ML17227A601: Difference between revisions
StriderTol (talk | contribs) (Created page by program invented by StriderTol) |
StriderTol (talk | contribs) (Created page by program invented by StriderTol) |
||
| Line 39: | Line 39: | ||
~~l.i~a 4 1 hi 0~L 4%~t U Ib s f Revision 2 08/01/92 3.0 INSERVICE TESTING PROGRAM FOR PUMPS 3.1 Code Compliance This IST Program for pumps meets the requirements of Subsection IWP of the Code and any interpretations or additional requirements imposed by Generic Letter 89-04.Where these requirements have been determined to be impractical, conformance would cause unreasonable hardship without any compensating increase in safety, or an alternative test provides an acceptable level of quality and safety, relief from Code requirements is requested pursuant to the requirements of 10 CFR 50.55a(g)(5)(iii) and Generic Letter 89-04.3.2 Allowable Ranges of Test Quantities The allowable ranges for test parameters as specified in Table IWP-3100-2 will be used for all measurements of pressure, flow, and vibration except as provided for in specific relief requests.In some cases the performance of a pump may be adequate to fulfill its safety function even though there may be a value of an operating parameter that falls outside the allowable ranges as set forth in Table IWP-3100-2. | ~~l.i~a 4 1 hi 0~L 4%~t U Ib s f Revision 2 08/01/92 3.0 INSERVICE TESTING PROGRAM FOR PUMPS 3.1 Code Compliance This IST Program for pumps meets the requirements of Subsection IWP of the Code and any interpretations or additional requirements imposed by Generic Letter 89-04.Where these requirements have been determined to be impractical, conformance would cause unreasonable hardship without any compensating increase in safety, or an alternative test provides an acceptable level of quality and safety, relief from Code requirements is requested pursuant to the requirements of 10 CFR 50.55a(g)(5)(iii) and Generic Letter 89-04.3.2 Allowable Ranges of Test Quantities The allowable ranges for test parameters as specified in Table IWP-3100-2 will be used for all measurements of pressure, flow, and vibration except as provided for in specific relief requests.In some cases the performance of a pump may be adequate to fulfill its safety function even though there may be a value of an operating parameter that falls outside the allowable ranges as set forth in Table IWP-3100-2. | ||
Should such a situation arise, an expanded allowable may be determined, on a case-by-case.basis, in accordance with IWP-3210 and ASME Code Interpretation XI-1-79-19. | Should such a situation arise, an expanded allowable may be determined, on a case-by-case.basis, in accordance with IWP-3210 and ASME Code Interpretation XI-1-79-19. | ||
3.3 Testing Intervals The test frequency for pumps included in the Program will be as set forth in IWP-3400 and related relief requests.A band of+25 percent of the test interval may be applied to a test schedule as allowed by the St.Lucie Unit 2 Technical Specifications to provide for operational flexibility. | |||
===3.3 Testing=== | |||
Intervals The test frequency for pumps included in the Program will be as set forth in IWP-3400 and related relief requests.A band of+25 percent of the test interval may be applied to a test schedule as allowed by the St.Lucie Unit 2 Technical Specifications to provide for operational flexibility. | |||
Revision 2 08/01/92 3.4 Pump Program Table Appendix A lists-those pumps'.included in'the IST Program with.references to parameters to be measured and*'pplicable requests for relief.3.5 Relief Requests for Pump Testing Appendix B includes all relief requests related to pump testing. | Revision 2 08/01/92 3.4 Pump Program Table Appendix A lists-those pumps'.included in'the IST Program with.references to parameters to be measured and*'pplicable requests for relief.3.5 Relief Requests for Pump Testing Appendix B includes all relief requests related to pump testing. | ||
0 Q Jet 4 4 4 x 1 Revision 2 08/01/92 4.0'INSERVICE.TESTING PROGRAM'OR VALVES.H 4.1 Code Compliance This IST Program for'alves meets'the requirements of Subsection IWV of the Code and any interpretations or additional requirements imposed by Generic Letter 89-04.Where these requirements have been determined to be impractical, conformance. | 0 Q Jet 4 4 4 x 1 Revision 2 08/01/92 4.0'INSERVICE.TESTING PROGRAM'OR VALVES.H 4.1 Code Compliance This IST Program for'alves meets'the requirements of Subsection IWV of the Code and any interpretations or additional requirements imposed by Generic Letter 89-04.Where these requirements have been determined to be impractical, conformance. | ||
| Line 443: | Line 445: | ||
*A valve whose failure in a position other than its normal position could cause all trains of a safeguard system to be inoperable; | *A valve whose failure in a position other than its normal position could cause all trains of a safeguard system to be inoperable; | ||
*A valve whose failure in a position other than its normal position that might cause a transient that could lead to a plant trip;or*When test requirements or conditions are precluded by system operation or access.Cold shutdown testing is performed under conditions outlined in Relief Request VR-1.Reactor Coolant 2998-G-078 Sh 107 V-1460 thru V-1466--Reactor Coolant System Gas Vents These valves are administratively controlled in the key-locked closed position with the power supply disconnected to prevent inadvertent operation. | *A valve whose failure in a position other than its normal position that might cause a transient that could lead to a plant trip;or*When test requirements or conditions are precluded by system operation or access.Cold shutdown testing is performed under conditions outlined in Relief Request VR-1.Reactor Coolant 2998-G-078 Sh 107 V-1460 thru V-1466--Reactor Coolant System Gas Vents These valves are administratively controlled in the key-locked closed position with the power supply disconnected to prevent inadvertent operation. | ||
Since these are Class 1 isolation valves for the reactor coolant system, failure of a valve to close or significant leakage following closure could result in a loss of coolant in excess of the limits imposed by Technical Specification 3.1.3 leading to a plant shutdown.Furthermore, if a valve were to fail open or valve indication fail to show the valve returned to the fully closed position following exercising, prudent plant operation would probably likely result in a plant shutdown.E-1 A~P'Vip ski&f1+l Revision 2 08/01/92 Reactor Coolant 2998-G-078 Sh 108 V-1474 and V-1475 Power-Operated Relief Valves.Due to the potential impact.of the resulting*transient should one of these valves open prematurely or stick in the open position, it is=considered imprudent to cycle them during plant operation with the reactor coolant system pressurized. | Since these are Class 1 isolation valves for the reactor coolant system, failure of a valve to close or significant leakage following closure could result in a loss of coolant in excess of the limits imposed by Technical Specification | ||
====3.1.3 leading==== | |||
to a plant shutdown.Furthermore, if a valve were to fail open or valve indication fail to show the valve returned to the fully closed position following exercising, prudent plant operation would probably likely result in a plant shutdown.E-1 A~P'Vip ski&f1+l Revision 2 08/01/92 Reactor Coolant 2998-G-078 Sh 108 V-1474 and V-1475 Power-Operated Relief Valves.Due to the potential impact.of the resulting*transient should one of these valves open prematurely or stick in the open position, it is=considered imprudent to cycle them during plant operation with the reactor coolant system pressurized. | |||
Chemical&Volume Control 2998-G-078 Sh.120 V-2522" Letdown Line Containment Isolation Valve Closing this valve during operation isolates the letdown line.from the RCS and would result in undesirable pressurizer level..transients with the potential for a plant trip.'f a valve failed to reopen, then-an-unexpected plant shutdown would.be required.Chemical 6 Volume Control 2998-G-078 Sh.121 V-2501 Volume Control Tank Outlet Valve Closing this valve during operation of a charging pump would isolate the VCT from the charging pump suction header damaging any operating charging pumps and interrupting the flow of charging water flow to the RCS with the potential of RCS transients and plant trip.V-2504 RWT Discharge Valve Opening this valve during operation would result in injection of RWT borated water into the reactor coolant system.This would, in turn, result in overboration with an adverse reaction in reactor power,and the potential for a power transient. | Chemical&Volume Control 2998-G-078 Sh.120 V-2522" Letdown Line Containment Isolation Valve Closing this valve during operation isolates the letdown line.from the RCS and would result in undesirable pressurizer level..transients with the potential for a plant trip.'f a valve failed to reopen, then-an-unexpected plant shutdown would.be required.Chemical 6 Volume Control 2998-G-078 Sh.121 V-2501 Volume Control Tank Outlet Valve Closing this valve during operation of a charging pump would isolate the VCT from the charging pump suction header damaging any operating charging pumps and interrupting the flow of charging water flow to the RCS with the potential of RCS transients and plant trip.V-2504 RWT Discharge Valve Opening this valve during operation would result in injection of RWT borated water into the reactor coolant system.This would, in turn, result in overboration with an adverse reaction in reactor power,and the potential for a power transient. | ||
E-2 | E-2 | ||
Revision as of 23:17, 8 October 2018
| ML17227A601 | |
| Person / Time | |
|---|---|
| Site: | Saint Lucie  |
| Issue date: | 08/11/1992 |
| From: | FLORIDA POWER & LIGHT CO. |
| To: | |
| Shared Package | |
| ML17227A598 | List: |
| References | |
| JNS-PSL-204, NUDOCS 9209240430 | |
| Download: ML17227A601 (544) | |
Text
FLORIDA POWER and LIGHT COMPANY NUCLEAR ENERGY SERVICES 700 Universe Boulevard t'uno Beach, Florida 33408 FIRST TEN-YEAR INSERVICE INSPECTION INTERVAL INSERVICE TESTING PROGRAM FOR PUMPS AND VALVES ST.LUCIE NUCLEAR POWER PLANT UNIT NO.2 DATE OF COMMERCIAL OPERATION:
AUGUST 8, 1983 FLORIDA POWER&LIGHT P.O.BOX 128 FT.PIERCE, FL.34954 NRC DOCKET NUMBER: 50-389 DOCUMENT NUMBER: JNS-PSL-204 REVISION 2 ST.LUCIE PLANT REVIEWS AND APPROVALS:
PREPARED BY: PSL LANT IST ENGINEER DATE'PPROVED BY: PS T ST&CODE SUPERVISOR DATE: 9209240430 5000389 I PDR ADQCK o PDR 6
Revision 2 08/01/92 Table of Contents Pacae Table of Contents Record of Revisions 1.0 Introduction
2.0 Applicable
Documents 3.0 3.1 3."2 3.3 3.4 Inservice Testing Program For Pumps Code Compliance Allowable Ranges of Test Quantities Testing Intervals Pump Program Table Relief Requests for Pump Testing 4.1 4.2 4.3 4'4.5 4.6 Inservice Testing Program For Valves Code Compliance Testing Intervals Stroke Time Acceptance Criteria Check Valve Testing Valve Program Table Relief Requests For Valve Testing A B C D E Pump Program Tables Pump Program Requests For Relief Valve Program Tables Valve Program Requests For Relief Cold Shutdown Justifications Revision 2 08/01/92 RECORD OF REVISIONS REVISION NUMBER 0 DESCRIPTION OF REVISION REASON FOR THE CHANGE Initial 10 year submittal Program Update Program Update for Generic Letter 89-04 DATE REVISED APPROVALS 08/08/83 01/30/87 08/01/92
~)4 I l4 t 4 I'P I Revision 2 08/01/92 INSERVICE TESTING (IST)PROGRAM PLAN ST.LUCIE UNIT 2
1.0 INTRODUCTION
Revision 2 of the St.Lucie Unit 2 ASME Inservice Inspection (IST)Program will be in effect through the end of the first 120-month (10-year)interval unless revised and reissued for reasons other than the routine update required at the start of the second interval per 10 CFR 50.55a(g).
The first inspection interval is defined as follows: Beceins August 8, 1983 Ends August 8, 1993This document outlines the IST Program for St.Lucie Plant, Unit 2, based on the requirements of Section XI of the ASME Boiler and Pressure Vessel Code, 1980 Edition, including all addenda thereto through Winter, 1980 (the Code).References in this document to"IWP" or"IWV" correspond to Subsections IWP and IWV, respectively, of the ASME Section XI, 1980 Edition, unless otherwise noted.The inservice testing identified in this Plan are to be performed specifically to verify the operational readiness of pumps and valves which have a specific function in mitigating the consequences of an accident or in bringing the reactor to a safe shutdown.
, t, D.<+i-Q.i~v a'>L 4 l:et+Vt~ac)~a:ii~e.
Revision 2 08/01/92 2.0 APPLICABLE.DOCUMENTS This Program Plan was developed per the requirements-and guidance provided by the following documents:
2.1 2.2 2.3 2.4 2.5 2.6 2'.7 2.8 2.9 2.10 2.11 2.12 Title 10, Code of Federal Regulations, Part 50 NRC Regulatory Guides-Division 1 Standard Review Plan 3.9.6,"Inservice Testing of Pumps and Valves Final Safety Analysis Report, St.Lucie Unit 2 St.Lucie Plant Unit 2 Technical Specifications ASME Boiler and Pressure Vessel Code,Section XI, 1980 Edition and Addenda through Winter, 1980 NRC Generic Letter 89-04,"Guidance on Developing
~Acceptable Inservice Testing Programs" Minutes of the Public Meetings on Generic Letter 89-04.St.Lucie Unit 1-Interim Relief From the Inservice Testing Program for Pumps and Valves (TAC No.74794)Supplement to Minutes of the Public Meetings on Generic Letter 89-04 by J.G.Partlow, 26 September.1991 Request for-Industry/NRC-Accepted Interpretation on"Practical" as Applied by ASME Code Section XI, IWV-3412(a)by Martin J.Virgilio, Assistant Director for Regions IV and V.St.Lucie Unit 2-Inservice Testing (IST)Program Relief Request, 5 December 1991
~~l.i~a 4 1 hi 0~L 4%~t U Ib s f Revision 2 08/01/92 3.0 INSERVICE TESTING PROGRAM FOR PUMPS 3.1 Code Compliance This IST Program for pumps meets the requirements of Subsection IWP of the Code and any interpretations or additional requirements imposed by Generic Letter 89-04.Where these requirements have been determined to be impractical, conformance would cause unreasonable hardship without any compensating increase in safety, or an alternative test provides an acceptable level of quality and safety, relief from Code requirements is requested pursuant to the requirements of 10 CFR 50.55a(g)(5)(iii) and Generic Letter 89-04.3.2 Allowable Ranges of Test Quantities The allowable ranges for test parameters as specified in Table IWP-3100-2 will be used for all measurements of pressure, flow, and vibration except as provided for in specific relief requests.In some cases the performance of a pump may be adequate to fulfill its safety function even though there may be a value of an operating parameter that falls outside the allowable ranges as set forth in Table IWP-3100-2.
Should such a situation arise, an expanded allowable may be determined, on a case-by-case.basis, in accordance with IWP-3210 and ASME Code Interpretation XI-1-79-19.
3.3 Testing
Intervals The test frequency for pumps included in the Program will be as set forth in IWP-3400 and related relief requests.A band of+25 percent of the test interval may be applied to a test schedule as allowed by the St.Lucie Unit 2 Technical Specifications to provide for operational flexibility.
Revision 2 08/01/92 3.4 Pump Program Table Appendix A lists-those pumps'.included in'the IST Program with.references to parameters to be measured and*'pplicable requests for relief.3.5 Relief Requests for Pump Testing Appendix B includes all relief requests related to pump testing.
0 Q Jet 4 4 4 x 1 Revision 2 08/01/92 4.0'INSERVICE.TESTING PROGRAM'OR VALVES.H 4.1 Code Compliance This IST Program for'alves meets'the requirements of Subsection IWV of the Code and any interpretations or additional requirements imposed by Generic Letter 89-04.Where these requirements have been determined to be impractical, conformance.
would cause unreasonable hardship without any compensating increase in safety, or an alternative test provides an acceptable level of quality and safety, relief from Code requirements is requested pursuant to the requirements of 10 CFR 50.55a(g)(5)(iii) and Generic Letter 89-04.4.2 Testing IntervalsThe test frequency for valves included in the Program will be as set forth in IWP-3400 and related relief requests.A band of+25 percent of the test interval may be applied to a test schedule as allowed by the St.Lucie Unit 2 Technical Specifications to provide for operational flexibility.
Where quarterly testing of valves is impractical or otherwise undesirable, testing may be performed during cold shutdown periods as permitted by IWV-3412(a).
Justifications for this deferred testing are provided in Appendix E.4.3-Stroke Time Acceptance-Criteria When required, the acceptance criteria for the stroke times of power-operated valves will be as set forth in Generic Letter 89-04.4.4 Check Valve Testing Full-stroke exercising of check valves to the open position using system flow requires that a test be performed whereby the predicted full accident condition flow rate through the valve be verified and measured.Any deviation to this requirement must satisfy the requirements of Generic Letter 89-04, Position 1.
Revision 2 08/01/92 4.5.Valve.Program Table-Appendix:C lists'those valves included in-the IST Program with references to required testing, respective test intervals, and applicable
'requests for relief.4.6 Relief Requests for Valve Testing Appendix D includes all relief requests related to valve testing.
Revision 2 08/01/92 Appendix A Pump Program Tables e'4g~--e FLORIDA POWER AND LIGHT COMPANY REVISION: 2 PUHP TABLES DATE: 08/01/92 Saint Lucia Nuclear Plant-Unit 2 PAGE: 1 PUHP NUMBER DESCRIPTION INLET DIFF~FLOW BEARING CL COORD SPEED PRES~PRES~--RATE VI BRA.TEMP.REHARKS AFM 2A AFW 28 AFW 2C BAH 2A AUXILIARY FEEDWATER PUMP 3 N-13 NA AUXILIARY FEEDWATER PUMP 3 M-13'A AUXILIARY FEEDWATER PUMP 3 K-13 Y BORIC ACID MAKEUP PUMP 2 8-5 NA Y Y Y:PR-4 Y Y Y:PR-4 Y Y Y:PR-4 Y:PR-8 Y Y:PR-5 N:PR-1 Y':PR-1 N:PR-1 Y N:PR-1 BAH 28 BORIC ACID MAKEUP PUHP 2 C-5 NA Y:PR-8 Y Y:PR 5 Y N:PR-1 CCM 2A CCW 28 CCM 2C CMG 2A CHG 28 CHG 2Ccscc DOT 2A DOT 28 HPSI 2A c MPSI 28 HYD 2A HYD 28 ICW 2A ICW 28 ICW 2C LPSI 2A LPSI 28 COMPONENT COOLIHG WATER PUHP 3 F-16 NA COMPONENT COOLING MATER PUHP 3 F-17 NA COMPONENT COOLING WATER PUMP 3 F-16 NA Y Y Y Y Y Y Y Y Y Y Y Y 2 C-3 2 E-3 CHARGING PUMP NA CHARGING PUMP CHARGING PUMP CONTAINMENT SPRAY PUHP CONTAINMENT SPRAY PUMP DIESEL OIL TRANSFER PUMP DIESEL OIL"TRANSFER PUHP NA 2 G-3 NA 2 G-4 NA, Y:PR-15 Y 2 H-4 HA.Y:PR-15 Y 3 J-12 HA 3 L-12 NA Y:PR-16 Y Y:PR-16 Y HI PRESS SAFETY INJECTION PUMP 2 D-6 NA Y:PR-15 Y N:PR-1 N:PR-1 Y N:PR-1 Y Y:PR-12 N:PR-1 Y:PR-12 N:PR-1 Y:PR-12 N:PR-1 Y:PR-6 Y:PR-6 H:PR-1 N:PR-1 Y:PR-7 Y N:PR-1 Y:PR-7 Y:PR-9 Y N:PR-1 Y N:PR-1 Y:PR-9 N:PR-1 HYDRAZINE PUMPS HYDRAZINE PUMPS INTAKE COOLING'WATER PUMP-" INTAKE COOLING WATER PUMP INTAKE COOLING WATER PUHP 2 C-11 Y 2 D11 Y 3 M-4 3 H-7 NA NA 3 H-5 NA N:PR-17N:PR-17 Y:PR-17 Y:PR-14 N:PR-1 N:PR-17N:PR-17 Y:PR-17 Y:PR-14 N:PR-1 Y:PR-11 Y Y Y:PR-13 N:PR-1 Y:PR-11 Y Y Y:PR-13 N:PR-1 Y:PR-11 Y Y V:PR-13 N:PR-1 LO PRESS SAFETY INJECTION PUMP 2 E-6 NA LO PRESS SAFETY INJECTION PUHP 2 D 6 NA Y:PR-15 Y Y:PR-10 Y Y:PR-15 Y.Y:PR-10 Y N:PR-1 N:PR-1 HI PRESS SAFETY INJECTION PUHP 2 8-6 NA':PR-15 Y 1 0 V Revision 2 08/01/92 Florida Power&Light Company INSERVICE TESTING-PUMP TABLES St.Lucie Nuclear Plant-Unit 2 PAGE: 2 LEGEND PUMP NUMBER DESCRIPTION Numerical designator indicated on the respective flow diagram.Generic name/function of the pump.CL COORD Test Parameters ISI Classification per the associated ISI boundary drawing(s)
Corresponds to the flow diagram coordinates of the pump.The-table.indicates-by a"Y" (yes)or"N"-(no)that the specific parameter is measured, evaluated, and recorded per the applicable Code requirement.
If a"N" is indicated, the associated relief request number is also noted in the same column.PR-XX Where indicated this refers to the specific relief request (See Appendix B)related to any deviation regarding the measurement or analysis of a parameter.
Revision 2 08/01/92 Appendix B Pump Program Relief Requests I a%1&i ki 4 f~ARE~t-'"-vw Revision 2 08/01/92 RELIEF REQUEST NO.PR-1 COMPONENTS:
All pumps in the Program SECTION XI RE UIREMENT: The temperature of all centrifugal pump bearings outside the main flow path and of the main shaft bearings of reciprocating pumps shall be measured at points selected to be responsive to changes in the temperature of the bearings.(IWP-3300, 4310)BASIS FOR RELIEF: The data associated with bearing temperatures taken at one-year intervals provides little statistical basis for.determining the incremental degradation of a bearing or any meaningful trending information or correlation.
In many cases the pump bearings are water-cooled and thus, bearing temperature is a function of the temperature of the cooling medium, which can vary considerably.
Vibration measurements are a significantly more reliable indication of pump bearing degradation than are temperature measurements.
All pumps in the program are subjected to vibration measurements in accordance with IWP-4500.Although excessive.
bearingtemperature is an indication of an imminent or existing bearing failure, it is highly unlikely that such a condition would go unnoticed during routine surveillance testing since it would manifest itself in other obvious indications such as audible noise, unusual vibration, increased motor current, etc.Any potential gain from taking bearing measurements, which in most cases would be done locally using portable instrumentation, cannot offset the cost in terms of dilution of operator effort, distraction of operators from other primary duties, excessive operating periods for standby pumps especially under minimum flow conditions, and unnecessary personnel radiation exposure.B-1 4t~p Revision 2 08/01/92 RELIEF REQUEST NO.PR-1 (cont.)BASIS FOR RELIEF cont.Based on the reasons similar to those set forth above,, the ASME deleted the requirement for bearing temperature measurements in ASME OM Code, Subsection ISTB, the revised version of the Code for pump testing.ALTERNATE TESTING: None.B-2 4->>V<4%4.,>g 4'+f~~'~i,e~aM I a I C o Revision 2 08/01/92 RELIEF REQUEST NO.PR-2 COMPONENTS:
Various SECTION XI RE UIREMENT: The full-scale range of each instrument shall be three times the reference value or less.(IWP-4120)
BASIS FOR RELIEF: Table IWP-4110-1 requires the accuracy of instruments used to>>".measure temperature and speed to-be equal.to or better than+5 percent for temperature and+2 percent for speed, both based on the full scale reading of the instrument.
This means that the accuracy of the measurement can vary as much as.+15 percent and+6 percent, respectively, assuming the range of the instruments extended to the allowed maximum.These IST pump-parameters are often measured with portable test instruments where commercially available instruments do not necessarily conform to the Code requirements for range.In these cases, high quality calibrated instruments will be used where the"reading" accuracy is at least equal to the Code-requirement.
for full-scale accuracy.This will-ensure that the measurements are always more accurate than the accuracy as determined by combining the requirements of Table IWP-4110-1 and Paragraph IWP-4120.ALTERNATE TESTING: Whenever portable instruments are used for measuring pump speed or bearing temperatures, the instruments will be such that the"reading" accuracy is as follows Temperature Speed+5 percent+2 percent B-3
's);h'iw Lii L,f Revision 2 08/01/92 RELIEF REQUEST NO.PR-3 COMPONENTS:
Applicable to all pumps in the Program SECTION XI RE UIREMENT: Each inservice test shall include the measurement and observation of all quantities in Table IWP-3100-1.(IWP-3300)
Pump inlet pressure shall be measured before starting a pump and during the test.(Table IWP-3100-1) t BASIS FOR RELIEF:-.If the pumps being tested are in operation as a result.of-plant or system needs, it is unreasonable to reconfigure system lineups simply-to provide for measurement of static inlet pressure.Inlet pressure prior to pump startup-is not a significant parameter needed for evaluating pump performance or its material condition..ALTERNATE TESTING: When performing a test on a pump that is already in operation""-~due-to system or.plant requirements,:
inlet pressure will only be measured during pump operation.
B-4 l~w.r g~)~r4.fC&~~l~
r r,l'.I Qo~Villi>>AWED~w Revision 2 08/01/92 RELIEF REQUEST NO.PR-4 COMPONENTS:
Auxiliary Feedwater (AFW)Pumps 2A thru 2C (2998-G-080, Sh 2)SECTION XI RE UIREMENT: Each inservice test shall include the measurement and observation of all quantities in Table IWP-3100-1.(IWP-3300)
Pump flow rate shall be measured during the test.(Table IWP-3100-1)BASIS FOR RELIEF: 'There are only two practical flow paths available for performing inservice.testing of the AFW Pumps.These include the primary flow path into the main feed supply lines and thence to the.steam.generator, , and the minimum-flow recirculation (mini-recirc*and-bypass test loop)which returns to the condensate storage tank.The former is provided with flow rate measuring instrumentation however the mini-recirc line is a fixed resistance circuit with no flow..instrumentation.
Pumping from the auxiliary feedwater system into the steam ,;;generators during':plant'ot operation is impractical and undesirable for the following reasons: During auxiliary feedwater injection via the main feedwater lines while the plant is operating at power, a large temperature differential (approximately 375 deg-F)could exist that would result in significant thermal shock and fatigue cycling of the feedwater piping and steam generator nozzles.Based on the expected duration of the testing and the flow rate of the pumps (150 to 200 gpm), it is expected that the cooldown of the steam generator would induce cooldown and contraction of the reactor coolant system resulting in undesirable reactivity variations and power fluctuations.
B-5 (e~A 41~5 il lI 1>>II~~t$
Revision 2 08/01/92 RELIEF REQUEST NO.PR-4 (cont.)ALTERNATE TESTING: During quarterly testing of the AFW pumps while the pumps are operating through the fixed-resistance mini-recirc line, pump differential pressure and vibration will be measured and evaluated per IWP-3200 and IWP-6000.During testing performed at cold shutdown, pump differential pressure, flow rate, and vibration will be recorded per IWP-3200 and IWP-6000.Testing during cold shutdowns will be on a frequency determined by intervals between shutdowns as follows: For intervals of 3 months or longer-each shutdown.For intervals of less than 3 months-testing is not required unless 3 months have passed since the last shutdown test.This alternate testing agrees with the-requirements of NRC Generic Letter 89-04, Position 9 and, as such, is considered to be approved upon submittal.
B-6 i,~~r~I 1~1 l 4', w II, gt t~g g V')V Revision 2 08/01/92 RELIEF REQUEST NO.PR-.5 COMPONENTS:
Boric Acid Makeup (BAM)Pumps 2A and 2B (2998-G-078, Sh 121)SECTION XI RE UIREMENT: Each inservice test shall include the measurement and observation of all quantities in Table-IWP-3100-1.(IWP-3300)
Pump flow rate shall be measured during the test.(Table IWP-3100-1)BASIS FOR RELIEF: There are three practical flow paths available for performing inservice testing of'the BAM Pumps.These include the primary flow path into the charging pump suction header, a recirculation line leading back to the refueling water tank, and the minimum-flow
.recirculation (mini-recirc and bypass test loop)which returns to the BAM Tanks.None of these flow paths is totally satisfactory for the following reasons:*.Operating the BAM-Pumps.discharging into, the, charging pump suction header requires the introduction of highly concentrated boric acid solution from the boric acid makeup tanks to the suction of the charging pumps.This, in turn, would result in'he addition of excess boron to the RCS.This rapid, insertion of negative reactivity would result in a rapid RCS cooldown and depressurization.
A large enough boron addition would result in an unscheduled plant trip and a possible initiation of Safety Injection Systems.During cold shutdown, the introduction of excess quantities of boric acid into the RCS is undesirable from the aspect of maintaining proper plant chemistry and the inherent difficulties that may be encountered during the subsequent startup due to over-boration of the RCS.The waste management system would be overburdened by the large amounts of RCS coolant that would require processing to decrease its boron concentration.
B-7
't L;~r4ryp C I><<i E/a'v a~.X*()w~""Yw~~f s<<gi i>iN*y s s~tv, tr~w 4>>>>i)"XWiCt~.Rl'.<a<<~i',8~244-~'V Revision 2 08/01/92 RELIEF REQUEST NO.PR-5 (cont.)*.-The second circuit:recirculates water to the-Refueling Water Tank (RWT)or the Volume Control Tank (VCT).During normal plant operation at power it is undesirable to pump to the RWT and deplete the BAM Tank inventory.
One of the two BAM Tanks is maintained at Tech.Spec.level while the other is used as required for plant operation.
The Tech.Spec.BAM Tank cannot be pumped from because it must be maintained at a level near the top of the tank.The other BAM Tank's level will vary from test to test by as much as 15 to 20 feet.This variance in pump suction pressure will have a direct affect on pump head and flow such that test repeatability would be questionable.
- The minimum-flow recirculation flow path is a fixed resistance circuit of one inch pipe containing a flow limiting orifice.No flow rate measuring instrumentation is installed in-this line.Pumping boric acid from tank to tank would be possible but the flow rates would be small,.limiting.pump operation,to, the high head section of the pump curve.In addition, one=of the two BAM Tanks is maintained at Tech.Spec.level.while the other is used as required for normal plant operation.
The Tech.Spec.BAM Tank cannot be pumped, from because it must be maintained at a level near the top of the tank.This narrow band limits the amount that can be pumped to it or'rom it to only a few hundred gallons.The other BAM Tank's level will vary from test to test by as much as 15 to 20 feet.This variance in pump suction pressure will have a direct affect on pump head and flow such that test repeatability would be questionable.
B-8 I k l~4,.~!i)i".<>g.'<>'%Upi Revision 2 08/01/92 RELIEF REQUEST NO.PR-5 (cont.)ALTERNATE TESTING: During quarterly testing of the BAM pumps, while the pumps are operating through the fixed-resistance mini-recirc line, pump differential pressure and vibration will be measured and evaluated per IWP-3200 and IWP-6000.During testing performed at each reactor refueling outage, jump differential pressure, flow rate, and vibration will be recorded per IWP-3200 and IWP-6000.-'his>>alternate testing agrees with the requirements of NRC Generic Letter 89-04, Position 9 and, as such, is considered to be approved upon submittal; B-9
~+ec Revision 2 08/01/92 RELIEF REQUEST NO.PR-6'COMPONENTS:
Containment Spray (CS)=Pumps 2A and 2B (2998-G-088)
SECTION XI RE UIREMENT: Each inservice test shall include the measurement and observation of all quantities in Table IWP-3100-1.(IWP-3300)
Pump flow rate shall be measured during the test.(Table IWP-3100-1)BASIS FOR RELIEF:.There are two practical flow paths available for performing
..inservice testing of the.CS Pumps.These include one that pumps borated water from the RWT to the RCS via the low-pressure injection header and the other, minimum-flow recirculation (mini-recirc and bypass test loop)which returns to the RWT The first would require modifying the shutdown cooling lineup while in cold shutdown;however, the shutdown cooling system...;..cannot-provide sufficient.letdown flow to, the RWT to accommodate full design flow from the RWT while maintaining the necessary core cooling fun'ction.
Thus, the only practical time-for testing these pumps=via'this, flow path is during refueling outages when water from the RWT is used to fill the refueling cavity.The minimum-flow recirculation flow path is a fixed resistance circuit containing a flow limiting orifice however no flow rate measuring instrumentation is installed.
ALTERNATE TESTING: The CS pumps recirc line differential per IWP-3200 are operated through the fixed-resistance mini-during the quarterly pump testing.Pump pressure and vibration are measured and evaluated and IWP-6000.
Ig N zlr, a P Revision 2 08/01/92 RELIEF REQUEST NO.PR-6 (cont.)ALTERNATE TESTING: cont.During the pump testing performed each reactor refueling, pump.differential pressure, flow rate, and vibration will be recorded per IWP-3200 and IWP-6000.This alternate testing agrees with the requirements of NRC Generic Letter 89-04, Position 9 and, as such, is considered to be approved upon submittal.
4a 4 taW 4 Ir I~j" Revision 2 08/01/92 RELIEF REQUEST NO.PR-7 COMPONENTS:
Diesel Fuel Oil Transfer Pumps 2A and 2B (2998-G-086,-Sh 1)SECTION XI RE UIREMENTS:
Flow rate shall be measured using a rate or quantity meter installed in the pump test circuit.(IWP-4600)
The allowable ranges of inservice test quantities in relation to the referenc'e values are tabulated in table IWP-3100-2.(IWP-3210)
BASIS FOR RELIEF: There are two flow paths available for performing inservice testing on these pumps: the normal day tank fill line and the transfer lines used to transfer fuel oil between diesel oil storage tanks.Neither of these flow paths have installed flow instrumentation.
The day tank would have to be drained to use it as the flow path for a pump flow test.To drain the day tank would require the pump to be disabled and additional diesel-,generator run.time to use-up the fuel oil or.draining over-200 gallons of fuel oil into 55 gallon drums.Neither.draining method is acceptable.
Even if the tank could be drained, the--'-.length"of the pump"test"would-be limited=by the small volume of the day tank.The most practical method of determining pump flow rate is by calculating the transfer rate of fuel oil between storage tanks.The pump flow test is divided into two sections.The pump is recirculated for 15 minutes to its own storage tank (A)for the first section of the flow test.During these 15 minutes, the pump is warmed up and vibration measurements are taken.Prior to the end of the 15 minutes, the pump's discharge valve is throttled to a preset value.The pump is stopped and the valve lineup is changed so that flow is now directed to the other storage tank (B).
Pell~l~4<<J~~'2 1 tw p Revision 2 08/01/92 RELIEF REQUEST NO PR-7 (cont.)BASIS FOR RELIEF: While the pump's lineup is-changed, the pump's storage tank (A)level is measured'by hand using a tape measure.The pump is then started and allowed to transfer a minimum of 3 inches of fuel oil, 5 to 6 inches is preferred.
A final storage tank (A)level is measured at the end of the test.The pump's flow rate is calculated by converting the storage tank (A)level change into a volume change and then dividing it by the number of minutes the pump was run.ALTERNATIVE TESTING: During quarterly testing of the Diesel Generator Fuel Oil Transfer Pumps, pump differential pressure, flow rate,, and vibration will be recorded per IWP-3200 and IWP-6000.Flow rate will be based on the storage tank level changes over a measured period of pump operation.
The allowable ranges for the test parameters as specified in Table IWP-3200-2 will be used for all measurements except for flow.In accordance with IWP-3200 and ASME Interpretation XI-1-79-19, the new pump flow limits and their calculations will be specified in the record of tests (IWP-6000).
+2 Sigma+2 Sigma+2 Sigma-2 Sigma 2 Sigma-2 Sigma F(avg)]F(avg)]F(avg)]F(avg)]F(avg)]F(avg)][1.02 x[1.02 x[1.00 x[0'6 x[0.94 x[0.94 x The Lower Acceptable limit incorporates a 4 0 range for a small amount of pump degradation.
This is the same amount that is included in the limits listed in Table IWP-3200-2.
