedure Insp Program.Initiative Includes Team Insp of B&W Plants Not Insp Under 1988 Initiative ML20245F8771989-04-18018 April 1989 Forwards Amend 103 to License DPR-54 & Safety Evaluation. Amend Revised Tech Specs by Changing Air Flow Rate Through Reactor Bldg Purge Valves,Adding Requirement to Test Reactor Bldg Purge Exhaust HEPA Filters 1990-09-14
[Table view] Category:OUTGOING CORRESPONDENCE
MONTHYEARML20217M8851999-10-0808 October 1999 Informs of Staff Determination That Listed Calculations Should Be Withheld from Public Disclosure,Per 10CFR2.790, as Requested in 990909 Affidavit ML20211J7731999-08-31031 August 1999 Forwards Insp Rept 50-312/99-03 on 990802-06.No Violations Noted.Insp Included Decommissioning & Dismantlement Activities,Verification of Compliance with Selected TS & Review of Completed SEs ML20211H7481999-08-13013 August 1999 Forwards Amend 126 to License DPR-54 & Safety Evaluation. Amend Changes Permanently Defueled Technical Specification (PDTS) D3/4.1, Spent Fuel Pool Level, to Replace Specific Reference to SFP Level Alarm Switches with Generic Ref ML20207E9181999-05-27027 May 1999 Informs That Effective 990328,NRR Underwent Reorganization. within Framework of Reorganization,Div of Licensing Project Mgt Created.Reorganization Chart Encl ML20206U7411999-05-18018 May 1999 Provides Summary of 990217-18 Visit to Rancho Seco Facility to Become Familar with Facility,Including Onsite ISFSI & Meeting with Representatives of Smud to Discuss Issues Re Revised Rancho Seco Ep,Submitted to NRC on 960429 ML20204H6751999-03-19019 March 1999 Forwards Insp Rept 50-312/99-02 on 990309-11.No Violations Noted.Portions of Physical Security & Access Authorization Programs Were Inspected ML20207L1711999-03-10010 March 1999 Informs of Staff Determination That Supporting Calculations & Drawings Contained in Rev 2 of Sar, Should Be Withheld from Public Disclosure,Per 10CFR2.790 ML20203D0761999-02-10010 February 1999 Ltr Contract:Task Order 37 Entitled, Technical Assistance in Review of New Safety Analysis Rept for Rancho Seco Spent Fuel Storage Facility, Under Contract NRC-02-95-003 ML20237A6031998-08-0707 August 1998 Forwards Insp Rept 50-312/98-03 on 980706-09.No Violations Noted ML20236Q9461998-07-15015 July 1998 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Rept 50-312/98-02 ML20236E8211998-06-0303 June 1998 Forwards Insp Rept 50-312/98-02 on 980519-21 & NOV Re Failure to Review & Consider All Info Obtained During Background Investigation.Areas Examined During Insp Also Included Portions of Physical Security Program IR 05000312/19980011998-03-25025 March 1998 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Rept 50-312/98-01 on 980205 ML20202C4641998-02-0505 February 1998 Forwards Insp Rept 50-312/98-01 on 980105-08 & Notice of Violation.Insp Included Decommissioning & Dismantlement Work Underway,Verification of Compliance W/Selected TS & Main & Surveillance Activities Associated W/Sfp ML20198K5391997-10-21021 October 1997 Forwards Insp Rept 50-312/97-04 on 970922-25 & Notice of Violation.Response Required & Will Be Used to Determine If Further Action Will Be Necessary ML20198G8141997-08-22022 August 1997 Forwards Amend 125 to License DPR-54 & Safety Evaluation. Amend Permits Smud to Change TS to Incorporate Revised 10CFR20.Amend Also Revises References from NRC Region V to NRC Region IV ML20149E5031997-07-10010 July 1997 Second Partial Response to FOIA Request for Documents. Forwards Records Listed in App C Being Made Available in Pdr.Records in App D Already Available in PDR ML20148P5161997-06-30030 June 1997 Second Partial Response to FOIA Request for Documents.App B Records Being Made Available in PDR ML20141A1721997-06-17017 