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Category:CORRESPONDENCE-LETTERS
MONTHYEARML20217K4391999-10-18018 October 1999 Provides Response to RAI to Support USI A-46 Program Submittal for North Anna Power Station,Units 1 & 2.Rev 10 to BNL Rept 52361,encl ML20217H3301999-10-14014 October 1999 Forwards Rev 0 to COLR for North Anna 2 Cycle 14 Pattern Su. No New Commitments Intended by Ltr ML18152B3541999-10-12012 October 1999 Requests Use of Code Case N-532 & N-619,per Provisions of 10CFR50.55a(a)(3).Detailed Info Supporting Request,Encl. Attachment 2 Includes Technical White Paper That Provides Further Technical Info ML20216K1681999-10-0101 October 1999 Forwards Vols I-VIII of Rev 35 to UFSAR for Naps.Rev Also Includes Update to Chapter 17 of Ufsar,Which Contains Operational QA Program.Changes to Program Description Do Not Reduce Commitments Contained Therein ML20212J9101999-10-0101 October 1999 Forwards SE Accepting Licensee 990916 & 27 Relief Requests IWE-3 for Plant.Se Addresses Only IWE-3 Due to Util Urgent Need for Relief.Requests IWE-7 & IWE-8 Will Be Addressed at Later Date ML18152B3391999-09-27027 September 1999 Forwards Revised Relief Request IWE-3,which Now Includes Addl Visual Exam Requirement After post-repair or Mod Pressure Testing Is Completed,Per Telcon with NRC ML20212G5091999-09-22022 September 1999 Forwards in Triplicate,Applications for Renewal of Licenses for Listed Individuals.Encls Withheld,Per 10CFR2.790(a)(6) ML18152B6671999-09-17017 September 1999 Forwards Two NRC Forms 536,containing Info on Proposed Site Specific Operator Licensing Exam Schedules & Estimated Number of Applicants Planning to Take Exams And/Or Gfes,In Response to NRC Administrative Ltr 99-03 ML18152B3331999-09-17017 September 1999 Forwards Revised 180-day Response to NRC GL 96-05, Periodic Verification of Design-Basis Capability of Safety-Related Motor-Operated Valves. ML18152B3341999-09-16016 September 1999 Requests Relief from Specific Requirements of Subsection IWE of 1992 Edition with 1992 Addenda of ASME Section XI Re Containment Liner Examination Requirements,For North Anna & Surry Power Stations ML20211N2531999-09-0808 September 1999 Responds to Request to Exceed 60,000 Mwd/Mtu Lead Rod Burnup in Small Number of Fuel Rods in North Anna Unit 2.Informs That NRC Offers No Objection to Requested Use of Rods in Reconstituted Fuel Assembly.Se Supporting Request Encl ML18152B4471999-09-0101 September 1999 Requests That NRC Remove Listed Labels from Distribution ML20211L9151999-09-0101 September 1999 Forwards Response to NRC Request for Comments Re Closure of Review of Response to GL 92-01,Rev 1,Suppl 1, Reactor Vessel Structural Integrity ML20211J2211999-08-31031 August 1999 Approves Request to Remove Augmented ISI (Aii) Program for RCS Bypass Lines from North Anna Licensing Basis.Se Re Request to Apply LBB to Eliminate Augmented Insp Program on RCS Bypass Lines Encl ML20211H4131999-08-27027 August 1999 Informs That Util Revised Encl Bases for TS 2.2.1, Reactor Trip Sys Instrumentation Setpoints, Discussing Steam Flow/ Feed Flow Mismatch Portion of Steam Flow/Feed Flow Mismatch & Low SG Water Level Reactor Trip Setpoint ML20138B3241999-08-23023 August 1999 Forwards Draft Response to Question 1 Re NAPS USI A-46 ML20211D9041999-08-20020 August 1999 Forwards Revised Pages to Third Ten Year ISI Program & Relief Requests, Replacing Pages in 990408 Submittal ML20211B3871999-08-17017 August 1999 Requests Permission to Routinely Discharge from SW Reservior to Waste Heat Treatment Facility Under Existing Vpdes Permit Through Outfalls 108 & 103.Discharges Are Scheduled to Commence on 990907,due to High Priority Placed on Project ML20210T0671999-08-13013 August 1999 Informs of Completion of Review of Proposed Revs of Schedule for Withdrawal of Rv Surveillance Capsules Submitted by VEPCO on 981217.Approves Proposed Revs.Forwards Safety Evaluation ML20210Q9841999-08-12012 August 1999 Forwards Rev 1 to Vepc COLR for North Anna Unit 2,Cycle 13 Pattern Ud, Per TS 6.9.1.7.d.COLR Was Revised to Include Temp Coastdown Operation at End of Cycle 13 ML18152B4081999-08-0606 August 1999 Forwards Response