A series of at least.four flow tests will be performed, for each pump to establish a new pump baseline.The calculated average flow rate, F(avg), of these tests will be used for the" pump's reference value."The"mean error for the individual flow rates and average flow rate will be calculated and combined by the sum of the squares to form a combined error (Sigma).The combined error will then be doubled (two standard deviations) to achieve a 95.4 4 accuracy that all acceptable flow rate tests will fall within this range.The new pump limits will be as follows: Required Action Upper Alert Upper Acceptable Lower Acceptable Lower Alert Required Action 4 44>>>>~4+>>S gl~4 a4w 44 N>>P$4 4 4(t>>t p4,~gy 4 g~>>4~/>>4 Revision 2 08/01/92 RELIEF REQUEST NO.PR-8 COMPONENTS:
~Boric Acid Makeup Pumps 2A and 2B (2998-G-078, Sh 121)SECTION XI RE UIREMENTS:
Each inservice test shall include the measurement and observation of all quantities in Table IWP-3100-1 except bearing temperatures, which shall be measured during at least one inservice test each year.(IWP-3300)
BASIS FOR RELIEF: The system installation does not provide any mechanism for measuring pump suction pressures, and thus, the requirement for measuring suction pressure and pump differential pressures cannot be satisfied.
A measure of pump suction pressure can;however, be determined by a calculation using the height of liquid in the boric acid makeup tanks.Since there is essentially fixed resistances between, the tanks and the pumps this will provide a consistent*
value for suction pressures.
Since the tank levels are not expected to vary significantly during the tests, tank levels and associated calculations will ,....,only.
be"taken once-during each.testinstead of.prior to..pump operation and during operation as required by Table IWP-3100-1~'I ALTERNATE TESTING: The Boric Acid Makeup Pump suction pressures will be calculated based on the height of liquid in the associated.tank once during each inservice test.Subsequently, these calculated values will be used to determine pump differential pressures for evaluation of pump parameters.
B-14
'4 Jy), S T~i(t~~>6 I~~~[r v,v~.,~Cp II V N J~
Revision 2 08/01/92 RELIEF REQUEST NO.PR-9 COMPONENTS:
High Pressure=Safety-Injection (HPSI)Pumps 2A and 2B (2998-G-078, Sh 130)'ECTION XI RE UIREMENT: Each inservice test shall include the measurement and observation of all quantities in Table IWP-3100-1.(IWP-3300)
BASIS FOR RELIEF: During quarterly testing of the HPSI Pumps, the pumps cannot develop sufficient discharge pressure to overcome RCS pressure.Flow is routed.through a minimum flow test line..leading to the RWT.This line has no installed flow rate measuring instrumentation and measuring.flow rate during quarterly testing is not practical.
During cold shutdown conditions, full flow operation of the HPSI pumps to the RCS is restricted to preclude RCS system pressure transients that could result in exceeding the pressure-temperature limits specified in the Technical..Specifications,.Section 3.4.9.3.NRC Generic Letter 89-04, Position 9, allows elimination of" minimum.flow~test line-flow rate measurements providing inservice tests are performed during cold shutdowns or refueling under full or substantial flow conditions where pump flow rate is recorded and evaluated.
ALTERNATE TESTING: During quarterly testing of the HPSI Pumps, pump differential pressure and vibration will be recorded per IWP-3200 and IWP-6000.During testing performed at each reactor refueling, pump differential pressure, flow rate', and vibration will be recorded per IWP-3200 and IWP-6000.This alternate testing agrees with the guidelines of NRC Generic Letter 89-04, Position 9 and, as such, is considered to be approved upon submittal.
h+~VI I<<f~t~l ay I~lt g~l Revision 2 08/01/92 RELIEF REQUEST NO.PR-10 COMPONENTS:
..Low-Pressure..Safety Injection (LPSI)Pumps 2A and 2B (2998-G-078, Sh 131)SECTION XI RE UIREMENT: Each inservice test shall include the measurement and observation of all quantities in Table IWP-3100-1.(IWP-3300)
BASIS FOR RELIEF: During quarterly testing of the LPSI Pumps, the pumps cannot develop sufficient discharge pressure to overcome RCS pressure.Flow is routed through a minimum'flow test line leading to the RWT.This line has no installed flow rate measuring instrumentation.and measuring flow rate during quarterly testing is not practical.
During cold"shutdown,'the"LPSI
'pumps are used for residual heat removal.The substantial flow tests can be performed at this time.Pump differential pressure and flow rate will be recorded.However, due to the vibrations induced in the..system, piping while the-.Reactor.Coolant Pumps are running,.pump vibration readings=will only be measured during cold shutdowns where the RCPs are secured.B-16 E5 v v I'p I~k Revision 2 08/01/92 RELIEF REQUEST NO PR-10 ALTERNATE TESTING: During quarterly testing of the LPSI Pumps, pump differential pressure and vibration will be recorded per IWP-3200 and IWP-6000.Substantial flow testing will be performed during cold shutdowns.
Pump differential pressure, flow rate, and vibration (if RCPs secured)will be recorded per IWP-3200 and IWP-6000.Testing will be on a frequency determined by intervals between shutdowns as follows: For intervals of 3 months or longer,-each shutdown.For intervals of.less than 3 months-testing is not required unless 3.months have passed since the last shutdown test.B-17
)'I' Revision 2 08/01/92 RELIEF REQUEST NO.PR-11 COMPONENTS:
Intake Cooling Water Pumps 2A, 2B and 2C (2998-G-082)
SECTION XI RE UIREMENT: Each inservice test shall include the measurement and observation of all quantities in Table IWP-3100-1.(IWP-3300)
Pump inlet pressure shall be measured before starting a pump and during the test.(Table IWP-3100-1)
BASIS FOR RELIEF: The pumps listed, above.are vertical line shaft pumps submerged in the intake, structure with no practical means of measuring pump inlet pressure.The inlet pressure, however, can be determined by calculation using, as input, the'measured height of water above the pump inlet as measured at the intake.During each inservice test, the water level in the intake pit remains relatively constant, thus only one measurement of level and the associated suction pressure calculation need be performed.
ALTERNATE TESTING: During testing of these pumps, one value of inlet pressure will be calculated based on water level at the inlet structure.
B-18 0 4'I'N I a>>k'<r p p~'I g+'h Revision 2 08/01/92 RELIEF REQUEST NO.PR-12 COMPONENTS:
Reactor Coolant Charging.Pumps 2A, 2B, and 2C SECTION XI RE UIREMENT: The frequency response range of the readout system (for instrument used to measure vibration amplitude) shall be from one-half minimum speed to at least maximum pump shaft rotational speed.(IWP-4520(b))
BASIS FOR RELIEF: The reactor coolant charging pumps operate at approximately 210-215 rpm which equates to a rotational frequency of 3.5 Hz.In accordance with the ASME Code, the frequency response for.the vibration instruments would have to be one half of this or.1.75.Hz.Following an extensive investigation of available and potentially suitable instrumentation, it has been determined that instruments satisfying this requirement for the charging pumps are commercially unavailable.
ALTERNATE TESTING: During testing of these pumps, vibration will be measured as'required by IWP-4510, except that the lower frequency response for the instruments will be 10 Hz.B-19 S~d%a W I l a~r J>4 a,~..4 si'll ir(~.Ip~")l 3~t<<iz e,~~jc')-c-4 Revision 2 08/01/92 RELIEF.REQUEST NO.PR-13 COMPONENTS:
Intake Cooling Water-Pumps 2A, 2B, and 2C SECTION XI RE UIREMENT: The frequency response range of the readout system (for instrument used to measure vibration amplitude) shall be from one-half minimum speed to at least maximum pump shaft rotational speed.(IWP-4520(b))
BASIS FOR RELIEF: The St.Lucie Plant has recently completed a major upgrade to its ASME pump vibration program to better comply with the Code.As part of the upgrade, new vibration instruments were-purchased.
The instruments were chosen for their ease of use and reliability; however,'he instrument's lower frequency response does not comply with the Code when used on the Intake.Cooling Water pumps.-The intake cooling water pumps operate at a shaft speed of approximately 885 rpm.Based on this speed and the Code requirement, the instrumentation used to measure vibration (displacement) would require a response range down to 7.38 hz.The new instruments are capable of a lower.frequency response to 10..hz, 2.62 Hz higher than the Code.The impact of procuring instruments along with the accompanying re-training that would be required is clearly unwarranted at this'ime simply.to gain a'slightly better frequency response.ALTERNATE TESTING: During testing of these pumps, vibration will be measured as required by IWP-4510, except that the lower frequency response for the instruments will be 10 Hz.B-20 4kt~,tt*J I g~yf,~f 4~~f<<l~f 5~
Revision 2 08/01/92 RELIEF REQUEST NO.PR-14 COMPONENTS:
Hydrazine Pumps 2A and 2B SECTION XI RE UIREMENT: The frequency response range of the readout system (for instrument used to measure vibration amplitude) shall be from one-half minimum speed to at least maximum pump shaft rotational speed.(IWP-4520(b))
BASIS FOR RELIEF:The hydrazine pumps operate as low as 105 rpms.This equates to a rotational frequency of 1.75 Hz.In accordance with the ASME Code, the frequency response for the vibration.
.:instruments would have to be one half of this or 0.875 Hz.Following an extensive investigation of available and potentially suitable instrumentation, it has been determined that instruments satisfying this.requirement for the hydrazine pumps'are commercially unavailable.
ALTERNATE TESTING: During testing of these pumps, vibration will be measured as.<<;.~required by IWP-4510,-except.
that the lower frequency response for the instruments will be 10 Hz.B-21 l LP 5~', I y~y M V~<f+~>fM:">1 J~"~~vvfPA"~IlJ 4~l, I../<M g<J l w I Revision 2 08/01/92 RELIEF REQUEST NO.PR-15 COMPONENTS:
Containment Spray Pumps 2A-and 2B (2998-G-088)
Hi Press Safety Inject.Pumps 2A and 2B (2998-G-078 SH 130)Lo Press Safety Inject.Pumps 2A and 2B (2998-G-078 SH 130)SECTION XI RE UIREMENTS:
Each inservice test shall include the measurement and observation of all quantities in Table IWP-3100-1 except bearing temperatures, which shall be measured during at least one inseryice test each year.(IWP-3300)
BASIS FOR RELIEF:The.system installation does not provide any installed suction gages.A measure of pump suction pressure can, however, be determined by calculation using the height of liquid in the Refueling Water Tank.During the quarterly pump tests, the flow rate, through the.suction-piping.,is very low, therefore, the amount of head loss is negligible.
This is not the case during the substantial flow tests.The flow rates used during these tests would cause a noticeable head loss in the suction piping.Since.the tank levels are not expected'to vary-significantly during the quarterly tests, tank levels and associated
..calculations, will..only be.taken.once.during each quarterly test instead of prior to pump operation and during operation as required by Table IWP-3100-1.
ALTERNATE TESTING: During the quarterly pump tests, the pumps'uction pressures will be calculated based on the height of liquid in the associated tank.Subsequently, these calculated values will be used to determine pump differential pressures for evaluation of pump parameters.
During the cold shutdown or refueling substantial flow testing of these pumps, temporary suction gages will be installed to measure pump suction pressure.B-22 1'4J"~I, II~-~'yFP~I I Revision 2 08/01/92 RELIEF REQUEST NO.PR-16 COMPONENTS:
Diesel Oil Transfer Pumps 2A and'2B'(2998-G-086 SH 1)SECTION XI RE UIREMENTS:
Each inservice test shall include the measurement and observation of all quantities in Table IWP-3100-1 except bearing temperatures, which shall be measured during at least one inservice test each year.(IWP-3300)
BASIS FOR RELIEF: The system installation does not provide any installed suction gauges.A measure of pump suction pressure can, however, be determined by calculation using the height of liquid in the.Diesel Oil Storage Tank.During the quarterly pump tests, the ,flow rate through the suction piping is very low, therefore,=
the amount of head loss is negligible.
Since the tank levels are not expected to vary significantly during the quarterly tests, tank levels and associated calculations will only be taken once during each quarterly test instead of prior to pump operation and during operation as required by Table IWP-3100-1.
ALTERNATE TESTING: During the quarterly pump tests, the pumps'uction pressures will be calculated based on the height of liquid in the associated tank.Subsequently, these calculated values will be used to determine pump differential
'pressures for evaluation of pump parameters.
B-23
&l l HL R*r.!.'-c k ,p Revision 2 08/01/92 RELIEF REQUEST NO.PR-17'OMPONENTS:
Hydrazine Pumps 2A and 2B (2998-G-088)
SECTION XI RE UIREMENTS:
Each inservice test shall include the measurement and observation of all quantities in Table IWP-3100-1 except bearing temperatures, which shall be measured during at least one inservice test each year.(IWP;3300)
Symmetrical damping devices or averaging techniques may be*'used"to,reduce
'instrumentfluctuations to within 24 of the observed reading.(IWP-4150)
BASIS FOR RELIEF:The Hydrazine Pumps are positive displacement pumps with a variable speed drive.They-operate at a very low rpm and flow rate (0.71 to 0.82 gpm).The flow instrument orifice is located in the pump's suction line.Its output signal pulsates sharply with each stroke and cannot readily be averaged.The flow recorder for the hydrazine pumps, FR-07-2-2, displays a wide trace for flow rate..The only way to know the true flow rate of the pumps is to collect the pumps output in a container and measure it.During the 1992 Unit 2 refueling outage, several flow tests per hydrazine pump were performed.
The discharge of one pump was directed to a container of a known volume.The amount of time to fill the container was measured and then used to calculate an average flow rate for the pump.Each of the flow tests for each pump were performed at a different pump rpm.A correlation between pump rpm and average flow rate was developed and compared to the expected value.The measured and the expected correlations between rpm and flow rate were in close agreement.
The expected correlation was based upon piston diameter, piston stroke, and pump rpm.Based upon these results, hydrazine pump flow rate.can be accurately set by selecting the proper pump rpm.B-24 kg~i~J k C"<<j'~'lfe(p,4 Is~'~>f j Sac ra qlS I Je'44J~~)r~
Revision 2 08/01/92 RELIEF REQUEST NO.PR-17 (cont.)BASIS FOR RELIEF cont.Frequent performance of the above mentioned flow testing can not be performed.
Hydrazine is a highly flammable liquid with cumulative.
toxic affects when absorbed through the skin, inhaled, or ingested.It has also been identified as a known carcinogen.
ALTERNATE TESTING: "" During the.quarterly pump tests, each pump's rpm will be measured to verify the required flow rate of 0.71 to 0.82 gpm.Pump flow will be recorded but not alert trended and vibration will-be measured during the quarterly tests.During each refueling outage at least one flow test will be performed for each pump to verify proper performance.
Pump vibration.
will be.,measured, during this flow test.B-25 0
Appendix C Valve Program Tables P)~=~)~
Revision 2 08/01/92 Florida Power&Light Company INSERVICE TESTING-VALVE TABLES St.Lucie Nuclear Plant-Unit 2 PAGE: 1 LEGEND VALVE NUMBER The plant alpha-numerical designator for the subject valve COORD CL CAT SIZE The coordinate location of the valve on the designated drawing.The ISI Classification of the valve as per the respective ISI boundary drawings The valve category per Paragraph IWV-2200 The valve',s nominal size in inches TYPE A/P ACT.TYPE NORM POS.REM IND FAIL MODE The valve type The active (A)or passive (P)determination for the valve per IWV-2100.The, valve.actuator type-.as follows: AO Air-operated DO-.Diaphram-operated MO Electric motor-operated MAN Manual valve PO Piston-operated S/A Self-actuated SO Solenoid-operated Designates the normal position of the valve during plant operation at power Notes if a valve has remote position indication Identifies the failure mode (open or closed)for a valve.FAI indicates the valve fails"as is".
J/MJe M f E I a ri 1'.", l-~i 4*
Revision 2 08/01/92 Forida Power&Light Company INSERVICE TESTING-VALVE TABLES St.Lucie Nuclear Plant-Unit 2 PAGE 2 LEGEND Cont.EXAM Identifies the test requirements for a valve as follows: CV/C CV/0.CV/PO EC EE EO FS INSP PEC PI SLT-1 SLT-2 SLT-3 SRV Check valve exercise to closed position.Check valve full-stroke exercise to open position.'Check-valve partial-stroke exercise to open position.Exercise to closed position.For all category A or B power-operated valves stroke times will be measured unless excluded by an associated relief request..Exercise valve to verify proper operation and stroking with no stroke time measurements.
Requires observation of system parameters or local observation of valve operation.
Exercise to open position.For all category A or.B power-operated valves stroke times will be measured unless excluded by an associ'ated relief request.Fail safe test Disassembly and inspection of check valves Partial closure exercise for power-operated valves~Position indication verification Seat leakrate test per 10 CFR 50, App J Seat leakrate test for pressure isolation valves.Seat'leakage test of air accumulator check valves.Set point check for safety/relief valves 0>~~" 1~',~C$
Revision" 2 08/01/92 Florida Power 6 Light Company INSERVICE TESTING-VALVE TABLES St.Lucie Nuclear Plant-Unit 2 C PAGE: 3 LEGEND Cont.TEST FREQ The required test interval as follows: QR CS 2Y RF SP Quarterly (during plant operation)
Cold shutdown as defined by Technical Specification Every 2 years Each reactor refueling outage (cycle).In the case where this is designated for safety/relief valves refer, to Table IWV-3510-1.
Other (See applicable Request for Relief)RELIEF REQ.Refers to the-specific relief request associated with the adjacent test requirement.(See Appendix D)
~<>~
FLORIDA PONER AND LIGHT COHPANY VALVE TABLES Saint-Lucie Nuclear Plant-Unit 2 REVISION: 2 DATE: 08/01/92 PAGE: 4 P 8 ID: 2998-G-078 SH 107 SYSTEH: REACTOR COOLANT SYSTEH ACT.NORM REH FAIL TEST RELIEF VALVE NUHBER COORD.CL CAT.SIZE TYPE A/P TYPE POS~IND MODE EXAH FREQ REQ.REMARKS V-1460 G-6 2 8 F 000 GLOBE A SO LC YES FC EO CS Pl 2Y V-1461 G-6 2 B 1.000 GLOBE A SO LC YES FC EO PI CS 2Y V-1462 E-6 2 8 1.000 GLOBE A SO LC YES FC EO PI CS 2Y V-1463 E-6 2 8 1.000 GLOBE A SO LC YES FC EO Pl CS 2Y V-1464 D-4 2 B 1.000 GLOBE'SO LC YES FC EO CS Pl 2Y V-1465 E-4 2 8 1.000 GLOBE A SO LC YES FC'O CS Pl 2Y V-1466 G-5 2 8 1.000'GLOBE A SO LC YES FC EO CS PI 2Y
~$f FLORIDA POWER AND LIGHT COMPANY VALVE TABLES Saint Lucie Nuclear Plant-Unit 2 REVISION: 2 DATE: 08/01/92 PAGE: 5 P 8 ID: 2998-G-078 SN 108 SYSTEM: REACTOR COOLANT SYSTEH ACT~NORH REH FAIL VALVE NUHBER COORD.CL CAT~SIZE TYPE A/P TYPE POS.IND MODE TEST RELIEF EXAH FREQ REQ., REMARKS V-1474 F-6 1 8 3.000 GLOBE A SO C YES FC EO CS PI 2Y V-1475 D-6 1 B 3.000 GLOBE A SO C YES FC EO CS PI 2Y V-1476 F-5 1 B 3.000 GATE A HO 0 YES FAI EC r PI 2Y V-1477 D-5'1 8 3.000 GATE A HO 0 YES FAI EC QR PI 2Y
%kg I'f~Wp~
FLORIDA PONER AND LIGHT COHPANY VALVE TABLES Saint Lucia Nuclear Plant-Unit 2 REVISION: 2 DATE: 08/01/92 PAGE 6 P 8 ID: 2998-G-078 SN 109 SYSTEH: REACTOR COOLANT SYSTEM ACT.NORH REH FAIL.VALVE NUHBER COORD.CL CAT.SIZE TYPE A/P TYPE POS.IND MODE EXAM TEST RELIEF'FREQ REQ.-REMARKS V-1200 G-6 1 C F 000 SAFETY A S/A C NO SRV RF V.1201 G 6 1 C 3.000 SAFETY A S/A C NO SRV RF V-1202 G-6 1 C 3.000 SAFETY A S/A C NO SRV RF
FLORIDA POMER AND LIGHT COHPANY VALVE TABLES Saint Lucia Nuclear Plant-Unit 2 REVISION: 2 DATE: 08/01/92 PAGE: 7 P 8 ID: 2998-G-078 SN 120 SYSTEH: CNEHICAL ANO VOLUHE CONTROL ACT.NORH REM FAIL TEST RELIEF VALVE NUMBER COORS CL CAT.SIZE TYPE A/P TYPE POS.IND HOOE EXAM FREQ REQ.REMARKS V-2522 E-7 2 A 2.000 GLOBE A DO 0 YES FC EC FS Pl SLT-1 CS CS 2Y 2Y
FLORIDA POWER AND LIGHT COMPANY VALVE TABLES Saint Lucie Nuclear Plant-Unit 2 REVISION: 2 DATE: 08/01/92 PAGE: 8 P II ID: 2998-G-078 SH 121 SYSTEM: CHEMICAL AND VOLUME CONTROL ACT.NORM REM FAIL TEST RELIEF VALVE NUMBER COORD.CL CAT.SIZE TYPE A/P TYPE-POS~IND MODE EXAM FREQ REQ~REMARKS FCV-2210Y C-2 2 B 1 F 000 GLOBE A DO C YES FC EC QR FS QR PI 2Y V-2177 C-3 2 C 3.000 CHECK A S/A C NO CV/0 RF VR-5 CV/PO CS V-2190 D-6'C 3.000 CHECK A S/A C NO CV/C QR CV/0 RF VR-5 CV/PO CS V-2191 E-3 2 C F 000 CHECK A S/A C NO CV/0 RF VR-5 CV/PO CS V-2443 C-4 2 C 3.000 CHECK A S/A C NO CV/C QR CV/0 RF VR-6 CV/PO QR VR-6 V-2444 B-4 2 C 3.000 CHECK A S/A C NO CV/C QR CV/0 RF VR-6 CV/PO QR VR-6 V-2501 F-4 2 B 4.000 GATE A MO 0 YES FAI EC CS Pl 2Y V-2504 F-3 2 B 3.000 GATE A MO C YES FAI EC EO Pl CS CS 2Y V-2505 G-7 2 A 1.000 GLOBE A DO C YES FC EC FS Pl SLT-1 CS CS 2Y 2Y V-2508 C-6 2 B 3.000 GATE'MO C YES FAI EO QR Pl 2Y V-2509 C-7 2 8 3.000 GATE A MO C YES FAI EO Pl QR 2Y V-2512 F-5 2 B F 000 GLOBE A DO C YES FC EC QR FS QR PI 2Y y~I~~'I FLORIDA POWER AND LIGHT COMPANY VALVE TABLES Saint Lucie Nuclear Plant-Unit 2 CRC CCRC P 8 ID: 2998-G-078 SH 121 (cont)SYSTEM: CHEMICAL AND VOLUHE CONTROL REVISION: 2 DATE: 08/01/92 PAGE: 9 ACT.VALVE NUMBER COORD.CL CAT~SIZE TYPE A/P TYPE HORN REM FAIL POS.IND MODE TEST RELIEF EXAM FREQ REQ.REMARKS V-2514 C-3 2 B 3.000 GATE A MO C YES FAI EO QR PI 2Y V-2524 F-7 2 A 1.000 GLOBE A DO C YES FC EC CS FS CS PI 2Y SLT-1 2Y V-2525 E 4 2 8 4.000 GLOBE A MO C YES FAI EC QR PI 2Y V-2526 E 3 2 C 4.000 CHECK A S/A C NO CV/0 RF VR-5 CV/PO CS V-2650 B-4 2 8 1.000 GLOBE A DO C YES FC EC QR FS'R PI 2Y V-2651 D-4 2 8 1.000 GLOBE A DO C YES FC EC QR FS QR PI 2Y Xf-l~0 FLORIDA POUER AND LIGHT COMPAHY VALVE TABLES Saint Lucia Nuclear Plant-Unit 2 REVISIOH: 2 DATE: 08/01/92 PAGE: 10 P 8 ID: 2998-G-078 SH 122 SYSTEM: CHEMICAL AND VOLUHE CONTROL ACT.NORM REM FAIL TEST RELIEF VALVE NUMBER COORD.CL CAT.SI2E TYPE A/P TYPE POS.IND MODE EXAM-FREQ REQ.REMARKS SE-02-01 8-6 1 B 2.000 GLOBE A SO 0 YES FO Ec EO FS PI QR QR QR 2Y SE-02-02 B-7 1 8 2.000 GLOBE A SO 0 YES FO Ec QR EO QR FS QR PI 2Y SE-02-03 D-7 1 8 2.000 GLOBE A SO LC YES Fc Ec CS EO CS FS CS PI 2Y SE-02-04 D-7 1 B 2.000 GLOBE A SO LC YES Fc Ec CS EO CS FS CS PI 2Y V-2167 G-2 2 C F 000 CHECK A S/A C NO CV/C QR CV/0 QR V-2168 E-2 2 C 2.000 CHECK A S/A C NO CV/C QR CV/0 QR V-2169 C-2 2 C 2.000 CHECK A S/A C NO CV/C QR CV/0 QR V-2324 C-2 2 C 1.500 RELIEF A S/A C HO SRV RF V-2325 E-2 2 C 1.500 RELIEF A S/A C NO SRV RF V-'2326 G-2 2 C F 500 RELIEF A S/A C NO SRV RF V-2431 D-8 1 C 2.000 CHECK A S/A C NO CV/0 CS V-2432 C-8 1 C 2.000 CHECK A S/A C NO CV/0 QR V-2433 8-8 1 C 2.000 CHECK A S/A C HO CV/0 QR V-2440 G-2 2 C 2.000 CHECK A S/A 0 NO CV/0 CS V-2462 B-6 2 C 2.000 CHECK A S/A C NO CV/0 QR 0 O'e'4 I~a FLORIDA PONER AND LIGHT COHPANY VALVE TABLES Saint Lucie Nuclear Plant-Unit 2 REVISION: 2 DATE: 08/01/92 PAGE: 11 P 8 ID: 2998-G-078 SN 122 (cont)SYSTEM: CHEHICAL AND VOLUHE CONTROL ACT.NORM REH FAIL TEST RELIEF---VALVE NUHBER COORD.CL CAT~SIZE.TYPE-A/P TYPE POS.IND'MODE EXAH-FREQ-REQ.-REMARKS V-2515 F-8 1 B 2.000 GLOBE A DO 0 YES FC EC CS FS CS PI 2Y V-25'16 F-7 1 A 2.000 GLOBE A DO 0 YES FC EC CS FS CS PI 2Y SLT-1 2Y V-2523 B-6 2 8 2.000 GLOBE P DO LO YES FO PI 2Y V-2553 F-2 2 8 2.000 GLOBE A HO 0 YES FAI EC QR PI 2Y V-2554 D-2 2 B 2.000 GLOBE A HO 0 YES FAI EC QR PI 2Y V-2555<<C-2 2 8 2.000 GLOBE A HO 0 YES FAI EC QR PI 2Y V-2598 C-6 2 8 3.000 GATE A HO 0 YES FAI EO*CS PI 2Y A , Apl'7 FLORIDA POWER AND LIGHT COMPANY REVISION: 2 VALVE TABLES DATE: 08/01/92 Saint Lucia Nuclear Plant-Unit 2 PAGE: 12 P 8 ID: 2998-G-078 SH 130 SYSTEM: SAFETY INJECTION SYSTEM ACT.NORM REM FAIL TEST RELIEF--VALVE-NUMBER COORD.CL CAT.SIZE TYPE A/P TYPE POS.IND MODE EXAM'FREQ REQ;=-REMARKS FCV-3301 E-2 2 B 10.000 BUTFLY A MO LO YES FAI EC QR PI 2Y FCV-3306 F-4 2 B 10 F 000 BUTFLY A MO LO YES FAI EC PI QR 2Y HCV-3512 E-2 2 B 10~000 BUTFLY A MOLC YES FAI EO PI QR 2Y HCV-3657 F-4 2 8 10.000 BUTFLY A MO LC YES FAI EO QR PI 2Y SE-03-2A G-2 2 A 2.000 GLOBE A SO C YES FC EC FS PI SLT-1 QR QR 2Y 2Y VR-4 SE-03-2B G-2 2 A 2.000 GLOBE A SO C YES FC EC FS PI SLT-1 QR QR 2Y 2Y VR-4 SR-07-1A E-7 2 C 0.750 RELIEF A S/A C NO SRV RF SR-07.18 D-8 2 C 0.750 RELIEF A S/A C NO SRV RF V-07000 F-7 2 C 14.000 CHECK A S/A C HO CV/0 CV/PO RF VR-7 QR VR-7 V-07001 E-7 2 C 14.000 CHECK A S/A C NO CV/0 RF VR-7 CV/PO QR VR-7 V.3101 H-3 2 C 2.000 CHECK A S/A C HO CV/0 RF VR-32 CV/PO CS VR-32 V-3102 D-6 2 C 2.000 CHECK A S/A C NO CV/C CV/PO INSP CS VR-30 QR VR-30 RF VR-30 V-3103 D-5 2 C 2.000 CHECK A S/A C HO CV/C CS VR-30 CV/PO QR VR-30 INSP RF VR-30 xf 4a I'l I FLORIDA POMER AHD LIGHT COMPANY VALVE TABLES Saint Lucia Nuclear Plant-Unit 2 REVISION: 2 DATE: 08/01/92 PAGE: 13 P&ID: 2998-0-078 SH 130 (cont)SYSTEM: SAFETY INJECTION SYSTEM ACT.NORM REM FAIL'" TEST RELIEF VALVE NUMBER COORS CL CAT~SIZE TYPE A/P TYPE POS~IHD MODE EXAM FREQ REQ.REMARKS V-3104 E-6 2 C 2.000 CHECK A S/A C NO CV/C CS VR-28 CV/0 RF VR-28 CV/PO QR VR-28 V-3105 D-6 2 C F 000 CHECK A S/A C NO CV/C CV/0 CV/PO CS VR-28 RF VR-28 QR VR-28 V-3106 F-5 2 C 10.000 CHECK A S/A C NO CV/0 CS V-3107 E 5 2 C 10.000 CHECK A S/A C NO CV/0 CS V-3401 D-7 2 C 6.000 CHECK A S/A C NO CV/0 RF VR-8 CV/PO QR VR-8 V-3410 B-7 2 C 6.000 CHECK A S/A C NO CV/0 RF VR-8 CV/PO QR VR-8 V-3412 C-4 2 C F 000 RELIEF A S/A C NO SRV RF V-3414 8-5 2 C 3.000 S/CHEK A S/A C NO CV/C QR CV/0 RF VR-9 CV/PO QR VR-9 V-3417 D-4.2 C 1~000 RELIEF A S/A C NO SRV RF V-3427 0-5 2 C 3.000 S/CHEK A S/A C NO CV/C QR CV/0 RF VR-9 CV/PO QR VR-9 V-3430 G-6 2 C 1.000 RELIEF A S/A C NO SRV RF V-3431 H-6 2 C 1.000 RELIEF A S/A C NO SRV RF V-3432 E-7 2 8 14.000 GATE A MO LO YES FAI Ec PI QR 2Y V-3439 F-3 2 C 1.000 RELIEF A S/A C HO SRV RF V-3444 E.7 2 8 14.000 GATE A MO LO YES FAI Ec'l QR 2Y V-3456 G-4 2 8 10.000 GATE A MO LC YES FAI EO QR Pl 2Y 40~)-I Cy+e' FLORIDA POWER AND LIGHT COHPANY REVISION: 2 VALVE TABLES DATE: 08/01/92 Saint Lucia Nuclear Plant-Unit 2 PAGE: 14 P B ID: 2998-G-078 SH 130 (cont)SYSTEH: SAFETY INJECTION SYSTEH SRCCtHC ACT.NORH REM FAIL TEST RELIEF VALVE NUMBER COORD.CL CAT.SIZE TYPE A/P TYPE POS.IND HODE EXAH FREQ REQ.REMARKS V-3457 F-2 2 B 10.000 GATE A MO LC YES FAI EO QR PI 2Y V-3463 G-2 2 A 2.000 GATE P HAN LC NO SLT-1 2Y V-3495 G-6 2 B 6.000 GLOBE A SO LO YES FC EC QR FS QR PI 2Y V-3496 G-5 2 B 6.000 GLOBE A SO LO YES FC EC QR FS QR PI 2Y V-3507 F-1 2 C 1.000 RELIEF A S/A C NO SRV RF V-3517 N-6 2 8 12 F 000 GATE , A HO LC YES FAI EO QR PI 2Y V-3522 B-4 2 C 3.000 CHECK A S/A C NO CV/0 RF VR-10 V-3523 A-2 2 B 3.000 GLOBE A'HO LC YES FAI EC" QR EO QR Pl 2Y V-3540 C-2 2 B 3.000 GLOBE A MO LC YES FAI EC EO PI QR QR 2Y V-3547 C-5 2 C F 000 CHECK A S/A C NO CV/0 RF VR-10 V-3550 C-2 2 B 3.000 GLOBE A MO LC YES FAI EC QR EO QR PI 2Y V-3551 A-2 2 8 3.000 GLOBE A HO LC YES FAI EC EO PI QR QR 2Y V-3570 C-3 2 C 1.000 RELIEF A S/A C NO SRV-RF V-3654 B-5 2 B 6.000 GATE A MO LO YES FAI EC OR PI 2Y V-3656 D-5'2 B 6.000 GATE A MO LO YES FAI EC QR Pl 2Y