June 1997 Forwards Insp Rept 50-312/97-03 on 970603-05.No Violations Noted.Areas Examined During Insp Included Portions of Physical Security Program ML20140G6341997-05-0707 May 1997 Forwards ERDS Implementation Documents Including Data Point Library Updates for McGuire Number 224,WNP2 Number 225, Beaver Valley Number 226 & Calvert Cliffs Number 227. W/O Encl ML20140E6911997-04-25025 April 1997 Forwards Insp Rept 50-312/97-02 on 970331-0403.No Violations Noted ML20137C7211997-03-21021 March 1997 Forwards Insp Repts 50-312/97-01 & 72-0011/97-01 on 970224-27.No Violations Noted ML20129G7431996-09-27027 September 1996 Forwards Insp Repts 50-312/96-03 & 72-0011/96-01 on 960909-12.No Violations Observed ML20059J9771994-01-14014 January 1994 Informs That Document Rancho Seco ISFSI Sar,Vol Iv,Drawings & Calculations Submitted on 931027,w/Pacific Nuclear Fuel Services Group Affidavit of 931006 Will Be Withheld from Public Disclosure,Per 10CFR2.790(b)(5),as Requested ML20058D6291993-11-19019 November 1993 Forwards Exemption from Requirements of 10CFR140.11(a)(4) to Extent That Primary Financial Protection in Stated Amount Shall Be Maintained ML20058C9721993-11-0202 November 1993 Ack Receipt of Transmitting Rev 6 of Section 5 to Plant Emergency Plan.Advises Revised Emergency Plan Continues to Meet Planning Stds in 10CFR50.47(b) & Requirements of 10CFR50 App E ML20057D1841993-09-27027 September 1993 Grants Exemption from Requirements in 10CFR50.120 to Establish,Implement,& Maintain Training Programs,Using Sys Approach to Training,For Categories of Personnel Listed in 10CFR50.120.Exemption Effective 931122 & Encl IR 05000312/19930031993-09-24024 September 1993 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Rept 50-312/93-03 ML20057A3251993-09-0202 September 1993 Forwards Environmental Assessment & Fonsi Re Exemption from Requirements of 10CFR50.120 at Plant ML20057C4971993-09-0202 September 1993 Forwards Insp Rept 50-312/93-06 on 930819.No Violations or Deviations Noted ML20056F0011993-08-11011 August 1993 Forwards Mgt Meeting Rept 50-312/93-04 on 930727 ML20056G0041993-06-25025 June 1993 Submits Info Re Implementation of Training Rule 10CFR50.120 for Licensees of Plant in Decommissioning Process ML20127D3451993-01-0808 January 1993 Advises That 921105 Rev 3 to Rancho Seco Security Training & Qualification Plan Consistent W/Provisions of 10CFR50.54(p) & Acceptable for Inclusion Into Plan ML20127D3351993-01-0606 January 1993 Ack Receipt of 921105 & 30 Ltrs,Transmitting Rev 6 & Suppl 1 to Physical Security Plan.Changes Consistent W/Provisions of 10CFR50.54(p) & Acceptable for Inclusion Into Plan ML20126E2751992-12-10010 December 1992 Forwards Insp Rept 50-312/92-07 on 921110-11.No Deviations or Violations Noted ML20062G9951990-11-15015 November 1990 Forwards Insp Rept 50-312/90-14 on 901003-04,09-11 & 1102. Violations Noted But Not Cited ML20062C1921990-10-24024 October 1990 Advises That Commissioner Jr Curtiss Will Visit Facility on 901105 to Tour Plant & Meet W/Util Mgt & Personnel to Review General Status of Activities.W/Certificate of Svc.Served on 901024 ML20058G4471990-10-18018 October 1990 Forwards Sept 1990 Rept to Commission on Implementation of TMI Action Plan Items,Per 900320 Commitment.W/O Encl.Review Concluded for All But Two Units ML20059N3331990-10-0202 October 1990 Forwards Notice of Consideration of Issuance of Amend to OL & Proposed NSHC Re 900426 Application for Possession Only License ML20059M6871990-09-14014 September 1990 Forwards Notice of Consideration of Issuance of Amend & Proposed NSHC Re Plant Physical Security Plan for Long Term Defueled Condition ML20059G9421990-09-10010 September 1990 Forwards Amend 115 to