to NRC 990520 & 0525 RAIs Re North Anna & Surry Responses to GL 95-07, Pressure Locking & Thermal Binding of SR Power-Operated Gate Valves. ML20210Q7661999-08-0606 August 1999 Requests Exception to 10CFR50.4 Requirement to Provide Total of Twelve Paper Copies When Submitting Surry & North Anna UFSAR Updates.Seek Approval to Submit Only Signed Original & One CD-ROM Version,Per Conversation with J Skoczlas ML18152B4091999-08-0505 August 1999 Forwards Vepc semi-annual fitness-for-duty Program Performance Data Rept for 990101-990630,IAW 10CFR26.71(d) ML20210N2921999-08-0505 August 1999 Discusses Which Submitted Proposed TSs Bases Change for Containment Leakage. Licensee Changes to Bases May Be Subj to Future Insps or Audits ML20210J8861999-08-0202 August 1999 Provides Clarification to Commitment Made in Identifying Extent by Which Existing Plant Design Complied with RG 1.97,specifically Re Variable, Radiation Exposure Rate ML20210F6121999-07-28028 July 1999 Forwards Supplemental Info on Proposed Irradiation of Fuel Rods Beyond Current Lead Rod Burnup Limit,Documenting Info Provided During 990624 Meeting & Suppl Original Submittal ML18152B3971999-07-26026 July 1999 Provides Estimates of Licensing Actions Expected to Be Submitted in Fys 2000 & 2001,in Response to NRC AL 99-02 ML20209E7621999-07-0909 July 1999 Provides Addl Info to Justify Use of Less than One Gpm Detectable Leakage Rate to Establish Required Margin for Crack Stability in LBB Analysis,Per 980623 Application on Reactor Coolant Loop Bypass Lines 05000338/LER-1999-005, Forwards LER 99-005-00,IAW 10CFR50.73.Commitment Made by Util Encl1999-07-0808 July 1999 Forwards LER 99-005-00,IAW 10CFR50.73.Commitment Made by Util Encl ML20209E3711999-07-0202 July 1999 Forwards Insp Repts 50-338/99-03 & 50-339/99-03 on 990425-0605.Violations Being Treated as Noncited Violations ML18152B4401999-07-0101 July 1999 Informs NRC That on 990511,Dominion Resources,Inc,Executed Amended & Restated Agreement & Plan of Merger with Consolidated Natural Gas Co ML18152B4371999-06-24024 June 1999 Forwards Response to NRC Request for Clarification of Relief Requests Submitted on 990212,requesting Relief from Performing Hydrostatic Testing for Certain Small Diameter Class 1,RCS Pressure Boundary Connections ML20196G2581999-06-23023 June 1999 Discusses Closure of GL 92-01,rev 1,suppl 1,reactor Vessel Structural Integrity ML20212J2951999-06-22022 June 1999 Forwards Corrected Markup & Typed Version of Affected Pages. Requests That Attached Pages for Those Previously Provided in 990506 Submittal Be Replaced & Incorporated Into NRC Review of Proposed TS ML18152B4361999-06-22022 June 1999 Forwards Response to RAI Re Surry & North Anna Power Stations,Units 1 & 2,per GL 96-06 ML20196F1151999-06-22022 June 1999 Forwards Relief Requests NDE-047 & NDE-048 for North Anna Power Station,Unit 1 Re ASME Section XI ISI Program ML20196G2211999-06-21021 June 1999 Forwards Licensee Sampling & Testing Obligations Re Vpdes Permit VA0052451 Reissuance Application.Details of Requests for Sampling & Testing Waivers,Included ML20195J7011999-06-15015 June 1999 Forwards Revised EPIP 2.01 Which Corrects Typo That Was Found in Step 10 of Procedure.Rev Does Not Implement Actions That Decrease Effectiveness of EP ML20195J1391999-06-11011 June 1999 Submits Addl Info as Addendum to Original Application Which Proposed Use of Three Chemicals in Bearing Cooling Tower at North Anna Power Station,Per Reissuance of Vpdes Permit ML18152B4301999-06-0303 June 1999 Informs of Util Intention to Revise Schedule for Submittal of License Renewal Applications for Surry & North Anna Power Stations to March 2002 ML20195C6601999-06-0101 June 1999 Forwards Response to NRC 990216 RAI Re Summary Rept of USI A-46 Program ML20207C9851999-05-28028 May 1999 Requests Regrading of Rt Robinson 990408 Written Exam,Based on Listed Reasons.Answer C for Question 18 Is Requested to Be Reconsidered as Correct or Question Be Deleted ML18152B4261999-05-28028 May 1999 Provides Formal Notification of Effect of Recent Organizational Restructuring on OLs of North Anna & Surry Power Stations,Per NRC 990513 Telcon Request