',CV ec V FLORIDA POWER AND LIGHT COHPANY VALVE TABLES Saint Lucie Nuclear Plant-Unit 2 REVISION: 2 DATE: 08/01/92 PAGE: 15 P 8 ID: 2998-G-078 SN 130 (cont)SYSTEM: SAFETY INJECTION SYSTEH ACT~NORH REH FAlL"VALVE NUMBER ,COORD.CL CAT.SIZE.TYPE A/P TYPE'POS~IND HODE TEST RELIEF EXAM'"FREQ REQ.REMARKS V-3658 G-7 2 8 12.000 GATE A MO LC YES FAI EO PI QR 2Y V-3659 G-6 2 8 3.000 GATE A HO 0 YES FAI EC PI QR 2Y V-3660 G-5 2 8 3~000 GATE A MO 0 YES FAI EC QR PI 2Y 4~re FLORIDA PONER AND LIGHT COMPANY VALVE TABLES Saint Lucie Nuclear Plant-Unit 2 REVISION: 2 DATE: 08/01/92 PAGE: 16 P 8 ID: 2998-G-078 SH 131 SYSTEM: SAFETY INJECTION SYSTEM ACT.NORM REH FAIL VALVE NUMBER COORS CL CAT~SIZE TYPE A/P'TYPE'POS~IND MODE'XAM TEST RELIEF FREQ'EQ., REMARKS HCV-3615 H-7 2 8 6.000 GLOBE A MO C YES FAI EO QR Pl 2Y HCV-3616 G-7 2 8 2~000 GLOBE A MO C YES FAI EO Pl QR 2Y HCV-3617 G-7 2 8 2.000 GLOBE A MO C YES FAI EO QR PI 2Y HCV-3625 F-7 2 8 6.000 GLOBE A MO C YES FAI EO QR PI 2Y HCV-3626 E-7 2 8 2.000 GLOBE A MO C YES FAI EO QR Pl 2Y HCV-3627 E-7 2 8 2.000 GLOBE A MO C YES FAI EO QR Pl 2Y HCV-3635 D-7 2 8 6.000 GLOBE A MO C YES FAI EO QR Pl 2Y HCV-3636 C-7 2 8 2.000 GLOBE A MO C YES FAI EO QR Pl 2Y HCV-3637 C-7 2 8 2.000 GLOBE A MO-C YES FAI EO QR Pl 2Y HCV-3645 8-7 2 8 6.000 GLOBE A MO C YES FAI EO QR Pl 2Y HCV.3646 A-7 2 8 2.000 GLOBE A MO C YES FAI EO QR PI 2Y HCV-3647 A-7 2 8 2.000 GLOBE A MO C YES FAI EO QR Pl 2Y V-3113 G-7 2 C 2.000 CHECK A S/A C HO'V/0 RF VR-11 CV/PO SP V-3114 H-7 2 C 6.000 CHECK A S/A C NO CV/C CS CV/0 CS V-3124 F-7 2 C 6.000 CHECK A S/A C NO CV/C CS CV/0 CS
+4a+c FLORIDA PONER AND LIGHT COMPANY-~VALVE TABLES Saint Lucie Nuclear Plant-Unit 2 REVISION: 2 DATE: 08/01/92 PAGE: 17 P 8 ID: 2998-G-078 SH 131 (cont)SYSTEM: SAFETY INJECTION SYSTEM ACT.NORM REM FAlL TEST RELIEF'VALVE NUMBER COORD.CL CAT.SIZE-TYPE A/P'YPE"'POS.'IND'MODE"" EXAM'FREQ'REQ~-"REMARKS V-3133 C-7 2 C 2.000 CHECK A S/A C HO'V/0 RF VR-11 CV/PO SP V-3134 D-7 2 C 6.000 CHECK A S/A C NO CV/C CS CV/0 CS V-3143 A-7 2 C 2.000 CHECK A S/A C NO CV/0 RF VR-11 CV/PO SP V-3144 8-7 2 C 6.000 CHECK A S/A C NO CV/C CS CV/0 CS V-3469 D-5 2 C 0.750 RELIEF A S/A C NO SRV RF V-3480 E-3 1 A 10.000 GATE A MO C YES FAI EO Pl SLT-2 CS 2Y SP VR-29 V-3481 E-4 1 A 10.000 GATE A MO C YES FAI EO CS Pl SLT-2 2Y SP VR-29 V-3482 E-4 2 C 0.750 RELIEF A S/A C NO SRV'F V-3524 F-5'I AC F 000 CHECK A S/A C HO CV/C SP VR-12 CV/0 RF VR-12 SLT-2 SP VR-2 V-3525 F-4 1 AC 3.000 CHECK A S/A C NO CV/C SP VR-12 CV/0 RF VR-12 SLT-2 SP VR-2 8 VR-12 V-3526 C-5 1 AC F 000 CHECK A S/A C NO CV/C CV/0 SLT-2 SP VR-12 RF VR-12 SP VR-2 V-3527 C-4 1 AC 3.000 CHECK A S/A C NO CV/C CV/0 SLT-2 SP VR-12 RF VR-12 SP VR-2 8 VR-12 V-3536 E-8 2 B F 000 GLOBE A MO LC YES FAI EC PI QR 2Y V-3539 C-B 2 8 4.000 GLOBE A MO LC YES FAI EC QR Pl 2Y
FLORIDA POWER AND LIGHT COMPANY VALVE TABLES Saint Lucie Nuclear Plant-Unit 2 REVISION: 2 DATE: 08/01/92 PAGE: 18 P 8 ID: 2998-G-078 SH 131 (cont)SYSTEH: SAFETY INJECTION SYSTEM ACT.NORH REM FAIL TEST RELIEF VALVE NUHBER-COORS-CL=CAT..SIZE-"-TYPE" A/P-"TYPE-POS IND HODE'EXAM'FREQ REQ.-REMARKS V-3545 E-4 1 8 10.000 GATE A HO LC YES FAI EO CS PI 2Y V-3571 8-4 1 8 1 F 000 GLOBE A DO C YES FC EC FS PI QR QR 2Y V-3572 F-4 1 B 1.000 PLOBE A DO C YES FC EC QR FS QR Pi 2Y V-3651 D-3 1 A 10.000 GATE A HO C YES FAI EO PI SLT-2 CS 2Y SP VR-29 V-3652 D-5 1 A 10.000 GATE A HO C YES FAI EO PI SLT-2 CS 2Y SP VR-29 V-3664 E-6 2 8 10.000 GATE A HO LC YES FAI EO CS Pl 2Y V-3665 C-6 2 B 10.000 GATE A HO LC YES FAI EO Pl CS 2Y V-3666 D-6 2 C 6.000 RELIEF A S/A C NO SRV RF V-3667 E-6 2 C 6.000 RELIEF A S/A C NO SRV RF V-3766 E-7 2 C 2.000 CHECK A S/A C NO CV/0 RF VR-11 CV/PO SP k l, g7 FLORIDA PONER AND LIGHT COMPANY VALVE TABLES Saint Lucie Nuclear Plant-Unit 2 REVISION: 2 DATE: 08/01/92 PAGE: 19 P.R ID: 2998-G-078 SH 132 SYSTEM: SAFETY INJECTION SYSTEM ACT.NORM REM FAIL TEST RELIEF..,,.VALVE NUMBER ,.COORD..CL CAT.SIZE TYPE-A/P TYPE POS.-IND.MODE--
EXAM.-FREQ REQ."-REMARKS HCV-3618 E-7 1 8 1.000 GLOBE A DO C YES FC EC QR FS QR PI 2Y HCV-3628 E-4 1 8 1.000 GLOBE A DO C YES FC EC FS PI QR QR 2Y HCV-3638 8-7 1 8 1.000 GLOBE A DO C YES FC EC QR FS QR PI 2Y HCV-3648 8-4 1 8 1.000 GLOBE A DO C YES FC EC QR FS QR PI 2Y SE-03-1A F-3 2 8 1.000 GLOBE A SO NC YES FC EC FS PI CS CS 2Y SE.03-18 F-7 2 8 1.000 GLOBE A SO NC YES FC EC FS PI CS CS 2Y SE-03-1C C-7 2 8 1 F 000 GLOBE A SO NC YES FC EC FS PI CS CS 2Y SE-03-1D C-3 2 8 1 F 000 GLOBE A SO NC YES FC EC FS PI CS CS 2Y V-3215 F-5 2 AC 12.000 CHECK A S/A C NO CV/C IHSP SLT-2 SP VR-13 SP VR-13 SP VR-2 V-3217 E-6 1 AC 12 F 000 CHECK A S/A C NO CV/C CV/PO IHSP SLT-2 SP VR-14 CS VR-14 SP VR-14 SP VR-2 V-3225 F-2 2 AC 12.000 CHECK A S/A C NO CV/C SP VR-13 INSP SP VR-13 SLT-2 SP VR-2
FLORIDA POMER AND LIGHT COMPANY VALVE TABLES Saint Lucie Nuclear Plant-Unit 2 REVISION: 2 DATE: 08/01/92 PAGE: 20 P 8 ID: 2998-G-078 SH 132 (cont)SYSTEH: SAFETY INJECTION SYSTEN ACT~NORH REN FAlL TEST RELIEF.VALVE.NUHBER
'COORD..CL CAT~SIZE TYPE-A/P-.TYPE-POS.IND NODE EXAN-FREQ-REQ~.REHARKS V-3227 E-6 1 AC 12.000 CHECK A S/A C NO CV/C CV/PO INSP SLT-2 SP VR-14 CS VR-14 SP VR-14 SP VR-2 V-3235 F-2 2 AC 12.000 CHECK A S/A C NO CV/C INSP SLT-2 SP VR-13 SP VR-13 SP VR-2 V-3237 E-6 1 AC 12.000 CHECK A S/A C NO CV/C CV/PO INSP SLT-2 SP VR-14 CS VR-14 SP VR-14 SP VR-2 V-3245 F-2 2 AC 12.000 CHECK A S/A C NO CV/C INSP SLT-2 SP VR-13 SP VR-13 SP VR-2 V-3247 E-6 1 AC 12.000 CHECK A S/A C NO CV/C CV/PO IHSP SLT-2 SP VR-14 CS VR-14 SP VR-14 SP VR-2 V-3258 F-2 1 AC 6.000 CHECK A S/A C NO CV/C CV/0 CV/PO SLT-2 SP VR-15 CS VR-15 SP SP VR-2 V-3259 F-5 1 AC 6.000 CHECK A S/A C NO CV/C CV/0 CV/PO SLT-2 SP VR-15 CS VR-15 SP SP VR-2 V-3260 8-5 1 AC 6.000 CHECK A S/A C NO CV/C CV/0 CV/PO SLT-2 SP VR-15 CS VR-15 SP SP VR-2 V-3261 8-2 1 AC 6.000 CHECK A S/A C HO CV/C CV/0 CV/PO SLT-2 SP VR-15 CS VR-15 SP SP VR-2 A I his 4wWw k b I FLORIDA POWER AND LIGHT COMPANY VALVE TABLES Saint Lucie Nuclear Plant-Unit 2 REVISION: 2 DATE: 08/01/92 PAGE: 21 P 8 ID: 2998-G-078 SH 132 (cont)SYSTEH: SAFETY INJECTION SYSTEH ACT.NORM REH FAIL TEST RELIEF VALVE NUMBER.=COORD.CL CAT.SIZE TYPE-A/P TYPE POS~IND HODE" EXAH'"FREQ.REQ.-REMARKS V-3611 F-6 2 8 1.000 GLOBE A AO C YES FC EC , CS FS CS PI 2Y V-3614 F-6 1 B 12.000 GATE A MO LO.YES FAI EC CS PI 2Y V-3621 F-3 2 8 1 F 000 GLOBE A AO C YES FC EC CS FS CS Pl 2Y V-3624 F-3 1 8 12.000 GATE A HO LO YES FAI EC CS Pl 2Y V-3631 B-6 2 B'1.000 GLOBE A AO C YES FC EC CS FS CS Pl 2Y V-3634 8-6 1 8 12.000 GATE A HO LO YES FAI EC CS PI 2Y V-3641 B-3 2 B 1.000 GLOBE A AO C YES FC EC CS FS CS PI 2Y V-3644 B-3 1 B 12.000 GATE A HO LO YES FAI EC CS PI 2Y V-3733 G-7 2 8 1 F 000 GATE A SO C YES FC EO CS Pl 2Y V-3734 G-7 2 B 1.000 GATE A SO C YES FC EO CS PI 2Y V-3735 G 4 2 8 1.000 GATE A SO C YES FC EO CS'I 2Y V-3736 G-4 2 8 1.000 GATE A SO C YES FC EO CS PI V-3737 D-7 2 8 1.000 GATE A SO C YES FC EO CS PI 2Y V-3738 0-7 2 8 1.000 GATE A SO C YES FC EO CS PI 2Y
+0 FLORIDA POWER AND LIGHT COHPANY VALVE TABLES.Saint Lucie Nuclear Plant-Unit 2 REVISION: 2 DATE: 08/01/92 PAGE: 22 P 8 ID: 2998-G-078 SN 132 (cont)SYSTEM: SAFETY INJECTION SYSTEH ACT.NORH REH FAIL TEST RELIEF ,VALVE NUHBER<<COORS CL CAT~SI2E TYPE A/P TYPE=POS.IND HODE.EXAM FREQ-REQ.-REMARKS V-3739 0-4 2 8 1.000 GATE A SO C YES FC EO PI'CS 2Y V-3740 D-4 2 8 1.000 GATE A SO C YES FC EO CS PI 2Y 4 4 J I' FLORIDA PONER AND LIGHT COMPANY VALVE TABLES Saint Lucie Nuclear Plant-Unit 2 REVISION: 2 DATE: 08/01/92 PAGE: 23 P 8 ID: 2998-G-078 SN 153 SYSTEH: SAMPLING SYSTEM ACT.NORM REM FAIL TEST RELIEF~BIVALVE NUHBER COORD.'L CAT~'iZE.TYPE'A/P-TYPE POS~"IND HODE--'EXAM'REQ" REQ." REMARKS SE-05-1A G-7 2 A 0.375 GLOBE A SO C YES FC EC QR FS QR Pl 2Y SLT-1 2Y SE-05-18 F-7 2 A 0.375 GLOBE A SO C YES FC EC QR FS QR PI 2Y SLT-1 2Y SE-05-1C E-7 2 A 0.375 GLOBE A SO C YES FC EC QR FS QR PI.2Y SLT-1 2Y SE-05-1D C-7 2 A 0.375 GLOBE A SO C YES FC EC QR FS QR PI 2Y SLT-1 2Y SE-05-1E G-5 2 A 0.375 GLOBE A SO C YES FC EC QR FS QR PI 2Y SLT-1 2Y V-5200 F-6 2 A 0.375 GLOBE A DO C YES FC EC OR FS QR PI 2Y SLT-1 2Y V-5201 E-6 2 A 0.375 GLOBE A DO C YES FC EC FS Pl SLT-1 QR QR 2Y V-5202 0-6 2 A 0.375 GLOBE A DO C YES FC EC FS PI SLT-1 QR QR 2Y V-5203 F-5 2 A 0.375 GLOBE A DO C YES FC EC QR FS QR Pl 2Y SLT-1 2Y FLORIDA POWER AND LIGHT COHPANY VALVE TABLES Saint Lucie Nuclear Plant-Unit 2 SHCSCCR 55ÃtSHJRCCC 0 Z CQ 555CCR5R5RCHXE 5$5RIIR CCRRii RC P 8 ID: 2998-G-078 SN'153 (cont)SYSTEH: SAHPLING SYSTEH REVISION: 2 DATE: 08/01/92 PAGE: 24 ACT~NORH REH FAIL TEST RELIEF VALVE, NUHBER..COORD..CL CAT.-SIZE'TYPE-A/P TYPE POS;-IND NODE"" EXAH-=-FREQ=REQ.REHARKS V-5204 E-5 2 A 0.375 GLOBE A DO C YES FC EC FS PI SLT-1 QR QR*2Y 2Y V-5205 D-5 2 A 0.375 GLOBE A DO C YES FC EC FS PI SLT-1 QR QR 2Y 2Y
FLORIDA POHER AND LIGHT COMPANY VALVE TABLES.Saint Lucia Nuclear Plant-Unit 2 REVISION: 2 DATE: 08/01/92 PAGE: 25 P 8 ID: 2998-G-078 SH 160 SYSTEM: llASTE MANAGEMENT SYSTEM CIZKRRCRI SZtO 5500555C 5 C5 C5I 5 1 0 5 ZX ACT.NORM REM FAIL VALVE NUMBER.COORD..CL CAT~-SIZE.TYPE-A/P TYPE=POS~-IND MODE=.EXAM TEST RELIEF-FREQ REQ.--REMARKS V-6341 E-7 2 A 3.000 DIAPH A AO 0 YES FC EC FS PI SLT-1 QR QR 2Y 2Y V-6342 E-6 2 A 3.000 D IAPH A AO 0 YES FC EC QR FS QR PI 2Y SLT-1 2Y FLORIDA POWER AND LIGHT COMPANY VALVE TABLES Saint Lucie Nuclear Plant-Unit 2 REVISION: 2 DATE: 08/01/92 PAGE: 26 P 4 ID: 2998-G-078 SH 163 SYSTEM: WASTE MANAGEMENT SYSTEM ACT.NORM REM FAIL TEST RELIEF VALVE NUMBER COORS CL CAT.SIZE TYPE A/P TYPE POS~IND MODE EXAM FREQ REQ.REMARKS V-6718 E-7 2 A F 000 DIAPH A AO 0 YES FC EC FS PI SLT-1 QR QR 2Y 2Y V-6741 8-2 2 A 1.000 GLOBE A AO 0 YES FC EC QR FS QR PI 2Y SLT-1 2Y V-6750 E-7 2 A 1.000 DIAPH A AO 0 YES FC EC QR FS QR PI 2Y SLT-1 2Y V-6792 C-7 2 AC F 000 CHECK A S/A C NO CV/C CS VR-17 SLT-1 2Y 4 0 FLORIDA POWER AND LIGHT COHPANY VALVE TABLES Saint Lucia Nuclear Plant-Unit 2 REVISION: 2 DATE: 08/01/92 PAGE: 27 P 5 ID: 2998-G-079 SN 1 SYSTEM: HAIN STEAH SYSTEH ACT.NORM REH FAIL TEST RELIEF.VALVE.NUHBER
.=COORD.CL-CAT~SIZE TYPE.A/P-TYPE POS."~IND MODE EXAM--FREQ-REQ.-REMARKS NCV-08-1A K-13 2 B 34.000 GLOBE A PO 0 YES EC CS PEC QR PI 2Y HCV-08-18 K-13 2 8 34 F 000 GLOBE A PO 0 YES EC CS PEC QR PI 2Y HV-08-12 N-8 2 8 4.000 GATE A HO C YES FAI EO QR PI 2Y HV.08.13 N-10 2 8 4.000 GATE A HO C YES FAI EO QR Pl 2Y MV-08-14 K-8 2 B 10.000 GATE P HO 0 YES FAI PI 2Y MV-08-15 K-10 2 B 10 F 000 GATE P HO 0 YES FAI PI 2Y HV-08-16 D-10 2 8 10~000 GATE P HO 0 YES FAI PI 2Y HV-08-17 D-8 2 8 10.000 GATE P HO 0 YES FAI PI 2Y MV-08-18A J-8 2 8 10.000 ANGLE A HO C YES FAI EC QR EO QR PI 2Y MV-08-188 0-10 2 8 10.000 ANGLE A MO C YES FAI EC QR EO QR PI 2Y HV-08-19A J-10 2 8 10.000 ANGLE A MO C YES FAI EC'R EO PI QR 2Y HV-08-198 D-8 2 8 10.000 ANGLE A HO C YES FAI EC QR EO QR PI 2Y MV-08-1A K-13 2 B F 000 GLOBE A MO C YES FAI EC QR Pl 2Y HV-08-18 C-13 2 8 3.000 GLOBE A HO C YES FAI EC PI QR 2Y la 1a FLORIDA POWER AND LIGHT COHPANY VALVE TABLES Saint Lucie Nuclear Plant-Unit 2 REVISION: 2 DATE: 08/01/92 PAGE: 28 P 8 ID: 2998-0-079 SH 1 (cont)SYSTEM: HAIN STEAM SYSTEH ACT.NORH REH FAIL TEST RELIEF.VALVE, NUMBER"COORS-CL-CAT.SIZE TYPE.A/P-TYPE POS.'IND HODE'EXAM-"FREQ-REQ.REHARKS HV-08-3 N-'14 3 B 4.000 GLOBE A HO C YES FAI EO QR PI 2Y SR-8201 J-12 2 C 6.000 SAFETY A S/A C NO SRV RF SR-8202 J-12 2 C 6.000 SAFETY A S/A C NO SRV RF SR-8203 J-12 2 C 6.000 SAFETY A S/A C NO SRV RF SR-8204 J-12 2 C 6.000 SAFETY A S/A C NO SRV RF SR-8205 C-11 2 C 6.000 SAFETY A S/A C NO SRV RF SR-8206 C-11 2 C 6.000 SAFETY A S/A C NO SRV RF SR-8207 C-11 2 C 6.000 SAFETY'S/A C NO SRV RF SR-8208 C-11 2 C 6.000 SAFETY A S/A C NO SRV RF SR-8209 J-12 2 C 6.000 SAFETY A S/A C NO SRV RF SR-8210 J-12 2 C 6.000 SAFETY A S/A C NO SRV RF SR-8211 J-12 2 C 6.000 SAFETY A S/A C NO SRV RF SR-8212 J-12 2 C 6.000 SAFETY A S/A C NO SRV RF SR-8213 C-11 2 C 6.000 SAFETY A S/A C NO SRV RF SR-8214 C-11 2 C 6.000 SAFETY A S/A C NO SRV RF SR-8215.C-11 2 C 6.000 SAFETY A S/A C NO SRV RF SR-8216 C-11 2 C 6.000 SAFETY A S/A C NO SRV.RF V-8130 L-10 3 C F 000 CHECK A S/A C NO CV/0 CS CV/PO QR INSP RF VR-31 V-8163 L-10 3 C 4.000 CHECK A S/A C NO CV/0 CS CV/PO QR INSP RF VR-31 j I' FLORIDA POMER AND LIGHT COHPANY VALVE TABLES Saint Lucie Nuclear Plant-Unit 2 REVISION: 2 DATE: 08/01/92 PAGE: 29 P 8 ID: 2998-G-080 SH 2 SYSTEM: FEEDNATER SYSTEM ACT.NORH REM FAIL TEST RELIEF ,-VALVE:NUHBER COORD.CL CAT.SIZE-"-TYPE.A/P TYPE POS.'IND'HODE EXAH FREQ REQ.REMARKS HCV-09-1A 8-14 2 8 20.000 GATE A PO 0 YES FO EC FS PEC PI CS CS QR 2Y HCV-09-18 8-13 2 8 20.000 GATE A PO 0 YES FO EC CS FS CS PEC QR PI 2Y NCV-09-2A E-13 2 8 20.000 GATE A PO0 YES FO EC CS FS CS PEC QR PI 2Y NCV-09-28 E-13 2 8 20.000 GATE A PO 0 YES FO EC FS PEC PI CS CS QR 2Y HV-09-09 G-16 2 8 4.000 GLOBE A HO C YES FAI EC QR EO QR PI 2Y HV-09-10 I-15 2 8 F 000 GLOBE A HO C YES FAI EC EO PI QR QR 2Y HV-09-'I1 G-12 2 8 4.000 GLOBE A HO C YES FAI EC EO PI QR QR 2Y HV-09-12 I-12 2 8 4.000 GLOBE A HO C YES FAI EC QR EO QR PI 2Y HV-09-13 M-17 3 8 2.500 GATE A HO C YES FAI EO QR PI 2Y MV-09-14 H-17 3 8 2.500 GATE A MO C YES FAI EO QR PI 2Y M
occcssca 5 N CRRRtIR 1 0555iRZCCSl55555 5SRC101a 5>>5R OSCSCC gg FLORIDA POWER AND LIGHT COMPANY VALVE TABLES Saint Lucia Nuclear Plant-Unit 2 REVISION: 2 DATE: 08/01/92 PAGE: 30 P&ID: 2998-G-080 SH 2 (cont)SYSTEM: FEEDWATER SYSTEM RRSSSR 5 0 15 5 5 41CCC01 5 0 I I 0 ZRCSSSS ACT~NORM REM FAIL TEST RELIEF VALVE NUMBER COORD.CL CAT~SIZE TYPE A/P TYPE POS.IHD MODE EXAM FREQ REGS REMARKS SE-09-2 K-15 3 8 4.000 GATE A SO C YES FC EC EE EO FS PI CS VR-33 QR VR-33 CS VR-33 QR 2Y SE-09-3 J-15 3 8 4.000 GATE A SO C YES FC EC EE EO FS PI CS VR-33 QR VR-33 CS VR-33 QR 2Y SE.09-4 H-11 3 8 F 000 GATE A SO C YES FC EC EE EO FS Pl CS VR-33 QR VR-33 CS VR-33 QR 2Y SE.09.5 l-11 3 8 F 000 GATE A SO C YES FC EC EE EO FS Pl CS VR-33 QR VR-33 CS VR-33 QR 2Y V-09107 M.14 8 C 4.000 CHECK A S/A C NO CV/C CS CV/0 CS V-09119 G-15 2 C 4.000 CHECK A S/A C NO CV/0 CS V.09123 L-14 8 C 4.000 CHECK A S/A C NO CV/C CS CV/0 CS V.09135 1-15 2 C 4.000 CHECK A S/A C NO CV/0 CS V-09139 J 14 8 C 6.000 CHECK A S/A C NO CV/0 CS V-09151 V-09157.G-12 2 C 4.000 CHECK A S/A C NO CV/0 CS I-12 2 C F 000 CHECK.A S/A C NO CV/0 CS V-09252 8 16 2 C 18.000 CHECK A S/A 0 NO CV/0 QR V-09294 E-16 2 C 18.000 CHECK A S/A 0 NO CV/0 QR FLORIDA POWER AND LIGHT COMPANY VALVE TABLES Saint Lucie Nuclear Plant-Unit 2 REVI SIGH: 2 DATE: 08/01/92 PAGE: 31 P 8 ID: 2998-G-080 SH 2 (cont)SYSTEM: FEEDWATER SYSTEM ACT.NORM REM FAIL TEST RELIEF.VALVE NUMBER , COORD.: CL,CAT~SIZE=TYPE'/P" TYPE'OS."cIHD MODE EXAM'-.".'FREQ.REQ:"-.-~REMARKS V-09303 L-13 3 C 2.000 CHECK A S/A C HO CV/PO INSP QR VR-27 RF VR-27 V-09304 M-12 3 C 1'00 CHECK A S/A C HO CV/PO INSP QR VR-27 RF VR-27 V-09305 N-'13 3 C 1.500 CHECK A S/A C NO CV/PO QR VR-27 INSP RF VR-27 Ug I.'bh~4<
FLORIDA POLIER AND LIGHT COHPANY VALVE TABLES Saint Lucia Nuclear Plant-Unit 2 REVISION: 2 DATE: 08/01/92 PAGE: 32 P 8 ID: 2998-G-082 SYSTEH: INTAKE COOLING UATER SYSTEH ACT~NORM REH FAIL TEST RELIEF-.--~VALVE~NUMBER COORD..CL SCAT.--SIZE TYPE A/P-.TYPE'POS.-IND"HOOE
'EXAH"-FREQ.REQ.-"REHARKS HV-21-2 E-5 3 8 24.000 BUTFLY A HO 0 YES FAI Ec PI QR 2Y HV-21-3 E-4 3 8 24~000 BUTFLY A HO 0'YES FAI Ec QR PI 2Y HV-21-4A I-3 3 8 3.000 BUTFLY A HO 0 YES FAI Ec QR PI 2Y HV-21-48 I-3 3 8~3.000 BUTFLY A HO 0 YES FAI Ec QR PI 2Y TCV-14-4A 8-3 3 8 30.000 BUTFLY A AO 0 NO FO Ec QR VR-34 FS QR TCV-'14-48 8-4 3 8 30.000 BUTFLY A AO 0 NO FO Ec QR VR-34 FS QR V-21162 H-4 3 C 30.000 CHECK A S/A C NO CV/C QR CV/0 QR V-21205 H-6 3 C 30 F 000 CHECK A S/A C NO CV/C QR CV/0 QR V-21208 H-7 3 C 30.000 CHECK A S/A C NO CV/C QR CV/0 QR V-21431 H-5 3 C 1.000 CHECK A S/A C NO CV/C QR CV/0 QR V-21434 H-5 3 C 1.000 CHECK A S/A C NO CV/C QR CV/0 QR V-21523 C 2.000 CHECK A S/A C NO CV/0 QR V-21524 I-7 3 C F 000 CHECK A S/A C NO CV/0 QR 4a i>e P~c~
FLORIDA PSIER AND LIGHT COMPANY VALVE TABLES Saint Lucie Nuclear Plant-Unit 2 REVISION: 2 DATE: 08/01/92 PAGE: 33 P 8 ID: 2998-G-083 SYSTEM: COMPONENT COOLING SYSTEM ACT.NORM REH FAlL TEST RELIEF.VALVE.NUHBER
...COORD..CL CAT~., SIZE TYPE-A/P TYPE POS~:.IND-MODE EXAM'"FREQ'REQ.'EMARKS HCV-14-1 C-6 2 A 8.000 BUTFLY A AO 0 YES FC EC CS FS CS PI 2Y SLT-1 2Y VR-4 8 VR-16 HCV-14-10 H-15 3 8 16.000 BUTFLY A AO 0 YES FC EC QR FS QR Pl 2Y HCV-14-2 C-1 2 A 8.000 BUTFLY A AO 0 YES FC EC CS FS CS PI 2Y SLT-1 2Y VR-4 8 VR-16 HCV-14-3A L-3 3 B 14 F 000 BUTFLY A DO 0 YES FO EO.CS FS CS PI 2Y HCV-14-38 M-3 3 8 14.000 BUTFLY A OO 0 YES FO EO CS FS CS Pl 2Y HCV-14-6 0-2 2 A 8.000 BUTFLY A AO 0 YES FC EC CS FS CS Pl 2Y SLT-1 2Y VR-4 8 VR-16 HCV-14-7 D-6 2 A 8.000 BUTFLY A AO 0 YES FC EC FS Pl SLT-1 CS CS 2Y 2Y VR-4 8 VR-16 HCV-14-BA G-14 3 8 16.000 BUTFLY A AO 0 YES FC EC QR FS QR, PI 2Y HCV-14-8B G-15 3 8 16.000 BUTFLY A AO 0 YES FC EC QR FS QR PI 2Y HCV-14-9 G-15 3 8 16.000 BUTFLY A AO 0 YES FC EC FS PI QR 2Y
~Cc' FLORIDA POWER AND LIGHT COHPANY REVISION: 2 VALVE TABLES DATE: 08/01/92 Saint Lucie Nuclear Plant-Unit 2 PAGE: 34 P 5 ID: 2998-G-083 (cont)SYSTEH: COHPONENT COOLING SYSTEH ACT~NORH REM FAIL TEST RELIEF VALVE NUHBER COORD.CL CAT~SIZE TYPE A/P TYPE POS.IND HODE EXAM FREQ REQ.REMARKS MV-14-1 D-16 3 8 24.000 BUTFLY A MO 0 YES FAI EC QR EO QR Pl 2Y MV-14-10 C-9 2 8 8.000 BUTFLY A HO 0 YES FAI EC QR PI 2Y HV.14-11 C-10 2 B 8.000 BUTFLY A HO 0 YES FAI EC QR Pl 2Y HV-14-12 C-10 2 8 8.000 BUI'FLY A, HO 0 YES FAI EC Pl QR 2Y HV-14-13 C-8 2 8 8.000 BUTFLY A HO 0 YES FAI EC QR PI 2Y HV-14-14 C-8 2 B 8.000 BUTFLY A HO 0 YES FAI EC QR PI 2Y HV-14-15 C-9 2 B 8.000 BUTFLY A HO 0 YES FAI EC QR PI 2Y MV-14-16 C-8 2 B 8.000 BUTFLY A HO 0 YES FAI EC QR PI 2Y MV-14-17 G-'l3 3 8 12.000 BUTFLY A HO 0 YES FAI EC QR Pl 2Y MV-14-18 G-13 3 B 12.000 BUTFLY A HO LC YES FAI EC PI QR 2Y MV-14-19 G-12 3 8 12.000 BUTFLY A HO 0 YES FAI EC QR Pl 2Y HV-14-2 D-17 3 8 24.000 BUTFLY A MO C YES FAI EC QR EO QR PI 2Y HV-14-20 G-12 3 8 12.000 BUTFLY A MO LC YES FAI EC QR PI 2Y HV-14-3 G-16 3 8 24.000 BUTFLY A HO 0 YES FAI EC EO PI QR QR 2Y fl,~-~, ILIES 4si~t>
FLORIDA POWER AND LIGHT COHPANY VALVE TABLES Saint Lucie Nuclear Plant-Unit 2 REVISION: 2 DATE: 08/01/92 PAGE: 35 P/4 ID: 2998-G-083 (cont)SYSTEH: COHPONENT COOLING SYSTEH ACT.NORH REM FAIL TEST RELIEF VALVE NUHBER.,COORD...CL:
CAT., SIZE TYPE A/P>>TYPE POS." IND HOOE EXAM-FREQ REQ.*REMARKS HV-14-4 G-17 3 B 24.000 BUTFLY A HO C YES FAI Ec QR EO QR PI 2Y MV-14-9 C-10 2 8 8.000 BUTFLY A HO 0 YES FAI Ec QR Pl 2Y V-14'l43 E-16 3 C 20.000 CHECK A S/A C NO CV/C QR CV/0 ,QR V-14147 E-17 3 C 20 F 000 CHECK A S/A C NO CV/C QR CV/0 QR V-14151 E-16 3 C 20.000 CHECK A S/A C NO CV/C QR CV/0 QR
FLORIDA POWER AND LIGHT COHPANY VALVE TABLES Saint Lucie Nuclear Plant-Unit 2 REVISION: 2 DATE:'08/01/92 36 PAGE P 8 ID:'2998-G-084 SYSTEH: HAKEUP WATER SYSTEH.VALVE.NUMBER ,COORD.CL CAT..SIZE ACT~NORH REH FAIL TEST RELIEF TYPE-A/P TYPE POS."IND"HODE"EXAM'FREQ
- REQ.~-REMARKS NCV-15-1 N-17 2 A 2.000 GLOBE A 00 0 YES FC EC FS PI QR QR 2Y SLT-1 2Y V-15328 I-17 2 AC 2.000 CHECK A S/A C NO CV/C CS VR-18 SLT-1 2Y FLORIDA PCMER AHD LIGHT COMPANY VALVE TABLES Saint Lucie Nuclear Plant-Unit 2 REVISION: 2 DATE: 08/01/92 PAGE: 37 P 8 ID: 2998-G-085 SH 1 SYSTEM: SERVICE AIR ACT~NORH REH FAIL TEST RELIEF VALVE NUHBER COORS.CL CAT.SIZE TYPE ,A/P ,TYPE-POS..IND MODE-EXAH-FREQ REQ.--REMARKS HCV-18-2 H-6 2 A 2.000 GLOBE A AO C YES FC EC FS Pi SLT-1 QR QR 2Y 2Y V-181270 H-5 2 AC 2.000 CHECK A S/A 0/C NO CV/C CS SLT-1 2Y V-18797 G-6 2 A 1.000 BALL P HAH LC NO SLT-1 2Y U 0 FLORIDA POWER AND LIGHT COMPANY VALVE TABLES Saint Lucie Nuclear Plant-Unit 2 REVISION: 2 DATE: 08/01/92 PAGE: 38 P&ID: 2998-G-085 SH 2 SYSTEM: INSTRUMENT AIR ACT.NORM REM FAIL TEST RELIEF , VALVE NUHBER-COORS CL CAT.SIZE TYPE A/P TYPE POS.IND MODE EXAM" FREQ RED.REMARKS HCV-18-1 G-7 2 A 2.000 GLOBE A DO 0 YES FC EC CS FS CS PI 2Y SLT-1 2Y V-18195 G6 2 AC 2.000 CHECK A S/A C NO CV/C 2Y VR-19 SLT-1 2Y V-18279 J-2 2 AC 0.500 CHECK A S/A C NO CV/C CS SLT-3 CS V-18283 J-1 2 AC 0.500 CHECK A S/A C NO CV/C CS SLT-3 CS V-18290 L-1 NC AC 0.750 CHECK A S/A C NO CV/C CS SLT-3'S V-18291 L-1 2 AC 0.750 CHECK A S/A C NO CV/C CS SLT-3 CS V-18294 M-1 2 AC 0.750 CHECK A S/A C NO CV/C CS SLT-3 CS V-18295 M-1 2 AC 0.750 CHECK A S/A C NO CV/C CS SLT-3 CS FLORIDA POMER AND LIGHT COMPANY VALVE TABLES Saint Lucie Nuclear Plant-Unit 2 REVISION: 2 DATE: 08/01/92 PAGE: 39 P&ID: 2998-G-086 SH 1 SYSTEM: MISCELLANEOUS SYSTEMS ACT.NORM REM FAIL TEST RELIEF VALVE NUMBER COORS CL CAT.SIZE TYPE A/P TYPE POS~IHD MODE EXAM FREQ REQ.REMARKS FCV-23-3 D-14 2 8 2.000 GATE A DO 0 YES FC EC FS PI QR 2Y FCV-23-5 D-15 2 8 2.000 GATE A DO 0 YES FC EC QR FS QR Pl 2Y FCV-23-7 D-17 2 8 0.500 GLOBE A DO 0 YES FC EC QR FS QR PI 2Y FCV-23-9 D-18 2 8 0.500 GLOBE A DO 0 YES FC EC QR FS QR PI 2Y SR-17221 SR-17222 J-13 3 C 0.750 RELIEF A S/A C HO SRV RF L-13 3 C 0.750 RELIEF A S/A C HO SRV RF V-17204 J-13 3 C 2.000 CHECK A S/A C HO CV/0 QR V-17214 L-13 3 C 2.000 CHECK A S/A C NO CV/0 QR t'l i%~
FLORIDA PONER AND LIGHT COHPANY VALVE TABLES Saint Lucia Nuclear Plant-Unit 2 REVISION: 2 DATE: 08/01/92 PAGE: 40 P 8 ID: 2998-G-088 SYSTEM: CONTAINMENT SPRAY SYSTEH ACT~NORH REH FAIL TEST RELIEF.VALVE NUHBER.COORD..CL.CAT.SIZE-'--TYPE:.A/P TYPE'POS.'~IND'MODE
""EXAM"~FREQ REQ.'REMARKS FCV-07-1A F-12 2 8 12.000 GATE A DO C YES FO EO FS PI QR QR 2Y FCV-07-18 F-12 2 8 12.000 GATE A DO C YES FO EO FS PI QR QR 2Y LCV-07-11A I-14 2 A 2.000 GLOBE A DO 0 YES FC EC FS PI SLT-1 QR QR LCV-07-118
->1-.13 2 A 2.000 GLOBE A DO 0 YES FC EC FS PI SLT-1 QR QR 2Y 2Y HV-07-1A E-3 2 8 24.000 BUTFLY A HO LO YES FAI EC QR Pl 2Y HV-07-18 E-2 2 8 24.000 BUTFLY A MO LO YES FAI EC Pl QR 2Y HV-07-2A I-12 2 8 24.000 BUTFLY A MO C YES FAI EO QR Pl 2Y HV-07-28 J-12 2 8 24.000 BUTFLY A HO C YES FAI EO Pl QR 2Y HV-07-3 F-11 2 8'12.000 GATE A MO 0 YES FAI EC PI QR 2Y HV-07-4 F-11 2 8 12.000 GATE A HO 0 YES FAI EC , PI QR 2Y SE-07-3A C-9 2 8 F 000 GLOBE A SO C YES FO EC , QR EO QR FS QR Pl 2Y SE-07-38 E-9 2 8 2.000 GLOBE A SO C YES FO EC EO FS Pl QR QR QR 2Y
FLORIDA PONER AND LIGHT COMPANY VALVE TABLES Saint Lucia Nuclear Plant-Unit 2 REVISION: 2 DATE: 08/01/92 PAGE: 41 P 8 ID: 2998-G-088 (cont)SYSTEM: CONTAINMENT SPRAY SYSTEM ACT.NORM REM FAIL TEST RELIEF VALVE NUMBER COORD.CL CAT.SIZE TYPE A/P TYPE POS~IND MODE EXAM FREQ REGS REMARKS SR-07-2A 8-10 2 C 1.500 RELIEF A S/A C NO SRV.'F SR-07-28 C-10 2 C 1.500 RELIEF A S/A C NO SRV RF V-7119 J-7 2 C 24.000 CHECK A S/A C NO CV/PO QR VR-20 CV/PO RF VR-20 INSP RF VR-20 V-7120 1-7 2 C 24.000 CHECK A S/A C NOCV/PO QR VR-20 CV/PO RF VR-20 INSP RF VR-20 V-7129 H-5 2 C 12~000 CHECK A S/A C NO CV/0 RF VR-21 CV/PO QR VR-21 V-7130 H-6 2 8 12.000 GATE A MAN 0 NO EE QR V-7143 G-5 2 C 12.000 CHECK A S/A C NO CV/0 RF VR-21 CV/PO QR VR-21 V-7145 G-6 2 8 12.000 GATE A MAH 0 NO EE QR V-7170 G-13 2 A F 000 GATE P MAN LC NO SLT-1 2Y V-7172 J-10 2 C 24.000 CHECK A S/A C NO INSP RFVR-22 V-7174 I-10 2 C 24.000 CHECK A S/A C NO INSP RF VR-22 V-7188 G-14 2 A 3.000 GATE P MAN LC NO SLT-1 2Y V-7189 G-14 2 A F 000 GATE P MAN LC NO SLT-12Y V-7192 E-14 2 C 10~000 CHECK A S/A C NO INSP RF VR-23 V-7193 E-14 2 C 10.000 CHECK A S/A C NO INSP RF VR-23 V-7206 G-13 2 A 3.000 GATE P MAN LC NO SLT-1 2Y V-7231 A-13 2 C 2.000 CHECK A S/A C NO CV/0 QR V-7232 A-13 2 C F 000 CHECK A S/A C NO CV/0 QR V-7256 E-8 2 C 1.500 CHECK A S/A C NO CV/0 RF VR-'24 V-7258 F-8 2 C F 500 CHECK A S/A C NO CV/0 RF VR-24 P
FLORIDA POWER AND LIGHT COMPANY VALVE TABLES Saint Lucie Nuclear Plant-Unit 2 REVISION: 2 DATE: 08/01/92 PAGE: 42 P&ID: 2998-G-088 (cont)SYSTEH: CONTAINHENT SPRAY SYSTEH ACT.NORH REH FAIL TEST RELIEF VALVE,NUHBER.COORD.CL..CAT.-SIZE-TYPE'-A/P
-TYPE-POS;-IND MODE-EXAM FREQ-REQ.--REHARKS V-7412 8-10 2 C 1.500 CHECK A S/A C NO CV/0 aR MV,4.
