Similar Documents at Surry |
---|
Category:Letter
MONTHYEARML24248A1712024-09-0303 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 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 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 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 IR 05000280/20240012024-04-30030 April 2024 Integrated Inspection Report 05000280-2024001 and 05000281-2024001 ML24142A3852024-04-30030 April 2024 2023 Annual Radioactive Effluent Release Report ML24122C6522024-04-30030 April 2024 Annual Radiological Environmental Operating Report IR 05000280/20244022024-04-29029 April 2024 Security Baseline Inspection Report 05000280/2024402 and 05000281/2024402 ML24122B3032024-04-29029 April 2024 Associated Independent Spent Fuel Storage Installation, Revision to Emergency Plan Report of Change IR 05000280/20240112024-04-24024 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 ML23312A1922024-01-18018 January 2024 Issuance of Amendment Nos. 316 & 316 Regarding a Risk Informed Approach for Tornado Classification of the Fuel Handling Trolley Support Structure IR 05000280/20230102024-01-18018 January 2024 Age Related Degradation Inspection Report 05000280-2023010 and 05000281-2023010 ML24003A9022024-01-0303 January 2024 Stations, Units 1 and 2, Emergency Plan Revision - Relocation of the Technical Support Center (TSC) - Editorial Correction IR 05000280/20233012023-12-28028 December 2023 NRC Operator License Examination Report 05000280/2023301 and 05000281/2023301 ML23283A3052023-12-20020 December 2023 Review of Appendix F to DOM-NAF2, Qualification of the Framatome ORFEO-GAIA and ORFEO-NMGRID CHF Correlations in the Dominion Energy VIPRE-D Computer Code (EPID L-2022-LLT-0003) (Nonproprietary) ML23352A3692023-12-18018 December 2023 Associated Independent Spent Fuel Storage Installation, Revision to Emergency Plan Report of Change ML23334A2342023-11-30030 November 2023 Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation ML23242A2292023-11-0707 November 2023 Issuance of Amendment Nos. 315 and 315, Regarding Emergency Procedure Relocation of the Technical Support Center ML23200A2622023-11-0202 November 2023 Issuance of Amendment Nos. 314 and 314, Regarding Technical Specification and Spent Fuel Pool Criticality Change 2024-09-03
[Table view] Category:Licensee Event Report (LER)
MONTHYEAR05000281/LER-2020-001, Cancellation of LER 2020-001-00 for Surry Power Station Unit 2 Re Loss of Containment Cooling Affecting Containment Partial Pressure Indication2020-11-0606 November 2020 Cancellation of LER 2020-001-00 for Surry Power Station Unit 2 Re Loss of Containment Cooling Affecting Containment Partial Pressure Indication 05000280/LER-2019-0022020-02-0404 February 2020 LER 2019-002-00 for Surry Power Station Unit 1, Items Non-Conforming to Design for Tornado Missile Protection 05000280/LER-2017-0012017-10-0606 October 2017 1 OF 3, LER 17-001-00 for Surry, Unit 1, Regarding Shutdown due to an Unisolable Leak in Reactor Coolant Pressure Boundary 05000281/LER-2016-0012016-12-0202 December 2016 Unit 2 Reactor Trip due to Generator Differential Lockout, LER 16-001-00 for Surry Power Station, Unit 2, Regarding Reactor Trip Due to Generator Differential Lockout 05000280/LER-2016-0012016-07-11011 July 2016 1 OF 4, LER 16-001-00 for Surry Power Station, Unit 1 and 2, Regarding Emergency Service Water Pump Inoperable Due to Corrosion of Valve Support ML1015505662009-03-0404 March 2009 Event Notification for Surry on Relief Valve Failure Results in Tritium and Cesium Spill ML0702501902007-01-17017 