ML18152B4221999-05-27027 May 1999 Forwards Info Concerning Changes to ECCS Evaluation Models & Application in Existing Licensing Analyses for Surry & North Anna Power Stations,Units 1 & 2 ML18152B4231999-05-26026 May 1999 Informs That Vepc Will Revise 180 Day Response to NRC GL 96-05,within 120 Days of Date of Ltr to Incorporate Commitment to Participate in Joint Owners Group Program as Applicable ML20206U7441999-05-20020 May 1999 Informs That NRC Unable to Conclude That NAPS Has Met Intent of Supplement 4 to GL 88-20.RAI Re Fire Area of IPEEE Encl. Response Requested within 90 Days of Submittal Date ML20207A8541999-05-20020 May 1999 Forwards RAI Re Licensee Listed Responses to GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power-Operated Gate Valves. Response Requested within 90 Days of Submittal Date ML20195B5381999-05-14014 May 1999 Forwards Rev 8,Change 2 to North Anna Units 1 & 2 IST Programs for Pumps & Valves. Summaries of Program Changes Provided for Each Unit IST Program.Relief Requests Have Been Removed from IST Programs ML18152A3701999-05-13013 May 1999 Submits Proposal to Use Provisions of ASME Section XI Code Case N-597 for Analytical Evaluation of Class 1,2 & 3 Carbon & Low Alloy Steel Piping Components Subjected to Wall Thinning as Result of Flow Accelerated or Other Corrosion ML20206L4661999-05-10010 May 1999 Forwards SE Accepting Request to Delay Submitting Plant, Unit 1 Class Piping ISI Program for Third Insp Interval Until 010430,to Permit Development of Risk Informed ISI Program for Class 1 Piping 1999-09-08
[Table view] Category:INCOMING CORRESPONDENCE
MONTHYEARML20217K4391999-10-18018 October 1999 Provides Response to RAI to Support USI A-46 Program Submittal for North Anna Power Station,Units 1 & 2.Rev 10 to BNL Rept 52361,encl ML20217H3301999-10-14014 October 1999 Forwards Rev 0 to COLR for North Anna 2 Cycle 14 Pattern Su. No New Commitments Intended by Ltr ML18152B3541999-10-12012 October 1999 Requests Use of Code Case N-532 & N-619,per Provisions of 10CFR50.55a(a)(3).Detailed Info Supporting Request,Encl. Attachment 2 Includes Technical White Paper That Provides Further Technical Info ML20216K1681999-10-0101 October 1999 Forwards Vols I-VIII of Rev 35 to UFSAR for Naps.Rev Also Includes Update to Chapter 17 of Ufsar,Which Contains Operational QA Program.Changes to Program Description Do Not Reduce Commitments Contained Therein ML18152B3391999-09-27027 September 1999 Forwards Revised Relief Request IWE-3,which Now Includes Addl Visual Exam Requirement After post-repair or Mod Pressure Testing Is Completed,Per Telcon with NRC ML20212G5091999-09-22022 September 1999 Forwards in Triplicate,Applications for Renewal of Licenses for Listed Individuals.Encls Withheld,Per 10CFR2.790(a)(6) ML18152B3331999-09-17017 September 1999 Forwards Revised 180-day Response to NRC GL 96-05, Periodic Verification of Design-Basis Capability of Safety-Related Motor-Operated Valves. ML18152B6671999-09-17017 September 1999 Forwards Two NRC Forms 536,containing Info on Proposed Site Specific Operator Licensing Exam Schedules & Estimated Number of Applicants Planning to Take Exams And/Or Gfes,In Response to NRC Administrative Ltr 99-03 ML18152B3341999-09-16016 September 1999 Requests Relief from Specific Requirements of Subsection IWE of 1992 Edition with 1992 Addenda of ASME Section XI Re Containment Liner Examination Requirements,For North Anna & Surry Power Stations ML18152B4471999-09-0101 September 1999 Requests That NRC Remove Listed Labels from Distribution ML20211L9151999-09-0101 September 1999 Forwards Response to NRC Request for Comments Re Closure of Review of Response to GL 92-01,Rev 1,Suppl 1, Reactor Vessel Structural Integrity ML20211H4131999-08-27027 August 1999 Informs That Util Revised Encl Bases for TS 2.2.1, Reactor Trip Sys Instrumentation Setpoints, Discussing Steam Flow/ Feed Flow Mismatch Portion of Steam Flow/Feed Flow Mismatch & Low SG Water Level Reactor Trip Setpoint ML20138B3241999-08-23023 August 1999 Forwards Draft Response to Question 1 Re NAPS USI A-46 ML20211D9041999-08-20020 August 1999 Forwards Revised Pages to Third Ten Year ISI Program & Relief