Similar Documents at Surry |
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Category:Inspection Report Correspondence
MONTHYEARML18222A3472018-08-10010 August 2018 Notification of Inspection and Request for Information for Nuclear Regulatory Commission Problem Identification and Resolution Inspection IR 05000280/20100042011-02-11011 February 2011 IR 05000280-10-004, 05000281-10-004, 05000280-10-501, and 05000281-10-501, on 10/29/10, Surry Power Station - Errata IR 05000280/20092012009-05-21021 May 2009 IR 05000280-09-201, and IR 05000281-09-201, on 03/27/2009, Surry Nuclear Power Plant - Security Inspection ML0711400732007-06-0606 June 2007 Ltr. to Mr. David A. Christian Surry Nuclear Power Station - Material Control and Accounting Program Inspection IR 05000280/20060092006-08-11011 August 2006 IR 05000280-06-009, IR 05000281-06-009, on 06/12-16/2006 & 06/26-30/2006 for Surry, Units 1 and 2; Triennial Fire Protection Inspection IR 05000280/20040042004-11-24024 November 2004 Errata Surry Power Station - NRC Integrated Inspection Report Nos. 5000280/2004004 and 5000281/2004004 - and Office of Investigations Case Number 2-2003-075 IR 05000280/20010052002-04-25025 April 2002 IR 05000280/2001-005, 05000281/2001-005, Surry Nuclear Power Station, Inspection on 12/30/2001 - 03/30/2002. No Findings of Significance Identified IR 05000280/20010072002-01-18018 January 2002 IR 05000280/2001-007, IR 05000281/2001-007, on 11/26-30 and 12/10-14/2001; Virginia Electric and Power Co., Surry Power Station, Units 1 & 2. Annual Baseline Inspection of the Identification and Resolution of Problems. No Violations Noted ML19095A2711978-04-0606 April 1978 Provide Information on Steam Generator Inspection on Unit 2, Which Supplement to Vepco'S Submittal of 4/4/1978 ML19093B0331977-11-30030 November 1977 Enclosed Justification for Tube Inspection Program & Plugging Criteria, Results of Completed Surry Unit No. 1 Inspection Program with Small Change in Denting ML19095A5231977-09-0202 September 1977 Response to Non-Compliance Item Reported in IE Inspection Reports 50/280/77-20 & 50/281/77-20, & Determined No Proprietary Information Is Contained ML19098B4291977-05-26026 May 1977 Response to Letter of 5/6/1977, in Reference to IE Inspection Reports 50-280/77-7 & 50-281/77-7, Advising No Proprietary Information Is Contained in Reports ML19098B4281977-05-16016 May 1977 Response to Letter of 4/21/1977, in Reference to IE Inspection Reports 50-280/77-4 & 50-281/77-4, Advising No Proprietary Information Is Contained in Reports ML19098B4271977-05-16016 May 1977 Response to Letter of 4/22/1977, in Reference to IE Inspection Reports 50-280/77-5 & 50-281/77-5, Advising No Proprietary Information Is Contained in Reports ML19098B4261977-04-29029 April 1977 Advising Completeness of Unit 1 Steam Generator Inspection Program & Presenting Results of Program in Attachment 1 ML19105A1821975-07-0909 July 1975 Report No. ISI 75-3, Preliminary Results of Inservice Inspection Program Refueling Outage No. 1, Surry Power Station Unit No. 2. 2018-08-10
[Table view] Category:Letter
MONTHYEARML24302A1762024-10-22022 October 2024 Core Operating Limits Report Surry 2 Cycle 33 Pattern Hot Revision 0 ML24283A0702024-10-0707 October 2024 Annual Submittal of Technical Specifications Bases Changes Pursuant to Technical Specification 6.4.J IR 05000280/20240102024-10-0202 October 2024 Biennial Problem Identification and Resolution Inspection Report 05000280/2024010 and 05000281/2024010 ML24270A0022024-09-25025 September 2024 Inservice Inspection Owners Activity Report (OAR) ML24248A1712024-09-0303 September 2024 Proposed License Amendment Request - Temporary Service Water Supply to the Component Cooling Heat Exchangers IR 05000280/20240052024-08-26026 August 2024 Updated Inspection Plan for Surry Power Station, Units 1 and 2 (Report 05000280/2024005 and 05000281-2024005), Rev 1 ML24219A2372024-08-23023 August 2024 Issuance of Amendment Nos. 319 and 319, Adoption of TSTF-577, Rev. 1, Revised Frequencies for Steam Generator Tube Inspection, ML24207A0402024-08-21021 August 2024 Summary of July 17, 2024, Public Meeting - TS 3.7/3.14 AOT for SW Piping Maintenance IR 05000280/20240112024-08-13013 August 2024 Comprehensive Engineering Team Inspection Report 05000280/2024011 and 05000281/2024011 ML24164A0012024-08-12012 