January 2007 Special Report on Qpt Not Less than Two Percent for Twenty Four Hours ML19105B1281979-08-21021 August 1979 LER 1979-011-03X for Surry Units 1 & 2 Loss of Power with Both Units at Cold Shutdown, Observed Radiation Monitors Without Power ML19093B4141978-09-26026 September 1978 Reporting Condenser Cooling Water Outlet Temperature to James River Decreased by 3.5oF as Measured at Station Discharge Structure ML19105A3001978-09-0808 September 1978 LER 78-013-03X-1, LER 78-029-03L-0, & LER 78-031-03L-0 for Surry 2 Re Critical Below Minimum Insertion Limit on D Control Bank ML19105A3011978-09-0101 September 1978 LER 1978-028-03L-0 for Surry 2 Re Containment Pressure Exceeded Allowable Limit ML19095A4971978-08-25025 August 1978 Submit Licensee Event Report No. LER 78-024/03L-0 Re No Alarm During a Planned Release of Liquid Radioactive Waste ML19095A4981978-08-22022 August 1978 Submit Licensee Event Report Nos. LER 1978-019/03L-0, LER 1978-021/03L-0, LER 1978-022/03L-0, LER 1978-023/03L-0, LER 1978-025/03L-0, LER 1978-026/03L-0 for Surry Unit No. 1 ML19105A0771978-08-16016 August 1978 Submit LER 78-027/03L-0 Re Seven Snubbers Not Meeting Inspection Criteria ML19105A0781978-08-16016 August 1978 Submit LER 78-027/03L-0 Re Seven Snubbers Not Meeting Inspection Criteria ML19105A0791978-08-11011 August 1978 LER 78-026/03L-0. Follow-up Inspection for Valve Cleanliness, Discovered That Containment Spray Isolation Valves (MOV-CS-201C and D) Contained No More That Five Milliliters. Technical Specification TS 6.6.2.b.(3) ML19095A4991978-08-0404 August 1978 Sutmit Licensee Event Report No. LER 78-018/03L-0 Re Two Main Steam Safety Valves Were Not within Plus or Minus 3% of Setpoint as Required ML19105A0801978-07-28028 July 1978 LER 1978-022-03L-0 Re Axial Power Distribution Monitoring Was Exceeded,& Three LERs 1978-021-03L-0, LER 1978-023-03L-0, & LER 1978-024-03L-0 Re Inlet Circulating Water Temperature Exceeded ML19095A5001978-07-28028 July 1978 Submit Licensee Event Report Nos. LER 78-017/03L-0 Re Not Documenting Four Electric Maintenance Procedures & Two Periodic Tests, & 78-020/03L-0 Re Suspended Air Bubbles in Reservoir Fluid ML19095A2281978-07-27027 July 1978 Reporting & Providing Additional Information on Incidence of Missing Two Steam Generator Tube Plugs Found During Inspection ML19095A2291978-07-26026 July 1978 Reporting of Cooling Water Discharge Temperature Change Rate on 7/9/1978 & Found No Evidence of Any Detrimental Effects in River or Its Inhabitants ML19095A5011978-07-21021 July 1978 Submit Licensee Event Report No. LER 78-016/03L-0 Re Valve MOV-RH-100 Was Not Opening ML19105A0821978-07-17017 July 1978 LER 1978-025-03L for Surry Unit 2 Excessive Gap Around Battery Room Ventilation Duct ML19105A0811978-07-17017 July 1978 LER 1978-025-03L for Surry Unit 2 Excessive Gap Around Battery Room Ventilation Duct ML19095A5021978-07-0707 July 1978 Submit Licensee Event Report Nos. LER 78-013/03L-0 Re Six Snubbers Not Meeting Test Criteria, & 78-014/03L-0 Re Mount Plate Was Warped, & 3 of 8 Bolts Were Insufficiently Embedded ML19095A5031978-06-27027 June 1978 Submit Licensee Event Report No. LER-78-015/03L-0 Re Valve Cleanliness Inspection Found Foreign Material on Valve Seating Surfaces ML19095A5041978-06-27027 June 1978 Submit Licensee Event Report No. LER-78-015/03L-0 Re Valve Cleanliness Inspection Found Foreign Material on Valve Seating Surfaces ML19105A0831978-06-23023 June 1978 LER 1978-017-03L, LER 1978-018-03L, LER 1978-019-03L, & LER 1978-020-03L for Surry Unit 2 Related to Snubbers ML19095A2481978-06-19019 