License DPR-54 & Safety Evaluation. Amend Revises License Condition Re Fire Protection Plan,Adds Administrative Controls to Tech Specs in Support of Fire Protection Plan & Relocates Fire Protection Requirements ML20056B4621990-08-22022 August 1990 Forwards Environ Assessment & Finding of No Significant Impact Re 900724 Request for Exemption to 10CFR50.47 ML20056A5991990-08-0303 August 1990 Responds to Re Interaction of NRC W/Util to Facilitate Expeditious Closure of Plant.Nrc Continuing to Work Expeditiously on Number of Other Requests from Util. Prioritization Schedule Developed for Pending Applications ML20058N6461990-07-31031 July 1990 Forwards Insp Rept 50-312/90-11 on 900527-0706.No Violations Indentified ML20055G9791990-07-20020 July 1990 Responds to Expressing Concern Re Issuance of Possession Only License Amend.Nrc Project Manager Will Notify by Telephone When Util Submits Application Matl for Possession Only License Amend ML20055E5151990-07-0303 July 1990 Requests Listed Addl Info on Licensee 900606 Plans Re Diesel Generator Operation as Peaking Power Supplies to Assure That Generators Will Be Maintained in Nondegraded Status IR 05000312/19900101990-07-0303 July 1990 Forwards Security Insp Rept 50-312/90-10 on 900611-22.No Violations Noted.Major Areas Inspected:Physical Protection. Rept Withheld (Ref 10CFR2.790 & 73.21) ML20055D5441990-06-28028 June 1990 Forwards Request for Addl Info Re 891129,900221 & 0327 Ltrs Concerning Computerized Commitment Tracking Sys,Long Range Scope List & Effluents & Water Mgt Project Action Plan Items Needing Deferral ML20058K5791990-05-22022 May 1990 Final Response to FOIA Request for Records.App G & H Records Available in Pdr.App H & Releasable Portions of App J Documents Encl.App I Records Withheld in Entirety & App J Record Partially Withheld (Ref FOIA Exemptions 5 & 7) ML20055D6511990-05-10010 May 1990 Partial Response to FOIA Request for Info.App D & Releasable Portions of App E Documents Encl.Portions of App E Documents & App F Documents Withheld (Ref FOIA Exemptions 5,6 & 7) ML20248D3411989-09-25025 September 1989 Forwards Amend 8 to Indemnity Agreement B-66,reflecting Changes to 10CFR140,effective 890701 1999-08-31
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~ UNITED STATES NUCLEAR REGULATORY COMMISSION i 'E, REGION V
% g[ 1450 MARIA LANE, SUITE 210 ..
WALNUT CREEK, CALIFORNIA 94596
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June-20, 1989
- -i Rancho Seco Nuclear Generating Station l Sacramento Municipal Utility District .
14440 Twin Cities Road Herald, California 95638-9799 l-Attention: Mr. Joseph F. Firlit Chief Executive Officer, Nuclear i
Dear Mr. Firlit:
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Subject:
Reactor Operator and Senior Reactor Operator Licensing Examinations In a telephone conversation between Mr. Max Harrell of your staff and
. Mr. Gary Johnston, Chief Examiner, arrangements were made for the administration ,
of licensing examinations.at the Rancho Seco Nuclear Power Plant.
1 The written examinations are scheduled for September 5,1989. The operating examinations are' scheduled for September 6-19, 1989. i To meet the above schedule, it will be necessary for you to furnish the reference material listed in Enclosure 1, " Reference Material Requirements for Reactor / Senior Reactor Operator Licensing Examinations," by July 10, 1989. >
Any. delay in receiving approved, properly bound and indexed reference material, or the submittal.of inadequate or incomplete' reference material may result in the examination being rescheduled. Mr. Harrell has been advised of our:
reference material requirements, and the address where each set is to be mailed.
