Letter Sequence RAI |
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MONTHYEARML20213F0381986-11-0707 November 1986 Advises of Revised Schedule for Completion of NUREG-0737, Item III.D.3.4 Re Control Room Habitability.Provisions to Complete Item III.D.3.4 Will Be Implemented Prior to Startup from Current Outage Anticipated in Early May 1987 Project stage: Other ML20235F7141987-06-30030 June 1987 Responds to NRC Re Deviations Noted in Insp Rept 50-312/87-14.Based on Encl Bechtel 870625 Evaluation, Application of Dow Corning 732 RTV Silicone Sealant in Essential HVAC Sys Acceptable Project stage: Other ML20237C2361987-12-15015 December 1987 Forwards Request for Addl Info Re Facility Modified Control Room Habitability Sys,Per 871109 Onsite Review.Sys Operability During All Modes of Operation Will Be Verified Project stage: RAI ML20149G7591988-02-0808 February 1988 Forwards Request for Addl Info Re Util 880113 Response to NRC Re Control Room Habitability Sys Project stage: RAI 1987-12-15
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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 ML20057C4971993-09-0202 September 1993 Forwards Insp Rept 50-312/93-06 on 930819.No Violations or Deviations Noted ML20057A3251993-09-0202 September 1993 Forwards Environmental Assessment & Fonsi Re Exemption from Requirements of 10CFR50.120 at Plant 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) 1999-08-31
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9 December 15, 1987 Docket No.: 50-312 Mr. G. Carl Andognini Chief Executive Of ficer, Nuclear Rancho Seco Nuclear Generating Station 14440 Twin Cities Road Herald, California 95638-9799
Dear Mr. Andognini:
SUBJECT:
RANCHO SECO NUCLEAR GENERATING STATION - CONTROL ROOM HABITABILITY, REQUEST FOR ADDITIONAL INFORMATION (TAC N0. 61413)
During the week of Hovember 9, 1987, the staff performed an onsite review of the modified control room habitability systens in support of the Safety Evaluation Report related to the restart of the Rancho Seco Nuclear Generating Station. As a result of this review, and the subsequent review of docun:ents received at the site, the staff has identified areas where additional information is required.
Please provide the information requested in the attachment to this letter as soon as possible so that our review can be completed without impacting your restart schedule.
It should be noted that an additional site visit will be required to verify i
system operability during all n,cdes of operation.
Sincerely, l
, George Kalman, Project Manager l 8712210177 871215 Project Directorate V i PDR ADOCK 05000312 ,
Division of Reactor Projects - III, P IV, Y and Special Projects PDR !
Office of Nuclear Reactor Regulation
Attachment:
As stated cc: See next page.
DISTRIBUTION.
Docket > File ? GKalman ACRS (10) GPA/PA NRC & Local'PDRs GKnighton TBarnhart(4) EJordan TMurley FMiraglia CRossi OGC-Bethesda PDV Reading JLee JPartlow i DMCrutchfield GMHolahan 0FC :DRSP/PDV :DRS DV :QP MPDV :0GC :ADR/DRSP :DRP/DRSP :ADP
,NAME :JLeef :GKsimen:CW :GP 'Jhton "r --- -wfiMHolahan :DCrutchfield FMiraglia :
lDATE:12f 7 :12// 3/87 :1/$/87 I :12/ /87C y(12 Q TF~iRT-i87 -:12/_/~87 0FC /:DONN , ' ~'
i : : : O .,: / : :
iNAME :IMURLEL _
DATE :12/. /87 Q, fig ( % :.
0FFICIAL RECORD COPY
Pr. G. Carl Andognini Rancho Seco Nuclear Generating Chief Executive Officer, Nuclear Station Sacramento Municipal Utility District s cc:
Mr. David S. replan, Secretary Mr. John Bartus and General Counsel Ms. JoAnne Scott Sacramento Municipal Utility Federal Energy Regulatory Cacc41ssion i District 825 North Capitol Street, N. E. -
6201 S Street Washington, D.C. 20426 z P. O. Box 15830 l Sacramento, California 95813 l
l Thomas A. Baxter, Esq.
Shaw, Pittman, Potts & Trowbridge 2300 N Street, N.W.