June 1978 06/19/1978 Letter Reporting Increase of Condenser Cooling Water Discharge ML19095A5051978-06-0707 June 1978 Submit Licensee Event Report No. LER-78-012/03L-0 Re Inside Recirculation Spray Pump 1-RS-P-1A, Failure to Rotate by Hand ML19105A0851978-05-23023 May 1978 LER 1978-015-03L for Surry Unit 2 Finding of Air Leak on Header of Control Room Emergency Air Supply Bank ML19095A5061978-05-23023 May 1978 Submit Licensee Event Report Nos. LER-78-008/03L-0, LER-78-009/03L-0, LER-78-010/03L-0, LER-78-011/03L-0 for Surry Unit No. 1 ML19105A0861978-05-12012 May 1978 LER 1978-013-03L for Surry Unit 2 Reactor Brought Critical Below Minimum Insertion Limit on D Control Bank ML19105A0871978-05-0505 May 1978 LER 1978-014-03L for Surry Unit 2 Charging Pump Service Water Pump a Tripped on High Current ML19095A5071978-05-0505 May 1978 Submit Licensee Event Report No. LER-78-007/03L-0 Re Leak on Body to Bonnet Joint Diaphragm Valve 1-CH-98 ML19105A0881978-04-19019 April 1978 LER 1978-006-01T for Surry Unit 2 Review of Fire Protection Yard Piping Revealed That Two Pipe Extensions May Not Have Been Seismically Qualified ML19095A5081978-04-19019 April 1978 Submit Licensee Event Report No. LER-78-006/01T-0 Re Seismically Disqualified Two Pipe Extensions on Fire Protection Yard Piping ML19095A5091978-04-0707 April 1978 Forwarding Licensee Event Report No. LER-78-005/01T-0 Re Westinghouse'S Error in LOCA-ECCS Evaluation Model, Which Will Result in Higher Calculated Peak Clad Temperature ML19105A0901978-04-0606 April 1978 LER 1978-012-01T for Surry Unit 2 Failure to Meet Containment Integrity ML19105A0921978-04-0404 April 1978 LER 1978-011-03L for Surry Unit 1 Loss of Service Water Flow Through Charging Pump Intermediate Seal Cooler ML19095A5101978-04-0404 April 1978 Submit Licensee Event Report No. LER-78-004/03L-0 Re Loss of Service Water Flow Through Charging Pump Intermediate Seal Cooler ML19105A0931978-03-30030 March 1978 LER 1978-008-03L Re Snubber Body in Contact with Structure; LER 1978-009-03L Re Trip of Boric Acid Transfer Pump; & LER 1978-010-03L Re Failure of Pressurizer Channel ML19095A5111978-03-28028 March 1978 Submit Licensee Event Report No. LER-78-003/03L-0 Re Failed Heat Tracing, Panel 8 Circuit 24 ML19095A5121978-03-21021 March 1978 Submit Licensee Event Report No. LER-78-002/01T-0 Re Additional Radial Peaking Factor Surveillance ML19105A0941978-02-27027 February 1978 LER 1978-006-03L Re Failure of Sola Transformer, & LER 1978-007-03L Re Trip of Boric Acid Transfer Pump on Thermal Overload ML19095A5131978-02-24024 February 1978 Submit Licensee Event Report No. LER-78-001/03L-0 Re Hydraulic Shock Suppressor Found Inverted with Empty Reservoir ML19105A0951978-02-16016 February 1978 LER 1978-003-03L Re Erroneous Readings of Loop a Hot Leg Temperature Protection Channel; LER 1978-004-03L Re Unqualified Welding of Two Diaphragm Welds on Heat Exchanger; & LER 1978-005-03L Re Low Current Condition from Heat Tracing ML19105A0971978-02-0202 February 1978 LER 1978-001-03L for Surry Unit 2 Inoperability of Condenser Circulating Water Outlet Valve ML19095A5141978-01-0909 January 1978 Submit Licensee Event Report Nos. LER-77-021/03L-0 & LER-77-022/03L-0 ML19105A0991978-01-0909 January 1978 LER 1977-021-03L Re Routine Sampling of Bast a Revealed Tank Was at Concentration of 11.5%, & LER 1977-022-03L Re Failure of Comparator to Trip During Routine Test of a Steam Generator Level Protection Channel II 2020-02-04
[Table view] |
Text
,.
- ,~-.,
--.**e ..
~.'
,I
- ~RIQHMO;D .y1im;1Nt.A:..2 3 ~ 61
.. Jul'y. '.*1976. 'r* *.** .