FLORIDA POMER AND LIGHT COMPANY VALVE TABLES Saint Lucie Nuclear Plant-Unit 2 REVISION: 2 DATE: 08/01/92 PAGE: 43 P 8 ID: 2998-G-091 SYSTEM: MISCELLANEOUS SYSTEMS ACT.NORM REH FAIL TEST RELIEF ,,,VALVE,NUHBER
.COORD..CL CAT.*-.SIZE-TYPE A/P-TYPE POS:"IND'HODE EXAH'-FREQ"REQ.=.""REMARKS V-00-101 B-6 2 A 8.000 GATE P HAN C NO SLT-1 2Y VR-4 8 VR-16-V.00.139 L-10 2 A 0.375 GLOBE P HAN LC NO SLT-1 2Y V-00-140 M-10 2 A F 000 GLOBE P HAN LC NO SLT-1 2Y V-00-143 M-11 2 A 1.000 GLOBE P HAN LC NO SLT-1 2Y V-00-144 L 11 2 A 0.375 GLOBE P MAN LC NO SLT-1 2Y C
FLORIDA POWER AND LIGHT COMPANY VALVE TABLES Saint Lucia Nuclear Plant-Unit 2 REVISION: 2 DATE: 08/01/92 PAGE: 44 P F ID: 2998-G-092 SH'I SYSTEM: MISC.SAMPLING SYSTEMS ACT.NORM REM FAIL TEST RELIEF VALVE NUMBER..COORD.CL.CAT~SIZE TYPE-A/P TYPE POS.IHD'MODE-EXAM""FREQ REQ.-REMARKS FCV-26-1 G-2 2 A 1.000 GLOBE A DO 0 YES FC EC QR FS QR Pl 2Y SLT-1 2Y FCV-26.2 G-4 2 A 1.000 GLOBE A DO 0 YES FC EC QR FS QR Pl 2Y SLT-1 2Y FCV-26-3 H-2 2 A 1.000 GLOBE A DO 0 YES FC EC QR FS QR PI 2Y SLT-1 2Y FCV-26-4 H-4 2 A 1 F 000 GLOBE A DO 0 YES FC EC QR FS QR PI 2Y SLT-1 2Y FCV-26-5 I-2 2 A 1.000 GLOBE A DO 0 YES FC EC FS PI SLT-1 QR QR 2Y 2Y FCV-26-6 I-4 2 A 1.000 GLOBE A DO 0 YES FC EC FS PI SLT-1.QR QR 2Y 2Y FSE-27-10 B-13 2 A 0.375 GLOBE A SO C YES FC EC EO FS PI SLT-1 QR QR QR 2Y 2Y FSE-27-11 C-13 2 A 0.375 GLOBE A SO C YES FC EC EO FS Pl SLT-1 QR QR QR 2Y 2Y I'
FLORIDA POWER AND LIGHT COHPANY VALVE TABLES Saint Lucia Nuclear Plant-Unit 2 REVISION: 2 DATE: 08/01/92 PAGE: 45 P 8 ID: 2998-G-092 SN 1 (cont)SYSTEH: MISC.SAMPLING SYSTEHS ACT.NORM REH FAIL TEST RELIEF VALVE NUHBER COORS CL CAT~.SIZE TYPE A/P'TYPE POS.'IND HODE'XAM'REQ REQ.REMARKS FSE-27-12 8-15 2 A 0.375 GLOBE A SO C YES FC EC EO FS PI SLT-1 QR QR QR'Y 2Y F SE-27-13 8-15 2 A 0.375 GLOBE A SO C YES FC EC EO FS PI SLT.1 QR QR 2Y FSE-27-14 B-15 2 A 0.375 GLOBE A SO C YES FC EC EO FS Pl SLT-1 QR QR QR 2Y 2Y F SE-27-15 D-13 2 A 0.375 GLOBE A SO C YES FC EC QR EO QR FS QR Pl 2Y SLT-1 2Y FSE-27-16 0-13 2 A 0.375 GLOBE A SO C YES FC EC QR EO QR FS QR Pl 2Y SLT-1 2Y FSE-27-17 D-14 2 A 0.375 GLOBE A SO C YES FC EC EO FS PI SLT-1 QR QR QR 2Y 2Y FSE-27.18 D-14 2 A 0.375 GLOBE A SO C YES FC EC QR EO QR FS QR PI 2Y SLT-1 2Y
FLORIDA POWER AND LIGHT COMPANY VALVE TABLES Saint Lucia'Nuclear Plant-Unit 2~~~CAR 5~RE 5 C C5 5 CCC 1 0 5 5~SR P 8 ID: 2998-G-092 SH 1 (cont)SYSTEM: MISC.SAMPLING SYSTEMS REVISION: 2 DATE: 08/01/92 PAGE: 46 ACT.NORM REM FAIL TEST RELIEF..VALVE.NUMBER , COORS CL CAT., SIZE TYPE-A/P TYPE POS: IND MODE'EXAM"""FREQ"'REQ.--'REMARKS FSE-27-8 A-13 2 A 0.375 GLOBE A SO C YES FC EC EO FS PI SLT-1 QR QR QR 2Y 2Y FSE-27-9 8-13 2 A 0.375 GLOBE A SO C YES FC EC QR EO QR FS QR PI 2Y SLT-1 2Y V-27101 8-14 2 AC 0.375 CHECK A S/A 0/C NO CV/C CS VR-25 CV/0 QR SLT-1 2Y V-27102 8-14 2 AC 0.375 CHECK A S/A 0/C NO CV/C CS VR-25 CV/0 QR SLT-1 2Y
~4 4 FLORIDA PSIER AND LIGHT COMPANY VALVE TABLES Saint Lucia Nuclear Plant-Unit 2 REVISION: 2 DATE: 08/01/92 PAGE: 47 P 8 ID: 2998-G-096 SH 1 SYSTEM: EMERGENCY DIESEL GENERATOR 2A ACT.NORM REM FAIL TEST RELIEF VALVE NUMBER COORD.CL CAT.SIZE TYPE A/P TYPE POS.IND MODE EXAM FREQ REQ.REMARKS FCV-59-1A1 M-6 3 B F 500 GATE A AO C NO Fc EO SP VR-26 FCV-59-2A1 FCV-59-3A1 J-10 3 B'500 GATE A AO C NO Fc EO SP VR-26 C-10 3 B 1'00 GATE A AO C NO Fc EO SP VR-26 FCV-59-4A1 M-2 3 B 1.500 GATE A AO C NO Fc EO SP VR-26 SE-59-1A1 B-16 3 B F 500 GLOBE A SO C NO Fc Ec EO FS QR QR QR SE-59.1A2 K-1 3 B 1.500 GLOBE A SO C NO Fc Ec QR EO QR FS QR SE-59-3A L-6 3 B00 GATE A SO C NO Fc EO SP VR-26 SE-59-4A L-3 3 B 1 F 500 GATE A SO C NO Fc EO SP VR-26 SE-59-5A J-9 3 B 1.500 GATE A SO C NO Fc EO SP VR-26 SE-59-6A C-10 3 B 1 F 500 GATE A SO C NO Fc EO SP VR-26 SR-59-3A J-12 3 C 0.750 RELIEF A S/A C NO SRV RF SR-59.4A J-11 3 C 0.750 RELIEF A S/A C NO SRV RF SR-59-5A.J-9 3 C 0.750 RELIEF A S/A C NO SRV RF SR.59-6A J-8 3 C 0.750 RELIEF A S/A C NO SRV RF V-59156 M-12 3 C 1.250 CHECK A S/A C NO CV/C SLT-3 QR QR V-59158 M-10 3 C 1.250 CHECK A S/A C NO CV/C QR SLT-3 QR V-59159 M-8 3 C 1.250 CHECK A S/A C NO CV/C QR SLT-3 QR V-59236 M-11 3 C 1.250 CHECK A S/A C NO CV/C QR SLT-3 QR a')g~g FLORIDA POl!ER AHD LIGHT COMPANY VALVE TABLES Saint Lucie Nuclear Plant-Unit 2 REVISION: 2 DATE: 08/01/92 PAGE: 48 P 8 ID: 2998-G-096 SH 2 SYSTEM: EMERGENCY DIESEL GENERATOR 28 ACT.NORM,REM FAIL TEST RELIEF ,.VALVE, NUMBER.COORS CL'CAT.-SIZE TYPE-A/P"TYPE'OS.*IHD"MODE" EXAM'*'-FREQ REQ.REMARKS FCV-59-181 C-10 3 8 1.500 GATE A AO C NO Fc EO SP VR-26 FCV-59-281 M 2 3 8 1.500 GATE A AO C HO Fc EO SP VR-26 FCV-59-381 J-10 3 8'1.500 GATE A AO C NO Fc EO SP VR-26 FCV-59.481 M-5 3 8 1.500 GATE A AO C , NO Fc EO SP VR-26 SE-59-181 8-16 3 8 1.500 GLOBE A SO C NO Fc Ec EO FS QR QR QR SE-59-182 K-1 3 8 1.500 GLOBE A SO C NO Fc Ec QR EO QR FS QR SE-59-38 L-6 3 8 1.500 GATE A SO C NO Fc EO SP VR-26 SE-59-48 L-3 3 8 1.500 GATE A SO C NO Fc EO SP VR-26 SE-59-58 K-9 3 8 1.500 GATE A SO C HO Fc EO SP VR-26 SE-59-68 D-10 3 8 1.500 GATE A SO C NO Fc EO SP VR-26 SR-59-38 J-12 3 C 0.750 RELIEF A S/A C NO SRV RF SR-59-48 SR-59-58 J-9 3 C 0.750 RELIEF A S/A C NO SRV RF J-11 3 C 0.750 RELIEF A S/A C NO SRV RF SR-59.68 J-8 3 C 0.750 RELIEF A S/A C NO SRV RF V-59203 M-12 3 C 1.250 CHECK A S/A C NO CV/C QR SLT-3 QR V-59204 M-11 3 C 1.250 CHECK A S/A C NO CV/C QR SLT-3 QR V-59205 M-10 3 C 1.250 CHECK A S/A C NO CV/C SLT-3 QR QR V-59206 M-9 3 C 1'50 CHECK A S/A C HO CV/C QR SLT-3 QR A i~
FLORIDA PONER AND LIGHT COMPAHY REVISION: 2 VALVE TABLES DATE: 08/01/92 Saint Lucie Nuclear Plant-Unit 2 PAGE 49 P&ID: 2998-G-878 SYSTEM: HVAC ACT.NORM REM FAIL TEST RELIEF.VALVE.NUMBER ,.COORS CL CAT.-SI2E TYPE A/P.'TYPE-POS.IND'MODE-'"EXAM FREQ REQ."'REMARKS FCV-25-1 C-2 NC 8 48.000 BUTFLY A PO C YES FC EC FS PI CS CS 2Y FCV-25-2 J-15 2 A 48.000 BUTFLY A PO C YES FC EC FS Pl SLT-1 CS CS 2Y 2Y VR-4&VR-16 FCV-25-3 J-15 2 A 48.000 BUTFLY A PO C YES FC EC FS Pl SLT-1 CS CS 2Y 2Y VR-4&VR-16 FCV-25-4 K-12 2 A 48.000 BUTFLY A PO C YES FC EC FS Pl SLT-1 CS CS 2Y 2Y VR-4&VR-16 FCV-25-5 K-12 2 A 48.000 BUTFLY A PO C YES FC EC CS FS CS PI 2Y SLT-1 2Y VR-16 FCV-25-6 C-8 NC 8 48.000 BUTFLY A PO C YES FC EC FS Pl CS CS 2Y FCV-25-7 L-12 2 A 24.000 BUTFLY A PO C YES FC EC EO FS Pl SL'7-1 QR QR QR 2Y 2Y VR-16 FCV-25-8 L-12 2 A 24.000 BUTFLY A PO C YES FC EC EO FS Pl SLT-1 QR QR QR 2Y 2Y VR-16 V-25-20 C-13 2 AC 24.000 CHECK A S/A C NO CV/C CS CV/0 CS SLT-1 2Y VR-16 1~
FLORIDA POWER AHD LIGHT COMPANY VALVE TABLES Saint Lucie Nuclear Plant-Unit 2 REVISION: 2 DATE: 08/01/92 PAGE: 50 P 8 ID: 2998-G-878 (cont)SYSTEM: HVAC LL CC ACT.NORM REM FAIL TEST RELIEF,VALVE NUMBER.COORD.-CL CAT..SIZE-TYPE A/P TYPE POS.'.IND.MODE
-EXAM'REQ-REQ.'REMARKS V-25-21 C-13 2 AC 24.000 CHECK A S/A C NO CV/C CV/0 SLT-1 CS CS 2Y VR-16 A4 Hl l>
FLORIDA POMER AND LIGHT COHPANY VALVE TABLES Saint Lucie Nuclear Plant-Unit 2 REVISION: 2 DATE: 08/01/92 PAGE: 51 P II ID: 2998-G-879 SN 2 SYSTEM: HVAC ACT.NORM REH FAlL TEST RELIEF.VALVE.NUHBER
,.COORS-CL-CAT.-SIZE~TYPE-A/P-~TYPE POS.-IND"HODE-EXAH-FREQ-REQ;REMARKS FCV-25-14 E-6 3 B 12.000 BUTFLY A MO 0 YES FAI EC QR EO QR PI 2Y FCV-25-15 E-7 3 B 12.000 BUTFLY A MO 0 YES FAI ECQR EO QR Pl 2Y FCV-25-16 E-5 3 B 12.000 BUTFLY A MO O YES FAI EC , QR EO QR PI 2Y FCV-25-17 E-8'B 12 F 000 BUTFLY A HO 0 YES FAI EC EO Pl QR QR 2Y FCV-25-18 C-16 3 B 6.000 BUTFLY A HO 0 YES FAI EC QR PI 2Y FCV-25-19 C-17 3 B 6.000 BUTFLY A HO 0 YES FAI EC QR PI 2Y FCV-25-24 A-16 3 B 10.000 BUTFLY A MO 0 YES FAI EC Pl QR 2Y FCV-25-25 A-17 3 B 10.000 BUTFLY A HO 0 YES FAI EC QR PI 2Y US'~%4 W FLORIDA PONER AND LIGHT COHPANY VALVE TABLES Saint Lucie Nuclear Plant-Unit 2 REVISION: 2 DATE: 08/01/92 PAGE: 52 P&ID: 2998-G-879 SN 3 SYSTEH: MVAC ACT~NORM REH FAIL VALVE NUHBER COORD.CL CAT.SIZE TYPE A/P TYPE POS.'ND HODE TEST RELIEF EXAM FREQ REQ.REMARKS FCV-25-11 N-4 2 8 16.000 BUTFLY A HO C YES FAI EC EO PI QR" QR 2Y FCV-25-12 J-4 2 8 16.000 BUTFLY A HO C YES FAI EC QR EO QR PI 2Y FCV-25-13 I-14 2 8 12.000 BUTFLY A HO C YES FAI EO QR PI 2Y FCV-25-20 J-12 2 A 8.000 BUTFLY A PO C YES FC EC FS PI SLT-1 8 VR-16 FCV-25-21 J-11 2 A 8.000 BUTFLY A PO C YES FC EC FS PI SLT-1 QR QR 2Y 2Y VR-4!L VR-16'CV-25-26 K-16 2 A 8.000 BUTFLY A PO C'ES FC EC FS Pl SLT-1 QR QR 2Y 2Y VR-4 8 VR-16 FCV-25-29 K-3 2 8 F 000 BUI'FLY A HO C YES FAI EC QR PI 2Y FCV-25-30 M-4 2 8 20.000 BUTFLY A HO C YES FAI EC EO PI QR QR 2Y FCV-25-31 J-4 2 8 20.000 BUTFLY A HO C YES FAI EC QR EO QR PI 2Y FCV-25-32 N-4 2 8 30.000 BUTFLY A MO 0 YES FAI EC QR EO QR Pl 2Y FCV-25-33 J-4 2 8 30.000 BUTFLY A HO 0 YES FAI EC QR EO QR PI 2Y yi FLORIDA POMER AND LIGHT COMPANY VALVE TABLES Saint Lucie Nuclear Plant-Unit 2 REVISION: 2 DATE: 08/01/92 PAGE: 53 P 8 ID: 2998-G-879 SH 3 (cont)SYSTEM: HVAC VALVE NUMBER FCV-25-34 ACT~NORM REM FAlL TEST RELIEF COORS ,CL CAT.SI2E TYPE A/P TYPE POS.IND MODE*EXAM'-FREQ REQ~REMARKS H-2 2 8 4.000 BUTFLY A MO C YES FAI EC QR Pl 2Y FCV-25-36 K-15 2 A 8.000 BUTFLY A PO C YES FC EC FS PI SLT-1 QR QR 2Y 2Y VR-4&VR-16 V-25.23 J-4 2 C 24.000 CHECK A S/A C NO CV/0 QR V-25-24 H-4 2 C 24 F 000 CHECK A S/A C NO CV/O QR 0 Wet (" 4 l~s I 1 Appendix D Valve Program Requests for Relief 0
Revision 2 08/01/92 RELIEF REQUEST NO.VR-1 SYSTEM: Various COMPONENTS:
Any valves tested during cold shutdown conditions.
CATEGORY Various FUNCTION: Various SECTION XI RE UIREMENT: I Valves shall be exercised...unless such operation is not practical during plant operation.
If only limited operation is practical during plant operation, the valve shall be part-stroke exercised during plant operation and full stroke exercised during cold shutdowns.
Full stroke exercising during cold shutdowns for all valves not full-stroke exercised during plant operation shall be on a frequency determined by the intervals between shutdowns as follows: For intervals of 3 months or longer-exercise during each shutdown.(IWV-3412, IWV-4315 and IWV-3522)BASIS FOR RELIEF: In many instances testing of all valves designated for testing during cold shutdown cannot be completed due to the brevity of an outage or the lack of plant conditions needed for testing specific valves.It has been the policy of the NRC that if testing commences in a reasonable time and reasonable efforts are made to test all valves, then outage extension or significant changes in plant conditions are not required when the only reason is to provide the opportunity for completion of valve testing.ASME/ANSI OMa-1987, Operation and Maintenance'Of Nuclear Power Plants, Part 10 (Paragraphs 4.2.1.2 and 4.-3.2.2)recognizes this issue and allows deferred testing as set forth below.D-1
\"l~'>"+~i 4'~'I K, 4 a~~4 Revision 2 08/01/92 RELIEF REQUEST NO.VR-1 (cont.)ALTERNATE TESTING: For those valves designated to be exercised or tested during cold shutdown, exercising shall commence as soon as practical after the plant'reaches a stable cold shutdown condition, as.defined by the applicable Technical Specification, but no later than 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> after reaching cold shutdown.If the outage is sufficiently long enough for the testing of all the cold shutdown valves, then the 48-hour requirement need not apply.If the 48-hour requirement is waved, then all cold shutdown valves must be tested during the outage.Valve testing need not be performed more often than once every three (3)months except as provided for in IWV-3417(a).
Completion of all valve testing during a.cold shutdown outage is not required if the length of the shutdown period is insufficient to complete all testing.Testing not completed prior to startup may be rescheduled for the next shutdown in a sequence such that the test schedule does not omit nor favor certain valves or groups of valves..The program tables identify those valves to-which cold shutdown testing applies.Refer to Appendix E for discussion of the reasons and justification for allowing cold shutdown vs.quarterly testing.D-2 kS K Ct'~4~'4E I<<,f e E P II+I I Revision 2 08/01/92 RELIEF REQUEST NO.VR-2 SYSTEM Safety Injection (2998-G-078, Sh.131&132)COMPONENTS:
V-3217 V-3258 V-3215 V-3524 V-3227.V-3259 V-3225 V-3525 V-3237 V-3260 V-3235 V-3526 V-3247 V-3261 V-3245 V-3527 CATEGORY: A/C (Check Valves)FUNCTION: These-check valves open-to provide for high-pressure and low-pressure safety injection to the RCS.Each of these valves is designated as a pressure isolation valve (PIV)and provides isolation of safeguard systems from the RCS.SECTION XI RE UIREMENT: The leakage rate for valves 6-inches or.greater shall be evaluated per Subsection IWV-3427(b).(IWV-3521)
BASIS FOR RELIEF:Leak testing of these valves is primarily for the purpose of confirming their capability of preventing overpressurization and catastrophic failure of the safety injection piping and components.
In this regard, special leakage acceptance criteria is established and included in, the.St.Lucie 2 Technical Specifications (Table 3.4-1)that addresses the question of valve integrity in a more appropriate manner for these valves.Satisfying both the Technical Specification and the Code acceptance criteria is not warranted and implementation woul'd be difficult and confusing.
Specifically applying the trending requirements of IWV-3427 (b)would result in frequent and excessive maintenance of these valves.The continuation of a strict leakrate acceptance criteria and more frequent testing than specified by the Code gives a high degree of assurance that these valves will satisfactory perform their safety function.D-3
~I y t+P Revision 2 08/01/92 RELIEF REQUEST NO.VR-2 (cont.)ALTERNATE TESTING: The leakage rate acceptance criteria for"these valves-will be established per the St.Lucie Unit 2 Technical Specifications, Table 3.4-1.Leakage rates greater than.1.0 gpm-are unacceptable.
Each of the Reactor Coolant System Pressure Isolation Valve check valve shall be demonstrated operable by verifying leakage to be within its limits: 1.At least once per 18 months.2.Prior to entering MODE 2 whenever the plant has been in COLD SHUTDOWN for 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or more and if leakage testing has not been performed in the previous 9 months.'~4~Prior to returning the valve to service following maintenance, repair or replacement work on the valve.Following flow through valve(s)while in MODES 1,2,3, or 4~5.A.Within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> by verifying valve closure, and B.Within 31 days by verifying leakage rate.Following flow through valve(s)while in MODES 5 or 6: A.Within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> of entering MODE 4 by verifying valve closure, and B.Within 31 days of entering MODE 4 by verifying leakage rate.D-4
'1 4t I II%J f(s,=~i>>c,P')><ss a"~4~~>l er tg Revision 2 08/01/92 SYSTEM: RELIEF REQUEST NO.VR-3 Various COMPONENTS Various CATEGORY: Various FUNCTION:~This is a generic request for relief SECTION XI RE UIREMENT:If, for power-operated valves, an increase in stroke time of 504 or more for valves with full-stroke times less than or equal to 10 seconds is observed, the test frequency shall be increased to once each month until corrective action is taken, at which time the original test frequency shall be resumed (IWV-3417 (a))BASIS FOR RELIEF: The stroke time measurements taken during testing of fast-acting valves=(those less than 2 seconds)are subject to considerable variation due to conditions unrelated to the material condition of the valve (eg.test conditions, operator reaction time).In accordance with Generic Letter 89-04, Position 6, an alternate method of evaluating stroke times is considered acceptable.
ALTERNATE TESTING: The stroke time evaluation for those valves designated in the Plant Test Procedures as"fast-acting" will not account for successive increases of measured stroke time per IWV-3417(a) with the change in test frequency as required.In lieu of this, the assigned maximum limiting value of stroke time will be established at 2 seconds.Upon exceeding the 2-second limit, the valve will be declared inoperable and corrective action taken in accordance with IWV-3417(b).
D-5 l
Revision 2 08/01/92 SYSTEM: RELIEF REQUEST NO.VR-4 Primary Containment COMPONENTS:
PENETRATION NO.DRAWING NO.VALVES 10 11 23 24 41 54 56 57 2998-G-878 2998-G-878 2998-G-083 2998-G-.083 2998-G-078 Sh 130 2998'-G-091 2998-G-879 2998-G-879 FCV-25-4 and Blank Flange FCV-25-2 and FCV-25-3 HCV-14-1 and HCV-14-7 HCV-14-2 and HCV-14-6 SE-03-2A and SE-03-2B V-00101 and Blank Flange FCV-25-36 and FCV-25-26 FCV-25-20 and FCV-25-21 CATEGORY: A or A/C FUNCTION: These valves are closed to provide containment isolation.
SECTION XI RE UIREMENT: Category A valves shall be seat leak tested and a maximum permissible leakage rate shall be specified.
Individual'valve leakage rates shall be evaluated per IWV-3426 and IWV-3427.(IWV-3426, IWV-3427, NRC Generic Letter 89-04):-BASIS FOR RELIEF: For several containment systems, individual leakage rate tests are impractical due to the configuration of the system's piping and components.
In these.cases it is customary to perform leakage tests with the test volume between valves in series or behind valves in parallel paths.D-6
~y g g's I<rp" y'p't Revision 2 08/01/92 RELIEF REQUEST NO.VR-4 (cont.)BASIS FOR RELIEF cont.In these cases where individual-valve testing is.impractical; the valves will be leak tested simultaneously in multiple valve arrangements.
A maximum permissible leakage rate will be applied to each combination of valves or valve and blank flange.In each of the valve pairs, the two valves are equal in size and type, and the leakage limit is in proportion to their size.The blank flanges used in testing penetrations 10 and 54 have diameters similar in size to their associated valves,FCV-25-4 and V-00101.The leakage limit assigned to each pair is such that excessive leakage through any valve, o'..flange, would be..detectable and the appropriate corrective.
action taken.ALTERNATE TESTING: The above stated valves and blank flanges will be leak rate tested in pairs.Leakage measurements from tests of multiple valves or blank flanges will be evaluated in accordance with IWV-3426 and IWV-3427.D-7 P~l gg P I 4'JC h~r"~r j Revision 2 08/01/92 RELIEF REQUEST NO.VR-5 SYSTEM: Chemical and Volume Control (2998-G-078 Sh 121)COMPONENTS:
V-2177 V-2190 V-2191 V-2526 CATEGORY: FUNCTION: V-2177 and V-2526 open to provide a flowpath for emergency boration from the boric acid makeup pumps to the suction of the charging pumps.Likewise, V-2190 opens to provide a flowpath for emergency boration via gravity drain from the boric acid makeup tanks to the suction of the charging pumps.V-2190 closes to prevent recirculation to the ,boric acid makeup tanks when the boric acid makeup pumps are in operation.
Valve V-2191 opens to provide a flow path from the refueling water tank (RWT)to the suction of the charging pumps as an alternate supply of borated water for boration.SECTION XI RE UIREMENT: Check valves shall be exercised at least once every 3 months, except as provided by IWV-3522.(IWV-3521)
BASIS FOR RELIEF Testing these valves in the open direction requires the introduction of highly concentrated boric acid solution from the boric acid makeup tanks to the suction of the charging pumps.This, in turn, would result in the addition of excess boron to the RCS.This rapid insertion of negative reactivity would result in a rapid RCS cooldown and depressurization.
A large enough boron addition could result in an unscheduled plant trip and a possible initiation of the Safety Injection Systems.D-8 1 1%'w II I 4g d'>iJ Q I~Q+illf It~p~t t L I E.)J Revision 2 08/01/92 RELIEF REQUEST NO.VR-5 (cont.)BASIS FOR RELIEF cont.During cold shutdown, the introduction.
of excess quantities of boric acid into the RCS is undesirable from the aspect of maintaining proper plant chemistry and the inherent difficulties that may be encountered during the subsequent startup due to over-boration of the RCS.The waste management system would also be overburdened by the large amounts of RCS coolant that would require processing to decrease the boron concentration.
Since the boron concentration is increased for shutdown margin prior to reaching cold shutdown, a part stroke exercise of these valves could be performed at that time.ALTERNATE TESTING: Check valve V-2190 will be verified closed quarterly.
All of the check valves will be part stroke exercised during each cold shutdown per VR-1 and full stroke exercised during each reactor refueling outage.D-9
/~e4 1 Revision 2 08/01/92 RELIEF REQUEST NO.VR-6 SYSTEM: ,Chemical and Volume Control System (2998-G-078, Sh 121)COMPONENT:
V-2443 V-2444 CATEGORY: FUNCTION: These valves open to provide a flow path from the boric acid makeup pumps to the emergency boration header.SECTION XI RE UIREMENT: Check valves shall be exercised at least once every 3 months, except as provided by IWV-3522.(IWV-3521)
BASIS FOR RELIEF:Full-stroke testing these valves requires operating the boric acid makeup pumps at or near rated flow and verifying full accident flow through each valve.Such testing would cause the introduction of highly concentrated boric acid solution from the boric acid makeup tanks to the suction of the charging pumps.This, in turn, would result in the addition of excess boron to the RCS.This rapid insertion of negative reactivity would result in a rapid RCS cooldown and depressurization.
A large enough boron addition would result in an unscheduled plant trip and a possible initiation of Safety Injection Systems.During cold shutdown, the introduction of excess quantities of boric acid into the RCS is undesirable from the aspect of maintaining proper plant chemistry and the inherent difficulties that may be encountered during the subsequent startup due to over-boration of the RCS.The waste management system would be overburdened by the large amounts of RCS coolant that would require processing to decrease its boron concentration.
D-10 F w 0 Revision 2 08/01/92 RELIEF REQUEST NO.VR-6 (cont.)BASIS FOR RELIEF cont.A second circuit that-recirculates water to the RWT-has flow-rate measuring instrumentation installed-however it is limited to 30 gpm.During an accident, either pump's discharge check valve must be able to pass a minimum flow capable of matching the demand of the two running charging pumps (greater than 80 gpm.).ALTERNATE TESTING: Each of these valves will be partial stroke exercised quarterly.
During testing of the.boric acid makeup pumps performed during each reactor refueling (See Relief Request PR-5), system flow rate will be measured to verify full stroke of these valves.
T 1 t Revision 2 08/01/92 RELIEF REQUEST NO.VR-7 SYSTEM: Safety Injection (2998-G-078 Sh 130)COMPONENTS:
V-07000 V-07001 CATEGORY: FUNCTION: These valves open,to, provide flow paths from the RWT to the suction of the associated low-pressure safety injection pump.SECTION XI RE UIREMENT: Check valves shall be exercised at least once every 3 months, except as provided by IWV-3522.(IWV-3521)
BASIS FOR RELIEF: Full stroke exercising these valves to the open position requires injection-into the,RCS via the LPSI pumps.During plant.operation this="is-precluded because the LPSI pumps cannot develop sufficient discharge pressure to overcome primary system pressure.At cold shutdown, the shutdown cooling system cannot provide sufficient letdown flow to the RWT to accommodate full design flow from the RWT while maintaining the necessary core cooling function.Thus, the only practical.
opportunity for testing these valves is during refueling outages when water from the RWT is used to fill the refueling cavity.D-12 Z R~1 g I Fte<<W1 Revision 2 08/01/92.RELIEF REQUEST NO.VR-7 (cont.)ALTERNATE TESTING: These valves w'ill be partial-flow exercised during-quarterly testing of the LPSI pumps via the minimum flow circuit and full-flow exercised during each reactor refueling-outage.