Washington, D.C. 20037 Mr. John V. Vinguist :
Acting Manager, Nuclear Licensing Sacramento Municipal Utility District Rancho Seco Nuclear Generating Station 14440 Twin Cities Road Herald, California 95638-9799 Mr. Robert B. Borsum Babcock & Wilcox Nuclear Power Generation Division 1700 Rockville Pike - Suite 525 kockville, Maryland 20852 Resident Inspector / Rancho Seco c/o U. S. N. R. C.
14440 Twin Cities Road Herald, California 95638 Regional Administrator, Region V U.S. Nuclear Regulatory Commission l 3450 Maria Lane, Suite 210 Walnut Creek, California 94596 Mr. Joseph 0. Ward, Chief Radiological Health Branch State Department of Health Services 714 P Street, Office Building #8 Sacramento, California 95814 Sacranento County Board of Supervisors 827 7th Street, Room 424 Sacramento, California 95814 Ms. Helen Hubbard P. O. Box 63 Sunol, California 94586
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,.i RANCHO SECO STARTUPc u CONTROL POOM HABITABILITY SYSTFM REQUEST F'OR ADDITIONAL INFORMATION ' '
O s PLANT SYSTEMS BRANCH
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Eig y[,0 1. Ranctlc Seco's procedure'for' air balance of ventilation systems, M-111, "HVAC Maintenance Procedure'for Air Balance of Ventilation Systems,"
is relied on for providing'essurance that unfiltered air inleakage is within the bounds of the assumptions used in the dose calculations and 3 x - toxic cas analyses and tle system otherwise functions as designated.
Wj q Provide the following information:
3,> '
(' a) The prockdures and data sheets do not indicate that the +,yts it! 'any particular mcde of operatinn are made in a continuous runs,' The data
'*. sheets provided do not include the mode of operation of the train that is in service or the time of day the measurements were taken.
Previde assurance that test datn Jresented to the review team g represerts data recorded durinotthe operation of distinct.'centinuous y W test cycles for the HVAC system modes of operation, or provide ;-
justification that data obtained in interrupted runs are acceptable.
,1 - .
b) Provide the data sheets associated with measurements (traverses on the A & B unit supplyind return) referrec' to in the remarks section.,of s the procedure dated April- 29, 1987 ~
c) Providethedatasheetassociatedwiththemeasurementbrhvarseon Utre A train outside air inia'te) referred to in the remarks section
~ "of the procedure dated April 29, 1987.
d) Provide justification for the validity of the readings recorded on the data sheet associated with the TSC return air data dated April 30, 1987. The remarks section of the procedure indicate that TSC return air.date were not taken on April 30, 1987 beceuse of a hole in the everhead grate. It should also be noted that since the
> overhead crea forms a common return air plenum, degraded grating ,
q could affect measurements on both the supply and return ducts. l e) Provide data sheets associated with traverse reedings taken on the control ro9m supply and return tm the filtration unit as referred to in remarks ' dated May 7,1987, asDH .h data sheets .for the several other meas'arements recorded in the remarks dated May 7,1987.
l f) Provideflowmeasurementdatasheetsforoutsideairmakeuptoboth of the HVAC trains for data taken on June 3, 1987 L ,
g) Provide the correct date associated with a flow measurement data sheet for the B train control room return. This data sheet was ;
attached to the procedure, but did not include a test date. !
k /
h) With regard to the balancing procedure, the current procedure shows f3s '
differential pressure readings for the control room to corridor and the TSC to the corridor, but does not provide differential pressure readings to other adjacent areas. Provide additional inforn tion to support the statement made in item 2.1.E of the most recent III.D.3.4 submittal dated July 22, 1987, that the system has been tested to verify that the control room TSC can be pressurized to at least 1/8 inch water gauge relative to all surrounding spaces.
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i) Procedure M-111 did not include any flow measurements in the ducts of the normal HVAC system or for any of the idle branches of the HVAC system. Further, the balaacing procedure did not measure '
exhaust air flow for fans located in the toilet, kitchen, and m
conference room areas of the control room. These measurements may show system inleakage or outleakage. *
.i ) Air balance. data for the air handling units taken on April 23,198h and September 30, 1987 irdicate.that the air inlet and the air outlet flows are exactly the same for both air handling unid.
In the staffs experience with testing of air handling unitsjar.d emergency filter trains at different plants, we have nev& observed any cases where the balancing (inlet to outlet air flowhtes) has agreed to the exact cfm.