August 2024 Proposed Alternative Relief Request V-1 Inservice Testing of Pressure Isolation Valves (EPID l-2023-LLR-0060) IR 05000280/20240022024-08-0101 August 2024 Integrated Inspection Report 05000280/2024002 and 05000281/2024002 05000280/LER-2024-001, Troubleshooting Initiated Unknown Turbine Trip Feature in Control System2024-07-30030 July 2024 Troubleshooting Initiated Unknown Turbine Trip Feature in Control System ML24165A2782024-07-17017 July 2024 Issuance of Amendment Nos. 318 and 318, Reclassification of Regulatory Guide 1.97 Variable for Low Head Safety Injection ML24165A1232024-07-17017 July 2024 Proposed Alternative Relief Request P-1, P-2 Inservice Testing of Residual Heat and Containment Spray Pumps (EPID l-2023-LLR-0058) ML24190A4192024-07-0808 July 2024 Inservice Testing (IST) Program for Pumps and Valves Revised Sixth IST Interval Start Date and Updated Technical Specifications References for Alternative Request V-1 ML24179A2932024-07-0101 July 2024 Notification of Inspection and Request for Information for NRC Problem Identification and Resolution Inspection ML24178A2422024-06-25025 June 2024 2023 Annual Report of Emergency Core Cooling System (ECCS) Model, Changes Pursuant to the Requirements of 10 CFR 50.46 ML24177A2792024-06-20020 June 2024 Preparation and Scheduling of Operator Licensing Examinations ML24166A0622024-06-18018 June 2024 – Proposed Alternative Relief Request P-3, P-4 Inservice Testing of Boric Acid, Component Cooling Water Pumps ML24157A0542024-06-13013 June 2024 Audit Summary in Support of License Amendment Request for Proposed Reclassification of Low Head Safety Injection Flow Instrumentation Related to Regulatory Guide 1.97 ML24143A1622024-06-12012 June 2024 – Correction to Issuance of Amendment Nos. 297 and 280 and Surry Units 1 and 2, Correction to Issuance of Amendment Nos. 317 and 317, to Change Emergency Plan Staff Augmentation Times ML24170B0532024-06-10010 June 2024 DOM-NAF-2-P/NP-A, Revision 0.5, Reactor Core Thermal-Hydraulics Using the VIPRE-D Computer Code ML24141A2862024-05-22022 May 2024 Information Request for the Cyber Security Baseline Inspection, Notification to Perform Inspection 05000280/2024403 and 05000281- 2024403 IR 05000280/20244032024-05-22022 May 2024 Information Request for the Cyber Security Baseline Inspection, Notification to Perform Inspection 05000280/2024403 and 05000281- 2024403 ML24141A2512024-05-20020 May 2024 Proposed License Amendment Request - Reclassification of Low Head Safety Injection Flow Indication Regulatory Guide 1.97 Variable - Supplemental Information ML24141A0482024-05-17017 May 2024 EN 56958_1 Ametek Solidstate Controls, Inc ML24136A2302024-05-13013 May 2024 Core 1 Cycle 33 Pattern Mdr Revision 0 ML24130A2032024-05-0909 May 2024 Proposed License Amendment Request Application to Revise Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam Generator Tube Inspections Supplemental Information ML24130A2492024-05-0909 May 2024 Submittal of Information in Support of Surry Power Station Unit 1 Thermal Shield Flexure Replacement Campaign ML24130A1192024-05-0707 May 2024 Inservice Test Program for Pumps and Valves Sixth Interval Update and Associated Relief and Alternative Requests - Response to Request for Additional Information Regarding Alternative Request V-1 ML24122C6522024-04-30030 April 2024 Annual Radiological Environmental Operating Report ML24142A3852024-04-30030 April 2024 2023 Annual Radioactive Effluent Release Report IR 05000280/20240012024-04-30030 April 2024 Integrated Inspection Report 05000280-2024001 and 05000281-2024001 ML24122B3032024-04-29029 April 2024 Associated Independent Spent Fuel Storage Installation, Revision to Emergency Plan Report of Change IR 05000280/20244022024-04-29029 April 2024 Security Baseline Inspection Report 05000280/2024402 and 05000281/2024402 ML24115A1952024-04-24024 April 2024 Notification of Surry Power Station Comprehensive Engineering Team Inspection - U.S. NRC Inspection Report 05000280/2024011 and 05000281/2024011 ML24054A0142024-04-22022 April 2024 Issuance of Amendment Nos. 297 and 280, and Surry Power Station Unit Nos. 1 and 2, Issuance of Amendment Nos. 317 and 317, to Change Emergency Plan Staff Augmentation Times ML24108A1812024-04-15015 April 2024 Proposed License Amendment Request - Reclassification