ŽD-13 h
Revision 2 08/01/92 SYSTEM: RELIEF REQUEST NO.VR-8 Safety Injection (2998-G-078 Sh 130)COMPONENTS:
V-3401 V-3410 CATEGORY: FUNCTION: These valves open to.provide flow paths from the RWT and the-containment sump to the suction of the associated high-pressure safety injection pumps (HPSI).SECTION XI RE UIREMENT: Check valves shall be exercised at least once every 3 months, except as provided by IWV-3522.(IWV-3521)
BASIS FOR RELIEF: Full stroke exercising these valves to the open position requires injection via the'HPSI pumps=into the RCS.During plant operation this is precluded because the HPSI pumps cannot develop sufficient discharge pressure to overcome primary system pressure.During cold shutdown conditions, operation of the HPSI pumps is restricted to preclude RCS system pressure transients that could result in exceeding the pressure-temperature limits specified in the Technical Specifications, Section 3.4.9.D-14 A g II, 4~II 4N p q 0 Revision 2 08/01/92 RELIEF REQUEST NO.VR-8 (cont.)ALTERNATE TESTING: These valves will be.partial-flow exercised'during quarterly testing of the HPSI.pumps via the minimum flow circuit and full-flow exercised during each reactor refueling outage.This alternate testing satisfies the requirement of Generic Letter 89-04, Position l.D-15 gg'Ib>>t~l elk t4 I al S,pc~Cgsg k V f g 4 Revision 2 08/01/92 RELIEF REQUEST NO.VR-9 SYSTEM: Safety Injection (2998-G-078 Sh 130)COMPONENTS V-3414 V-3427 CATEGORY: FUNCTION: These valves open to provide flow paths from the respective-HPSI pumps to the high-pressure safety injection headers.They close to prevent recirculation through an idle pump.SECTION XI RE UIREMENT: Check valves shall be exercised at least once every 3 months, except as provided by IWV-3522.(IWV-3521)
BASIS FOR RELIEF: Full stroke exercising these valves to the open position~requires injection-into"the RCS via the"HPSI pumps.During plant operation this is precluded because the HPSI pumps cannot develop sufficient discharge pressure to overcome primary system pressure.During cold shutdown conditions, operation of the HPSI pumps is restricted to preclude RCS system pressure transients that could result in exceeding the pressure-temperature limits specified in the Technical Specifications, Section 3.4.9.Partial flow exercising of these valves i's performed whenever its associated HPSI pump is used to refill a SI Tank.The acceptable SI Tank level band specified by the Technical Specification is very narrow.The SI Tanks are only refilled on an as needed basis;therefore, the partial flow test cannot readily be incorporated into a quarterly test.
k Revision 2 08/01/92 RELIEF REQUEST NO.VR-9 (cont.')ALTERNATE TESTING: These valves will be verified closed quarterly and full-flow exercised to the open position during each reactor refueling outage.These valves will be part-stroked open while refilling a SIT as plant conditions warrant.D-17 Xa II M7 I>s'v~~w-kl-&E, Revision 2 08/01/92 RELIEF REQUEST NO.VR-10 SYSTEM: Safety Injection (2998-G-078 Sh 130)COMPONENTS:
V-3522 V-3547 CATEGORY: FUNCTION: These valves open to provide flow paths from the high-pressure safety injection pumps to the RCS for hot-leg injection.
SECTION XI RE UIREMENT: Check valves shall be exercised at least once every 3 months, except as provided by IWV-3522.(IWV-3521)
BASIS FOR RELIEF: Full stroke exercising of these valves would require operating a high pressure safety injection (HPSI)pump and injecting into the reactor coolant system through the hot leg injection system.At power operation this is not possible because the HPSI pumps do not develop sufficient discharge pressure to overcome reactor coolant system pressure.During cold shutdown conditions, operation of the HPSI pumps is restricted to preclude RCS system pressure transients that could result in exceeding the pressure-temperature limits specified in the Technical Specifications, Section 3.4.9.D-18 4 I N I Revision 2 08/01/92 RELIEF REQUEST NO.VR-10 ALTERNATE TESTING: At least once during each reactor refueling outage these valves will be full-stroke exercised to the open position.This alternate testing satisfies the requirement of Generic Letter 89-04, Position 1.D-19 h\'s h 4~QV I'i>I Revision 2 08/01/92 RELIEF REQUEST NO.VR-11 SYSTEM:-Safety Injection (2998-G-078 Sh 131)COMPONENTS:
V-3113 V-3133 V-3143 V-3766 CATEGORY: FUNCTION: These valves open to provide flow paths from the high-pressure safety injection headers to the RCS.SECTION XI RE UIREMENT: Check valves shall be exercised at least once every 3 months, except as provided by IWV-3522.(IWV-3521)
BASIS FOR RELIEF., Full stroke exercising of:these valves would require operating a high pressure safety injection (HPSI)pump at nominal accident flow rate and injecting into the reactor coolant system.At power operation this is not possible because the HPSI pumps do not develop sufficient discharge pressure to overcome reactor coolant system pressure.During cold shutdown conditions, operation of the HPSI pumps is restricted to preclude RCS system pressure transients that could result in exceeding the pressure-temperature limits specified in the Technical Specifications, Section 3.4.9.Partial flow exercising of these valves is performed whenever its associated SI Tank is refilled.The acceptable SI Tank level band specified by the Technical Specification is very narrow.The SI Tanks are only refilled on an as needed basis;therefore, the partial flow test cannot readily be incorporated into a quarterly test.D-20
Revision 2 08/01/92 RELIEF REQUEST-NO.VR-11 (cont.)ALTERNATE TESTING: These valves will be partial flow exercised when ever its associated SI Tank is filled.At least once during each reactor refueling outage these valves will be full-stroke exercised to the open position.D-21
~-~'lf's~a s a 1-I VfA 4 k Revision 2 08/01/92 RELIEF REQUEST NO.VR-12 SYSTEM: Safety Injection (2998-G-078 Sh 131)COMPONENTS:
V-3524 V-3525 V-3526 V-3527 CATEGORY: A/C FUNCTION:These valves open to provide flow paths from the high-pressure safety injection pumps to the RCS for hot leg injection and close to isolate the safety injection headers from the high pressure of the reactor coolant system.SECTION XI RE UIREMENT: Check valves shall be exercised at least once every 3 months, except as provided by IWV-3522.(IWV-3521)
BASIS FOR RELIEF: Full stroke exercising of these valves would require operating a high pressure safety injection (HPSI)pump at nominal accident flow rate and injecting into the reactor coolant system.At power operation this is not possible because the HPSI pumps do not develop sufficient discharge pressure to overcome reactor coolant system pressure.During cold shutdown conditions, operation of the.HPSI pumps is restricted to preclude RCS system pressure transients that could result in exceeding the pressure-temperature limits specified in the Technical Specifications, Section 3.4.9.D-22 II I f tt N W~~4 P~i C g Revision 2 08/01/92 RELIEF REQUEST NO.VR-12'(Cont.)BASIS FOR RELIEF cont.These are simple check valves with no external means of position indication, thus the only practical means of verifying closure is by performing a leak test or back flow test.Performing leak tests of V-3524 and V-3526 involves a considerable effort.The test connection for these valves are located in a high radiation area in the pipe penetration room, and one of the two connections is located over 12 feet above the floor.Testing during operation or at each cold shutdown outage would constitute an unreasonable burden on the plant staff.The other check valves, V-3525 and V-3527,.have upstream pressure alarms.Should either valve leak by, the pressure instruments would detect the increase and alarm in the control room when the alarm setpoint is exceeded.ALTERNATE TESTING: These valves will be full-stroke exercised to the open position at least once during each, reactor refueling outage.This satisfies the requirements of Generic Letter 89-04, Position 1.At least once every 18 months these valves will be verified to close in conjunction with PIV leak testing (see VR-2).In addition, V-3525 and V-3527 will be leak tested if the upstream pressure monitors indicate alarm during normal operation.
D-23 J~eA e F ,S 4 J' Revision 2 08/01/92 RELIEF REQUEST NO.VR-13 SYSTEM Safety Injection (2998-G-078 Sh 132)COMPONENTS:
V-3215 V-3225 V-3235 V-3245 CATEGORY: A/C FUNCTION: These valves open to provide flow paths from the safety injection tanks to the RCS and close to isolate the tanks from the high pressure of the reactor coolant system and the safety injection headers.SECTION XI RE UIREMENT: Check valves shall be exercised at least once every 3.months, except as provided by IWV-3522.(IWV-3521)
BASIS FOR RELIEF: Full stroke exercising of.these valves would require injecting from a tank under nominal pressure into a de-pressurized reactor coolant system'.At power operation this is not possible because the SI Tank pressure is insufficient to overcome reactor coolant system pressure.Under a large break LOCA accident conditions, the maximum (peak)flow rate through these valves would be approximately 20,000 gpm.During cold shutdown or refueling the required test conditions for developing this full accident flow cannot be established.
D-24 I t J t I~A I C'r l t~l 1+')~<bc H~e a.'t.Nt~i"f 4 T$A f Revision 2 08/01/92 RELIEF REQUEST NO.VR-13 (Cont.)BASIS FOR RELIEF cont.The SIT discharge isolation valves are motor operated valves with a nominal stroke"time of 52 seconds.Therefore, the isolation valve cannot be used to simulate the LOCA flow conditions by opening it with a full or partially pressurized SIT.The discharge.
flow rate would only increase gradually due to the long stroke time of the discharge isolation valve.The flow rate would not be anywhere near the expected peak blowdown rate of 20,000 gpm.expected during a large break LOCA.FP&L has reviewed the operating and maintenance history of these valves and similar valves used throughout the industry-under comparable conditions.
Based on these reviews, there is no evidence of valve degradation with respect to their ability to open and satisfactorily pass the required flow.It is apparent from the failure data that the primary mode of failure is related to valve leakage-both past the seat and external through the body-bonnet and hinge pin gasket joints.It should also be noted that these valves are not subjected to any significant flow during plant operation as well-as maintenance periods;thus it is unlikely that these valves would experience any service-related damage or wear.Although check valve disassembly is a valuable maintenance tool that can provide,a great deal of information about a valve's internal condition, due to the difficulties associated with these maintenance activities, it'should only be performed under the maintenance program at a frequency commensurate with the valve type and service.In this light, FP&L considers the frequency of=inspection for these valves of once each 10-year inspection interval to be adequate to ensure the continued operability of these valves.These are simple check valves with no external means of position indication, thus the only practical means of verifying closure is by performing a leak test or back flow test.The back flow tests are performed as part of the pressure isolation testing per VR-2.D-25 II*D li.1%,T It I 4 i I'A.
Revision 2.08/01/92 RELIEF REQUEST,NO.
VR-13 (cont.)ALTERNATE TESTING: At least once during each ISI (10 year)inspection interval each of these valves will be disassembled, inspected, and manually stroked to verify operability.
Should a valve under inspection be found to be inoperable, then the remaining three valves will be inspected during the same outage.Assurance of proper reassembly will be provided by performing a leak test'or partial-flow test prior to returning a valve'to service following disassembly.
These valves will be verified closed in conjunction with PIV leak testing.See VR-2 for PIV testing frequency.
D-26 If h h Revision 2 08/01/92 RELIEF REQUEST NO.VR-14-SYSTEM Safety Injection (2998-G-078 Sh 132)COMPONENTS:
V-3217 V-3227 V-3237 V-3247 CATEGORY: ,A/C FUNCTION: These valves open to provide flow paths from the safety injection headers to the RCS and close to isolate the headers from the high pressure of the reactor coolant system.SECTION XI RE UIREMENT Check valves shall be exercised at least once every 3 months, except as provided by IWV-3522.(IWV-3521)
BASIS FOR RELIEF: Full stroke exercising of these, valves would require injecting from a tank under nominal pressure into a de-pressurized reactor coolant system.At power operation this is not possible because the SI Tank pressure is insufficient.to overcome reactor coolant system pressure.Under a large break LOCA accident conditions, the maximum (peak)flow rate through these valves would be approximately 20,000 gpm.During cold shutdown or refueling the required test conditions for developing this full accident flow cannot be established.
D-27 gS~4 f 4~t 0.
Revision 2 08/01/92 RELIEF REQUEST NO.VR-14 (Cont.)BASIS FOR RELIEF cont.The SIT discharge isolation valves are motor operated valves with a nominal stroke time of 52 seconds.'herefore, the isolation valve cannot be used to simulate the'LOCA flow conditions by opening it with a full or partially pressurized SIT.The discharge flow rate would only increase gradually due to the long stroke time of the discharge isolation valve.The flow rate would not be anywhere near the expected peak blowdown rate of 20,000 gpm.expected during a large break LOCA.FP&L has reviewed the operating and maintenanc'e history of these valves and similar valves used throughout the industry under comparable conditions.
These four valves have been in operation in Unit 2 since the'lant startup in 1983.A total of 2 plant work orders have been initiated for work.on these valves.Of the two work orders, one was to repair seat leakage identified by a seat leakage test and the other was for disassembly and inspection per Generic Letter 89-04.A search of the Nuclear Plant Reliability Data System for problems with valves similar to these revealed 12 reports-7 due to seat leakage and the remaining 5 were related to gasket leaks.Based on these reviews there is no evidence of valve degradation with respect to their ability to open and satisfactorily pass the required flow.It is apparent fromthe failure data that the-primary mode of failure is related to valve leakage-both past the seat and external through the body-bonnet and hinge pin gasket joints.4 In order to disassemble and inspect these valves, the reactor coolant system must be placed in mid-loop or"reduced inventory" condition for several days.In response to issues raised in NRC Generic'Letter 88-17, FPS<L is concerned about continued operations with the plant in a condition of"reduced inventory." During these periods, the risk of over-heating the core is increased due to the higher probability of an incident where shutdown cooling is lost.This risk is compounded by the reduced volume of water available to act as a heat sink should cooling be lost.Since 1982 there have been at least six (6)reported events in the industry where cooling flow was lost while a.plant was in a"reduced inventory" condition.
D-28 "l ,tN Wf 4 e~i~, L f<
- A valve whose failure in a position other than its normal position could jeopardize the immediate safety of the plant or system components;
- A valve whose failure in a position other than its normal position could cause all trains of a safeguard system to be inoperable;
- A valve whose failure in a position other than its normal position that might cause a transient that could lead to a plant trip;or*When test requirements or conditions are precluded by system operation or access.Cold shutdown testing is performed under conditions outlined in Relief Request VR-1.Reactor Coolant 2998-G-078 Sh 107 V-1460 thru V-1466--Reactor Coolant System Gas Vents These valves are administratively controlled in the key-locked closed position with the power supply disconnected to prevent inadvertent operation.
3.1.3 leading
to a plant shutdown.Furthermore, if a valve were to fail open or valve indication fail to show the valve returned to the fully closed position following exercising, prudent plant operation would probably likely result in a plant shutdown.E-1 A~P'Vip ski&f1+l Revision 2 08/01/92 Reactor Coolant 2998-G-078 Sh 108 V-1474 and V-1475 Power-Operated Relief Valves.Due to the potential impact.of the resulting*transient should one of these valves open prematurely or stick in the open position, it is=considered imprudent to cycle them during plant operation with the reactor coolant system pressurized.
Chemical&Volume Control 2998-G-078 Sh.120 V-2522" Letdown Line Containment Isolation Valve Closing this valve during operation isolates the letdown line.from the RCS and would result in undesirable pressurizer level..transients with the potential for a plant trip.'f a valve failed to reopen, then-an-unexpected plant shutdown would.be required.Chemical 6 Volume Control 2998-G-078 Sh.121 V-2501 Volume Control Tank Outlet Valve Closing this valve during operation of a charging pump would isolate the VCT from the charging pump suction header damaging any operating charging pumps and interrupting the flow of charging water flow to the RCS with the potential of RCS transients and plant trip.V-2504 RWT Discharge Valve Opening this valve during operation would result in injection of RWT borated water into the reactor coolant system.This would, in turn, result in overboration with an adverse reaction in reactor power,and the potential for a power transient.
E-2
""A V I I h'I it" hL Ak*~I Revision 2 08/01/92 V-2505 and V-2524 RCP Control Bleedoff Isolation Valves Exercising either of these valves to the closed position when any of the reactor coolant pumps (RCP's)are in operation would interrupt flow from the RCP seals and result in damage to the pump(s).Chemical&Volume Control 2998-G-078 Sh.122 SE-02-03 and SE-02-04 Auxiliary Pressurizer Spray Valves Opening either of these valves (or failure in the open position)during plant operation would cause an RCS pressure transient that could potentially adversely affect plant safety and lead to a plant trip.In addition, the pressurizer spray piping would be subjected to undesirable thermal shock.~V-2431 Auxiliary Pressurizer Spray Check Valve In order to test this valve, either SE-02-03 or SE-02-04 must be opened.Opening either of these valves (or failure in the open position)during plant operation would cause an RCS pressure transient that could potentially adversely affect plant safety and lead to a plant trip.In addition, the pressurizer spray piping would be subjected to undesirable thermal shock.V-2440 Charging Pump Discharge Check Valve To Safety Injection Opening this valve requires operating a charging pump and discharging into the RCS via the safety injection nozzles.Per Technical Specification 3.5.2, thermal cycling of the safety injection nozzles is undesirable and should be avoided.E-3 Revision 2 08/01/92 V-2515 and V-2516 Letdown Line Isolation Valves Closing these valves during operation isolates..the letdown line from the RCS and would result in undesirable pressurizer level transients with the potential for a plant trip.If a valve failed to reopen, then an unexpected plant shutdown would be required.V-2598 Charging Line Isolation Valve Closing this valve during operation isolates the charging pumps from the RCS and would result in undesirable pressurizer level transients with the potential for a plant trip and potential damage to the charging pumps.If the valve failed to'reopen, then an unexpected plant shutdown would be required.Safet In ection Residual Heat Removal 2998-G-078 Sh 130 V-3106 and V-3107 LPSI Pump Discharge Check Valves During normal plant operation, the LPSI Pumps cannot develop sufficient discharge pressure to pump through these valves to the RCS and exercise them in the open direction.
The only other test flow path available is through the shutdown cooling line recirculating to the RWT.During this test there would be significant backpressure on both LPSI minimum flow discharge lines such that the there may not be adequate cooling to the non-test LPSI Pump should accident response be required.This could result in both LPSI Pumps being.effectively inoperable.
.SW tl rr sea 0 Revision 2 08/01/92 Safet In'ection Residual Heat Removal 2998-G-078 Sh 131 V-3114, V-3124, V-3134, and V-3144 LPSI Cold Leg Injection Check Valves During normal plant operation, the LPSI Pumps cannot develop sufficient discharge--pressure to pump through these valves to the RCS and exercise them in the open direction.
V-3480, 3481, 3651, and 3652 Shutdown Cooling RCS Isolation Valves These valves are provided with electrical interlocks that prevent opening whenever Reactor Coolant System pressure exceeds 275 psia.This precludes exercising these valves in any other plant condition than cold shutdown.V-3545, V-3664, and V-3665 Shutdown Cooling Isolation and Cross Connect Valves The motor-operated valves V-3664 and V-3665 are isolation valves for shutdown cooling,and V-3545 is the cross connect valve between the two trains of shutdown cooling.These valves are normally locked closed.A failure of these valves in any other position could jeopardize the integrity of the Low Pressure Safety Injection System.Safet In'ection Residual Heat Removal 2998-G-078 Sh 132 SE-03-1A thru 1D SI Tank Drain Valves Stroke testing these valves could allow the associated SI Tank to drop below its Technical Specification in tank pressure and/or level.Failure in this mode would render the SI Tank inoperable and require a plant shutdown.V-3611, V-3621, V-3631, and V-3641 SI Tank Fill Valves Stroke testing these valves could allow the associated SI Tank to drop below its Technical Specification in tank pressure and/or level.Failure in this mode would render the SI Tank inoperable and require a plant shutdown.E-5
~t U+o Revision 2 08/01/92 V-3614, V-3624, V-3634, and V-3644 SI Tank Discharge Isolation Valves Stroke testing these valves in the closed direction during normal operation is not possible.The valves are normally locked open with their breaker opened.Also they are interlocked to open when RCS pressure exceeds 500 psia.Therefore, the valves cannot be cycled except during cold shutdowns when RCS pressure is (500 psia.V-3733 thru V-3740 SI Tank Vent Valves Opening any of these valves during normal plant operation with the SI Tanks pressurized is undesirable since if a valve were to fail to re-close the result would be depressurization of the, affected SI Tank and-pressurization of the containment building with the potential for safety system actuation.
Main Steam 2998-G-079 Sh 1 HCV-08-1 AGB Main Steam Isolation Valves During plant operation at power, full closure of either of these valves is not practical as it would require isolating a steam generator which would result in a severe transient on.the'steam and reactor systems and a possible plant trip.V-8130 and V-8163 Steam-Driven AFW Pump Steam Supply Check Valves Verifying closure of these valves at normal operating pressures would required isolating the associated steam generator from the steam supply lines and venting the piping between the closed isolation valve and the check valve.It is considered to be imprudent to isolate the steam supply during operation and, in addition, it is undesirable to subject plant personnel to the hazards associated with venting the steam line at these operating conditions.
Full stroke operation of these valves requires operating 2C AFW Pump and full accident flow rate which is not practical during plant operation at power.(See Relief Request PR-4)E-6 h V V Revision 2 08/01/92 Feedwater 2998-G-080 Sh 2 HCV-09-1 A&B and HCV-09-2 A&B Main Feedwater Isolation Valves During plant operation at power, closure of any of these valves is not practical as it would require isolating a steam generator which would result in a severe transient on the steam and reactor systems and a plant trip.V-9107, 9123, and 9139 Auxiliary Feedwater Pump Discharge Check Valves Full-stroke exercising of these valves would require operation of the related auxiliary feedwater pump and injection of cold water (85 deg-F)into the hot (450 deg-F)feedwater supply piping.This, in turn, would result in unacceptable thermal stress on the feedwater system piping components.
V-9119, 9135, 9151, and 9157 Auxiliary Feedwater Supply Check Valves Full-stroke exercising of these valves would require operation of a related auxiliary feedwater pump and injection of cold water (85 deg-F)into the hot (450 deg-F)feedwater supply piping.This,.in turn, would result in unacceptable thermal stress on the feedwater system piping components.
Com onent Coolin S stem 2998-G-083 HCV-14-1,2(6
&7 RCP Cooling Water Supply/Return Isolation Valves These valves are required to be open to ensure continued cooling of reactor coolant pump auxiliary components and the control rod drives.Closing any of these valves during plant operation would result in severe RCP and CRD damage leading to plant operation in a potentially unsafe mode and a subsequent plant shutdown.E-7 Pl I T Revision 2 08/01/92 HCV-14-3 A&B Shutdown Heat Exchanger Return Valves Testing either of these.valves during plant operation, would result in an unbalanced flow condition in the affected CCW train and decreased flow to essential equipment.
This could result in component damage or an undesirable plant transient.
Service Air 2998-G-085 Sh 1 V-181270 Service Air Containment Isolation Check Valve During normal power operation, the service air supply to the containment building is isolated.The containment isolation valves, HCV-18-2, is a normally shut valve used to isolate the service air system inside containment.
Testing a check valve in an isolated section.of a system is not warranted.
The check valve will be back flow tested during cold shutdowns when the section of-the service air system inside the containment building is in service.Instrument Air 2998-G-085 Sh 2 HCV-18-1 Primary Containment Instrument Air Supply Closing this valve isolates operating air to critical components in the containment building including the pressurizer spray valves and CVCS letdown isolation valves and could cause severe plant transients and a plant trip.Failure in the closed position would cause a plant shutdown.E-8 phd V 4 4=I II ya Revision 2 08/01/92 V-18279 and V-18283 Maintenance Hatch Door Seal Accumulator Air Supply Performing the closed test on these valves requires entry into the Shield Building and isolating.the air,.supply.to,the vacuum relief valves.During operation this is a neutron radiation area.Due to ALARA considerations, these check valves will only be tested during cold shutdowns."Heatin Air Conditionin And Ventilation
&Air Conditionin 2998-G-878 FCV-25-1 thru FCV-25-6 Primary Containment Purge and Vent Valves These valves are required to remain closed at all times when the plant is operating in Modes 1.through 4, thus they arenot required to operate (close)during operational periods.Due to the large size of these valves and the potential for damage as a result of frequent cycling, it is not prudent to operate them more than is absolutely necessary.
V-25-20 and V-25-21 Containment Vacuum Breakers These valves can only be exercised manually requiring direct access to each valve.,Since these valves are located within the containment building, access is limited and not routinely practical.
, E-9
REACTOR CONTAINMENT BUILDING INTEGRATED LEAKAGE RATE TEST FINAL REP RT ST L.UCIE UNIT NO 2.NUCLEAR POWER PLANT FT PI.ERCE, EL DOCKET NUMBER 50-389 9209250218 1
I I I I I I I ST.LUCIE PLANT UNIT NO.2 NUCLEAR POWER PLANT FT.PIERCE, FLORIDA DOCKET NO.50-389 REACTOR CONTAINMENT BUILDING INTEGRATED LEAKAGE RATE TEST Prepared By: Duane Mumper ILRT Engi er Reviewed By: Jim C nor Test&Code Lead Engineer Approved by: D.H.West Technical Supervisor Date of Test Completion:
June 17, 1992
I.INTRODUCTION AND
SUMMARY
IX.TEST DISCUSSION A.Description of the Containment B.Description of ILRT Instrumentation 1.Temperature Instrumentation 2.Humidity Xnstrumentation 3.Pressure Instrumentation 4.Flow Instrumentation 5.Instrument Selection Guide (ISG)Containment Pressurization Equipment Description of the Computer Program Description of the Testing Sequence Ca~~~lculat son 2'2 4 6 7 8 8 9 9 10 11 III.ANALYSIS AND XNTERPRETATION A.Instrumentation System Performance B.Temperature Stabilization Phase C.Leakage Survey Phase D.Integrated Leakage Rate Phase E.Verification Controlled Leakage Rate~~~~Phase~~~~~~~~~~~~16 16 18 19 20 21 SECTION A.B.C.D.E.F.IV FIGURES RTD Locations and Volumes RHD Locations and Volumes Flow Diagram for Pressure Sensing and Leakage Data Collection Output, and Storage Flow Diagram for Pressurization System St.Lucie Unit 2 ILRT Sequence~~~~~~~~~~~~~~~Controlled
~~~~~~~~~~~~~~~~~~~~22 23 24 25 26 27 28 SECTION V APPENDICES APPENDIX A.TABULATION OF nAS FOUNDn AND i<AS LEFTn ILRT RESULTS~~~~~~~~~~~~~~~~~~~~~A Correction of ILRT Result for"AS-FOUND" Case B.Correction of ILRT Results for"AS-LEFT" Case Appendix B: ILRT Raw Data and Graphical Interpretations
~~~~~~~~~~~~~~~~~~~~~~~~Stabilization Data Figure G Stabilization Period Air Mass&Vapor Pressure Figure H Stabilization Period Average Temperature
&Vapor Pressure Figure I Historical vs Latest ILRT Vapor Pressure Trends Figure J 4RH by Elevation During Stabilization Figure K Temperature By Elevation During Stabilization ILRT DATA~~~~~~~~~~~~~~~~~~~~Figure L ILRT Containment Absolute Pressure Figure M ILRT Weighted Average Temperature Figure N ILRT Weighted Average Vapor Pressure 29 31 31 32 33 34 64 65 66 67 68 69 86 87 88 Figure 0 ILRT Calculated Air Mass Figure P ILRT Bn-Top Rates Relative To L imits~~~~~~~~~~~~~~~~Figure Q Local Sensor Deviations Affects Air Mass Calculation Figure R ILRT CLRT Air Mass and Fitted Leakage R ates CLRT DATA..........~.~~Figure S CLRT Containment Absolute Pressure Figure T CLRT Weighted Vapor Pressure'igure U CLRT Weighted Average Temperature Figure V CLRT Calculated Air Mass Figure W CLRT Bn-Top Rates Relative to Limits APPENDIX C LOCAL LEAKAGE RATE TESTING CONDUCTED SINCE 1989 89 90 92 93 103 104 105 106 107 108 VI.LOCAL LEAKAGE RATE PROBLEMS SINCE LAST ILRT......119 A.Main Purge Exhaust (FCV-25-5)
...........119 B.Personnel Air Lock....'............120 I I I I.INTRODUCTION AND
SUMMARY
A periodic Type"A" Integrated Leakage Rate Test (ILRT)was successfully conducted on the primary containment structure of the Florida Power&Light Company St.Lucie Plant Unit No.2 Pressurized-Water Reactor.This test was performed at full pressure in accordance with the facility Technical Specifications.
This ILRT test was performed using the"Absolute Method" of testing in accordance with the Code of Federal Regulations, Title 10, Part 50=Appendix J,"Primary Reactor Containment Leakage Testing for Water-Cooled Power Reactors," in accordance with ANSI N45.4-1972, American National Standard,"Leakage Rate Testing of Containment Structures for Nuclear Reactors," and the methodology and calculational requirement of Topical Report BN-TOP-1, Revision 1,"Testing Criteria for Integrated Leakage Rate Testing of Primary Containment Structures for Nuclear Power Plants." The ILRT was performed at a pressure in excess of the calculated peak containment internal pressure related to the design basis accident as specified in the Final Safety Analysis Report (FSAR)and the Technical Specifications.
This report describes and presents the results of the periodic Type"A" leakage rate testing, including the supplemental test method utilized for verification.
In addition, Florida Power&Light Company performs types"B" and"C" testing in accordance with the requirements of 10CFR50, Appendix J, and the Technical Specifications.
The results of types"B" and"C" testing performed since the last ILRT are provided in this report.
I The resulting reported"as-found" Type"A" containment leakage at 42.3 psig is 0.052 percent of the contained mass per day.This value includes the difference between the as-found and as-left minimum pathway Types"B" and"C" local leakage measurements as required by the NRC I6E Information Notice 85-71.The resulting reported"as-left" Type"A" containment leakage at 42.3 psig is 0.052 percent of the contained mass per day.The acceptance criteria for this test as contained in the facility Technical Specifications is that leakage cannot exceed 0.375 percent of the contained air mass per day for either the"as-found" or"as-left" case.II.TEST DISCUSSION A.Description of the Containment The containment.
vessel completely encloses the entire reactor and reactor coolant system to ensure no leakage of radioactive
'materials to the, environment in the unlikely event of a loss of coolant accident.The containment system design incorporates a free-standing containment vessel surrounded by a low-leakage concrete shield building.A four-foot annular space is provided between the outer wall of the containment vessel and the inner wall of the shield building to allow filtration of containment vessel leakage during I I I accident conditions to minimize off-site doses.The free-standing containment vessel is a two-inch thick r'ight circular cylinder with a one-inch thick hemispherical dome and two-inch thick ellipsoidal bottom.The overall vessel dimensions are 140-foot diameter by 232-foot high.The vessel wall thickness is increased to a minimum of four inches adjacent to all penetrations and openings.The vessel is fabricated of ASME-SA 516 Grade 70 fully kilned pressure vessel quality steel plate.The net free volume of the containment vessel is 2.5 x 10~cubic feet.The containment vessel structure includes one personnel airlock, one emergency escape lock, one fuel transfer tube, one equipment maintenance hatch and one seal-welded construction hatch.All process piping and electrical penetrations are welded directly to the containment vessel nozzles with the exception of the main steam, main feedwater, and fuel transfer tube penetrations.
These penetrations are provided with testable multiple ply expansion bellows to allow for thermal growth or building differential motion.The containment vessel is designed and constructed in accordance with the requirements for Class MC vessels contained in Section IZZ of the ASME Code.The containment vessel is code stamped for a design internal containment pressure of 44 psig at a temperature of 264'F.The containment vessel and all penetrations I I I I I I I are designed to limit leakage to less than 0.5 percent by weight of the contained air per day at the above design conditions.
The calculated peak accident pressure for the design basis accident for the St.Lucie Plant No.2 is 41.8 psig, in accordance with Technical Specification 3.6.1.2.a.1 B.Description of ILRT Instrumentation The containment system was equipped with instrumentation to permit leakage rate determination by the"absolute method." Utilizing this method, the actual mass of dry air within the containment is calculated.
The leakage rate becomes the time rate of change of this, value.The mass of air (Q)is calculated according to the Perfect Gas Law as follows: where: P-Containment Total Absolute Pressure Pv-Containment Water Vapor Pressure (Average)V-Containment Net Free Volume R-Gas Constant T-Containment Absolute Temperature (Average)The primary measurement variables required are containment absolute pressure, containment relative humidity, and containment temperature as a function of time.During the supplementary verification test,.containment bleed-off flow is also recorded.
Average containment absolute temperature is determined by measuring discrete local temperatures throughout the containment and applying a mass and volume weighted averaging technique.
The volume fraction for each sensor is determined based upon solid geometrical calculations:
vs-=E-T Tx where: T-Containment Absolute Temperature (Average)T>-Local Temperature for Sensor i Vf;-Volume Fraction for Sensor i Average containment water vapor pressure is determined by measuring discrete local relative humidities throughout the containment, converting these to local vapor pressures using local group temperatures and applying a mass and volume weighted averaging technique.
The volume fractions for the relative humidity sensors are determined in the same manner as for the temperature'ensors above.Pv>=SRH>*Psat for T>
where: 4RH;-Relative Humidity for Sensor j Psat for T;-Steam Table Saturation Pressure for local Pv Pv VF)group average temperature near sensor j Calculated local vapor pressure for sensor j Containment Water vapor pressure (Average)Containment Absolute Temperature (Average)Volume Fraction for sensor j Local temperature for sensor j The Instrument Selection Guide or ISG is used to determine the ability of the instrumentation system to measure the leakage rate.The calculated ZSG for this test met all acceptance criteria for all test instrumentation systems.1.Temperature Instrumentation Forty precision Resistance Temperature Detectors (RTDs)were located throughout the containment to allow measurement of the weighted average air temperature.
The location of the temperature detectors in the containment is depicted in Figure A.Each RTD sensor was supplied with a calibrated resistance versus temperature curve accurate to+0.5'F.The sensitivity and repeatability of each RTD sensor is less than+0.01'F.The signal conditioning circuit and readout for the RTD
sensors was a Fluke 2280B data logger operating in a constant current mode.The operating parameters for the RTD constant current card are accurate to+0.16'F and has a resolution of+0.01 oF Each RTD was in situ calibration checked after installation to verify correct operation.
The data logger operating as a total loop with an RTD in the circuit has a repeatability of+0.01'F and a resolution of+0.01'F.2.Humidity Instrumentation Ten Resistance Humidity Detectors (RHDs)were located throughout the containment to allow measurement of the weighted average containment vapor pressure.The location of the RHDs in the containment is depicted in Figure B.The calibrated accuracy of the RHDs is+2.5 percent RH, the repeatability of the RHDs is+0.01 percent RH, and the sensitivity of the RHDs is+0.1 percent The readout device used for the RHDs was a Fluke 2280B data I logger.The repeatability*of this device is+0.01 percent RH while the resolution of the device is+0.01 percent RH.Each RHD was in situ calibration checked after installation to verify correct operation.
3.Pressure Instrumentation Two precision vibrating cylinder element pressure sensors were used to determine containment absolute pressure.The arrangement of tubing connections between the pressure sensors and the containment is shown in Figure C.Either pressure sensor could be used as the primary pressure sensor for leakage rate calculations with the remaining sensor being considered.
as a backup.The calibrated accuracy of the manometers is+0.015 percent of reading.The sensitivity, repeatability, and resolution of the pressure sensors is+0.002 psi.Binary Coded Decimal (BCD)output from both pressure sensors was connected to the Fluke 2280B data logger.4.Flow Instrumentation A variable area float-type rotameter was used to superimpose leakage during the supplementary CLRT.The piping connection between the'otameter and the containment is shown in Figure C.The accuracy, repeatability, and sensitivity for the rotameter in units of SCFM and converted to equivalent leakage values is given below: Peak Pressure Rotameter Accuracy Repeatability sensitivity SCFg+0~20+0.05+0.05 Equivalent Laa~acae+0.0031 4/day+0.0008 4/day+0.0008 4/day
5.Instrument Selection Guide (ISG)Calculation The Instrument Selection Guide is a method of compiling the instrumentation sensitivity and resolution for each process measurement variable used during the ILRT and evaluating the total instrumentation system's ability to detect leakage rates in the range required.The ISG formula is described in American National Standard ANSI/ANS 56.8-1987.