The difference between inlet and outlet readings is most likely attributable to instrument error and variations in system flow. Provide additional information to support these data measurements.
k) Test data rded on June 3, 1987 for this procedure shows that~
more air is being returned from the control ronm envelope to the Essential HVAC system than is being' supplied t/ these units. Train A shows 297 cfm and Train B shows 601 cfm more, air returning to the essential units from the envelope than is being supplied. After reviewing Rancho Seco's system configuration, it appears that the nomal HVAC systen that continues to ron may be responsib4.for tMs additional flow. Therefore, provide assurance that inleakroe flow P through the isolation damper in the nomal supply duct fron AH-H-2 during operation in emergency modes is adeouately addressed by the assumptions of the dose calculations and toxic gas calculations and-is m(ot :rel lied s on for assuring adequate pressuri.Tation of the control- ' ronm envghpc. .
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- 2. R.G.1.52 Position 5.d provides that leak testiry of the carbon atorber section be conducted if the intentity of the afsorber is affected.
(),
Procedures STP 1063A, " Control Room /TSC Essentini Filtration Unit C' Air / Aerosol Mixing Uniformity Test Train A" artIW1063B, Control g' Room /TSC Essential Filtration Unit Air / Aerosol Mixing Unifomity Test '
Train B", require the removal of carbon filter, trays to perform the test.
.- ~
The procedures do not require 'a Freon in-puce test after the carbon filter trays are reinstalled.
j Provide additicnal information which 1 essures that the carbon trays hyve been properly reinstalled (thereb limiting bypass flow) without performance of this type of test, or '
modify the test procedure or otherwise provide [ assurance that the ,
adsorber section will be leak tested. .
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- 3. With regard to procedure I.044, " Calibration Procedure for Chlorine Analyses Probes AE-54701 and AE-5470?"" and I.045, " Calibration
- b. Procedure for Chlorine Analyses AIT-54701 and AIT-54702", provide the following infomation:
a) Verification that the detectors are capable of detecting a chlorine concentration of 5 ppm per Position C.d.d(1) of Regulatory Guide 1.95.
b) Frequency of the calibration. (Neither procedure included this
)g infomation) . Position c.4.d(6) of R.G.1.95 requires calibration c'.v's once every six months.
- q. 7 c) Verification that routine operational checks are conducted at one week intervals per Position c.4.d(6) of R.G.1.95 or justification for any deviation. (No procedures or checklist was provided to 1 the review team that indicated that a weekly operational check is being perfomed on the chlorine detectors).
,, d) R.G.1.95 states that the control room should be isolated in 10
/ seconds for a type V control room after a chlorine concentration
,1' of 5 ppm reaches the detectors. It is not evident that either l procedure 1.044 or 1.045 verifies that this response time is l being met for the detectors. Provide justification for this l apparent deviation.
l .t l 4. Af ter reviewing the licensee's control room envelope configuration, it l appears that a door in the shift supervisor's office opens directly to the outside. Provide additional information to support the apparent i deviation from R.G.1.95 Position 4.b.(3) that a control rom exit leading
,, directly to the outside of the building should have two interlocking low-leakage doors in series.
- 5. The SPUD letter dated June 30, 1987, addressing the NPC's concern regarding deviation from the RG 1.52 position on the use of silicone sealants in FSF filter systens., addressed only the radiation resistance of the sealant.
Provide rational adcressing other potentially significant effects on sealant
.furctions with age in service. Where test results are relied on or where tests 1
are proposed, describe how the conditions represent (and limitations) the as-installed condition of~the sealant over the life of the plant considering the aterials in contact with the sealant, the characteristics of the inter-f ace b'etween the sealant and these materials, the so lent temperature, the effect of mass transfer between the sealant and the surroundings, and variable stresses due to vibration and pressure cycling.
Describe the measured parameters and hw they provide assurances that the sealant is perfoming the function to adequataly limit air inleakage.
Otha-wise, provide means for verifying over the life of the plant the in-leakage rates assumed in the dose calculations, e.g., periodic testing of the function of the sealant.
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'4 6.
The CR/TSC Essential A'ir Conditioning System Status Report, Rev.1, addresses each problem.45 licensee identified problems and plans for resolution of Licensee-identified concerns / questions are also addressed in the document " Expanded Augmented System Review and Test Program, Evalu-etion of the CP/TSC Essential HVAC System."