of Low Head Safety Injection Flow Indication Regulatory Guide 1.97 Variable Supplemental Information ML24095A2172024-04-12012 April 2024 – Review of the Spring 2023 Steam Generator Tube Inspection Report ML24088A2482024-03-26026 March 2024 Inservice Testing Program for Pumps and Valves Sixth Interval Update and Associated Relief and Alternative Requests- Response to Request for Additional Information ML24087A2082024-03-22022 March 2024 Proposed License Amendment Request Addition of Containment Limiting Condition for Operation and Surveillance Requirements ML24078A2642024-03-21021 March 2024 – Regulatory Audit in Support of License Amendment Request to Proposed Reclassification of Regulatory Guide 1.97 Variable for Low Head Safety Injection Flow Instrumentation ML24087A1522024-03-18018 March 2024 Annual Changes, Tests, and Experiments Report Regulatory Commitment Evaluation Report ML24023A5762024-03-0808 March 2024 Correction to Issuance of Amendment Nos. 315 and 315, Regarding Revised Emergency Plan for Relocation of the Technical Support Center IR 05000280/20230062024-02-28028 February 2024 Annual Assessment Letter for Surry Power Station, Units 1 and 2 - NRC Inspection Reports 05000280/2023006 and 05000281/2023006 ML24032A4712024-02-20020 February 2024 Exemption from Select Requirements of 10 CFR Part 73 - Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting ML24057A0612024-02-19019 February 2024 And Virgil C. Summer Power Nuclear Stations - Nuclear Property Insurance Coverage ML24051A1782024-02-19019 February 2024 Proposed License Amendment Request - Application to Revise Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam Generator Tube Inspections IR 05000280/20230042024-02-0909 February 2024 Integrated Inspection Report 05000280/2023004 and 05000281/2023004 IR 05000280/20244012024-02-0606 February 2024 Security Baseline Inspection Report 05000280/2024401, 05000281/2024401 and 07200002/2024401 2024-09-03
[Table view] Category:Response to Request for Additional Information (RAI)
MONTHYEARML24141A2512024-05-20020 May 2024 Proposed License Amendment Request - Reclassification of Low Head Safety Injection Flow Indication Regulatory Guide 1.97 Variable - Supplemental Information ML24130A1192024-05-0707 May 2024 Inservice Test Program for Pumps and Valves Sixth Interval Update and Associated Relief and Alternative Requests - Response to Request for Additional Information Regarding Alternative Request V-1 ML23220A1482023-08-0707 August 2023 Proposed Emergency Plan Revision - Relocation of the Technical Support Center (TSC) Response to Request for Additional Information ML23208A0922023-07-26026 July 2023 Request for Approval of Appendix F of Fleet Report DOM-NAF-2-P Qualification of Framatome ORFEO-GAIA and OORFE-NMGRID CHF Correlations in the Dominion Energy Vipre-D Computer Code Response L-04-002, Stations - NRC Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors Fleet Response to Request for Additional Information2023-05-0808 May 2023 Stations - NRC Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors Fleet Response to Request for Additional Information ML23096A1972023-04-0606 April 2023 License Amendment Request - Application of Risk-Informed Approach for Tornado Classification of the Fuel Handling Trolley Support Structure - Response to Request for Additional Information ML23096A2982023-04-0606 April 2023 Units 1 and 2 and Millstone Power Station, Units 2 and 3 - Request for Approval of Appendix F of Fleet Report DOM-NAF-2-P Qualification of the Framatome ORFEO-GAIA and ORFEO-NMGRID CHF Correlations in the Dominion ML23089A3542023-03-30030 March 2023 Response to Request for Additional Information Regarding Proposed License Amendment Request to Revise Emergency Plan Staff Augmentation Times ML23044A0392023-02-11011 February 2023 Alternative Request to Defer ASME Code Section XI Inservice Inspection Examinations for Pressurizer and Steam Generator Pressure-Retaining Welds and Full Penetration Welded Nozzles Response to Request for Additional Information ML23025A1252023-01-25025 January 2023 Response to Request for Additional Information License Amendment Request, NRC Approval of Methodology Change and Reclassification of the Turbine Building as a Tornado Resistant Structure ML22343A0002022-12-0909 December 2022 Response to Request