Requests, Replacing Pages in 990408 Submittal ML20210Q9841999-08-12012 August 1999 Forwards Rev 1 to Vepc COLR for North Anna Unit 2,Cycle 13 Pattern Ud, Per TS 6.9.1.7.d.COLR Was Revised to Include Temp Coastdown Operation at End of Cycle 13 ML20210Q7661999-08-0606 August 1999 Requests Exception to 10CFR50.4 Requirement to Provide Total of Twelve Paper Copies When Submitting Surry & North Anna UFSAR Updates.Seek Approval to Submit Only Signed Original & One CD-ROM Version,Per Conversation with J Skoczlas ML18152B4081999-08-0606 August 1999 Forwards Response to NRC 990520 & 0525 RAIs Re North Anna & Surry Responses to GL 95-07, Pressure Locking & Thermal Binding of SR Power-Operated Gate Valves. ML18152B4091999-08-0505 August 1999 Forwards Vepc semi-annual fitness-for-duty Program Performance Data Rept for 990101-990630,IAW 10CFR26.71(d) ML20210J8861999-08-0202 August 1999 Provides Clarification to Commitment Made in Identifying Extent by Which Existing Plant Design Complied with RG 1.97,specifically Re Variable, Radiation Exposure Rate ML20210F6121999-07-28028 July 1999 Forwards Supplemental Info on Proposed Irradiation of Fuel Rods Beyond Current Lead Rod Burnup Limit,Documenting Info Provided During 990624 Meeting & Suppl Original Submittal ML18152B3971999-07-26026 July 1999 Provides Estimates of Licensing Actions Expected to Be Submitted in Fys 2000 & 2001,in Response to NRC AL 99-02 ML20209E7621999-07-0909 July 1999 Provides Addl Info to Justify Use of Less than One Gpm Detectable Leakage Rate to Establish Required Margin for Crack Stability in LBB Analysis,Per 980623 Application on Reactor Coolant Loop Bypass Lines 05000338/LER-1999-005, Forwards LER 99-005-00,IAW 10CFR50.73.Commitment Made by Util Encl1999-07-0808 July 1999 Forwards LER 99-005-00,IAW 10CFR50.73.Commitment Made by Util Encl ML18152B4401999-07-0101 July 1999 Informs NRC That on 990511,Dominion Resources,Inc,Executed Amended & Restated Agreement & Plan of Merger with Consolidated Natural Gas Co ML18152B4371999-06-24024 June 1999 Forwards Response to NRC Request for Clarification of Relief Requests Submitted on 990212,requesting Relief from Performing Hydrostatic Testing for Certain Small Diameter Class 1,RCS Pressure Boundary Connections ML18152B4361999-06-22022 June 1999 Forwards Response to RAI Re Surry & North Anna Power Stations,Units 1 & 2,per GL 96-06 ML20196F1151999-06-22022 June 1999 Forwards Relief Requests NDE-047 & NDE-048 for North Anna Power Station,Unit 1 Re ASME Section XI ISI Program ML20212J2951999-06-22022 June 1999 Forwards Corrected Markup & Typed Version of Affected Pages. Requests That Attached Pages for Those Previously Provided in 990506 Submittal Be Replaced & Incorporated Into NRC Review of Proposed TS ML20195J7011999-06-15015 June 1999 Forwards Revised EPIP 2.01 Which Corrects Typo That Was Found in Step 10 of Procedure.Rev Does Not Implement Actions That Decrease Effectiveness of EP ML18152B4301999-06-0303 June 1999 Informs of Util Intention to Revise Schedule for Submittal of License Renewal Applications for Surry & North Anna Power Stations to March 2002 ML20195C6601999-06-0101 June 1999 Forwards Response to NRC 990216 RAI Re Summary Rept of USI A-46 Program ML18152B4261999-05-28028 May 1999 Provides Formal Notification of Effect of Recent Organizational Restructuring on OLs of North Anna & Surry Power Stations,Per NRC 990513 Telcon Request ML20207C9851999-05-28028 May 1999 Requests Regrading of Rt Robinson 990408 Written Exam,Based on Listed Reasons.Answer C for Question 18 Is Requested to Be Reconsidered as Correct or Question Be Deleted ML18152B4221999-05-27027 May 1999 Forwards Info Concerning Changes to ECCS Evaluation Models & Application in Existing Licensing Analyses for Surry & North Anna Power Stations,Units 1 & 2 ML18152B4231999-05-26026 May 1999 Informs That Vepc Will Revise 180 Day Response to NRC GL 96-05,within 120 Days of Date of Ltr to Incorporate Commitment to Participate in Joint Owners Group Program as Applicable ML20195B5381999-05-14014 May 1999 Forwards Rev 8,Change 2 to North Anna Units 1 & 2 IST Programs for Pumps & Valves. Summaries of Program Changes Provided