.*. rJJ~i{/. > <*:_.: : ... , ~
Mr. N?rman' c. *Moseley, *Di'rector .... * * :__
- office of Inspection and -Enforcem~t *, ~6;-, , .. * :* * . 4.
- ~s~-.* '\i15'?: :_,. . * -Serial No. 114
I U. *s. Nu.clear_ Re'gulatory Commissi~_ <J,\:;Ji* *.1,\ ~ 00i-,o~* . ....._ -
Region II - Suite *818 ..._. 0 * * .... '.~:c . .c' _* *. * ,':f_ '. Docke't No. ' ;50-280:
230 Peachtree*street,-'Northwest -_*. /' :-:,-. ~ _,('()_
- Licens.e No .. DPR.:..32 Atlanta,. Georgia *. 303.03 : .. :*.:* * * . -*_-
. . . *.' . *.* ~.
Dear' Mr. Moseley:
. . .. Th~::V!rg:lnia ~1~*~ir.ic:* and Power *G~pan~ hereby submit~ ~ c~py. of the
. supplemerit_al_ report to Special Report :sR.:.si-75-08 entitled' "Summary* R,:port
- .*. Conta:1.Ulllent**:~~ak'Rate. Testing 11 for.* Uni(* 1 dated .June *30, ..1976~ ..
. . . . *.. ' .. The. s~b~t;nce\,£ th':i,s*: rep~rt' h_a'{.,been .reviewed by the: .s~at,ion Nuclear
. Safety* and* Operating.'Conmittei-an"d :will ,b,./*pla:'ced,ori the age*nda .for* the riext_
meeting of* the Systei\1 *Nuc.ie:ar: S~fety,.an.d:Op<?rat:i.ng Comnit.tee*~ . . . .
Very- truly yours, ..
'. *. ~ '
- Y! *.::")/>~ ;* ~L'?*q:-t2(:_*.. ~. :'*
,lj,~*~1.~~1~
' ..' ' ,, ' ~ , .
.* :,_, . ::, -: /-.::_ ._:c.j_.1'.'!**At'.'111ings ,* :,..
, :c.Vi~_e* President.:.Power Supply
. and Pr'oduction_* Operat:l.'oris:
Enclosure*
c_c: Mr* Rober~ W* Re:t°d, : *chief (46 *copies)(:.
_: Operating Reactors B;r.~nch'-.. 4. . . .
I *, .* *.*
I
. ~' ,, .
SUPPLEMENTAL REPORT l
-t It SPECIAL REPORT l'
l i
SR-Sl-75-08 I
'iI i
i
.* I
SUMMARY
REPORT CONTAINMENT LEAK RATE I~.'.!1!!Q.
DOCKET NOo 50-280 LICENSE NO. DPR-32 JUNE 30, 1976 SURRY POWER STATION VIRGINIA ELECTRIC AND POWER COMPANY
e This report is submitted to provide supplemental information to SR-Sl-75-08, Summary Report of Containment Leak Rate Testing. The following topics will be discussed:
- 1. Errors inherent in correlating Type A leakage tests with Type B and C tests.
- 2. Instrument error analysis.
I. Correlation of Type A, Band C Tests Proposed Appendix J to 10CFR50 dated August 27, 1971 and specified in Technical Specifications states that if repairs are necessary to meet
- the acceptance criteria of the Type "A" Test, the test need not be repeated provided local measured leakage reductions achieved by repairs reduce the containment's overall measured leak rate to meet the acceptance criteria.
This*calculation is explained on pages 16-18 of SR-Sl-75-08. The results are repeated below with the addition of a correction for instrument error in the Type "B" and "C" tests (5.4%).
Correlation of data:
Integrated Leak Rate (1617 SCFH) *.I.,*
plus confidence band (60 SCFH) + 1677 SCFH Leakage reduction through SG tubes 1232 SCFH Leakage reduction through containment isolation valves in systems connecting the cont. atmosphere 38 SCFH with open systems outside the containment Leakage reduction thru containment isolation valves in systems connecting. the cont. :-atmosphere 796 SCFH with closed systems outside the containment.