for RAI on ASME Operation & Maintenance Code Inservice Testing Program - Request for Approval of Alternative Request V-01 Use of Mechanical Agitation Process for Pressure Isolation Valve 1-SI-241 Seat Leakage Testing ML22342A4242022-12-0707 December 2022 Response to 3/12/2012 Request for Information Enclosure 2, Recommendation 2.0, Flooding Focused Evaluation Integrated Assessment Submittal Revised Commitment Completion Date ML22312A4432022-11-0707 November 2022 NRC Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors Fleet Response to RAI ML22300A1882022-10-27027 October 2022 License Amendment Request 10-Day Allowed Outage Time for Opposite Unit Auxiliary Feedwater Cross-Connect Capability Response to Request for Additional Information ML22220A2162022-08-0808 August 2022 License Amendment Request 10-Day Allowed Outage Time for Opposite Unit Auxiliary Feedwater (AFW) Cross-Connect Capability Supplemental Information ML22164A8532022-06-13013 June 2022 Proposed License Amendment Request Removal of Refueling Water Chemical Addition Tank and Replacement of Containment Sump Buffer - Response to Request for Confirmation ML22153A1352022-06-0202 June 2022 Proposed License Amendment Request (LAR) - Removal of Refueling Water Chemical Addition Tank and Replacement of Containment Sump Buffer - Response to Request for Additional Information ML21292A3022021-10-19019 October 2021 Response to Question on License Amendment Request to Revise Reactor Core Safety Limit ML21259A0852021-09-15015 September 2021 North Ann, and Surry, Units 1 and 2, Millstone, Units 2 and 3, Request for Approval of Appendix E of Fleet Report DOM-NAF-2-A Qualification of the Framatome BWU-I CHF Correlation in the Vipre-D Computer Code Response to Request for Addition ML21133A4212021-05-13013 May 2021 Response to NRC Request for Additional Information Regarding Proposed License Amendment Request Update of LOCA Alternative Source Term Dose Analysis ML21133A2852021-05-13013 May 2021 Stations, Units 1 & 2 and Millstone Power Station, Units 2 and 3 - Request for Approval of Appendix E Fleet Report DOM-NAF-2-A Qualification of the Framatome Bwui CHF Correlation in the Dominion Energy VIPRE-D Computer Code ML21098A2612021-04-0808 April 2021 Subsequent License Renewal Application, Response to Request for Additional Information Re Environmental Review ML21084A2732021-03-24024 March 2021 License Amendment Request - Application of Leak-Before-Break Methodology to Reactor Coolant System Branch Piping - Response to Request for Additional Information and Clarification ML21056A5412021-02-25025 February 2021 NRC Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors Final Supplemental Response ML21042B9262021-02-11011 February 2021 ASME Section XI Inservice Inspection Program Request for NRC Approval of Proposed Alternative Requests S1-I5-ISl-05 and S2-I5-ISl-06 - Response to Request for Additional Information ML22040A1012021-02-0909 February 2021 Response to Request for Additional Information 2021 Steam Generator Inservice Report ML20296A7272020-10-22022 October 2020 Stations Units 1 & 2 - Proposed License Amendment Requests Addition of Analytical Methodology to the Core Operating Limits Report for a Small Break LOCA Supplement to the Response to Request for Additional Information ML20247J6352020-09-0303 September 2020 Virginia Electric & Power Co - Subsequent License Renewal Application (SLRA) Environmental Review, Response to Request for Additional Information Concerning Aquatic Resources ML20181A4222020-06-29029 June 2020 Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors Response to Request for Additional Information ML20181A3082020-06-23023 June 2020 Response to Request for Additional Information on 2019 Steam Generator Inservice Inspection Report ML20269A4072020-06-0202 June 2020 Enclosure 2 - Dominion Energy Surry Power Station Vpdes Permit No. VA0004090: Application for Permit Reissuance - 316(b) 40 CFR 122.21(r)(2)-(13), Part 2 of 3 ML20269A4062020-06-0202 June 2020 Enclosure 2 - Dominion Energy Surry Power Station Vpdes Permit No. VA0004090: Application for Permit Reissuance - 316(b) 40 CFR 122.21(r)(2)-(13), Part 3 of 3 ML20269A4082020-06-0202 June 2020 Enclosure 2 - Dominion Energy Surry Power Station Vpdes Permit No. VA0004090: Application for Permit Reissuance - 316(b) 40 CFR 