You are-responsible for providing adequate space and accommodations for administration of the written examinations. Enclosure 2, " Requirements _for Administration of Written Examinations," describes our requirements for conducting these examinations. Mr. Harrell has also been informed of these requirements.
Enclosure 3 contains the Rules arid Guidelines that will be in effect during the administration of the written examination. The facility management is responsible for ensuring tiiat all applicants are aware of these rules.
The facility staff review of the written examination will be conducted in accordance with requirements specified in Enclosure 4, " Retirements for Facility Review of Written Examinations." Mr. Harrell has been informed of these requirements.
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Mr. Joseph F. Firlit _
2 June 20, 1989 i.
All completed reactor operator and senior reactor operator license applications. -:-
should be submitted at least 30 days before the first examination dates
. so that we will be able to review the training and experience of the candidates, I process the medical certifications, and. prepare final examiner assignments after
- applicant eligibility has been_ determined. If the applications. are not received .
at.least 30 days before_the examination dates, it is likely that a postponement I will be necessary.: i :
-This request is covered by Office of Management and Budget Clearance Number.
3150-0101 which expires May 31, 1992. The estimated average burden is 7.7 hours8.101852e-5 days <br />0.00194 hours <br />1.157407e-5 weeks <br />2.6635e-6 months <br />' i per response, including. gathering, xeroxing and mailing the required material. !
' Send comments regarding this burden estimate or any other aspect of this __
i collection of information', including suggestions for reducing this burden, to the Records and Reports Management Branch, Division of Information Support .
Services, Office of Information Resources Management, U.S. Nuclear Regulatory Commission, Washington, D.C. 20555; and to the Paperwork Reduction Project.
(3150-0101), Office of Management and Budget, Washington, D.C. 20503.
Thank.you for your consideration in this matter. If you have any questions regarding the examination procedures and requirements, please contact Mr. Lew Miller, Chief, Operations Section, (415-943-3869), or Mr. Gary Johnston, .
ChiefExaminer,(415-943-3758). l Sincerely, D n k
Kirsch, Chief Reactor Safety Branch
Enclosures:
- 1. _ Reference Material Requirements for Reactor / Senior Reactor Operator Licensing Examinations
- 2. _ Requirements for Administration of Written Examinations
- 3. NRC Rules and Guidelines for Written Examinations
- 4. Requirements'for Facility Review of Written Examinations ;
cc w/ enclosures (1), (2), (3) and (4):
R. Cross, RV (2 copies) ,
J. Vinquist, Quality Assurance Managae.- '
S. Crunk, Manager, Nuclear Licensing M. Harrell, Supervision, Licensed Operator Training cc w/o enclosures (1), (2), (3) and (4):
A. D'Angelo, SRI G. Kalman, NRR L. Miller, RV G. Johnston, RV 1
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,, ENCLOSURE'1 REFERENCE MATERIAL REQUIREMENTS FOR' REACTOR / SENIOR REACTOR OPERATOR-LICENSING EXAMINATIONS
- 11. Existing learning objectives, Job Performance Measures and lesson plans F (including training manuals, plant orientation manual, system descriptions,
, reactor _ theory,-thermodynamics,etc.).
A copy of the facility Job and Task Analys.is (JTA), specifying.the -
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- knowledges"and abilities required of an operator at the facility. Each particular knowledge and/or ability will' include an importance rating 3 correlating,it to ensuring the health and the safety of the public. If !
a'JTA is not furnished, tne Knowledges and Abilities Catalog for Nuclear Power Plant Opentors,,NUREG 1122 will' be used to establish content I validity for the examination.
All Job Performance Measures (JPMs) used to ascertain the competence of the. operators in performing tasks within the control room complex and, as identified in'the facility JTAs, outside of the control room, i.e.,
local operations.