for Each Unit IST Program.Relief Requests Have Been Removed from IST Programs ML18152A3701999-05-13013 May 1999 Submits Proposal to Use Provisions of ASME Section XI Code Case N-597 for Analytical Evaluation of Class 1,2 & 3 Carbon & Low Alloy Steel Piping Components Subjected to Wall Thinning as Result of Flow Accelerated or Other Corrosion ML20206H0221999-05-0303 May 1999 Informs That Licensee Changes Bases for TS 3/4.6.1.2, Containment Leakage. Changes Allow Use of Other NRC Staff Approved/Endorsed Integrated Leak Test Methodologies to Perform Containment Leakage Rate Testing.Ts Bases Page,Encl ML20206G9481999-05-0303 May 1999 Informs NRC That Insp of 58 Accessible safety-related Pipe Supports Completed in Response to NOV from Insp Rept 50-338/98-05 & 50-339/98-05.Commitments Made Include Plans to Perform Assessment of Welding & Welding Insp ML20205T1181999-04-16016 April 1999 Requests NRC Approval Prior to Proposed Irradiation of Fuel Rods Beyond Current Lead Rod Burnup Limit.Nrc Concurrence with Irradiation Program Requested by End of June 1999 ML20205P1891999-04-0808 April 1999 Forwards ISI Program for Third ten-yr ISI Interval for North Anna Unit 1 for Class 1,2 & 3 Components & Component Support.Third ten-yr Insp Interval for North Anna Unit 1 Begins on 990501.Page 2-26 of Encl Not Included ML20205K3631999-04-0505 April 1999 Requests That Relief Request IWE-3 Be Removed from 980804 Relief Requests Submitted to Nrc.Subject Relief Request Was Inadvertently Retained in Attachment 1 for Unit 1 ML20205K2191999-04-0101 April 1999 Forwards Response to NRC 990106 RAI Re Util Summary Rept on USI A-46 Program,Submitted 970527.Calculations & Corrected Table 11.1-1,encl ML18151A5851999-03-31031 March 1999 Forwards Rept on Status of Decommissioning Funding for Each of Four Nuclear Power Reactors,Per 10CFR50.75(f)(1) ML18152A2801999-03-30030 March 1999 Forwards Summary of Structural Integrity Evaluation of Thermally Induced Over Pressurization of Containment Penetration Piping During DBA for SPS & Naps,Units 1 & 2,per GL 96-06.Draft Proposed UFSAR Revised Pages,Encl ML20204H0331999-03-17017 March 1999 Forwards Rev 5 to PSP for Surry & North Anna Power Stations & Associated Isfsis.Description & Justification for Changes Included with Plan Rev.Rev 5 to PSP Withheld Per 10CFR73.21 ML20205E2701999-02-25025 February 1999 Forwards Rept on Status of Decommissioning Funding for North Anna Power Station,Units 1 & 2.Trust Agreement Between Old Dominion & Bankers Trust Co,Effective 990301,attached ML20207A8741999-02-25025 February 1999 Draft Response to NRC Telcon Re Licensee Request for Approval of LBB Evaluation in Support of Elimination of Augmented Insp Program on RCS Loop Bypass Lines.Response Justifies Use of Less than One Gpm Detectable Leakage Rate ML18152B5401999-02-11011 February 1999 Requests Relief from Specific Requirements of Subsection Iwl of 1992 Edition with 1992 Addenda of ASME Section Xi,Per 10CFR50.55a(a)(3) ML20203C8181999-02-0505 February 1999 Forwards Response to NRC 981217 Telcon RAI Re risk-basis of Nitrogen Accumulator Action Statement to Complete NRC Review of 951025 Proposed TS Changes 1999-09-27
[Table view] |
Text
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e VIRGINIA Eu:cTRic ann POWER COMi%NY l RicuuoNo, ha:N A 23ni July 7,1998 l
US Nuclear Regulatory Commission Serial No. 98-378A Region ll NL&OS/MAE R4' l Atlanta Federal Center Docket No. 72-16 61 Forsyth Street, SW, Suite 23T85 License No. SNM-2507 Atlanta, Georgia 30303 Gentlemen:
l VIRGINIA ELECTRIC AND POWER COMPANY j NORTH ANNA INDEPENDENT SPENT FUEL STORAGE INSTALLATION PREOPERATIONAL TESTING (TAC NO. L22113) l On June 30,1998, Virginia Electric and Power Company (Virginia Power) submitted the preoperational test acceptance criteria and the test results for the dry run of spent fuel
- cask handling activities associated with the Independent Spent Fuel Storage Installation (ISFSI) pursuant to 10 CFR 72.82(e) (Serial No.98-378). This letter submits the l preoperational test acceptance criteria and 11-4 test results for the ISFSI construction
! (attached). The preoperational test results were acceptable.