122.21(r)(2)-(13), Part 1 of 3 ML20149K6942020-05-28028 May 2020 Response to Request for Additional Information, to Proposed License Amendment Requests Addition of Analytical Methodology to the Core Operating Limits Report for a Small Break Loss of Coolant Accident ML20034F0532020-01-31031 January 2020 Proposed License Amendment Request: Allowed Outage Time Extension for Replacement of Reserve Station Service Transformer C 5KV Cables to Transfer Bus F Response to Request for Clarification and Additional Information ML19350A0042019-12-12012 December 2019 License Amendment Request Addition of 24-Hour Completion Time for an Inoperable Reactor Trip Breaker Response to NRC Request for Additional Information ML19283B6222019-10-10010 October 2019 Subsequent License Renewal Application Safety Review - Documentation of Draft Third Round Requests for Additional Information ML19291B0342019-10-0101 October 2019 Response to March 12, 2012 Request for Information Enclosure 2, Recommendation 2.1, Flooding Focused Evaluation/Integrated Assessment Submittal ML19269B7342019-09-19019 September 2019 Subsequent License Renewal Application - Response to Requests for Additional Information - Sets 3 and 4 Revised SLRA Mark-Ups ML19267A0422019-09-16016 September 2019 Subsequent License Renewal Application Response to NRC Requests for Confirmation of Information Set 2 ML19253B3302019-09-0303 September 2019 Response to Requests for Additional Information - Sets 3 and 4 - Subsequent License Renewal Application ML19249B7672019-08-29029 August 2019 Enclosure 1 - Millstone, Units 2 and 3 and ISFSI; North Anna, Units 1 and 2 and ISFSI; and Surry, Units 1 and 2 and ISFSI - Response to EAL Scheme Change RAIs ML19204A3572019-07-17017 July 2019 Subsequent License Renewal Application Response to Request for Additional Information - Set 2 ML19198A0592019-07-11011 July 2019 Subsequent License Renewal Application - Response to NRC Requests for Confirmation of Information ML19196A1102019-07-0909 July 2019 Attachments 2, 3 & 4 - Response to NRC Request for Additional Information and Correction of SBLOCA Analysis Error and Revised Marked-Up/Typed NAPS and SPS Technical Specifications Pages ML19183A3862019-06-27027 June 2019 Subsequent License Renewal Application - Response to Requests for Additional Information - Set 1 ML19148A4212019-05-10010 May 2019 All Enclosures with Coversheets ML18304A3302018-10-25025 October 2018 Proposed License Amendment Request TSTF-490 & Update of Alternative Source Term Analyses Response to Request for Additional Information & Revised Proposed Technical Specifications ML18302A1212018-10-18018 October 2018 Response to Request for Additional Information, Revised Reactor Vessel Materials Surveillance Capsule Withdrawal Schedules ML18303A2882018-10-18018 October 2018 Response to Request for Additional Information Regarding Relief Request S2-I5-LMT-P01 Examination Category R-A, Preservice Weld Examinations 2024-05-07
[Table view] |
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RESPONSE TO THE NON-COMPLIANCE ITEM REPORTED IN IE INSPECTION REPORT NO. 50-280/77-4 AND 50-281/77-4 NRG Comment Contrary to Technical Specification 4.4.B.a and the provisions of Section 6 of ANS 7.60 (April 29, 1970), sensor output of thermometric devices used to obtain temperature and humidity data during the Unit 2 containment integrated leak rate test on April 24-27, 1976, were not com-pared over the expected operating range with a reference the1mometer of established calibration traceable to standards with a known valid relation-ship to the National Bureau of Standards or other recognized standard.
Response
The above infraction is correct as stated. It is recognized that all instr~mentation is required to be calibrated to standards traceable to the National Bureau of Standards prior to use, even though the maximum deviation from that instrument is included in the error analysis.
Specifically, pursuant to section 2.-201 of the }..TRC' s "Rules of Practice",
Part 2, Title 10, Cod_e of Federal Regulations, the following information is submitted:
- 1. Corrective steps taken and the results achieved, specifically in NRG Request (Item 2)
Any calibration performed subsequent to the Type A test which reconfirmed that the results of the test stated in your report SR-S2-76-01 remain valid.