Training materials shall include all substantive written material'used for for preparing applicants for initial R0 and SR0 licensing. The written ;
material'shall include learning objectives and the details presented j during lectures,,rather than outlines.. Training materials shall be ' '{
identified by plant and unit, bound, and indexed. FAILURE TO PROVIDE COMPLETE, PROPERLY B0UND AND INDEXED PLANT REFERENCE MATERIAL MAY RESULT IN THE RETURN OF THE MATERIAL TO THE PERSON WHO IS THE HIGHEST LEVEL OF CORPORATE MANAGEMENT WHO IS RESPONSIBLE FOR PLANT OPERATIONS (E.G., 4 VICE PRESIDENT OF NUCLEAR OPERATIONS). ACCOMPANYING THE MATERIAL WILL BE A C0VER LETTER: EXPLAINING THE DEFICIENCIES IN THE REFERENCE MATERIAL AND THE FACT THAT THIS WAS THE REASON THE EXAMINATIONS WERE CANCELLED OR POSTPONED. Training materials which include the following shall-be provided:
. System descriptions including descriptions of all operationally }
, relevant flow paths, components, controls and instrumentation. '
System training material should draw parallels to the actual ;
procedures used for operating the applicable system.
. Complete and operationally useful descriptions of all safety-system interactions and, where available, B0P System interactions ,
under emergency and abnormal conditions, including consequences )
of anticipated operator error, maintenance error, and equipment i failure.
. Training material used to clarify and strengthen understanding of emergency' operating procedures.
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.c Enclosure 1-(continued)
. . Comprehensive theory material that includes' fundamentals in
.the area of theory of reactor operation,. thermodynamics, heat :
transfer and fluid flow. as well as specific application to l' actual in-plant components. For example, mechanical theory material' on pumps shallcinclude pump theory as well as descriptions of how these principles actually apply to major ' f plant pumps and the systems in which they are installed-(i.e., p Reactor Coolant Pumps, all ECCS pumps, Recirculation pumps,.
Feedwater pumps and Emergency Feedwater pumps). Reactor Theory :
material shall include descriptions that draw explicit ties i.
between the fundamentals and the actual. operating limits p followed in the ' plant (i.e., reactor theory material shall ! ;
contain explanations how principles relate to the actual curves i used by operators to verify shutdown margin or calculate an ECP). .
- 2. Complete Pr0cedure Index (including surveillance procedures, etc.).
- 3. All administrative procedures.(as applicable to reactor operation or-safety).
- 4. All integrated plant procedures (normal or general operating procedures).
- 5. All emergency procedures (emergency instructions, abnormal or special procedures).
6.. Standing orders-(important orders that are safety related and may supersede the regular procedures).
- 7. Surveillance procedures (procedures that are run' frequently, i.e. weekly or that can'be run on the simulator).
- 8. Fuel-handling and. core-loading procedures, (initial core-loading procedure, when appropriate).
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- 9. All annunciator / alarm procedures.
- 10. Radiation protection manual (radiation control manual or procedures).
- 11. Emergency plan implementing procedures.
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- 12. Technical Specifications (and interpretations, if available) for all _
units for which licenses are sought. '
- 13. System operating procedures.
- 14. Piping and instrumentation diagrams, electrical single-line diagrams, or flow diagrams.
- 15. Technical Data Book, and/or plant curve information as used by operators !
and facility precautions, limitations, and set points (PLS) for the facility. i l
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3 Enclosure 1 (continued) ,
16.. Questions and answers specific to the facility training program which may be.used in the written or operating examinations (voluntary by l facility licensee).
17 Additional material required by the' examiners to develop examinations b that meet the requirements of these staadards and the regulations. !
The above reference material shall be approved, final issues and shall be ,
so marked. If a plant has not finalized some of the material, the Chief !
Examiner shall verify with the facility that the most complete, up-to-date material is available and that agreement has been reached with the licensee for limiting changes before the administration of the examination.
All procedures and reference material shall be bound with appropriate indices or tables of contents so that they can be used efficiently. Failure to provide complete, properly bound and indexed plant reference material could result in cancellation or rescheduling of the examinations.