! Please contact us if you have any questions or require additional information.
Very truly yours, James P. O'Hanlon Senior Vice President - Nuclear Attachment Commitments made by this letter: None i
f
.l 3
O
. s. 1 a ,h \
- l 9807140187 990707 !
PDR ADOCK 0500 3 0 j
\
. 1 cc: 'Mr. Carl J. Paperiello, Director Office of Nuclear Material Safety and Safeguards U. S. Nuclear Regulatory Commission Washington, D. C. 20555 1
Mr. J. W. Shea Office of Nuclear Material Safety and Safeguards
, U. S. Nuclear Regulatory Commission, Mail Stop 14-H-22 Washington, D. C. 20555
.W;M Attention: Document Control Desk Washington, D. C. 20555 Mr. M. J. Morgan NRC Senior Resident inspector North Anna Power Station l
l i
l l
1 l
r Attachment Preoperational Testing for the ISFSI Construction t
l
\ l l
1 E___ __ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _
__ j
1.0 Introduction This preoperational test report addresses the construction of the North Anna independent Spent Fuel Storage Installation (ISFSI). The functional testing of l the ISFSI was conducted in accordance with test plans that were part of the design change packages used to construct the facility. This report covers testing of normal power, emergency power, security systems, cask monitoring system, j telephone system and system interferences due to radios.
l 2.0 Functional Testing of the ISFSI Facility l
Functional Testing of the ISFSI Facility was performed following the completion l of work ca each system and was completed on July 3,1998. The following are l
l the preoperational testing acceptance criteria and test results for the construction
! of the ISFSI.
2.1 Normal Power
, 2.1.1 Transfer of Permanent Power To Facility l
Applicable Procedures:
0-NAT-E-003, Attachment 11.2, Checklist for Circuit Energi:ation
! Acceptance Criterion:
l
- 1. Verify the transfer from temporary construction power to the 34.5 kv power feed to 480 volt and 120 volt circuits dedicated to the ISFSI site.
Results:
! Between June 29,1998 and July 3,1998, power was transferred from temporary construction power to permanent 34.5 kv circuits for the ISFSI. The 480 volt and l 120 volt circuits successfully operated as designed.
1 l
Page 1 of 9
2.2 Emergency Power
~
2.2.1 Emergency Diesel Preoperational Checks Applicable Procedures: l 0-NAT-E-001, Attachment 11.1, Electrical Loop Functional Checkout 0-PT-4.1, 0-FH-DG-1, ISFSI Emergency Diesel Generator Test Acceptance Criteria:
- 1. Verify there are no oil, fuel or water leaks associaed with the diesel generator.
- 2. Verify proper radiator coolant level and fuel oil supply, that drive belts are intact, and that the exhaust system is tight.
- 3. Verify alarm system lamps operate.
- 4. Verify the automatic float / equalize battery charger indicates a voltage of !
greater than or equal to 12 volts and amperage between 0 and 10 amps, inclusive.
- 5. Verify the alarm "lSFSI Lighting Contactor" has been received in the Central Alarm Station (CAS) when the local control switch is placed in the off position.
- 6. Verify that all of the . lighting is illuminated.
Results:
Prior to starting the diesel generator on June 29,1998, the system was verified to be leak tight and there was proper coolant and fuel oil supply. Drive belts were determined to be intact and the exhaust system was tight. An alarm system lamp check was performed and all lights illuminated satisfactorily. The voltage and amperage on the automatic float / equalize battery charger circuits were verified to be within specifications. The CAS received the alarm "lSFSI
. Lighting Contactor" when the local control switch was placed in the off position.