Correction-for instrument error in Type Band + 112 SCFH c*Tests (5.4%)
277 ,SCFH
- * - * * *.~~,-..---.- .. ,-,* * * * . *** *****.** , * * , ... .;Q _ _ _ ~-,~* ..., * . .*, ' . ' * * * . * ~ ,~- - * * - . .---... ......... ~----**
~ .... ---.~ -~, ............... *-*~""" . ...------~~-,,.,. ....... .
- ' ,,*. -~ "**'<""*..- - - ,,,._'-~**, .. **I'
e e The apparent negative leakage is due to errors inherent in this type of correlation which tend to give different results in Type "B" and "C" tests than the leakage which existed at the time of the _Type "A" test. This error is due to the difficulty of duplicating during the Type "B" and "C" tests the exact conditions which existed at the time of the Type "A" test. Causes of this type of error include the following:
- 1. For leakages through valves which connect the containment with closed systems outside, a significant back pressure may have existed during the Type "A" test which was not present for the "B" and "C" tests. This would yield higher results in the Band C tests than existed during the Type A test.
- 2. During the Type "A" test, the containment sump is flooded
_to simulate accident conditions. As a:result,the leakage through_*certain '.Valves is water leakage rather than air leakage. -
Type "B" and "C" tests are air leakage tests and thus tend to give* higher leakage rates than existed during the Type "A" test. For this test, the outside recirculation spray pump suction valves (MOV-RS-155A & B) and the Low Head Safety Injection Pump Suction Valves (MOV-1860 A&B) which have water leakage during the Type "A" test, were major sources of leakage. The as found leakage test results for these valves were probably conserva*tive contributing to the negative corrected leakage.
The above items are the major sources of error in the correlation of leakages from Type A, Band C tests~ Other sources include changes in seating due to valve cycling betwe~n tests, seating variations due to different pressurization rates between tests, and instrument error.
.e .e II. INSTRUMENT ERROR Equipment Descriptions The differential pressure between the reference bulbs and the containment atmosphere was measured with a 0-60 inch U-Tube manometer, Meriam Instrument Model 20CB10. The fluid used was an oil with a specific gravity of 1.04. Accur-acy was to 0.01 inches with repeatibility to 0.0025 inches of oil.
The absolute pressure of the containment atmosphere was measured with a 0-120 inch mercury manometer, Exactel Model 500. Digital readout and accuracy were to 0.001 inches of mercury with repeatibility to .00025 inches of mercury.
Containment temperature was measured with 18 RTD's, Electric Thermometer Inc.
Model P-B2155. Individual RTD accuracy was to 0.1°F. An additional error of.*
.05°F is inherent in computer analog to digital conversion. Therefore accuracy is to 0.15°F with *repeatibi!itj 1* to 0.04°F.
Vapor pressure was determined using two dew cells, Foxboro Model 2711AG.
Accuracy~ including computer error was to 0.55%, repeatibility to .14%. This corresponds to .OS in H20 and .01 in H o, respectively.
2 The makeup air flow meter used for verification was an American Meter Controls, Inc. Model AL2300 with an accuracy.of 0.5%.
Instrument Error Analysis Both the reference and the absolute method of leakage determination require an hourly calculation of the mass of air in the containment. The leakage rate is then determined by a least squares fit of the calculated masses over a 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> period. The uncertainty in the mass calculation for each method is estimated as follows.
e Reference Method - uncertainty in mass calculation.,
The reference method mass calculation is by the formula:
WHERE: Q = quantity of air in containment at time, ti; lb mass.
Qo = quantity of air in containment at time, to; lb mass.
PD = manometer differential pressure at time, ti; in H2o.
Pno = manometer differential pressure at time, to; in n2o.
Pv = containment vapor pressure at time, ti; in H 0.
2 Pv
. 0
= containment vapor pressure at time, to; . in H o.
2 T = average containment temperature at time, ti; oR.
The change or uncertainty in Q due to uncertainties in the measured variables is given by:
- ~Q = 1.7558 X The formula assumes*that all errors are systematic rather than random
~PD = JpD = ep = epD = .01 in. H20 0 Do Jv0 = ~v\ = ev0 = ev = .os in. HzO JT =- eT = o.15/ {Ts = .035°R I
e e Combining equivelant terms:
eQ C 1.7558 e = 23.'4 lb mass i Q
Absolute Method - uncertainty in mass calculation.
The absolut.e method mass calculation is by the formula *.