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b ENCLOSURE 2 i' 1 REQUIREMENTS FOR ADMINISTRATION OF WRITTEN EXAMINATIONS
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l'. . A single room shall be provided for administration.of'the' written I examination. The location of this room and supporting restroom facilities shall-be such as to prevent contact with all-other facility and/or !
contractor personnel during the written examination. If necessary, I
' the' facility should_ make arrangements for the use of a suitable room 'at 1-a local school, motel, or other building. Obtaining this room is the responsibility of the licensee-
- 2. Minimum spacing is' required to ensure examination integrity as determined l by the Chief Examiner. Minimum spacing sho'ldu be one candidate per table, l with a 3. foot space between tables.
, 3. Suitable arrangements shall be made by the-facility if the candidates
-are to have lunch,-coffee or other refreshments. Thes.a arrangements shall: comply with Item 1 above and shall be reviewed by the examiner and/or proctor.
- 4. The facility licensee shcIl provide pads of 8-1/2 by 11-inch lined paper in unopened packages for each candidate's use in completing the examination.
The examiner shall distribute these pads to the applicants.
- 5. Applicants may bring pens', pencils, calculators or slide rules into the '
examination room. Only black ink or dark pencils should be used.for
, writing answers to questions.
- 6. The licensee shall provide one set of steam tables for each applicant.
The-examiner shall. distribute'the steam tables to the applicants. No wall charts, models, and/or other training materials shall be present in the examination room. No other equipment or reference material shall be allowed unless provid.9d by the examiner.
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NRC RULES AND GUIDELINES FOR LICENSE EXAMINATIONS-
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PROCEDURES.FOR THE' ADMINISTRATION'0F WRITTEN EXAMINATIONS
- 1. Check identification badgest i
Pass out examinations and all handouts. Remind applicants not to review
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- 2. .L examination until' instructed'to do so. l t
' READ THE FOLLOWING INSTRUCTIONS VERBATIM: l Duringithe administration of this examination the following' rules apply: -
- 1. Cheating on the' examination means an automatic denial of your.
application and could result in more severe penalties.
- 2. 'After the examination has been completed, you'must sign the statement on the' cover sheet indicating that the work is your own and you have not received or given assistance in completing the examination. 'This'must be done after you complete the examination.
READ THE FOLLOWING. INSTRUCTIONS I
- 1. - Restroom. trips are to be limited and only one applicant at'a time may. j leave. .You must avoid all contacts with anyone outside the examination .1
- - room tol avoid even the appearance or possibility of cheating.
- 2. - Use black ink or dark pencil only to facilitate legible reproductions. i 3 .' . - Print your name in the blank provided in the upper right-hand corner of :
the examination cover sheet. .q
'4. Fill:in the date on the cover sheet of the examination (if necessary)..
- 5. . You.may write your answers on the examination question page or on a separate' sheet of paper. USE ONLY THE PAPER PROVIDED AND'00 NOT WRITE ON THE BACK SIDE OF THE PAGE.
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- 6. If you write your answers on the examination question page and you need more space to answer a specific question, use a separate sheet of the i paper provided and insert it directly after the specific question. D0 K
NOT WRITE ON THE BACK SIDE OF THE EXAMINATION QUESTION PAGE.
- 7. Print you name in the upper right hand corner of the first page of each section of your answer sheets whether you use the examination question pages or separate sheets of paper. Initial each page.
- 8. Before you turn in your examination, consecutively nunber each answer sheet, including any additional pages inserted when writing your answers on the examinatica question page.
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Enclosure.3(continued) 9.- .If.you are using' separate sheets, number each answer as to~ category and
- number;(i.e.- 1.04, 6.10)'and skip at.least'3 lines between answers to allow space.for grading.
- 10. . Write "End of Category " at the end of your answers to a category.
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- 11. Start each category on a new page. l
- 12. Writo "Last Page" on.the last answer sheet.
- 13. . Use abbreviations only;if .they are commonly .used in facility literature.
Avoid using symbols such as or signs to avoid a simple transposition error resulting in an incorrect answer. Write it out. I
- 14. The point value for each question is indicated in parentheses after the question. The amount of blank space on an examination question page.is ,
NOT an. indication of the depth of answer required.
- 15. .Show all calculations, methods, or assumptions used to obtain an answer.
- 16. Partial. credit'may be given. 'Therefore, ANSWER ALL PARTS OF THE QUESTION ,
AND DO NOT LEAVE ANY ANSWER BLANK.