Although the ISG is a very conservative measure of sensitivity, the general industry practice for this test has been to require sensitivity at least four times better than the containment allowable leakage or ISG<0.25La.The calculated ISG for the instrumentation used for this test was 0.0078 percent per day, for'n 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> test.The allowable value for this test is 0.25La or 0.125 percent per day, for an 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> test.The ISG calculation met all recommended criteria and demonstrated the ability of the ILRT instrumentation system to measure containment leakage with a sensitivity exceeding that required by the appropriate industry standards.
C.Containment Pressurization Equipment The equipment used to pressurize the containment is shown in Figure D.The'nine oil-free industrial diesel-driven air compressors had a total nominal capacity of 13,200 SCFM.The compressed air was then routed to water-cooled aftercoolers,
moisture separators, and refrigerant air dryers.This equipment assured that clean and dry air was used to pressurize the containment.
D.Description of the Computer Program The Ebasco ILRT computer program is an interactive program written specifically for fast, easy utilization during all phases of the ILRT and CLRT.The program iq written in a high-level, compiled, structured language and is operated on portable MS-DOS personal computer.The program has been verified and meets all requirements of the Ebasco and Florida Power&Light Quality Assurance Programs.As necessary, data entry and modifications are readily accomplished by the data'cquisition team.In addition to extensive data verification routines, the program calculates, on demand, total time and mass point leak rates as well as the 95 percent Upper Confidence Level for these leakage rate calculations.
Calculations and methodology of the program are derived from American National Standard ANSI N45.4-1972, ANSI/ANS 56.8-1987 and Topical Report BN-TOP-1, Revision 1.Input data may be deleted for a given instrument in the case of a sensor malfunction.
The deletion of a given instrument is performed on all samples in the data base.Weighting factors, if applicable, are then recalculated for the remaining instrument 10 I I I I I I sensors of that type (see section III.A).Data evaluations are enhanced by the flexible display of either sensor variables or various computed values in tabular or graphical form on the computer screen or printer.Data is recorded on magnetic media to prevent loss during the testing.All data is stored on the computer system in use, with retrieval capability to any desired data base throughout the testing.Ancillary portions of the program assist the user in determination of temperature stabilization, determining the ILRT termination criteria, performing ISG calculations, performing in situ instrument loop performance calculations and determination of acceptable superimposed CLRT leakage verification.
Temperature, pressure and humidity data are transmitted from the ILRT instrumentation system to the computer via an RS-232 link at 20 minute intervals.
Computer verification and checking routines supplement data verification by the data acquisition team.Modifications are promptly made when errors are detected.E.Description of the Testing Sequence Preparations to pressurize the containment for the conduct of the ILRT included internal and external inspections of the containment structure; installation and check out of the ILRT 11 instrumentation; Types"B" and"C" Local Leakage Rate Tests;alignment of valves and breakers for test conditions; and the installation and check out of the temporary pressurization facilities.
These preparations were completed on June 15, 1992.I All ILRT in5trumentation was declared operable with performance within manufacturers'olerances, with the exception of TE-20 and TE-38.These were deleted from computer calculations and the volume fractions adjusted accordingly.
Pressure sensor No.1 was selected to be the primary pressure instrument, as it had exhibited better repeatability and stability during the in situ testing.Three penetrations were required to be in service during the ILRT and were not lined up to simulate accident conditions; P-7 (Primary Makeup Water), P-52D (ILRT Pressure Sensing Line), and P-52E (ILRT Controlled Bleed off Line).Primary water to the containment is required for fire protection, and the two ILRT penetrations are used to conduct the test.The minimum pathway leakage for these penetrations, determined during Type"C" local testing, is added to the measured ILRT leakage to account for these penetrations being in service during the test.(P-54 ILRT pressurization line is normally isolated with a blank flange and one valve.During the Test the only isolation is the valve outside containment is shut.As a conservative measure the leakage for this penetration is also used in Appendix A for 12 calculation of the"as-left" condition.)
Pressurization of the containment started at 10:10 hours on June 15,1992.Figure E pictorially depicts the sequence of testing at pressure.The pressurization rate was maintained at 4.4 psi/hr, and a target pressure of 58.48 psia was achieved at 20:00 hours on 6/15/92.This target pressure was 1.98 psi above the minimum test pressure to account for the expected pressure decrease due to temperature stabilization and to allow for some leakage margin during the test sequence.Data acquisition and analysis during the temperature stabilization phase began at 20:00 hours at.20 minute intervals.
During pressurization, Leak Survey Teams found no indication j of any significant leakage on any of the leak chase points The containment temperature stabilization criteria was met at 00:00 hours on June 16,1992, after acquisition of four hours of data.During this period, the temperature and pressure decreases followed predictable trends.Because of high relative humidity readings, and indications of instability in the vapor pressure calculations stabilization was conservatively continued until 15:20 on'/16/92.For more detailed discussion see Analysis and Interpretation Section.The 8.67 hour7.75463e-4 days <br />0.0186 hours <br />1.107804e-4 weeks <br />2.54935e-5 months <br /> period of leakage measurements started at 15:20 hours on June 16,1992, and was successfully terminated at 00:00 I 13 I I I I I I hours on June 17,1992, with acceptable leakage values determined.
The data accumulated displayed the following leakage rates: Simple BN-TOP-1 Leakage Rate=-0.0232 4/day Fitted BN-TOP-1 Leakage Rate=-0.0104 4/day 954 Upper Confidence Level (UCL)=0.0516 4/day The leakage plot had a negative skew after 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.The acceptance criteria for this test is 0.75 La or 0.375 4/day.To verify the results of the ILRT, a verification Controlled Leakage Rate Test (CLRT)was conducted.
Using the variable area full-pressure rotameter, a superimposed flow of 17.79 SCFM was added to the leakage already present in the containment.
This superimposed flow is equivalent to leakage of 0.264 percent per day.Aone-hour stabilization period was allowed to lapse after addition of this leakage in accordance with the requirements of Topical Report BN-TOP-1.Data accumulation for the CLRT was started at 01:00 hours on June 17,1992 and the CLRT was conducted for a 4.4 hour4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> period.The measured CLRT leakage rates for this period were: Simple BN-TOP-1 Leakage Rate=0.2524 4/day Fitted BN-TOP-1 Leakage Rate=0.2529 4/day Target CLRT Leakage Rate=0.253 4/day 14 I I I I I I The target CLRT leakage for this test was 0.253+0.125 percent per day, or within the criteria as measured.As shown in figure g the calculated air mass and fitted leakage rate quickly changed when the controlled leak rate was introduced.
The ILRT and CLRT were declared successful at 05:30 hours on June 17,1992.At 05:31 hours on June 17,1992, depressurization of the containment was initiated at a rate of 6 psi/hr.Containment entry for post-test inspection purposes occurred when the containment pressure was approximately 1.6 psig at 14:00 hours on June 17,1992.The post-test inspection detected no anomalies or damage other than several broken lighting fixture covers.Particular attention was paid for evidence of any leakage that may have contributed to high humidity levels, none was found.Corrections were made to the measured ILRT leakage to account for the three penetrations which were in service during the ILRT and to account for the difference between the as-found and as-left minimum pathway local leakage values as required by NRC I&E Information Notice 85-71.954 Upper Confidence Level (UCL)during ILRT=5.16 x10~4/day Corrections for Local Leakage Measurements
=8.5 x 10~~~a Total Reported Containment UCL=5.25 x 10~4/day This value satisfies the acceptance criteria for the test of being less than 0.375 percent per day.15 I I I I I I III.ANALYSIS AND INTERPRETATION A.Instrumentation System Performance All of the 38 temperature detectors inservice at the start of the test performed as expected with no anomalous behavior detected by the Ebasco ILRT computer program error checking routines during the conduct of the test.This computer program also determines the in-situ temperature loop repeatability which consists of process measurement variations as well as sensor noise.The average in situ loop repeatability for the 38 operating temperature sensors was 0.0104'F.This performance compares well with the vendor-claimed temperature sensor loop repeatability, excluding process variations, as given in Section II.B.1.However several RTD's showed a significantly higher calculated repeatability than the group as a whole.A detailed review of the data gathered reveals that between test samples 85 and 100 there were some oscillations in RHD-6, RHD-7 and TE-13, TE-21, TE-22, TE-27.These deviations are believed to indicate a density turnover and are not believed to indicate any sensor failure.However this data also shows the sensitivity of leakage calculations when small leakage rates are being measured.This does not necessarily indicate a sensor malfunction, but may indicate local variations in process as well, see figure P.Ten relative humidity sensors were installed in the 16 I I I I I I containment for the ILRT.All ten channels for humidity operated as expected with no anomalous behavior detected by the ILRT computer program error checking routines, except as noted above.The average in situ loop repeatability for the relative humidity sensors was 0.07 percent RH.At the start of the stabilization period group average humidity ranged from 444 at the lowest elevation to 644 at the upper elevation.
Because of the high humidity levels experienced during the test the humidity group at the top elevation reached saturation levels as the containment atmospheric temperatures equalized with the structure temperatures.
Also because of the stratification of humidity by elevation; mixing and stabilization were slow to occur.Sensor response was monitored during the test, phase and depressurization phase.All sensor trends followed group trends and expected response based on pressure and temperature changes.Two pressure sensors were installed for the ILRT, with one utilized for testing and one considered as a spare.Prior to containment pressurization, computer analysis demonstrated that pressure sensor 1 was more stable over an eight-hour period than the other sensor.During the ILRT, the in-situ pressure loop repeatability for both sensors was 0.0002 psi.This performance compares well with the vendor-claimed pressure sensor loop repeatability, excluding process variations, given in Section II.B.3.The variable area rotameter performed as expected with no 17 I I I I I I I evidence of unstable reading, float sticking, or moisture in the float.tube.In summary, all of the ILRT test instrumentation performed in an adequate manner to allow determination of containment leakage rates to the sensitivity required, as verified by the controlled leakage rate test.B.Temperature Stabilization Phase Prior to pressurization of the containment, the atmospheric conditions were very unstable.In-situ humidity checks varied from 59%to 75%, depending on the day they were performed.
For several days prior to the ILRT the site had experienced severe afternoon thunder storms with high temperatures in the 90's.Prior to pressurization the containment was purged with two of the pressurization compressors and dryers for several hours in an attempt to reduce average humidity levels.Average humidity was reduced from approximately 754 to 604.During pressurization, the cool and dry air introduced at the bottom of containment acts as a"piston" and compresses and heats the air at the top of containment.
At the end of pressurization, the average temperature was 102.9'F with a maximum spread of temperature from the highest reading sensor to lowest reading sensor of 24.4'F.The results of the temperature stabilization phase are presented in Appendix B.l.The acceptance criteria given in Topical Report 18 BN-TOP-1, Revision 1, are described in Note 2 in that appendix.However as seen in figures F, G, and H vapor pressure did not stabilize as quickly as temperature.
This shows that modeling the containment with a discrete number of sensors can overstate the effects of the vapor pressure correction to the Ideal Gas Law, during periods of high unstable humidity.The data presented shows that a smooth and predictable temperature stabilization occurred.At the end of stabilization, the average temperature was 91.1'F with a maximum spread of temperature from the highest reading sensor to the lowest reading sensor of 7.4'F.This demonstrates that the heat sinks of concrete and steel in the containment were returning the containment atmosphere to a stable temperature condition.
C.Leakage Survey Phase Leakage survey teams found no indications of any significant leaks during the test at any of the leak chase detection points.Since the total type B&C minimum path leakage was 1.17 SCFM (1.75X10~4/day)this result was not unexpected.
Leakage rate measurements on the containment were started after the temperature stabilization phase using the total time leakage rate methods of Topical Report BN-TOP-1, Revision 1.As an additional diagnostic tool, mass point leakage rate measurements,-as described in ANSI/ANS 56.8-1987, were conducted in parallel.The mass point leakage calculations are not sensitive to the starting point of the 19 I
test and will detect changes in containment leakage more rapidly than the total time method.D.Integrated Leakage Rate Phase Leakage measurements were started at.15:20 hours on June 16, 1992.The total time BN-TOP-1 results for 8.67 hours7.75463e-4 days <br />0.0186 hours <br />1.107804e-4 weeks <br />2.54935e-5 months <br /> of.leakage measurements are presented in Appendix B.3.A summary of the measured leakage after eight hours is: BN-TOP-1 Total Time Simple Leakage Rate Fitted Leakage Rate Upper Confidence Level Type B&C Minimum Path-0.0232 4/day-0.0104 4/day 0.0516 4/day 0.0175 4/day The higher Upper Confidence Level of the BN-,TOP-1 measurements is due to the nature of performing regression analysis on simple leakage rates instead of regression analysis on masses and the more conservative statistics utilized by BN-TOP-1..A conservative calculation of the minimum path leakage based on the Type"B"&"C" test'program is 0.0175 4wt/day.This small value combined with the instabilities described in section III.B help explain the very small calculated leakage rates.If the temperature sensor with the largest sample to sample deviation is deleted the new calculated leakage rates are: fitted leakage rate 0.0193, and UCL of 0.0810.20
As all acceptance criteria for a Reduced Duration BN-TOP-1 ILRT were met after 8.67 hours7.75463e-4 days <br />0.0186 hours <br />1.107804e-4 weeks <br />2.54935e-5 months <br /> as presented in Appendix B.2, the lLRT was declared acceptable.
Appendix A presents the corrections to the measured ZLRT leakage rates for local leakage rate measurements for both the"as-found" and"as-left" cases.E.Verification Controlled Leakage Rate Phase Subsequent to the acceptance of the ILRT results, a superimposed leakage equivalent to 0.264 percent per day was added to the existing containment leakage using the variable area rotameter.
A one-hour stabilization period was allowed to lapse ,after addition of this leakage in accordance with the requirements of Topical Report BN-TOP-1.Leakage measurements were initiated to verify the results of the ZLRT.The minimum duration for the Controlled Leakage Rate Phase was determined to be 4.33 hours3.819444e-4 days <br />0.00917 hours <br />5.456349e-5 weeks <br />1.25565e-5 months <br /> in accordance with Topical'eport BN-TOP-l.As presented in Appendix B.3, the leakage measurements met the acceptance criteria for the verification phase.BN-TOP-1 Total Time Simple Leakage Rate Fitted Leakage Rate 0.252 4/day 0.253 4/day 21
SECTION IV FIGURES 22 I I RTD LOCATIONS AND VOLUMES 3 RTD'sel.194 VOLUME 242,055 CU FT.9 RTD'Sel.171'OLUME 453,235 CU FT 10 RTD'Sel.130'OLUME 669,627 CU FT'l0 RTD'Sel.84'OLUME 600,926 CU FT 8 RTD'SEL.40'OLUME 534,157 CU FT Figure A I I I I I I I I RHP LOCATIONS AND VOLUMES 3 RHD'Sel 171'OLUME 1,049,347 CU FT 4 RHD'Sel 84'OLUME 900,640 CU FT 3 RHD'Sel 40'OLUME 550,0'l3 CU FT Figure 8 I I I I I I FLOW DIAGRAM ILRT PRESSURE SENSING Bc CONTROLLED LEAKAGE INSTRUMENTS preclsfon vtbrotfng cyffn der presswe sensor INSIDE CONTAINMEQ OUTSIDE CONTAINMENT precfsfon vfbratfng monitored vent CO DE/SATE PO-fan%--~"~B~L5p CO DE SATE P L YARIABL AREA ROTA METER ILRT INSTRUMENTATION DIAGRAM DATA COLLECTION, OUTPUT, AND STORAGE RTD Volumetrics Pressure Sensor 40 Fluke Data Logger IBM PC EBASCO Software Humidity Detector 10 Hum etc p Data Col}ection
- Data Analysis Diskette IBM PC EBASCO*II Software Diskette I I I I I I I ILRT PRESSURIZATION Bc l3EPRESSURIZING SYSTEM TO ATMOSPHERE I i TO UNIT NO.1 ILRT PENEIRATION dl Ip pot I l Pl I PI outside containment I inside containment I I I I I I I 8" blind flange removed for ilrt P54 5 refrigerant dryers wig moisture seperators Diesel driven industrial 100Fo oil free ir corn ress 0 p ors/(13.200 aim total)/(9 COITlpl'BSSWS) l-a gc-~a/c~a/d St.Lucie Unit 2 ILRT Sequence A B C D E 60 55 50 6)L.N U)0 CL tQ ca C C I 0 C 0 O 40 30 20 A.Pressurization B.ContainrrIent Stab C., Integrated Leakag D.Verification Test Controlled Leakag E.Depressurizaiion
.4.psi/lization Rate Th r erio st (~RT)Rate T 6 psi/st (I LRT}10 20 Hours into Test 40 60 I I I I I I I I I I I SECTION V APPENDICES 29
APPENDIX A TABULATION OF"AS-FOUI'6) 326)"AS-LEFT" ILRT RESULTS 30 I I I I I I APPENDIX A: TABULATION OF"AS-FOUND" AND"AS-LEFT" ILRT RESULTS A Correction of ILRT Result for"AS-FOUND" Case In accordance with NRC I&E Information Notice 85-71, additions are required to the ILRT results due to repairs and/or adjustments made due to Local Leakage rate testing during an outage in which an ILRT is conducted.
The corrections include only repairs or adjustments made to containment leakage boundaries which were made prior to the ILRT.These corrections are the difference between the pre-repair and post-repair leakages calculated in the minimum pathway case and corrected for uncertainties in the measurements.
During the 1992 refueling outage, three such corrections are necessary.
Penetration Total Minimum Pathwa Re ai Uncertaint ILRT Total P-28A SIT Sample P-50 Spare Personnel Airlock 40 sccm 55 sccm 20,000 sccm 1'9 1'9 347 41.79 56.79 20,347 The total local minimum pathway leakage plus uncertainty must be added for the penetrations which are in use during the ILRT and whose containment Penetratio isolation valves are Total Minimum Pathwa Leaka e Unce tai t ILRT Total not tested during the ILRT: P-52D ILRT Test P-52E ILRT Test P-7 Primary Water P-54 ILRT Test 100 sccm 80 sccm 400 sccm 900 sccm 1.79 1.79 12.8 109 101.79 81.79 412.8 1009 31 I I I I I The total"as-found" correction can be found adding the above ILRT to both corrections.
Correction of ILRT results for"as-found" or Measured ILRT leakage at a 954 UCL Reported"as-found" ILRT results Acceptance Criteria (75%La)case 22,051 sccm 1.167 x 10~4/day+5.16 x10 4/day 5.172 x10~0/day 0.375 4/day B.Correction of ILRT Results for"AS-LEFT" Case The only correction for the"as-left" ILRT case involves the penetrations which were in use during the test, P-52D, P52E, P-54, and P-7.From the above section, the ILRT"as-left" correction can be determined.(Note: A conservative simplification was made by not performing a root-mean-scpxare summation of the local uncertainties.)
Correction of ILRT results for"as-left" Measured ILRT Leakage at a 95 4 UCL Reported"as-left" ILRT results Acceptance Criteria (754 La)case 1605.4 sccm or 8.49~4/day+5.16x 10'/day 5.25x10'/day 0.375 4/day 32 I I I I Appendix B: ILRT Raw Data and Graphical Interpretations 33 I I I Sample Number TEST TIME Stabilization Data RTD 1 RTD 2 DEG F DEG F RTD 3 DEG F RTD 4 DEG F 31 32 33 34 35 36 37 38 39 40 41 42 43 44 45 46 47 48 49 50 51 52 53 54 55 56 57 58 59 60 61 62 63 64 65: 66 67 68 69 70 71 72 73 74 75 76 77 78 9~817 10.15 10.483 10.817 11.150 11.483 11.817 12.150 12.483 12.817 13.150 13.483 13'17 14.150 14.483 14'17 15.150 15.483 15.817 16.150 16.483 16 817 17.150 17.483 17'17 18.150"18.483 18.817 19.150 19.483 19'17 20'50 20.483 20'17 21.150 21.483 21.817 22.150 22.483 22'17 23.150 23.483 23'17 24.150 24.483.24.817 25.150 25.483 89.344 88.093 87.891 87.750 87.653 87.557 87.483 87.429 87.387 87.344 87.310 87.290 87.257 87.232 87.203 87.178 87.149 87.140 87.106 87.095 87.075 87.053 87'39 87.032 87.010 86'79 86.990 86.967 86.967 86.967 86.956 86.947 86.947 86.925 86.925 86.893 86.893 86.893 86.871 86.878 86.860 86'49 86.828 86.866 86.840 86'28 86.828 86.828 91.791 89.792 89.108 88.830 88.647 88.540 88.423 88.338 88.262 88.209 88.155 88.101 88'70 88;034 87.994 87.958 87.943 87.889 87.867 87.835 87.813 87.793 87.797 87.770 87.748 87'17 87.706 87.685 87.685 87.652 87.643 87.621 87'21 87.609 87'89 87.578 87.567 87.556 87.547 87.531 87.524 87.524 87.502 87.489 87.482 87.460 87.471 87.448 88.971 87.741 87.494 87.409 87.378 87.324 87.270 87.217 87.185 87.143 87.098 87.067 87.044 87.019 86.993 86.966 86.939 86.928 86.894 86.885 86.874 86'63 86'4@86.820 86.798 86.798 86.778 86.778 86.766 86.755 86.746 86.735 86.724 86.724 86.713 86.701 86'92 86.681 86'81 86'77 86'48 86.659 86.648 86'45 86.627 86.627 86.639 86.616 88.296 87.239 87.013 86.896 86.831 86.777 86.724 86.692 86.639 86.596 86.565 86.520 86.500 86.484 86.446 86.430 86.403 86.381 86.361 86.350 86.327 86.318 86.314 86.285 86.274 86.265 86.253 86.253 86.231 86.220 86'11 86.200 86.200 86.188 86.168 86.157 86.157 86.157 86.146 86'41 86.135 86.124 86.115 86.110 86'03 86.092 86.092 86.081 34 I I I I I I'I I I I I Sample Number TEST TIME Stabilization Data RTD 1 RTD 2 DEG F DEG F RTD 3 DEG F RTD 4 DEG F 79 80 81 82 83 84 85 86 87 88 25.817 26.150 26.483 26'17 27.150 27.483 27'17 28.150 28.483 28.817 86'17 86.806 86.806 86.797 86.786 86.801 86.763 86.786 86.752 86.763 87.439 87.428 87.428 87.417 87.406 87.413 87.397 87.386 87.375 87.375 86.616 86'05 86.596 86.596 86.605 86.601 86.585 86.596 86.596 86.596 86.081 86.070 86.070 86.070 86.061 86.068 86.050 86.050 86.050 86.050 35
Sample Number TEST TIME Stabilization Data RTD 5 RTD 6 RTD 7 DEG F DEG F-DEG F RTD 8 DEG F 31 32 33 34 35 36 37 38 39 40 41 42 43 44 45 46 47 48 49 50 51 52 53 54 55 56 57 58 59 60 61 62 63 64 65 66 67 68 69 70 71 72 73 74 75 76 77 78 9.817 10.150 10.483 10.817 11.150 11.483 11.817 12.150 12.483 12'17 13.150 13.483 13.817 14.150 14.483 14.817 15.150 15.483 15'17 16.150 16.483 16'17 17.150 17.483 17.817 18.150 18.483 18.817 19'50 19..483 19.817 20'50 20.483 20.817 21.150 21.483 21.817 22.150 22.483 22.817 23.150 23.483 23.817 24.150 24.483 24.817 25.150 25.483 88.001 87.061 86.825 86.729 86.610 86.536 86.503 86.482 86.440 86.417 86.386 86.364 86.343 86.328 86'90 86.285 86'67 86.236 86.225 86.225 86.202 86.193 86.177 86.160 86'48 86.139 86'28 86.117 86.106 86.097 86.097 86.086 86.074 86.074 86.063 86.052 86.043 86.032 86.043 86.027 86'09 86.020 85.998 85.996 85.989 85.989 85.978 85.967 88.815 87.991 87.733 87.648 87.583 87.509 87.433 87.370 87.316 87.262 87.219 87'75 87.143 87.118 87.069 87.042 87.004 86'73 86.950 86.928 86.896 86.876 86.860 86.831 86.811 86.789 86.769 86.757 86.735 86.726 86.703 86.692 86'81 86.672 86.661 86.650 86.638 86.627 86.618 86.614 86.607 86.596 86.596 86.582 86.576 86.564 86'53 86.542 89.150 88.188 87.972 87.856 87.759 87.672 87.587 87.533 87.479 87.425 87.394 87.340 87.308 87.273 87.223 87.185 87.158 87.125 87.104 87.073 87.051 87.028 87.026 86.997 86.974 86.965 86.943 86.932 86.923 86.912 86.889 86.878 86.869 86.858 86.835 86.826 86.815 86.804 86.793.86.788 86.773 86.773 86.761 86.757 86.739 86.728 86.728 86.719 88.280 87.187 86.985 86.888 86.823 86'69 86.727 86.693 86.650 86'08 86.588 86.543 86.511 86.496 86.469 86.453 86.415 86.404 86.383 86.361 86.350 86.330 86'36 86.307 86.287 86.276 86.265 86.253 86.242 86.222 86'11 86.199 86.191 86~179 86.168 86,168 86'57 86.146 86.137 86.132 86.125 86.114 86.103 86.110 86.094 86'094 86.083 86.072 36 Sample Number TEST TIME Stabilization Data RTD 5 RTD 6 RTD 7'DEG F DEG F DEG F RTD 8 DEG F 79 80 81 82 83 84 85 86 87 88 25~817 26.150 26.483 26.817 27.150 27.483 27'17 28.150 28.483 28.817 85.978 85.955 85.955 85.947 85.947 85.942 85.935 85.924 85.924 85.924 86.542 86.531 86.531 86.522 86.511 86.517 86.499 86.499 86.488 86.499 86.708 86.696 86.685 86.676 86.676 86.672 86.654 86.654 86.643 86.643 86.072 86.060 86.049 86.049 86.040 86.047 86.040 86.029 86.029 86.018 37 I