Lighting illuminated properly. The preoperational checks of the emergency diesel generator were determined to be successful.
Page 2 of 9
2.2.2 Transfer of Power From Normal to Emergency Source Applicable Procedures:
0-NAT-E-001, Attachment 11.1, Electrical Loop Functional Checkout 0-PT-4.2, Testing ISFSI UPS and 0-FH-DG-1 Acceptance Criteria:
- 1. Verify that the diesel generator automatically starts within 6 seconds of loss of normal power.
- 2. Verify the diesel generator loads within 300 seconds of reaching 90% of rated voltage.
- 3. Verify the diesel generator operates under load for an initial run of 60 minutcs or more.
- 4. Verify the diesel generator re-transfers load to the normal power supply after closing Breaker No. 5 in panel 0-FH-DB-4.
- 5. Verify the diesel generator automatically shuts down after the " cool down" cycle of approximately 5 minutes after load transfer to the normal bus.
l Results:
On June 29,1998, a functional test of the diesel generator was performed us'ing procedure 0-NAT-E-001, Attachment 11.1, Electrical Loop Functional Checkout.
The purpose of this procedure is to ensure the diesel generator operates in l accordance with the vendor technical manual. This test was successfully completed.
On July 3,1998, the diesel generator was tested in accordance with 0-PT-4.2, Testing ISFSI Security UPS and 0-FH-DG-1. The diesel generator automatically I l
started by initiating a loss of normal power by opening Breaker No. 5 in panel 0-FH-DB-4, which is the normal power supply to the transfer switch. The diesel I generator started in 6.73 seconds. This was greater than the acceptance criteria of 6 seconds. An engineering evaluation was performed and it was determined that the initial acceptance criteria was overly conservative and that a start time of
? l Page 3 of 9
l l .
L 10 seconds or less is acceptable. 0-PT-4.1,0-FH-DG-1 ISFSI Emergency Diesel Generator Test, and 0-PT-4.2 were revised to reflect the new start time. The diesel generator assumed load within 6.87 seconds after reaching 90% of rated voltage and ran for 70 minutes. The transfer of load to the normal power source was completed within 7.65 seconds of closing Breaker No. 5 in panel 0-FH-DB-4 and the diesel generator automatically shutdown in the " cool down" cycle after 5 minutes 4 seconds. The transfer of power from the normal power source to the l
emergency power source was successfully completed.
2.3 Security 2.3.1 Verification of Perimeter Lights Applicable Procedures:
SPIP-015, Security Inspections and Tests l Acceptance Criteria:
- 1. Verify lighting is sufficient to assess threats or unauthorized activities by use of the unaided eye.
- 2. Verify the ability to detect and recognize a person dressed in standard l
working clothes in a prone, crawling or standing and walking position.
Results:
The initial survey was performed on July 1,1998 which provided satisfactory l results to meet the acceptance criteria. However, light adjustments were made to maximize the use of available lighting capabilities and ancther survey was performed on July 2,1998. The results of the survey on July 2 exceeded the acceptance criteria established for the ISFSI.
l 2.3.2 Verification of Closed Circuit Television System' 1
l Applicable Procedures:
SPIP-015, Security inspections and Tests 0-IPM-SEC-PER-001, ISFSI Perimeter Protection System Preventive Page 4 of 9 w ____-__-__ _-_ _
l Maintenance j Acceptance Criteria: '
l l 1. Verify that the CAS/ Secondary Alarm Station (SAS) operator has visual 1
observation of the camera's associated zone and the video switcher directs the signal to the SAS and CAS for the alarmed zone.
- 2. Verify alarms are received when camera junction boxes are opened.
- 3. Verify alarms clear when camera junction boxes are closed.
Results:
Testing of the closed clicuit television system (CCW) was conducted on July 2 and 3,1998. Testing was performed in conjunction with the testing of microwave zones 1 through 6. Testing determined that the CAS/SAS had visual observation of each camera's associated zone ?t the ISFSI site at the time of the alarm. Camera junction boxes were openea and it was verified that the CAS/SAS received the appropriate alarms. When camera junction boxes were closed, it was verified that alarms reset. Testing of the CCW system was performed successfully.