- 17. -Proportional grading will be applied. Any additional wrong information that is provided may count against you. For example, if a ques, tion is worth one point and asks for four responses, each of which is worth 0.25 points, and you- give five responses, each of your responses will be worth 0.20 points. If one of your five responses is incorrect, 0.20 will be deducted and your total credit for that question will b 0.80 instead of 1.00 ever, though you got the four correct answers.
- 18. If the intent of a question is unclear, ask questions of the examiner i only.
- 19. When turning in your examination, assemble-the completed examination with examination questions, examination aids and answer sheets. In addition, turn in all scrap paper.
- 20. To pass the examination, you must achieve an overall grade of 80% or greater and at.least 70% in each category. I I
- 21. There is a time limit of (6) hours for completion of the examination. j (or some other time if less than the full examination is taken). !
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- 22. When you are done and have turned in your examination, leave the examination area (DEFINE THE AREA). If you are found in t.is area while I the examination is still in progress, your license may be denied or revoked.
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ENCLOSURE 4 l
REQUIREMENTS FOR FACILITY REVIEW 0F WRITTEN EXAMINATIONS
- 1. At the option of the Chief Examiner, the facility may review the written examination up to two weeks prior to its administration. This review may take place at the facility or in the Regional office. The Chief-Examiner will coordinate the details of the review with the facility.
An NRC examiner will alwasy be present during the review.
Whenever this option of examination review is utilized, the facility reviewers will sign the following statement prior to being allowed access to the examination. The examination or written notes will not by retained by the facility.
- a. Pre-Examination Security Agreement I agree that I will not knowingly divulge any information concerning the replacement (or initial) examination scheduled for to any unauthorized persons.
I understand that I am not to participate in any instruction involving those reactor operator or senior reactor operator applicants scheudled to be administered the above replacement (or initial) examination from now until after the examination has been administered. I understand that violation of this security agreement could result in the examination being voided.
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Signature /Date In addition, the facility staff reviewers will sign the following statement after the written examination has been administered.
- b. Post-Examination Security Agreement I did not, to the best of knowledge, divulge any information concerning the written examination administered on to any unauthorized persons. I did not participate in providing any instruction to those reactor operator and senior reactor operator applicants who were administered the examination from the time that I was allowed access to the examination.
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2 Enclosure 4 (continued)'.
- 2. Regardless of whether the_above examination review option _is exercised, immediately following the administration of the written examination, the-facility staff shall be provided a marked'up copy of the examination and
? the answer key. The copy'of.the written examination shall. include pen and ink changes madeLto questions during the examination administration.
If the facility did not review the examination prior to its administration, they will have five (5) working days from the day of the written examination to submit formal comments. If the facility. reviewed
'the examination prior to this administration, any additional comments must be'given to an examiner prior to his/her leaving the site at the end of the week of. the written examination administration. In either case, '
the comments.will be addressed to the responsible Regional Office by the-highest on site level of corporate management for plant operations, I e.g., Vice president for Nuclear Operations. A copy of the submittal will be forwarded to the Chief Examiner, as appropriate. Comments not submitted within the required time frame.will be' considered for inclusion in the grading process on a case-by-case basis by the Regional Office Section Chief. Should the comment submittal deadline not be met, a long delay in grading the examinations may occur.
,3. The following format should be adhered to for submittal of specific comments:
- a. Listing of NRC Question, answer and reference
- b. Facility comment / recommendation
- c. Reference (to support' facility comment) '!
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NOTES: 1. ~ No change to the examination will be made without submittal- 1 l of a reference to support the facility comment. Any supporting :
documentation that was not previously supplied, should be l provided.
- 2. Comments made without a concise facility recommendation will ,
not be addressed. ]l
- 4. A two hour post examination review may be held at the discretion of the Chief Examiner. If this review is held, the facility staff should be informed that only written comments that are properly supported will be considered in the grading of the examination.
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4 Mr. Joseph F. Firlit. 2 June 20, 1989 RV/jk i a
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1.JJQQEST COPY R ST COPY ] REQUESI GORY
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