Sample Number TEST TIME Stabilization Data RTD 9 RTD 10 RTD 11 DEG F DEG F DEG F RTD 12 DEG F 31 32 33 34 35 36.37 38 39 40 41 42 43 44 45 46 47 48 49 50 51 52 53 54 55 56 57 58 59 60 61 62 63 64'5 66 67 68 69 70 71 72 73 74 75 76 77 78 9.817 10~150 10.483 10.817 11.150 11.483 11.817 12.150 12.483 12'17 13.150 13.483 13'17 14.150 14'83 14'17 15.150 15.483 15'17 16'50 16.483 16.817 17.150 17.483 17'17 18.150 18.483 18.817 19'50 19.483 19.817 20'50 20.483 20'17 21.150 21.483 21.817 22.150 22.483 22'17 23.150 23.483 23'17 24.150 24.483 24.817 25.150 25.483 107.34 105.33 103.91 103.09 102.51 102.08 101.70 101.38 101.08 100.89 100.63 100.'46 100'1 100.02 99.749 99.520 99.255 99.009 98.796 98.558 98.302 98.107 97.878 97.690 97.486 97.293 97.120 96.950 96.766 96.596 96.446 96.295 96'23 95.984 95.845 95.695 95.576 95.426 95.309 95.208 95.074 94.966 94.847 94.746 94.623 94.527 94 419 94.312 105.85 103.61 102'5 101.55 100.92 100.49 100.07 99.696 99.318 98.986 98'07 98.448 98.221 98.003 97.781 97.574 97.363 97.170 96.985 96.803 96.630 96'59 96.316 96.147 96.019 95.869 95.729 95.579 95.448 95.309 95.201 95.085 94.954 94.858 94.761 94.653 94.546 94.440 94.332 94.242 94.139 94.009 93.912 93.834 93.719 93.622 93.537 93.429 107.57 105.41 103.80 102.94 102'0 102.03 101'9 101.44 101'9 100.95 100'3 100.51 100.25 99.980 99.695 99.424 99'49 98.902 98.656 98.409 98.183 97.948 97.742 97.520 97.328 97.135 96.952 96.770 96'98 96.439 96.266 96.105 95.955 95.805 95.667 95.539 95.389 95.250 95.132 95.011 94.885 94.767 94'50 94.539 94.424 94'17 94'12 94.104 107.52 105.12 103.62 102.78 102'1 101.90 101.53 101.18 100.88 100.59 100.35 100.13 99.867 99.573 99.276 99.036 98.762 98.546 98'19 98.052 97.859 97.632 97.403 97.181 96.976 96.806 96.613 96.440 96.269 96.076 95.934 95.775 95.613 95.463 95.313 95.216 95.054 94.947 94.796 94.664 94.538 94.410 94.302 94.201 94.078 93.959 93.862 93.777 38 I I I I I I I I Sample Number TES'9 TIME Stabilization Data RTD 9 RTD 10 RTD 11 DEG F DEG F DEG F RTD 12 DEG F 79 80 81 82 83 84 85 86 87 25.817 26.100 26.483 26.817 27.150 27.483 27.817 28.150 28.483 94'15 94.119 94.011 93.915 93.830 93.740 93.626 93.539 93.465 93.333 93.256 93.149 93.075 92.989 92.920 92.828 92.742 92.677 94.008 93.912 93.816 93.708 93.612 93.532 93.429 93.344 93.270 93.681 93.551 93'65 93.358 93.272 93.194 93.099 92.994 92.906 39 I I I I I I I I Stabilization Data Sample Number TEST TIME RTD 13 DEG F RTD 14 DEG F RTD 15 DEG F RTD 16 DEG F 31 32 33 34 35 36 37 38 39 40 41 42 43 44 45 46 47 48 49 50 51 52 53 54 55 56 57 58 59 60 61 62 63 64 65 66 67 68 69 70 71 72 73.74 75 76 77 9.817 10.150 10.483 10.817 11.150 11.483 11.817 12.150 12.483 12'17 13.150 13.483 13'17 14.150 14.483 14.817 15'50 15.483 15.817 16.150 16.483 16'17 17.150 17.483 17'17 18'50 18.483 18'17 19.150 19.483 19'17 20.150 20.483 20.817 21.150 21.483 21'17 ,22.150 22.483 22.817 23.150 23.483 23.817 24.150 24.483 24'17 25.150 107.14 104.86 103.37 102.55 101.96 101.52 101'3 100.82 100.56 100.29 100.07 99.905 99.658 99.460 99.283 99.054 98.790 98.532 98.316 98.103 97.857 97.661 97.433 97.244 97.029 96.868 96.675 96.482 96.321 96.139 95.978 95'18 95.668 95.538 95.379 95.238 95.110 94.982 94.841 94.720 94.628 94.521 94.402 94.281 94.155 94.166 94.144 107.64 105.32 103.74 102.74 102.16 101.70 101.43 101.16 100.90 100.63 100.35 100.07 99.817 99.565 99.257 98.982 98'19 98.503 98.267 98.029.97.793 97.525 97'05 97'40 96.900 96'96 96.482 96.298 96'38 95.988 95.792 95.632 95.448 95.320 95'38 95.008 94.857 94.729 94.599 94.488 94.309 94.169 93.987 93.886 93.803 93.729 93.601 106.96 104.60 103.22 102.24 101.64 101.17 100.80 100.51 100.23 99.947 99.711 99.462 99.238 99.009 98.809 98.623 98'12 98.239 98.046 97.907 97.842 97.661 97.591 97.414 97.264 97.091 96.909 96.748 96.577 96.405 96.254 96.093 95.954 95.792 95.653 95.514 95.375 95.245 95.106 95.005 94.871 94.752 94.635 94.535 94.409 94.301 94.196 106.33 104.80 103.33 102.39 101.70 101.21 100.82 100.49 100.19 99.910 99.643 99.407 99.18 98.972 98.752 98.554 98.354 98.170 98.042 97.977 97.903 97.722 97.578 97.410 97.228 97.055 96.873 96.701 96.539 96.380 96'18 9,6.034 95.906 95.767 95'17 95.478 95.339 95.198 95.070 94.937 94'12 94.704 94.576 94'75 94.361 94.253 94.157 40 I I I I I I I I Sample Number TEST TIME Stabilization Data RTD 13 RTD 14 RTD 15 DEG F DEG F DEG F RTD 16 DEG F 78 79 80 81 82 83 84 85 86 87 88 25.483 25.817 26.150 26.483 26'17 27.150 27.483 27.817 28.150 28.483 28'17 94.059 93.940 93.889 93'12.93.705 93.620 93.541 93.458 93.351 93.254 93.192 93.502 93.374 93.277 93.158 93.053 92.954 92.833 92.752 92.687 92.601 92.451 94.089 93.992 93.884 93.788 93.703 93'04 93.515 93.423 93.338 93.252 93~176 94.049 93.944 93.848 93.771 93.686 93.601 93.520 93.428 93.354 93.247 93.159 41 I I I I I I I I Sample Number TEST TIME Stabilization Data RTD 17 RTD 18 RTD 19 DEG F DEG F DEG F RTD 20 DEG F 31 32 33 34 35 36 37 38 39 40 41 42 43 44 45 46 47 48 49 50 51 52 53 54 55 56 57 58 59 60 61 62 63 64 65 66 67 68 69 70 71 72 73 74 75 76 77 78 9.817 10.150 10.483 10.817 11.150 11.483 11.817 12.150 12.483 12'17 13.150 13.483 13.817 14.150 14.483 14.817 15.150 15.483 15'17 16.150 16.483 16'17 17.150 17'83 17.817 18'50 18.483 18.817 19.150 19.483 19.817 20'50 20.483 20'17 21.150 21.483 21.817 22.150 22.483 22.817 23.150 23.483 23.817 24.150 24.483 24.817 25.150 25.483 107.85 105.55 103.93 102.90 102.41 101.98 101.57 101'7 100.84 100.58 100.31 100.07 99.865 99.590 99.316 99'96 98.841 98.562 98.304 98.056 97.829 97.519 97.332 97.110 96.874 96.658 96.422 96.066 95.904 95.734 95.549 95.387 95.228'5.023 94'15 94.765 94 637 94.506 94.378 94.234 94.108 94.012 93.895 93.749 93.645 93.583 93'63 93.378 107.98 105.65 104.01 103.03 102.44 102.05 101.71 101.43 101.18 100.95 100.74 100.41 100.08 99'15 99.539 99'90 99'14 98.745 98.520 98.296 98.049 97'45 97'48 97.437 97.233 97.051 96.867 96.686 96.513 96.331 96.170 96'20 95.870 95'19 95'80 95.430 95.291'5.163 95.033 94.933 94.787 94.659 94.552 94.440 94.316 94.220 94.112 94.005 101.58 99.533 98.492 98.041 97.451 97.108 96.764 96.603 96'10 96.206 96.035 95.885 95.712 95.569 95.412 95'91 95.145 95.026 94.898 94.768 94.661 94.555 94.454 94.340 94.244 94.136 94.028 93.943 93.847 93.750 93.654 93.589 93.493 93'19 ,93.331 93.246 93'70 93.096 93.022 92.952 92.872 92.795 92.730 92.674 92'91 92.549 92'64 92.410 Deleted Deleted Deleted Deleted Deleted Deleted Deleted Deleted Deleted Deleted Deleted Deleted Deleted Deleted Deleted Deleted Deleted Deleted Deleted Deleted Deleted Deleted Deleted Deleted Deleted Deleted Deleted Deleted Deleted Deleted Deleted Deleted Deleted Deleted Deleted Deleted Deleted Deleted Deleted Deleted Deleted Deleted Deleted Deleted Deleted Deleted Deleted Deleted 42 I
Sample Number TEST TIME Stabilization Data RTD 17 RTD 18 DEG F DEG F RTD 19 DEG F RTD 20 DEG F 79 80 81 82 83 84 85 86 87 88 25.817 26.150 26.483 26'17 27.150 27.483 27'17 28.150 28.483 28.817 93'81 93.185 93.097 92.980 92.904 92.825 92.722 92.648 92.529 92.452 93.897 93.790 93.693 93.608 93.512 93.422 93'19 93.234 93.158 93.061 92.345 92.280 92.217 92.163 92.110 92.051 91'91 91.937 91.883 91.820 Deleted Deleted Deleted Deleted Deleted Deleted Deleted Deleted Deleted Deleted 43 Sample Number TEST TIME Stabilization Data RTD 21 RTD 22 RTD 23 DEG F DEG F DEG F RTD 24 DEG F 31 32 33 34 35 36 37 38 39 40 41 42 43 44 45 46 47 48 49 50 51 52 53 54 55 56 57 58 59 60 61 62 63 64 65 66 67 68 69 70 71'2 73 74 75 76 77 78 9.817 10.150 10.483 10.817 , 11.150 11.483 11'17 12.150 12.483 12'17 13.150 13.483 13'17 14.150 14.483 14.817 15.150 15.483 15'17 16.150 16.483 16.817 17.150 17.483 17'17 18.150 18.483 18'17 19'50 19'83 19'17 20'50 20.483 20'17 21.150 21.483 21'17 22.150 22.483 22'17 23.150 23.483 23'17 24.150 24.483 24.817 25.150 25.483 99.575 97.817 96.926 96.335 95.916 95.455 95.220 95.036 94.865 94.737 94.618 94.490 94.371 94.237 94.136 94.028 93.911 93.815 93.718 93.620 93.535 93'18 93.330 93.234 93.149 93.063 92.967 92.891 92.805 92.769 92.689 92.619 92.538 92'69 92.388 92.280 92.233 92'41 92.088 92.011 91.980 91.915 91.852 91.794 91.744 91.702 91.637 91.583, 99.300 97.800 96.760 96.247 95.850 95.624 95.411 95.230 95.046 94.896 94.768 94'41 94.511 94.387 94.275 94.168 94.063 93.955 93.859 93.772 93.666 93.579 93.494 93.409 93.324 93.236 93.162 93'77 92.927 92.838 92.755 92.677 92.596 92.526 92.446 92.338 92.291 92.200 92.135 92.070 92.007 91.942 91.877 91'30 91.761 91.696 91.642 91.600 44 100.09 98.112 96.956 96.324 96.097 95.831 95.723 95.573 95.360 95.199 95'80 94.941 94.825 94'10 94.610 94.502 94.386 94.321 94.244 94'71 94.063 93.978.93.882 93.785 93.720 93.624 93.550 93'85 93.411 93.342 93.261 93'72 93.100 93.042 92.950 92.885 92.838 92.746 92.703 92'18 92.576 92.511 92.446 92.390 92.329 92".265 92.211 92.137 99.832 98.133 96.911 96.449 96.159 95.912 95.687 95.483 95.333 95.171 95.032 94'81 94.785 94.682 94.592 94.484 94.376 94.291 94.194 94.098 93.981 93.916 93.820 93.734 93.615 93.561 93'65 93.368 93.314 93'13 93.153 93.117 93'14 92.946 92.863 92.778 92.753 92.670 92.616 92.531 92.500 92.446 92.361 92.334 92.253 92'10 92.156 92.102
Sample Number TEST TIME Stabilization Data RTD 21 RTD 22 RTD 23 DEG F DEG F DEG F RTD 24 DEG F 79 80 81 82 83 84 85 86 87 88 25.817 26.150 26.483 26.817 27.150 27.483 27.817 28.150 28.483 28.817 91.520 91.466 91.424 91'79 91'16 91.262 91.208 90.746 90'15 90.672 91.526 91.461 91.407 91.365 91.322 91.280 91.237 91.183 91.150 91.096 92.083 92.029 91.987 91.933 91.879 91.848 91.806 91.761 91'18'1.676 92.049 91.963 91'10 91.867 91.802 91..739 91'63 91.620 91.566 91.501 45 Sample Number TEST TIME Stabilization Data RTD 25 RTD 26 RTD 27 DEG F DEG F DEG F RTD 28 DEG F 31 32 33 34 35 36 37 38 39 40 41 42 43 44 45 46 47 48 49 50 51 52 53 54 55 56 57 58 59 60 61 62 63 64 65 66 67 68 69 70 71 72 73'4 75 76 77 78 9.817 10.150 10.483 10.817 11.150 11.483 11'17 12'50 12.483 12'17 13'50 13'83 13.817 14.150 14.483 14.817 15.150 15.483 15'17 16.150 16.483 16.817 17.150 17.483 17.817 18.150 18.483 18.817 19.150 19.483 19'17 20'50'0.483 20'17 21.150 21.483 21.817 22.150 22.483 22'17 23.150 23.483 23'17 24'50 24.483 24.817 25.150 25.483 105.78 103.61 102.45 101.74.101.22 100.80 100.48 100.19 99.924 99.677 99'31 99.206 98.991 98.769 98.563 98.379 98.197 98.005 97.834 97.650 97.491 97.307 97.137 96.987 96.825 96.666 96.516 96.366 96.205 96.061 95.893 95.772 95.615 95.483 95.337 95'19 95.098 94.963 94.833 94.705 94.587 94.481 94.374 94.251 94.139 94.042 93.944 93.839 99.629 97.940 96.834 96.297 95.899 95.620 95.405 95.234 95.083 94.975 94.793 94.685 94.589 94.443 94.319 94.191 94.072 93.966 93.870 93.805 93.685 93.580 93.526 93.429 93.321 93.236 93'71 93.095 93.009 92'19 92.838 92.791 92.751 92'15 92.591 92.506 92.448 92.344 92 290 92.236 92.194 92.117 92.066 92.018 91 947 91.881 91.839 91.774 46 98.998 97.357 96.501 96'30 95.804 95.537 95.344 95.183 94.990 94.851 94.701 94.583 94.444 94.309 94.197 94.092 93.973 93.854 93.758 93.673 93.556 93.480 93.395 93.319 93.223 93.149 93.073 92.999 92.914 92.833 92.752 92.674 92.602 92.544 92.452 92.378 92.342 92.239 92.174 92.121 92.024 91.971 91.906 91.850 91.778 91'93 91'17 91'43 99.187 97.664 96.485 95.606 95.286 95'71 94.869 94'19 94.580 94.450 94.311 94'50 94.011 93.877 93.787 93.691 93.583 93.518 93.422 93.294 93'09 93.122 93.048 92.951 92.844 92.801 92.727 92.694 92.609 92.519 92.481 92.412 92.340 92.262 92.192 92.127 92'91 92.000 91.946 91.881 91.827 91.773 91.708 91.664 91'92 91'49 91.496 91.420 I I I I I I I
'Sample Number TEST TIME Stabilization Data RTD 25 RTD 26 RTD 27 DEG F DEG F DEG F RTD 28 DEG F 79 80 81 82 83 84 85 86 87 88 25~817 26.150 26.483 26'17 27'50 27.483 27'17 28'50 28.483 28'17 93.731 93.635 93.538 93.453 93.357 93.261 93'73 93.088 93.003 92'18 91.742 91.668 91'14 91.571 91.506 91.475 91.441 91.378 91.356 91.282 91.478 91.413 91.339 91.286 91'12 91'58 91.082 91.008 90.932 90.835 91;377 91.334 91.303 91.227 91.196 91~131 91'88 91.034 90.981 90'07 47 Sample Number TEST TIME Stabilization Data RTD 29 RTD 30 RTD 31 DEG F DEG F DEG F RTD 32 DEG F 31 32 33 34 35 36 37 38 39 40 41 42 43 44 45 46 47 48 49 50 51 52 53 54 55 56 57 58 59 60 61 62.63 64 65 66 67 68 69 70 71 72 73 74 75 76 77 78 9~817 10.150 10.483 10'17 11.150 11.483 11.817 12.150 12'83 12.817 13'50 13.483 13.817 14.150 14'83 14.817 15.150 15.483 15.817 16'50 16.483 16~817'7~150 17.483 17'17 18.150 18.483 18'17 19'50 19'83 19'17 20.150 20.483 20'17 21.150 21.483 21.817 22.150 22.483 22'17 23.150 23.483 23.817 24.150 24.483 24'17 25'50 25.483 110.36 107.61 105.73 104.44 103.67 102.99 102.52 101.90 101.49 101.04 100.70 100.39 100.08 99.774 99.502 99.222 98.955 98.697 98.439 98.192 97.978 97.743 97.559 97.323 97.119 96.937 96.744 96.562 96.390 96.215 96.037 95.914 95.757 95.604 95.456 95.329 95.207 95.039 94.911 94.804 94.676 94.557 94'38 94.328 94'14 94.095 93.999 93.893 112.32 109.41 107'1 105.82 104.73 103.80 103.10 102'1 101.93 101.47 101.06 100.65 100.25 99.886 99.581 99.237 98.959 98.669 98.422 98.175 97.928 97.715 97.488 97.275 97.059 96.855 96'62 96.491 96.298.96.132 95.966 95'11 95'31 95.499 95.322 95'82 95'70 94'13 94.774 94.666 94.550 94.399 94.291 94.179 94.076 93.959 93.852 93.744 112.16 109.35 107.29 105.68 104.56 103.75 103.00 102.38 101.79 101.27 100.85 100.47 100.09 99.718 99'13 99.082 98.793 98.471 98.204 97.862 97.669 97.392 97.049 96.812 96.599 96.331 96.107 95.946 95'33 95.548 95.337 95.161 94.962 94.798 94.630 94.481 94.349 94.203 94.011 93.872 93.680 93'19 93.349 93'26 93.134 92.995 92'88 92.749 112.40 109.53 107.35 105.92 104.82 103.94 103.28 102.67 102.11 101.63 101.11 100.73 100.41 100.08 99.788 99.509 99.220 98.950 98.692 98.456 98.200 9'7.962 97.738 97.513 97.287 97.094 96'12 96.739 96.546 96.382 96.203 96.050 95.870 95.760 95'92 95.430 95.309 95.163 95.013 94.905 94.778 94.659 94.551 94.430 94'15 94.208 94.134 93.994 48 I I I I I I I I I I Sample Number TEST TIME Stabilization Data RTD 29 RTD 30 DEG F DEG F RTD 31 DEG F RTD 32 DEG F 79 80 81 82 83 84 85 86 87 88 25.817 26.150 26.483 26'17 27.150 27.483 27'17 28'50 28.483 28'17 93.797 93.700 93.593 93.496 93.400 93.312 93.227 93.142 93.057 92.969 93.636 93.529 93.443 93.347 93.250 93.154 93.057 92.972 92.896 92.822 92.642 92.535 92.430 92.334 92.238 92.141 92.043 91.916 91.819 91~681 93.887 93.768 93.683 93.683 93.575 93.490 93.351 93.265 93'12 93.147 49
Sample Number TEST TIME Stabilization Data RTD 33 RTD 34 DEG F DEG F RTD 35 DEG F RTD 36 DEG F 31 32 33 34 35 36 37 38 39 40 41 42 43 44 45 46 47 48 49 50 51 52 53 54 55 56 57 58 59 60 61 62 63 64 65 66 67 68 69 70 71 72 73 74 75 76 77 78 9.817 10.150 10.483 10.817 11.150 11.483 11'17 12.150 12.483 12'17 13.150 13.483 13'17 14'50 14.483 14'17 15.150 15.483 15.817 16.150 16.483 16'17 17.150 17.483 17.817 18.150 18.483 18'17 19.150 19.483 19.817 20.150 20.483 20.817 21.150 21.483 21.817 22.150 22.483 22'17 23.150 23.483 23.817 24 150 24.483 24.817 25.150 25.483 112.76 109.82'107.57 106.12 105.10 104.18 103.44 102.82 102.18 101.70 101.27 100.88 100.46 100.09 99.777 99.465 99.167 98'98 98.608 98.361 98'14 97.890 97.654 97.450 97.246 97.031 96.849 96.678 96.485 96.308 96'51 95.987 95.830 95.687 95.669 95.510 95.366 95.209 95.079 94.974 94.844 94.727 94.597 94.487 94.362 94 254 94.115 94.072 111.99 109.44 107.56 106.06 105.02 104.12 103.42 102.77 102.19 101.73 101.30 100.91 100.54 100.20 99'08 99.584 99.306 99.027 98.780 98'21 98.274 98.049 97'33 97'19 97.404 97.210 97.006 96.835 96.651 96.487 96'09 96'54 95.985 95.842 95.684 95.556 95.435 95.278 95'36 95'30 94.900 94.783 94.664 94.554 94.439 94.320 94.224 94.107 111.14 108.53 106.63 105.36 104.27 103.40 102.70 102.12 101.65 101.22 100.82 100.45 100.11 99.792 99.475 99.165 98.864 98'74 98.273 98.038 97.779 97.555 97.319 97.081 96.879 96.664 96.459 96.266 96'62 95'09 95'18 95'12 95.323 95.211 95.023 94'07 94.675 94.506 94.367 94.251 94.109 93.970 93.874 93.741 93.627 93'10 93.360 93.252 111.66 109'6 106.94 105.62 104.47 103.71 103.01 102.36 101.81 101.27 100.93 100.61 100.11 99.826 99'12 99.200 98'64 98.717 98.461 98.169 97.924 9.7.709 97.493 97.257 97.053 96.871 96.667 96'96 96.303 96.160 95.991 95.827 95.670 95 493 95.381 95.208 95.098 94.961 94.802 94.694 94.564 94.436 94.339 94.218 94.104 93.985 93.877 93.781 50 I I I I Sample Number TEST TIME Stabilization Data RTD 33 RTD 34 RTD 35 DEG F DEG F DEG F RTD 36 DEG F 79 80 81 82 83 84 85 86 87 88 25.817 26.150 26.483 26'17 27.150 27.483 27.817 28'50 28.483 28.817 93.953 93.848 93.740 93.633 93.548 93.440 93.355 93.258 93'86 93.023 94.019 93.903 93.806 93.709 93.622 93.516 93.420 93.332 93.247 93.161 93.187 93.048 92.963 92.824 92.727 92.619 92.512 92.404 92.202 92.061 93.675 93.567 93.491 93.386 93.289 93.193 93.116 93.020 92.935 92.850 51 I I I'I I I I I I Sample Number TEST TIME Stabilization Data RTD 37 RTD 38 RTD 39 DEG F DEG F DEG F RTD 40 DEG F 31 32 33 34 35 36 37 38 39 40 41 42 43 44 45 46 47 48 49 50 51 52 53 54 55 56 57 58 59 60 61 62 63 64 65 66 67 68 69 70 71 72 73 74 75 76 77 78 9.817 10.100 10.483 10'17 11.150 11.483 11.817 12.150 12.483 12'17 13.150 13.483 13.817 14.150 14.483 14'17 15.150 15.483 15'17 ,16.150 16.483 16.817 17.150 17.483 17.817 18.150 18.483 18'17 19.150 19.483 19'17 20'50'0.483 20.817 21.150 21.483 21.817 22.150 22.483 22'17 23.150 23.483 23.817 24.150 24.483 24'17 25.150 25.483 112.37 109.63 107.43 106.12 105.02 104.29 103.38 102.78 102.21 101.68 101.23 100.82 100.46 100.09 99.772 99.449 99'48 98.850 98'12 98'76 98.109 97.917 97.681 97.454 97.241 97.046 96.853 96.683 96.468 96'15 96.158 95.981 95.835 95.692 95.503 95.376 95.263 95.106 94.979 94.840 94.721 94.582 94.474 94.364 94.239 94'42 94.035 93.927 Deleted Deleted Deleted Deleted Deleted Deleted'eleted Deleted Deleted Deleted Deleted Deleted Deleted Deleted Deleted Deleted Deleted Deleted Deleted Deleted Deleted Deleted Deleted Deleted Deleted Deleted Deleted Deleted Deleted Deleted Deleted Deleted Deleted Deleted Deleted Deleted Deleted Deleted Deleted Deleted Deleted Deleted Deleted Deleted Deleted Deleted Deleted Deleted 111.64 108.70 106.54 105.06 103.94 102.97 102.23 101.50 100.92 100.35 99.861 99.443 99.024 98.653 98.285 97.951 97.653 97.363 97'94 96.836 96.601 96.343 96'18 95'03 95.690 95.486 95.304 95'23 94.939 94.775 94.596 94.432 94.275 94.132 93.963 93.836 93.724 93.558 93.439 93.300 93.172 93.053 92.926 92.813 92.699 92.592 92.486 92.379 112.16 109.81 107.66 106.27 105.13 104.22 103.48 102.88 102.17 101.63 101.20 100.75 100.37 100.01 99.698 99.382 99'63 98.742 98.473 98.217 97.959 97.744 97.526 97.304 97.068 96.875 96.671 96.487 96'17 96'44 95.982 95.812 95.662 95.480 95.361 95.189 95.049 94.922 94.792 94.648 94.536 94.386 94.278 94.166 94.052 93.935 93'16 93.666 52 I I I I I I I I Sample Number TEST TIME Stabilization Data RTD 37 RTD 38 RTD 39 DEG F DEG F DEG F RTD 40 DEG F 79 80 81 82 83 84 85 86 87 88 25.817 26.150 26.483 26.817 27.150 27.483 27.817 28.150 28.483 28.817 93.811 93.703 93.607 93.521 93.414 93.329 93.253 93.156 93.071 92.986 Deleted Deleted Deleted Deleted Deleted Deleted Deleted Deleted Deleted Deleted 92.282 92.175 92.078 91.982 91.886 91.789 91.704 91'08 91.520 91.435 93.569 93.442 93.354 93.249 93.161 93.083 92.980 92.895 92.787 92.722 53 I I I I I Sample Number TEST TIME Stabilization Data RHD 1 RHD 2 RHD 3 RH RHD 4 RH 31 32 33 34 35 36 37 38 39 40 41 42 43 44 45 46 47 48 49 50 51 52 53 54 55 56 57 58 59 60 61 62 63 64 65 66 67 68 69 70 71 72 73 74 75 76 7.7 78 9.817 10.150 10.483 10.817 11.150 11.483 11.817 12'50 12.483 12'17 13.150.13.483 13'17 14.150 14.483 14.817 15.150 15.483 15'17 16.150 16.483 16'17 17.150 17.483 17.817 18.150 18.483 18.817 19.150 19.483 19.817 20.150 20'83 20'17 21.150 21.483 21.817 22.150 22.483 22.817 23.150 23.483 23.817 24.150 24.483 24'17 25.150 25.483 41.75 42.60 42.87 43.25 43.54 43.66 43.79 43.90 44.06 44.23 44'1 44.59 44.82 45.06 45.33 45.55 45'3 46'1 46.30 46'8 46.81 47.12 47.43 47.69 47.86 48.15 48.54 48.73 49.02 49.26.49.61 49.76 49.92 50.15 50.48 50.71 50.98 51.19 51.45 51.62 51.96 52.22 52.51 52.76 52.93 53.18 53'6 53.69 47.51 48.52 49.26 49.82 49.99 50.39 51.00 51.55 52.11 52.68 53'1 53.84 54.32 54.76 55.10 55.49 55.84 56.22 56.47 56.80 57.09 57'0 57.82 58'1 58.57 58'6 59'7 59.54 59'1 60.09 60.39 60.67 60.96 61.25 61.55 61.84 62.11 62.36 62.63 62.88 63.17 63'9 63'6 63.88 64.13 64.35 64.62 64'1 39~31 39.88 40.88 41.62 43.43 45.27 46.34 47.18 47.77 48.29 49.02 49.59 50.18 50.76 51.28 51.77 52.27 52.78 53.20 53.63 54.04 54.45.54.85 55.21 55.55 55'1 56.20 56.52 56.80 57.06 57.44 57.79 58.18 58'0 58.81 59.15 59'5 59'6 60.04 60.36 60.64 60.91 61.20 61.49 61.77 62.03 62.29 62.57 52.19 57.21 60.08 56.52 63.05 66.99 72.35 72'8 72.48 73.80 74.53 75.36 76.06 77.24 77.87 77.90 78.58 79.08 79'1 79.60 79.82'79.96 80.11 80.23 80.13 80.18 80.24 80.55 80'7 80.51 80.51 80.67 80'8 80.89 80.80 81 F 00 80.92 81.08 81.14 81~24 81.30 81.28 81.29 81.26 81.38 81.30 81.36 81.42 54 Sample Number TEST TIME Stabilization Data RHD 1 RHD 2 RHD 3 RH RH%RH RHD 4 RH 79 80 81 82 83 84 85 86 87 88 25~817 26.150 26.483 26.817 27.150 27.483 27.817 28.150 28.483 28.817 53.90 54.06 54.26 54.50 54.68 54.94 55.10 55.31 55.50 55.67 65.04 65.25 65.46 65.69 65.92 66.13 66.31 66.49 66.68 66.84 62.80 63.07 63.30 63.55 63.82 64.06 64.28 64.53 64.77 64.99 81.58 81.54 81.52 81.45 81.56 81.55 81.57 81.57 81.48 81.46 55 Sample Number TEST TIME Stabilization Data RHD 5 RHD 6 RHD 7 RH RH RH RHD 8 RH 31 32 33 34 35 36 37 38 39 40 41 42 43 44 45 46 47 48 49 50 51 52 53 54 55 56 57 58 59 60 61 62 63 64 65 66 67 68 69 70 71 72 73 74 75 76 77 78 9.817 10.150 10.483 10'17 11.150 11.483 11.817 12'50 12.483 12'17 13'50 13.483 13.817 14.150 14.483 14.817 15~150 15.483 15.817 16.150 16.483 16'17 17.150 17.483 17'17 18.150 18.483 18.817 19'50 19'83 19'17 20'50 20.483 20'17 21.150 21.483 21.817 22.150 22.483 22'17 23.150 23.483 23'17 24.150 24.483 24.817 25.150 25.483 80.28 81.47 81.89 86.56 79.84 87.83 87.52 86.81 87.23 87'9 86.74 86.28 85.77 85.98 85.65 85.51 85.51'5.67 85.71 85.49 85.38 84.77 84.55 84.29 84.19 84.18 84.30 84.60 84.47 84.36 84.41 84.56 84.36 84.39 84.50 84.60 84.63 84.96 85.22 85.27 85'4 85.01 85.15 85.18 85.16 85.08 85'2 84.81 83.1 84.53 85.28 82.33 81'4 80.85 77.83 77.10 76.87 76.08 76.04 74.69 73.63 73.36 73.16 72.83 71.72 71.48 70.03 69.53 70.43 69.85 69.31 70'8 70.00 70'2 70'9 70.58 70.60 71.12 71.61 71.85 70.81 71.56 71.63 72.04 71.93 71.60 71.68 71.26 71.39 71.12 70'8 71.22 71.32 71.36 71.11 72.24 78.05 81'3 82'6 83.05 82.63 82.19 81.61 81.21 80.86 80.95 80.90 81.00 81.01 81.02 81.05 81.25 81.17 80.90 80.90 80.88 80.82 80'2 80.69 80.86 80.57 80.42 80.44 80.66 80.70 80.68 80.56 80'3 80.69 80.71 80'8 80.47 80.49 80.57 80.21 80.09 80.09 80.37 80.42 80.41 79'8 79.51 79.59 79.64 57.56 60.93 62.88 64.83 68.41 72.70 78.79 82.49 84'1 86 F 00 86.47 86.69 87.35 87.84 88.24 89.00 89.96 89.84 90.36 91.56 91.28 91.71 92.23 92.46 93'1 93.38 93.54 93.95 95.04 94.61 94.79 95'3 95.42 95'8 96'2 96.30.96.57 97.68 97.08 97.27 97.44 97.67 97.90 98.02 99.12 99.12 98.60 99.27 56 I I I I I I I I I sample Number TEST TIME Stabilization Data RHD 5 RHD 6 RHD 7 RH RH RH RHD 8 79 80 81 82 83 84 85 86 87 88 25.817 26.150 26.483 26'17 27.150 27.483 27.817 28.150 28.483 28.817 84'1 84.97 84.95 85.05 85.12 85.17 85'5 85.16 85.20 85'4 72.35 71~64 72.48 71.23 72.67 72.54 72.30 72.20 72.84 72.85 79.42 79.42 78.96 78.96 78.92 78.93.79.07 79.35 79.29 79'1 99..38 99.25 99.28 99.74 99.72 100.12 101.01 100.42 100.46 100.70 57
Sample Number TEST TIME Stabilization Data RHD 9 RHD 10 RH 4 RH 31 32 33 34 35 36 37 38 39 40 41 42 43 44 45 46 47 48 49 50 51 52 53 54 55 56 57 58 59 60 61 62 63 64 65 66 67 68 69 70 71 72 73 74 75 76 77 78 9.817 10.150 10.483 10.817 11.150 11.483 11'17 12'50 12.483 12.817 13.150 13.483 13'17 14.150 14.483 14.817 15.150 15.483 15.817 16.150 16.483 16'17 17.150 17.483 17'17 18.150 18.483 18.817 19.150 19.483 19;817 20.150 20'83 20.817 21'50 21.483 21.817 22.150 22.483 22.817 23.150 23.483 23.817 24.150 24.483 24'17 25.150 25.483 60.04 61.87 65.53 68.20 69.58 71.49 73;00 75.58 78.44 79.66 80.77 81.77 82.67 83.42 84.13 84.80 85.39 85.99 86'7 87.04 87.57 88.07 88.57 88.93 89.39 89.84 90.27 90.63 90.96 91.34 91.73 92.02 92.43 92.73 93.06 93.34 93.72 94.05 94'1 94.69 95.01 95.28 95.58 95.94 96.26 96.61 97.02 97.34 64.60 65.83 63'6 63.91 64.54 66.73 70.76 73.93 76.61 77.74 78.78 79.80 80.83 81.65 82.41 83.14 83.75 84.35 84.94 85.46 85'7 86.46 87.04 87.37 87'6 88.32 88.70 89.07 89.55 89.92 90.26 90.46 90.95 91.17 91.49 91.89 92.22 92.38 92.60 92.95 93.25 93.73 93.98 94.31 94.67 95.02 95.44 95.66 58 Sample Number TEST TIME Stabilization Data RHD 9 RHD 10 RH 4 RH 79 80 81 82 83 84 85 86 87 88 25~817 26~150 26.483 26.817 27.150 27.483 27'17 28.150 28.483 28.817 97.66 97.99 98.33 98.61 98.91 99'7 99.44 99.67 99.89 100.12 95.87 96.14 96.61 96.80 97.23 97.44 97.72 98'7 98.45 98.57 59
Sample Number TEST TIME Stabilization Data VAPOR CONT.PRESSURE PRESSURE PSIA PSIA 31 32 33 34 35 36 37 38 39 40 41 42 43 44 45 46 47 48 49 50 51 52 53 54 55 56 57 58 59 60 61 62 63 64 65 66 67 68 69 70 71 72 73 74 75 76 77 9.817 10.150 10.483 10.817 11.150 11.483 11.817 12'50 12.483 12'17 13'50 13.483 13'17 14'50 14'83 14'17 15.150 15.483 15.817 16.150 16.483 16.817 17'50 17.483 17.817 18.150 18.483 18'17 19.150 19.483 19'17 20'50 20.483 20'17 21'50'1'83 21'17 22.150 22.483 22.817 23.150 23.483 23.817 24.150 24.483 24.817 25.150 0.7121 0'879 0.6673 0.6543 0.6484 0.6606 0.6700 0.6739 0.6777 0.6767 0'751 0.6723 0.6700 0.6689 0.6669 0.6651 0.6632 0.6607 0.6581 0.6568 0.6550 0.6525 0.6507 0.6493 0.6475 0.6466 0.6452 0.6442 0'435 0.6418 0.6407 0.6404 0.6378 0.6375 0.6365 0.6360 0.6353 0.6352 0.6332 0.6323 0.6314 0.6306 0'296 0.6294 0.6295 0.6286 0.6274 58.480 58.219 58.095 58.014 57.954 57.905 57.863 57.827 57.794 57.765 57.737 57'12 57.689 57.667 57'46 57.626 57.607 57.589 57.571 57.554 57.538 57.522 57.507 57.493 57'78 57.465 57.452 57.439 57.426 57.414 57.402 57.391 57.380 57.369 57.358 57.348 57.338 57.328 57.318 57.309 57.300 57.29157.282 57.273 57'.265 57.256 57.248 60
Sample Number TEST TIME Stabilization Data VAPOR CONT.PRESSURE PRESSURE PSIA PSIA 78 79 80 81 82 83 84 85 86 87 88 25.483 25.817 26.150 26.483 26'17 27.150 27.483 27.817 28.150 28.483 28'17 0.6280 0.6274 0.6260 0.6259 0.6248 0.6254 0.6251 0.6252 0.6241 0.6238 0.6235 57.240 57.232 57.224 57.217 57.209 57.202 57.195 57.187 57.180 57.174 57.167 61 Sample Number TEST TIME Stabilization Data CONT.DELTA T/HR DELTA T/HR AVERAGE LAST 2 HRS LAST 1 HR TEMP 1HR to 2HR DELTA T/HR CHANGE 31 32 33 34 35 36 37 38 39 40 41 42 43 44 45 46 47 48 49 50 51 52 53 54 55 56 57 58 59 60 61 62 63 64 65 66 67 68 69 70 71 72 73 74 75 76 77 9.817 10.150 10.483 10'17 11.150 11.483 11'17 12.150 12 483 12.817 13.150 13.483 13.817 14.150 14.483 14.817 15.150 15.483 15.817 16.150 16.483 16.817 17.150 17.483 17.817 18.150 18.483 18.817 19.150 19.483 19.817 20.150 20.483 20~817 21~150 21.483 21.817 22.150 22.483 22.817 23.150 23.483 23.817 24.150 24.483 24.817 25.150 102.892 100.892 99.603 98'10 98.253 97.813 97.451 97.139 96.847 96.590 96'62 96.147 95.940 95'39 95.549 95.367 95'85 95.014 94.855 94.700 94.550 94.402 94.265 94'20 93.983 93.854 93.726 93.604 93.483 93'69 93.255 93'48 93'41 92.942 92.838 92.737 92.652 92.551 92.461 92.377 92.289 92.204 92.119 92'46 91'63 91.892 91.820-2.721-1.877-1.378-1.110-0'46-0.833-0.756-0.700-0.649-0.612-0.589-0.567-0.543-0.520-0'00-0.483-0.460-0.447-0.436-0.423-0'12-0'99-0.391-0.376-0.364-0.353-0.343-0'31-0.323-0.316-0'02-0.299-0.290-0.283-0.275-0.267-0.,267-0'53-0.249-0.243-0.235-4.082-2.639-1.790-1.359-1.114-0.966'-0.861-0.777-0.700-0.650-0'23-0.598-0.573-0.554-0'35-0.512-0'85-0.464-0.453-0.435-0.430-0'19-0.411-0.394-0.379-0.371'0.357-0.349-0.335-0.328-0'13.-0'10-0.304-0'90-0.287-0'76-0.275-0.262-0'57-0'58-0.243-0.241-0.227-0'26 0.763 0.412 0.249 0.169 0.133 0.106 0.077 0'51 0.039 0.035 0.032 0.031 0.035 0.036 0.030 0.025 0.017 0.017 0.012 0.018 0.020 0.020 0.019 0.015 0.018 0.015 0.018 0.013 0.012 0.012 0.012 0.014 0.008 0.013 0.010 0.009 0.010 0.008 0.016 0.009 62