- ~~... ...... Q = 1.7558 X 10 5
Pa = *1. 755.8 X 105 (P-Pv)
T T WHERE!: Q = quantity of air in con ta inmen t, lb mass.
Pa = containment ab.solute pressure, in. H20 P = containment pressure~ in H 0 2
Pv = containment vapor pressure, in. H20 0
T * = c*ontainment average temperature, R The change or uncertainity in Q due to uncertainties in the measured variables is given by:
. 5
[(
~ . ~p
,2.+(~. ~ Pv + d..Q. .~ _)2]
2 .( * .
I V~
-~Q = 1.7558 x 10 olP d.R, 1 d:f The formula assumes that all errors are systematic rather than random in character. The error in eQ = 1. 7558 X I/ II e
. p = .001 . Hg =.0136 H20 eV =
e = .15°R + .035°R T fl8
e Q
= 1.7558 x 10
- [f t
. **: -6...;.
.0136\
540 =-1 2
+ /.os, ts40J 2
. e
+ //1491.0 - 4.2) .035'2] 1/2
\l540 X 540 /
= 1. 7558 10 5 -10
+ 8.5
-9
+ ~-2
-81J 1/2 .
X [ 6.3 X 10 X 10_ X 10
= 1. 7558 X 10 5 [ 4.11 X 10- 8 Jl/ 2
.eQ = 35.6. lb *.*:mass
- R'e
- pea.':tibili t,y Error Analysis Using the same formulas as above, the repeatibity error for the two methods is estimated as follows:
Reference method:
Instrument repeatibility epD '
= .0025 *H2o 11 e = .0100 H 0
, V 2 eT = .007°R 112 eQ ~ 1.7558 X 10 5[2[.00:i~c,+,2/.0l\2 +ll28.423~2Q 02Q-4.244+4.l87).0Q7\il J
0
. *\*540 ,. ~4a°/ ' * ~ 540 X 540 )
sr -11 -10 * -14] l/2
~ 1$7558 x 10 L4.3 x 10 + 6.9 X 10 + 4
= le7558 X 105 X 2.7{ X 10-S eQ = 4.76: lb. mass.
. . ... e e instrument repeatibility:
11 11 ep = .00025 Hg = .0034 H 0 0 2 I/
ev = .01 H0 2
eT = .04 OR= .009 f,18 ;*
eQ = l. 7558 X 10 [
5 f003~2 +
540 fo\)2 540
+(1491-4.2) 540x540
.oofJ1'2 5 10-ll 10-lO + 2 11 10-9] l/Z
= 1. 7558 X 10 ( 3.61 X + 3.00 X 0 X
5 -5
= 1.7558 X 10 X 4 95 0 X 10
= 8.69 lb. mass.
Leakage rate error due to instrument error.
As shown on pages 6 and 7 of report SR-Sl-75-08, the, leakage rate is,,
. determined by a least squares fit analysis of the hourly calculations of mass over the 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> test period. The effects of systematic instrument error are diminished by this method of analysis rendering repeatibility error the predom-inent source of instrument uncertainty. The effects of errors in individual mass calculations on the *overall leak rate may be estimated by the formula e
m
(}:X) 2 tr'"
-::1
.. )
Where e = error in slope in lbm/hr
0 For the reference method, the instrument repeatibility translates to an error in leakage rate as follows.
e m
= 4. 76 2
/ l:X - o:x) 2 ..,.
V . N ..:*,
e m =
em = .0007wt%/24Hr.
e For the absolute method.
= 8.69 2
~r.x -(EX)~
= .24 / lb/hr
= .0012 \wt%/24 hr.
Type Band C tests are performed using rotameters of various ranges manufactured by the Brooks Instrument Co. All are accurate to+ 5%. Flow pressure corrections are made based on a 0-50 psig Ashcroft pressure gage of+ 2% accuracy. Commutation of these uncertainties yields an overall error of 5.4%.
e =
In conclusion, a negative corrected leakage rate could be expected due to the errors inherent in _correlating the Type A, B, and C tests as discussed herein. A correction for instrument error during the Type Band C tests still yields a negative corrected leakage after repairs. It is believed that the correlation between the Type A, B, and C tests remains valid and the measured leakage reductions achieved by repairs have reduced the containment's overall measured leak rate to acceptable limits.