Response
a) . In December 1976, a test was performed to confirm the accuracy of the installed containment air temperature RTD's. This involved a comparison of the RTD's computer output with the reading of a portable temperature detector adjacent* to the installed RTD. Two of .the installed RTD's were tested in this manner, and agreement was within the 1/2 degree accuracy of the instrument.
A computer sensor calibration was performed prior to the unit containment integrated leak rate test to verify in-strument repeatability. In addition, all RTD's responded in unison to the air temperature changes which occurred during the test period.
Based on their performance during the leak rate test, the computer repeatability check and the RTD accuracy test of December 1976, it' is concluded that the accuracies of the contai_nrnent air temperature RTD' s were within the
- d *for thei'r use 1.'n the containment air accuracy require
- --* e mass calculations as shown in the error analysis.
- b) In January 1977, a test was performed to verify the accuracy of the installed dew cells which were used in the contain-ment air mass calculations. This test involved comparison of the dew cell output with results obtained from a hand held psychrometer adjacent to the dew cells. Results in-dicated that the installed dew cells were in .error in ex-cess of the manufacturers specifications. In all cases, the reading obtained from the installed dew cells was lower than the actual value.
Computer sensor calibration checks of the dew cell. signals indicated acceptable repeatability for all dew cells. The dew cells responded in unison- to the humidity changes which occurred during the test period. These results indicate that during the containment integrated leak rate test, the installed dew cells were operational, with acceptable re-peatability, but were low in their indications.
The dewpoint temperature is used to determine a vapor pressure correction to the overall containment pressure.
A small variation of dew point temperature was experienced during this test; therefore, the repeatability of the dew cells is of greater significance than the instruments over-all accuracy in these calculations.
The error in dew cell indication did produce a small error in leakage rate calculations due to the non-linear relation-ship between vapor pressure and dew point temperature. A study was performed to determine the maximum effect which this error could have produced in overall test results.
All calculations for both the reference and absolute method were performed with corrections for the worst *case dew cell error. These calculations indicate that assuming the worst observed dew cell error; only a small conservative error.
in the overall leak rate calculation results. Based on these results, it is.concluded that any error due to dew cell inaccuracies was in the conservative direction, and of such.
magnitude that there was no significant effect on overall results.
'NRG Request (Item 3)
Those actions taken which assure that flow measurement devices, used to obtain Type C local leak rate, have been calibrated in accordance with the current approved quality assurance program re-quirements, and this calibration confirmed the Type C data of your report SR-S2-76-0l.
Response, Nine rotameters were used for air flow rate measurements with the three, which were traceable to the NBS and certified to~ 1%,
. *e
- used wherever ,.possible. :The remainder were tested using the non-traceable instruments, which are certified to+/-5% by the manufacturer.
In order to verify the accuracy of-these instruments, each of the non-traceable instruments was cross-calibrated with a traceable instrument. *The* average error of the non-traceable instruments was found to **be *considerably better than the 5% stated by the man-ufacturer.
Therefore, the Type C error of 5%, assumed for the calculations in report SR-S2-76-0l, was conservative.
Additional rotameters, traceabie to the NBS, have been received.
These instruments should eliminate the need for use of non-traceable rotameters in Type C testing. All instruments used for Type C test-ing, including pressure gages and rotameters will be calibrated within 90 *days prior to their use. Calibration will be done by the man-ufacturer, or by our calibration staff via cross-calibration with an instrument of known accuracy.
- 2. Corrective steps which will be.taken to avoid further non-compliance, specifically in response to:
NRC Request (Item 1)
Those actions which assure that temperature and humidity mea-
. surement instrument calibrations are on a calibration schedule con-sistent with your current quality assurance program requirements.
Response
The RTD's, due to their design and principle of operation, have been and continue to be accurate and reliable. Therefore, a calibra-tion within 90 days prior to the contairnnent integrated leak test is proper and will verify the acceptability of the temperature data for use in the containment air mass calculations.
The calibration of the dew cells will-also occur within 90 days prior to the contairnnent integrated leak test.
- 3. The date when full compliance will be achieved:
.As the calibrations and subsequent error analysis cf both the Type A and Type G tests have been completed' satisfactorily .and the temper-ature and humidity measurement instruments are on a schedule con-sistent with our quality assurance program requirements, full com-pliance has been achieved.