2.3.3 Verification of Perimeter Intrusion Detection System (PIDS)
Applicable Procedures:
SPIP-016, Security inspections and Tests 0-IPM-SEC-PER-001, ISFSI Perimeter Protection System Preventive Maintenance 0-PT-4.2, Testing ISFSI UPS and 0-FH-DG-1 Acceptance Criteria:
- 1. Verify that the CAS receives alarms for each microwave zone when the transmitter and receiver domes are loosened, the transmitter and receiver electronics enclosures are opened, and the transmitter junction box and receiverjunction box are opened. I
- 2. Verify that the CAS receives normal indication following the tightening of Page 5 of 9
each transmitter and receiver dome, closure of each transmitter and receiver electronics enclosure, and closure of the transmitter junction box and receiverjunction box.
- 3. . Verify a minimum of 30 personnel intrusions were successfully performed in each microwave zone.
- 4. Verify the Security Uninterruptible Power Supply (UPS) provides power to the ISFSI security alarm monitoring and communicating devices during load transfers to and from the diesel generator.
Results:
Alarm indication was received in the CAS for tampering of microwave zone transmitters and receivers domes, transmitter and receiver electronics-enclosures and the transmitter junction box and the receiver junction box. Alarm indication returned to normal in the CAS upon returning equipment to its normal state. A minimum of 30 personnel intrusions were successfully performed in each microwave zone to ensure equipment operated correctly to detect personnel intrusion and tampering of equipment. In addition, when the diesel-generator was tested, it was verified that the UPS provided power to ISFSI security alarm monitoring and communication devices during load transfers to and from the diesel generator. Testing of the microwave system was performed satisfactorily.
2.3.4 Verification of Card Reader Applicable Procedures:
L . SPIP-015, inspections and Tests 0-IPM-SEC-PER-001, ISFSI Perimeter Protection System Preventive Maintenance 0-PT-4.2, Testing ISFSI UPS and 0-FH-DG-1 Acceptance Criteria:
- 1. Verify that upon removal of a card reader from its mounting that the CAS L
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operator receives an alarm.
- 2. Verify that upon re-installation of the card reader that the CAS operator receives normalindication.
Results:
The CAS operator was able to receive alarms when card readers were removed from their mounted location. Upon replacement of the card readers, the CAS operator received normal indication. The card readers were tested to ensure they can adequately determine personnel access and egress to the ISFSI site.
Testing of the card readers was performed satisfactorily.
2.4 Cask Monitoring 2.4.1 Verification Of Cask Parameter Alarms Applicable Procedures:
0-NAT-E-001, Attachment 11.1, Electrica! Loop Functional Checkout 0-PT-4.4, Testing ISFSI Dry Cask Alarm Panels Acceptance Criteria:
- 1. Verify alarms on panel 0-FH-IND-1 function properly.
- 2. Verify the remote alarm, "lSFSI Cask Status," in the CAS functions properly.
- 3. Verify the heaters for panels 0-FH-PNL-1 and 2 operate properly.
Results:
On July 3,1998, testing of the cask monitoring alarms was conducted. The test mode on the ISFSI Cask Pressure Alarm D. splay Monitor was selected to verify alarms for cask locations 1-1 through 1-28 on the alarm panel indicated "PS A&B Low (Pressure Switch A&B Low)." The alarms were received as expected. It l was also verified that the alarm "lSFSI Cask Status" was received in the CAS.
- Upon resetting of the system to normal, the alarms cleared on the local panel and in the CAS. A simulated loss of power was alsc performed. This test verified the CAS received the alarm "lSFSI Cask Status."
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On June 30,1998, the heaters for panels 0-FH-PNL-1 and 2 were tested to l ensure the heaters would properly energize and de-energize based on environmental conditions. The heaters operated as designed. The thermostats were set to energize with a decreasing temperature of 60 F in the panels.
Testing verified that cask monitoring parameter alarms operated satisfactorily.
2.5 Telephone 2.5.1 Verification Of Connection Applicable Procedures:
Not applicable Acceptance Criterion:
- 1. Verify proper installation of the telephone by sending and receiving phone messages.
Results:
Following the installation of the telephone at the ISFSI alarm panel station, phone calls were both sent and received successfully.
2.6 System Interferences 2.6.1 Interferences From 800 MHz Radios Applicable Procedures:
0-NAT-E-001, Attachment 11.1, Electrical Functional Checkout Acceptance Criterion:
- 1. Verify that 800 MHz radios in close proximity to the control and alarm panels do not interfere with system operation.
Resulta-On July 1,1998, an 800 MHz hand held radio was operated in close proximity l
(less than one foot) to the cask monitoing alarm panels. No radio interference occurred. Test results were satisfactory.
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i-l 3.0 Conclusion
- The functional testing of the ISFSI was successfully completed. These tests
, verified that the ISFSI will operate safely in accordance with approved
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