Additional releted licensee identified problems and plans for resolution exist (e.g. Diesel Exhaust Fumes in CP/TSC Atmosphere 1 Provide a description (including results) of evaluations, analyses, measurements, changes, training, revisions, verifications, corrections, tests performed or planned (provide schedule) to resolve Justify each of the related licensee-identified problems and concerns.
thesr: cases where you do not plan resolution prior to restart.
7.
Provide assurance that there will be no unfiltered inleekage, while operatinn in any emergency mode, through the return ducts around the essential filtration units. Describe the safety significerce of establishing steady flow through the essential filtration unit prior to opening the outside air intake dampers after receipt of a radiological emergency signal. Provide assurance that this sequence will occur in radiological emergencies.
- 8. Provide assurance that filter by-pass and other potential air flow through drains will not adversely affect operation of the control room habitability system.
9.
Provide assurance that the reliance on the installed " semi-remote" chlorine detectors and the absence of ammonia detectors is in compliance with SRP 6.4 and meets the intent of RGs 1.78 and 1.95, considering:
(a) shipments of chlorine and ammonia to the site, (b) meteorological conditions, including building wake effects, that would transport released chlorine or ammonia to the control room but not be detected in time. to adequately protect the control room operators, (c) pntential improvements to safety afforded by reliance on chlorine detectors and ammonia detectors located at the points of potential release and administrative controls durirg deliveries of these materials to the site, (d) exhausts from operation of the emergency diesels.
- 10. Provide ,1vstification for the deviation from the RG 1.78 regarding provision of readout of the toxic gas monitors in the control room.
H. Regarding RG 1.57, provide ,4 justification for the discrepancy between
- the charcoal efficiency used in the dose calculations, and the f laboratory testing acceptance criterie used.
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- 12. Provide an evaluation of all potential release points that have not been previously analyzed in conjunction with the operator dose calculations (e.g., radiation waste exhaust vent on the auxiliary building level).
)
13.
Provide on evaluation of accident doses to the operators involving all potentiallouvered building pathways other than from the outside through the auxiliary door.
14 Provide dose calculations to include the tine during which both trains of the energency filtration system would be running and the time required for flow stabilization after system initiation. Provide assurance that -
the system will be operated within the bounds of the dose calculations (i.e. limit times for both trains running and for flow stabili7ation). i
- 15. Provide additional infomation which confirms that control room operators are adequately trained regarding HVAC equipment potential failures (single failures, etc.) to be able to promptly identify failures and take the necessary corrective actions.
- 16. Provide additional information to demonstrate adequate detailed operator training in use of the self-contained breathing apparatus in the control room.
- 17. Provide justification for the significant reliance on the non-safety related IDADS computer systen for HVAC equipment status information during emergencies as opposed to reliance on the safety-related instrumentation display and readout on the control room panels (especially regarding identifying single failures of the HVAC system).
- 18. Provide additienal information which justifies that the IDADS computer's flow response time in displaying changing HVAC system flow rates will not impact the ability to operate the system properly.
- 19. Provide additional information to explain the staff's observation of flow measurement readout in the IDADS output when the particular train of the system was considered shutdown and inoperable.
- 20. Provide additional information that justifies that the control roon boundary doors will be properly maintained closed in order to ensure control room integrity during emergencies. Specifically consider maintenance of seals and provision of administrative controls to ensure closure.
- 21. Provide additional information that confims that current surveillance procedures adequately provide for the surveillance of hardcast tape in-stallations or provide specific identification of hardcast tape installation locations alona with the procedure.
O
- 22. In addition, the staff will request that the system be operated and maintenance / surveillance testing be conducted in accordance with approved station procedures and observed by the staff as follows:
(a) Each train, independently, would be operated sequentially in the r.ormal, toxic gas, normal and radiation modes. The staff would observe characteristics of system operation at the controls (control room), IDADS system data output (technical support center) and other indications (HVAC equipment location on the roof). The staff would also verify the initiation of the toxic gas and radiation modes for each. train upon receipt of appropriate initiating signals (manual, toxic gas detection, radiation detection). During operation in the radiological modes, the staff also would observe measurements made by the licensee of the differential pressure of various areas of the control room envelope with respect to important adjacent areas.
(b) During operation in the radiation mode, the staff would observe licensee testing of appropriate system flow rates to verify that unfiltered inleakage air flow rates through isolation dampers in the rormal HVAC supply duct (AH-H-2), or through another path deemed appropriate, because of potential significance through prior discussions with the staff, are within the levels assumed i'n the dose calculations and toxic gas analyses.
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