Sample Number TEST TIME Stabilization Data CONT.DELTA T/HR DELTA T/HR AVERAGE LAST 2 HRS LAST 1 HR TEMP 1HR to 2HR DELTA T/HR CHANGE 78 79 80 81 82 83 84 85 86 87 88 25.483 25.817 26.150 26.483 26'17 27.150 27.483 27.817 28.150 28.483 28.817 91.743 91.672 91.597 91.531 91.465 91.399 91.338 91.269 91.195 91.130 91.066-0'31-0.224-0.225-0'16-0.214-0.211-0.203-0.202-0.201-0.201-0.200-0.220-0.220-0.223-0.212-0.207-0.198-0.193-0.196-0.204-0'08-0.203 0.011*0.004*0.002*0.004*0.007*0.013*0.010*0.006*0.003*0.008*0.004*NOTES 1)THE 1 HOUR AND 2 HOUR DELTA TEMPERATURE VALUES ARE NOT VALID UNTIL 1 HOUR AND 2 HOURS'ESPECTIVELY'AVE PASSED IN THE TEST 2), THE STABILIZATION CRITERIA IS MET WHEN:-THE HOURLY AVERAGE DELTA T FOR THE PRECEDING HOUR DIFFERS FROM THE HOURLY AVERAGE DELTA T FOR THE PRECEDING 2 HOURS BY LESS THAN 0.5 DEGREES F.OR-THE HOURLY AVERAGE DELTA T FOR THE PRECEDING 2 HOURS IS LESS THAN 1.0 DEGREES F.-THE STABILIZATION PERIOD IS A MINIMUM OF 4 HOURS 3)THE"*" INDICATES THAT THE STABILIZATION CRITERIA HAS BEEN MET.63 I I I I M&M M M M M M M M M Ibs 693,100 Stabilization Period St.Lucie Unit 2 June 1992 psia 0,7 693,000 692,900 692,800 I Z)692,700 Ch Q 692,600 P Temperature Stabilization
~~Criteria met ILRT Start 0.68 0.66 0.64 692,500 692,400 10 15 20 Test Time 25 0.62 30 Air Mass Note inverse trends of airmass vs vapor pressure Weighted vapor pressure I I I I Deg E 104 Stabi ization Period St.Lucie Unit 2 June 1992 P S I CI 0.72 102 100 98 96 cn C 94 92 Temperature Stabilization Criteria met ILRT Start 0~A 4 0.7 0.68 0.66 9.64 0.62 90 10 15 20 Test Time 25 0.6 30 Avg.T~era erature Stabilization extended after temperature criteria met due to vapor pressure affects Avg.Vapor Pressure wamaQe~
0.8 Comparison
of Different Vapor Pressure Trends Historical vs Latest ILRTs at St.Lucie Vapor Pressure (psia)0.5 OA5 0.75 OA 1 Z)0.35 (D~~~~~~~~~~~~~~~~~t~~~F 4'~~OlttO~~~~~~~~~I~~Oyy~~~~~1'~~~~0~~~~~1~~~yy~1~~'~ill~yy~~~~~~~~1~~~0~~g~y~g4~y goto~~0~~~~0~~g~~~0~++~+~~+~+0.7 0.65 0.3~%%%a~~~~~~W&W~W&WAWW&&&%%%%&%%&&&%a~~~&%%%%%%&&AM&%&&%%%w&%&ma&AM&&~%&ww&%&
0.6 0.25 89 8c 90 Stabilization Sample number PSL 2 1989 PSL 1 1990 PSL 2 1992 0.55 92 PSL 2 1992 Yopor PressUre Scole Offset I I I I I I
%RH by Elevation During Stabilization Period St.Lucie Unit 2 June 1992 e*Saturation reached at upper elevation as temperature stabilized 100 90 80-ri 70 60 0)~50 0 0 40 10 15 20 Test Time 25 30 RH 40 f't.%RH 84 ft.%RH 17 1 ft..---o---Note minimal of mixing of water vapor by elevation I I I I I I Temp by Elevation During Stabilization Period St.Lucie Unit 2 June 1992 DEG F 115 110'l05 100 Z)95 cD 90 L~~~WAN~~~ooo~O~~oooo~~~~~os~~~ooooo~~o~~~O~O o~~ooo~oo oo~~~ooo~O~ooooo~~~~~~~~~~o~o~o~~~o~~o~~o~o~~~~~~o~o~~~o~~~O~o~~o~o~o~~o~~~~~~~~~~~~85 10 15 20 Test Time 30 DEG F 40 ft.DEG F 84 ft.DEG F 130 ft.DEG F 171 ft.DEG F 194 FT.Note convergence of all groups above 62 ft.operating deck
.I I I I I I I I ILRT DATA 69 I I I I I I I Sample Number 89 90 91 92 93 94 95 96 97 98 99 100 101 102 103 104 105 106 107 108 109 110 111 112 113 114 115 TEST TIME 29.150 29.483 29.817 30'50 30.483 30.817 31~150 31.483 31.817 32.150 32.483 32'17 33.150 33.483 33'17 34'50 34.483 34'17 35.150 35.483 35.817 36.150 36.483 36'17 37.150 37.483 37~817 RTD 1 DEG F 86.770 86.752 86.743 86.752 86.752 86.732 86.743 86.743 86.743 86.710 86.732 86.721 86.732 86.721 86.721 86.721 86.728 86.728 86.705 86.710 86.716 86.698 86.698 86.698 86.689 86'05 86'98 ILRT Dat:a RTD 2 DEG F 87.370 87'52 87.343 87.343 87.343 87.321 87.321 87'10 87.310 87.299 87.290 87.290 87.278 87.278 87.278 87.267 87.263 87.263 87.252 87.247 87.243 87.225 87.225 87.214 87.214 87.209 87.202 RTD 3 DEG F 86.592 86.585 86.585 86.574 86.574 86.585 86.574 86.562 86.574 86'74 86.562 86.562 86.562 86.574 86'62 86.562 86.558 86.558 86.558 86.542 86.558 86.551 86.542 86.551 86'42 86.549 86.542 RTD 4 DEG F 86.045 86.038 86.027 86.018 86.027 86'18 86.018 86.018 86.018 86.007 86.007 86.007 85.996 85.996 85.996 85.996 86.003 86.003 86'03 85.985 85'91 85.985 85.985 85.973 85.985 85.991 85.985 70 ILRT Data Sample Number 89 90 91 92 93 94 95 96 97 98 99 100 101 102 103 104 105 106 107 108 109 110 111 112 113 114 115 TEST TIME 29.150 29.483 29.817 30.150 30.483 30.817 31.150 31.483 31.817 32.150 32.483 32.817 33.150 33.483 33.817 34.150 34.483 34.817 35.150 35.483 35.817 36.150 36.483 36.817 37.150 37.483 37.817 RTD 5 DEG F 85.931 85.924 85.913 85.913 85.913 85.902 85.902 85.913 85.902 85.893 85.893 85.893 85.882 85.882 85.882 85.882 85.899 85.888 85.888 85.882 85.888 85.882 85.882 85.882 85.882 85.877 85.870 RTD 6 DEG F 86.484 86.479 86.479 86.468 86'57 86.457 86.457 86.457 86.446 86.446 86.434 86.434 86.425 86.425 86.425 86.414 86.421 86.421 86.421 86.403 86.410 86.403 86.403 86.392 86.392 86.398 86.392 RTD 7 DEG F 86.638 86.622 86.622 86.622 86.611 86.600 86.600 86.600 86.589 86.589 86.589 86.578 86.578 86.578 86.569 86.569 86'75 86.575 86.564 86.557 86.564 86.546 86.546 86.546 86.546 86.542 86.526 RTD 8 DEG F 86.024 86.007 86.007 86.007 85.995 85.986 85.995 85.995 85.986 85.995 85.975 85.975 85.964 85.975 85.975 85.964 85.971 85.959 85.959 85.953 85.959 85.953 85.953 85.953 85.944 85.948 85.944 71 I I I I I I I I I I I I Sample Number TEST TIME RTD 9 DEG F ILRT Data RTD 10 DEG F RTD 11 DEG F RTD 12 DEG F 89 90 91 92 93 94 95 96 97 98 99 100 101 102 103 104 105 106 107 108 109 110 ill 112 113 114 115 29.150 29.483 29'17 30.150 30.483 30.817 31.150 31.483 31~817 32.150 32.483 32.817 33.150 33.483 33.817 34.150 34.483 34.817 35.150 35.483 35.817 36.150 36.483 36.817 37.150 37.483 37.817 93.268 92.511 93.187 92.419 93.111 92.345 93.026 92.268 92.949 92.194'2.876 92.118 92.799 92.055 92.737 91.979 92.629 91.905 92.564 91.84b 92'10 91.763 92.437 91.709 92.372 91.658 92.318 91'93 92.253 91.539 92.179 91.474 92'32 91.415 92.067 91.352 92'13 91.299 91.953 91.238 91.897 91.202 91.836.91'53 91.771 91.110 91.729 91.130 91.664 91.065 91.628 90.998 91'79 90.895 93.104 93.013 92.937 92.863 92.787 92.713 92.637 92.563 92.498 92.433 92'71 92.295 92.221 92.156 92.102 92.037 91.993 91~917 91.863 91'03 91.745 91.686 91.633 91.579 91.525 91.490 91.429 92.774 92.660 92.586 92.500 92.424 92.359 92.285 92.200 92.135 92.081 91.995 91.930 91.856 91.803 91.726 91.652 91.605 91.540 91.486 91.394 91.367 91.298 91.244 91'79 91.136 91.089 91.028 72 I I I I I I I I I I ILRT Data Sample Number 89 90 91 92 93 94 95 96 97 98 99 100 101 102 103 104 105 106 107 108 109 110 111 112 113 114 TEST TIME 29.150 29.483 29.817 30.150 30.483 30'17 31.150 31.483 31.817 32.150 32.483 32'17 33.150 33.483 33'17 34.150 34.483 34'17 35.150 35.483 35'17 36'50 36.483 36.817 37.150 37.483 RTD 13 DEG F 93.102 93.042 92.965 92.858 92.827 92.750 92.676 92.600 92.526 92.119 92'15 92.204 92.152 92.087 92.011 91'80 91.998 91'79 91'48 91.798 91'40 91.659 91.637 91.606 91.518 91.494 RTD 14 DEG F 92.370 92.257 92.192 92.096 92'19 91.934 91.806 91.752 91.687 91.622 91.548 91.494 91.408 91.343 91.267 91.235 91'77 91.080 91'18 90.934 90.876 90.827 90.784 90.710 90.645 90.575 RTD 15 DEG F 93.087 92.983 92.898 92.833 92.748 92.672 92.598 92.533 92.459 92.383 92.309 92.244 92.179 92.125 92.062 92.009 91.928 91'65 91.823 91.751 91.704 91.632 91.578 91.525 91.482 91.426 RTD 16 DEG F 93.069 92.978 92.892 92.816 92.753 92.677, 92.561 92.334 92.238 92.195 92.099 92.034 91.949 91.895 91'30 91.767 91.729 91.720 91.655 91.594 9'1.547 91.498 91.433 91.370 91.325 91.278 73 I I ILRT Data Sample Number 89 90 91 92 93 94 95 96 97 98 99 100 101 102 103 104 105 106 107 108 109 110 111 112 113 114 115 TEST TIME 29.150 29.483 29'17 30'50 30.483 30'17 31.150 31'83 31'17 32.150 32.483 32.817 33'50 33.483 33'17 34.150 3'4.483'34~817 35~150 35.483 35.817 36'50 36.483 36'17 37.150 37.483 37.817 RTD 17 DEG F 92.405 92.313 92.227 92.162 92.088 91.992 91.938 91.852 91'07 91.744 91.691 91'14 91.540 91.432 91.401 91.324 91.288 91.223 91.160 91.077 91'30 90.981 90.884 90.830 90.819 90.763 90'91 RTD 18 DEG F 92.992 92.889 92.815 92.739 92.665 92.580 92.504 92.450 92'65 92.300 92.257 92.194 92.107 92.044 92 F 000 91.946 91.890 91.814 91.751 91.690 91.643 91.560 91.507 91.444 91.390 91.343 91.303 RTD 19 DEG F 91.785 91.724 91.670 91.616 91.574 91.540 91.498 91.455 91.413 91.370 91.327 91.262 91.231 91.197 91.166 91'35 91.108 91'034 90.980 90.951 90'15'0.877 90.843 90'12 90.781 90.787 90.727 RTD 20 DEG F Deleted Deleted Deleted Deleted Deleted Deleted Deleted Deleted Deleted Deleted Deleted Deleted Deleted Deleted Deleted Deleted Deleted Deleted Deleted Deleted Deleted Deleted Deleted Deleted Deleted Deleted Deleted
Sample TEST Number TIME RTD 21 DEG F ILRT Data, RTD 22 DEG F RTD 23 DEG F RTD 24 DEG F 89 90 91 92 93 94 95 96 97 98 99 100 101 102 103 104 105 106 107 108 109 110 111 112 113 114 115 29.150 29.483 29'17 30.150 30.483 30.817 31.150 31.483 31'17 32.150 32.483 32.817 33.150 33.483 33'17 34.150 34.483 34.817 35.150 35.483 35.817 36.150 36.483 36.817 37'50 37.483 37'17 90.576 90.522 90.457 90.394 90.329 90.287 90.222 90.159 90.105 90.029 89.962 89.890 89.793 89.708 89.515 89.435 89.385 89.257 89.204 89.215 89.183 89.150 89'76 89.033 89.011 88.979 88'14 91.065 91.011 90.968 90.926 90.883 90.841 90.798 90.765 90.722 91.011 91.083 91.076 91.107 91.096 90.980 90.953 90.926 90.872 90.798 90.765 90.776 90.722 90.648 90.606 90.561 90.510 90'76 91.591 91.559 91'17 91.483 91.452 91'98 91.356 91.324 91.302 91.226 91.127 91.055 90.959 90.894 90.874 90'70 90.841 90.789 90.744 90'13 90'70 90.639 90.585 90.552 90.520 90.498 90'78 91.458 91.4'05 91.373 91.308 91.277 91.212 91.149 91.115 91.061 90.998 90.972 90.922 90.859 90.848 90.826 90.790 90.718 90.687 90.622 90.579 90.516 90.516 90.505 90'4 90.301 90.278 90.247 75 l
Sample Number TEST TIME RTD 25 DEG F ILRT Data RTD 26 DEG F RTD 27 DEG F RTD 28 DEG F 89 90 91 92 93 94 95 96 97 98 99 100 101 102 103 104 105 106 107 108 109 110 111 112 113 114 115 29.150 29.483 29.817 30.150 30.483 30.817 31~150 31.483 31~817 32.150 32.483 32'17 33.150 33.483 33.817 34'50 34.483 34.817 35'50 35.483 35.817 36'50 36.483 36.817 37.150 37.483 37'17 92.864 92.788 92.69292.618 92.542 92.468 92.392 92'18 92.242 92.179 92.098 92.040 91.975 91.899 91.836 91.778 91'18 91.655 91.601 91 536.91.471 91'18 91.355 91.301 91.259 91'94 91'51 91.205 91'63 91.109 91.066 91'35 90.992 90.947 90.904 90.873 90.830 90.803 90.765 90.722 90.700 90.657 90.633 90.594 90.561 90'41 90.507 90.475 90'44 90.422 90.390 90.359 90'14 90.305 90.782 90'19 90.676 90'12 90.538 90.493 90.430 90.334 90'91 90.108 90.061 89.553 89.349 89.188 89.081 89.013 88.899 88'14 88.642 88.579 88'72 88.407 88.364 88.299 88.248 88'18 88.056 90.918 90.875 90.822 90.779 90.746 90.714 90.672 90.618 90.533 90.511 90.486 90.392 90.372 90.349 90'87 90'60 90'99 90'90 90'37 90'94 90.072 90.061 90.029 89.987 89.975 89.922 89.890 76 I I I I I I ILRT Data Sample Number 89 90 91 92 93 94 95 96 97 98 99 100 101 102 103 104 105 106 107 108 109 110 111 112 113 114 115 TEST TIME 29~150 29.483 29.817 30'50 30.483 30.817 31.150 31'83 31.817 32.150 32.483 32.817 33.150 33.483 33.817 34.150 34.483 34.817 35.150 35.483 35.817 36.150 36.483 36.817'7.150 37.483 37.817 RTD 29 DEG F 92.873 92.788 92.702 92.649 92.541 92.456 92.359 92.294 92.220 92.124 92.066 91.985 91 920 91.846 91.781 91.723 91.631 91.566 91.503 91.416 91.353 91.277 91'23 91.169 91.095 91.030 90.988 RTD 30 DEG F 92.725 92.651 92.553 92.467 92.393 92'17 92.243 92.189 92.104 92.039 91.972 91.889 91.835 91.761 91.696 91.637 91.557 91.503 91.449 91.375 91.332 91.267 91.213 91'48 91.106 91.052 90.998 RTD 31 DEG F 91'73 91.489 91.381 91.328 91.220 91.135 91.039 90'12 90.889 90.804 90.735 90.590 90.548 90.516 90.451 90.331 90.259 90'85 90'21 90.036 89.993 89'17 89.864 89.801 89.725 89'62 89.555 RTD 32 DEG F 93.082 93'19 92.922 92.846 92.750 92.664 92.590 92.503 92.406 92.290 92.296 92.225 92'71 92.097 92.021 91.953 91.882 91.817 91.754 91.700 9'1~64 6 91.570 91.527 91.473 91.431 91.368 91.323 77 ILRT Data Sample Number 89 90 91 92 93 94 95 96 97 98 99 100 101 102 103 104 105 106 107 108 109 110 111 112 113 114 TEST TIME 29.150 29.483 29'17 30'50 30.483 30.817 31.150 31.483 31.817 32.150 32.483 32.817 33'50 33.483 33.817 34.150 34.483 34.817 35'50 35.483 35.817 36'50 36.483 36.817 37.150 37.483 RTD 33 DEG F 92.958 92.873 92.797 92'12 92.615 92.519 92.465 92.411 92.400 92.292 92.203 92'33 92'91 92.015 91.941 91.947 91.737 91.737 91.714 91.768 91.683 91.575 91.521 91.459 91'83 91.318 RTD 34 DEG F 93.096 92.999 92.925 92.840 92.764 92'78 92'13 92.528 92.463 92.389 92.330 92.258 92.195 92'41 92.065 92.009 91'48 91.894 91.829 91.766 91.712 91.659 91.593 91.540 91.497 91.443 RTD 35 DEG F 91.955 91.859 91.794 91.709 91.601 91.525 91.235 91'73 91'08 91.043 90.995 90.892 90.829 90.776 90.722 90.643 90'03 90.540 90.464 90'10 90.356 90.294 90.271 90'17 90.163 90.089 RTD 36 DEG F 92.762 92.688 92.603 92.526 92.452 92'65 92.302 92.217 92.141 92.087 92.020 91.937 91.874 91.809 91.744 91.676 91.616 91.551 91.486 91.434 91.380 91.304 91.273 91.208 91.154 91'00 78 I I I.I I I I I I I I I Sample Number 89 90 91 92 93 94 95 96 97 98 99 100 101 102 103 104 105 106 107 108 109 110 111 112 113 114 115 TEST TIME 29.150 29.483 29.817 30.150 30.483 30.817 31'50 31.483 31'17 32.150 32.483 32.817 33.150 33.483 33.817 34.150 3'4.483 34.817 35.150 35.483 35'17 36.150 36.483 36.817 37.150 37.483 37'17 RTD 37 DEG F 92.901 92'13 92'17 92.632 92.567 92.493 92.428 92.343 92.278 92.204'92.168 92.085 92.022 91.957 91.892 91.836 91.776 91.722 91.668 91.614 91.561 91.507 91.453 91.399 91.357 91.314 91.240 ILRT Data RTD 38 DEG F Deleted Deleted Deleted Deleted Deleted Deleted Deleted Deleted Deleted Deleted Deleted Deleted Deleted Deleted Deleted Deleted Deleted Deleted Deleted Deleted Deleted Deleted Deleted Deleted Deleted Deleted Deleted RTD 39 DEG F 91.361 91.265 91~189 91~104 91.039 90'53 90.879 90'14 90.738 90.653 90.595 90.525 90.460 90.396 90.322 90.274 90.203 90'40 90'86 90'21 89.979 89.894 89.840 89'18'89.744 89.690 89.658 RTD 40 DEG F 92'32 92.54 92.464 92.368 92.305 92.229 92.164 92.079 92'14 91.951 91.863 91.801 91.724 91.662 91'17 91.565 91.518 91.442 91.377 91'08 91.261 91.200 91.135 91.081 91.027 90.992 90.900 79.
ILRT Data Sample Number 89 90 91 92 93 94 95 96 97 98 99 100 101 102 103 104 105 106 107 108 109 110 111 112 113 114 115 TEST TIME 29.150 29.483 29'17 30.150 30.483 30.817 31.150 31.483 31'17 32.150 32.483 32.817 33.150 33.483 33'17 34.150 34.483 34'17 35.150 35.483 35.817 36.150 36.483 36'17 37.150 37.483 37.817 RHD 1 RH 55'1 56.11 56.29 56'6 56.61 56.81 56.97 57.21 57.42 57;73 57.90 58.18 58.44 58.63 58.92 59.14 59.32 59.56 59'1 59.99 60.23 60.46 60.62 60.85 61.06 61.27 61.48 RHD 2 RH 67.03 67.18 67.34 67.51 67.65 67.82 67.97 68.11 68.27 68.42 68.56 68'1 68.86 69.03 69.16 69'9 69.43 69'7 69'1 69.83 69.97 70.10 70.21 70.35 70.48 70.60 70.73 RHD 3 RH 65.25 65.45 65.67 65.90 66.11 66.31 66.53 66.73 66.91 67.11 67.31 67.52 67.73 67.93 68.12 68'7 68.58 68'4 68.95 69.17 69.36 69.53 69.67 69.90 70.06 70.24 70.35 RHD 4 81.60 81.38 81.58 81.62 81'1 81.38 81.48 81.27 81.24 81~42 81~24 81~11 81.36 81.26 81.15 81.28 81.10 81~12 81.09 81.00'81.04 81~02 81.06 81~07 80.68 80.92 80'8 80 Sample TEST Number TIME RHD 5 RH ILRT Data RHD 6 RH RHD 7 RH RHD 8 RH 89 90 91 92 93 94 95 96 97 98 99 100 101 102 103 104 105 106 107 108 109 110 111 112 113 114 115 29.150 29.483 29.817 30'50 30.483 30.817 31.150 31'83 31.817 32.150 32.483 32'17 33.150 33.483 33'17 34.150 34.483 34'17 35.150 35.483 35.817 36.150 36.483 36'17 37.150 37.483 37.817 85.13 85.08 85.05 85.04 84.99 84.95 84.99 84.92 84.93 84.92 84.80 84.75 84.77 84.77 84.62 84.61 84.58 84.47 84.50 84.37'4.33 84.25 84.17 84.11 84.00 84.03 83.75 72.85 72.82 73.34 73.54 73.57 74.75 74.52 75.20 76.14 77.06 77.07 76.80 77.37 76.71 77.93 78'0 78.65'8.98 79.21 79.40 78.97 79.72 79.45 79.85 79.82 79.90 79.80 79.85 79.89 79.79 79.89 79.78 79.58 79.61 79.35 81.98 79.88 79.67 79.43 79.59 81'8 80.29 79.80 79.56 79.50 79.44 79.49 79.30 79.36 79.18 79.22 79.29 79.17 79.06 100.85 101.47 101.50 101.68 101.08 102'9 102.25 101.35 102.36 102.16 102.19 101.93 102.77 102.02 101.88 102.00 102.76 103.18 102.44 102.72 102.20 102.22 102.35 102,15 102'1 102.39 102.80 81 I
ILRT Data Sample Number 89 90 91 92 93 94 95 96 97 98 99 100 101 102 103 104 105 106 107 108 109 110 111 112 113 114 115 TEST TIME 29.150 29.483 29.817 30'50 30.483 30.817 31'50 31.483 31.817 32.150 32.483 32.817 33'50 33.483 33'17 34.150 34.483 34'17 35.150 35.483 35.817 36.150 36.483 36.817 37.150 37.483 37.817 RHD 9 RH 100.33 100.51 100.76 100.91 101.03.101.17 101.32 101.41 101.53 101.66 101.79 101.82 102.02 102.07 102.11 102.22 102.24 102.31 102.41 102.44 102.50 102.55 102.57 102.58 102.62 102.71 102.66 RHD 10 RH 98.86 98.96 99.11 99.42 99.09 99.63 99.63 99.94 100.04 100'4 99'3 99.68 100.42 100.56 100.78 100.65 100.98 100'1 100.99 101.00 101.10 100.87 101.17 101.35 101.41 101.43 101.24 CONT.PRESSURE 57.160 57.154 57.147 57'41 57.135 57.128 57.122 57.116 57.110 57.105 57.099 57.094 57.088 57.083 57.077 57.072 57.067 57.062 57.057 57.052 57.047 57.042 57.038 57.033 57.029 57.024 57.020 VAPOR PRESSURE 0.6233 0.6228 0.6226 0.6224 0.6203 0'217 0.6206 0'191 0'219 0'201 0.6186 0.6171 0.6189 0.6180 0.6174 0.6168 0.6171 0.6169 0.6157 0.6153 0'.6140 0.6134 0.6129 0.6125 0'119 0.6116 0.6105 82 I I I I I I I Sample Number TEST TIME AVERAGE TEMP ILRT Data AIR MASS LEAK SIM 4/DAY LEAK FIT UCL 4/DAY 4/DAY 89 90 91 92 93 94 95 96 97 98 99 100 101 102 103 104 105 106 107 108 109 110 111 112 113 114 115 29'50 29.483 29.817 30.150 30.483 30.817 31.150 31.483 31.817 32.150 32.483 32.817 33.150 33.483 33'17 34 150 34.483 34'17 35.150 35.483 35'17 36.150 36.483 36.817 37.150 37.483 37'17 91.010 90.945 90.888 90.830 90.777 90.720 90.662 90.604 90.554 90.497 90.456 90.392 90'39 90.291 90.239 90.197 90.153 90.103 90.055 90.011 89.974 89.927 89.887 89.848 89.807 89.768 89.724 692744 692757 692747 692747 692767 692735 692750 692766 692722 692754 692750 692789 692760 692769 692768 692767 692758 692763 692775 692775 692776 692781 692789 692780 692791 692783 692802-0~134-0.015-0.011-0.059 0.019-0.009-0.033 0.028-0'12-0.006-0.042-0.014-0.020-0.018-0.016-0.009-0.011-0.018-0.017-0'17-0.018-0.021-0.016-0.020-0.016-0'23 0.009-0.020 0.013 0.014 0.002 0.020 0.017 0.016 0.003 0.002 0.000-0.002-0.003-0.002-0.002-0.003-0.004-0.005-0.'006-0.008-0.008-0.009-0.009-0'10 0~467 0.282 0.204 0.168 0.145~0~144 0~132 0.123 0.112 0.104 0.096 0.090 0.085 0.081 0.078 0'74 0'70 0.067 0.064 0.061 0.059 0.056 0.054 0.052 83 I I I I I I I I CONTAINMENT INTEGRATED LEAKAGE RATE TEST LEAKAGE RATE IS MEASURED USING THE ABSOLUTE METHOD AND IS COMPUTED USING THE TOTAL TIME METHOD IN STRICT ACCORDANCE.
WITH TOPICAL REPORT BN-TOP-1 (REV 1)TEST PERIOD STARTED AT 15:20 HOURS ON 6/16/92 TEST CONDUCTED FOR 8.67 HOURS FREE SPACE VOLUME OF CONTAINMENT IS 2500000 CU FT CONTAINMENT WAS PRESSURIZED TO 57.16 PSIA FITTED TOTAL TIME ILRT LEAKAGE RATE Lam UPPER LIMIT OF 95%CONFIDENCE LEVEL UCL CONTAINMENT DESIGN LEAKAGE RATE La ILRT ACCEPTANCE CRITERIA 75%La-0.010%/DAY 0.052%/DAY 0.500%/DAY 0.375%/DAY BN-TOP REDUCED DURATION ILRT TERMINATION CRITERIA-THE TREND OF THE TOTAL TIME CALCULATED LEAKAGE RATE SHALL INDICATE THAT THE MAGNITUDE OF THE LEAKAGE RATE IS TENDING TO STABILIZE AT A VALUE LESS THAN OR EQUAL TO 75%OF La.La=0.500%/DAY 75%La=0.375%/DAY Lam=-0.010%/DAY with a Negative Skew-AT THE END OF THE ILRT THE UPPER LIMIT OF THE 95%'ONFIDENCE LEVEL SHALL BE LESS THAN OR EQUAL TO 75%OF La.UCL=0.052%/DAY-THE MEAN OF THE MEASURED LEAKAGE RATES OVER THE LAST 5 HOURS OR 20 DATA SETS, WHICHEVER PROVIDES THE MOST POINTS, SHALL BE LESS THAN OR EQUAL TO 75%OF La.MEAN OF SIMPLE LEAKAGE FOR SAMPLES=-0.016%/DAY 84 I I I I I I I I I I I DESCRIPTION OF VARIABLES AVE TEMP-CONTAINMENT MEAN TEMPERATURE CALCULATED FROM VOLUMETRICALLY WEIGHTED RTD SENSOR INDICATIONS; PRESSURE-PRIMARY CONTAINMENT PRESSURE INDICATION.
VAPOR PRES-CONTAINMENT VAPOR PRESSURE CALCULATED FROM VOLUMETRICALLY WEIGHTED HUMIDITY/DEWPOINT SENSOR INDICATIONS.
LEAK SIM-SIMPLE TOTAL TIME MEASURED LEAKAGE RATE.LEAK FIT LEAKAGE RATE CALCULATED FROM FIRST ORDER REGRESSION OF SIMPLE TOTAL TIME LEAKAGE RATE DATA.954 UCL-UPPER LIMIT OF THE 954 CONFIDENCE LEVEL OF FITTED LEAKAGE RATE DATA.AIR MASS-CONTAINMENT AIR MASS.NOTES FOR TABULAR DATA-1.TABLE VALUES OF ZERO SIGNIFY THE DATA IS NOT APPLICABLE TO THE CALCULATION.
2."DELETED" SIGNIFIES THE SENSOR WAS DELETED.SENSOR VOLUME FRACTIONS TEMPERATURE SENSORS 1 to 5 6 to 10 11 to 15 16 to 20 21 to 25 26 to 30 31 to 35 36 to 40 0.026708 0.026708 0.026785 0.026785 0'26708 0.026708 0.020144" 0.020144 0.026708 0.026708 0'26785 0.026785 0'26708 0.026708 0'20144 0.020144 0.026708 0.026708 0.026785 0'26785 0.026708 0.026708, 0.020144 0 F 000000 0.026708 0.026785 0.026785 0'26708 0.026708 0'20144 0'20144 0.048409 0'26708 0.026785 0.026785 0.000000 0.026708 0.020144 0.020144 0.048409 HUMIDITY/DP SENSORS 1 to 5 0.073335 0.073335 0.073335 0.090064 0.090064 6 to 10 0.090064 0.090064 0.139913 0.139913 0.139913 NOTE: VALUE OF ZERO INDICATES A DELETED SENSOR.85
)SlG ILRT Containment Absolute Pressure 57.2 57.1 cO rm<5/I 56.9 56.8 30 34 Test Time Containment Pressure IL RT Weighted Average Temperature St.Lucie Unit 2 June 1992 Deg F 92~90 Zt 88 86 30 Test Time Average Containment TemperatUre El I I I I I I I I ILRT~A~eighted Average Vapor Pressure St.Lucie Unit 2 June 1992 ps I G 0.7 0.68 0.66 0.64 u3 c 0.62 (D 0.6 0.58 0.56 30 34 Test Time Vapor Pressure Lbs 693,400 693,200 693,000 692,800 a3 c 692 600 692,400 iLRT Ca culated Air Mass St.Lucie Unit 2 June 1992 692,200 692,000 30 34 Test Time Containment Air Moss ILRT Bn-Top Rates Relative To limits St.Lucie Unit 2 June 1992.wt.7/day 0.6 0.5 0.4 0.3 0.2 0.1 0 0~10~0~0~0~~0~~~0 F 000 F 000'00'0'0~~~~POOO 05$'0~00~~00~~~0~~0~0~~~0~~~~~~~~0~~~~~~0~~~~0~0~~~~~0~0~~0~0~0~0~0~0~~~~~~~0~0~~~~~~~(o.<)30 34.Test Time La 0.75 La Bn-Top UCL Fitted Leakage Type B8cC min path Note Type 8 8c C expected Minimum path leakage I I I I I'y k~~I I I I I I Local Sensor Deviation Effect on Air Mass Calculation Deg F 94 91 90 89 88 87 30~Os~(jss+0,~~38 RTD 13 RTD-21 RTD-22 RlD-22%Relative HurT1idity 84 82 80 78 76 74 72 Lbs 692,900 30 32 RHD-DS RH+OT 36 692,850 692,800 692'75 c 692,700 30 West Time34 1LR~TAi Mass Figure Q 91 I I I I I I I I I I LRT 2 CLRT Air mass and Fitted Lecikage Rates Pounds Mass wt.%%u o/Day 692,900 04 692,800 692,700 I 692,600 692,500 XI 692 400 28.30 t J t C I I I I 1 34 36 38 Test Time 40 0.3 0.2 0.1 (o.~)Air mass Fitted I eakage OWP%~&~0 Note rapid change in calculated mass and leakage rate when known leak of 17.79 SSCM (0.264 wt.%/Day)added at hour 37.9 l I I CLRT DATA 93 I
CLRT Data Sample Number 118 119 120 121 122 123 124 125 126 127 128'29 130 131 132 TEST TIME 38.8170 39.150 39.483 39.817 40.150 40.483 40'17 41.150 41.483 41.817 42.150 42.483 42.817 43.150 43.217 RTD DEG 86.678 86.685 86.674 86.674 86.656 86.667 86.674 86'56 86.656 86.656 86.654 86.654 86'36 86.631 86.'642 RTD DEG 87'71 87.167 87.167 87.155 87.151 87'40 87.147 87.129 87.129 87.129 87.124 87.124 87.106 87.113 87.113 RTD 3 DEG F 86'31 86.527 86.527 86'27 86.509 86.509 86'15 86'20 86.520 86.520 86.515 86'04 86.509 86.515 86'04 RTD 4 DEG F'5.965 85.960 85.971 85'71 85.953 85.953 85.960 85.953 85.953 85.953 85 949 85.949 85.942 85.949 85'49 Sample Number 118 119 120 121 122 123 124 125 126 127 128 129 130 131 132 TEST TIME 38.817 39.150 39.483 39.817 40.150 40.483 40'17 41'50 41.483 41.817 42.150 42.483 42.817 43.150 43.217 RTD DEG 85.870 85.877 85..866 85'77 85.859 85'48 85.866 85.859 85.828 85.848 85.855 85.855 85.848.85.846 85.846 RTD DEG 86'71 86.378 86.373 86'78 86'71 86.371 86.378 86.360 86.360 86.360 86.367 86.356 86.349 86.356 86.356 RTD 7 DEG F 86.515 86.510 86.510 86.510 86.492 86.492 86.499 86.492 86.492 86.481 86.488 86.479 86.472 86.488 86.479 RTD 8 DEG F 85.921 85.939 85'29 85'28 85.921 85.921 85.917 85.910 85'10 85.910 85.917 85'17 85'99 85.917 85.906 94 I I I I I I I CLRT Data Sample Number TEST TIME RTD 9 DEG F RTD 10 DEG F RTD 11 DEG F RTD 12, DEG F 118 119 120 121"122 123 124 125 126 127 128 129 130 131 132 38.817 39.150 39.483 39~817 40.150 40.483 40.817 41.150 41'83 41.817 42.150 42.483 42.817 43.150 43'17 91.429 91.370 91'17 91.285 91.236 91.193 91.146 91.097 91.063 91.010 90.974 90'31 90.882 90.846 90.835 90.776 90.740 90.686 90.643 90.605 90.679 90.675 90.540 90.497 90'62 90.439 90.396 90.358 90.320 90.320 91.268 91.221 91.179 91~136 91.087 91'33 90.998 90.948 90.904 90.872 90.837 90.794 90.754 90'18 90'18 90.867 90.820 90.763 90'14 90.674 90.631 90.573 90.535 90.504 90.461 90.423 90.371 90.320 90.284 90.284 Sample Number 118 119 120 121 122 123 124 125 126 127 128 129 130 131 132 TEST TIME 38~817 39.150 39.483 39.817 40'50 40.483 40'17 41.150 41.483 41.817 42.150 42.483 42'17 43.150 43 217 RTD 13 DEG F 91.283 91.267 91'67 91.247 91'98 91.155 91.108 91.059 90'63 90.929 90.851 90.808 90'59 90'12 90.701 RTD 14 DEG F 90.321 90.265 90.200 90'69 90'19 90.054 89.931 89.924 89'04 89'61 89.834 89.791 89,.688 89.641 89.641 RTD 15 DEG F'1.215 91.168 91.115 91'72 91.012 90.969 90.911 90.882 90.828 90.797 90.761 90.707 90.669 90.599 90.633 RTD 16 DEG F 91~059 91.012 91.035 90.935 90.940 90.908 90.893 90.855 90.801 90.770 90.743 90.700 90.608 90.572 90.572 95 I I I I I I I I CLRT Data Sample Number 118 119 120 121 122 123 124 125 126 127 128 129 130 131 132 TEST TIME 38.817 39.150 39.483 39'17 40'50 40.483 40.817 41.150 41.483 41.817 42.150 42.483 42.817 43.150 43'17 RTD 17 DEG F 90.594 90.547 90.504 90.462 90.433 90.433 90.354 90.325 90.271 90.239 90.192 90.149 90.154 90.118 90.127 RTD 18 DEG F 91.110 91.063 91.021 90.967 90.906 90.864 90'17 90.768 90.725 90.705 90.678 90.635 90.586 90.562 90.55 RTD 19 DEG F 90.566 90.550 90'13 90.454 90.404 90.373 90.337 90.297 90.297 90.254 90'07 90.176 90.095 90.079 90.068 RTD 20 DEG F Deleted Deleted Deleted Deleted Deleted Deleted Deleted Deleted Deleted Deleted Deleted Deleted Deleted Deleted Deleted Sample Number 118 119 120 121 122 123 124 125 126 127 128 129 130 131 132 TEST TIME 38.817 39 150 39.483 39'17 40'50 40.483 40.817 41.150 41.483 41.817 42.150 42.483 42'17 43.150 43'17 RTD 21 DEG F 88.849 88.840 88.813 88.814 88.796 88.764 88.764 88.782 88.753 88.753 88.771 88.722 88.760 88.749 88.749 RTD 22 DEG F 90'69 90.326 90.295 90.279 90.252 90.230 90.198 90.174 90.145 90'22 90.066 90.049 90.044 90.013 90.013 RTD 23 DEG F 90.371 90.339 90.305 90.281 90.252 90.221 90.189 90.162 90 124 90'04 90.100 90.059 90.035 90.003 90.003 RTD 24 DEG F 89.946 89.818 89.742 89.675 89.626 89.583 89.518 89.482 89.453 89.433 89.417 89.390 89.386 89.352 89.352 96
CLRT Data Sample Number 118 119 120 121 122 123 124 125 126 127 128 129 130 131 132 TEST TIME 38.817 39.150 39.483 39.817 40.150 40'83 40.817 41.150 41.483 41.817 42.150 42.483 42.817 43.150 43'17 RTD 25 DEG F 90.979 90.927 90.882 90.847 90.786 90.744 90.690 90.643 90.605 90.562 90.526 90.477 90.450 90.408 90.397 RTD 26 DEG F 90.208 90.175 90.154 90'27 90.100 90.067 90.035 90.020 89.981 89.961 89.934 89.907 89.880 89.849 89.849 RTD 27 DEG F 87.906 87.830 87.797 87.762 87.745 87.702 87.617 87.601 87.521 87.476 87.463 87.425 87'98 87.355 87.344 RTD 28 DEG F 89.794 89.772 89.772 89.747 89.729 89.687 89.655 89.662 89.602 89.579 89.575 89.548 89.521 89.501 89.501 Sample Number 118 119 120 121 122 123 124 125 126 127 128 129 130 131 132 TEST TIME 38.817 39.150 39.483 39'17 40.150 40.483 40.817 41.150 41.483 41.817 42.150 42.483 42.817 43.150 43.217 RTD 29 DEG F 90.826 90.775 90.721 90.663 90.602 90.537 90.494 90.459 90.409 90.344 90.320 90.281 90.223 90.181 90.201 RTD 30 DEG F 90.839 90.796 90.742 90.704 90.646 90.601 90.559 90.523 90.473 90.419 90.384 90'34 90.298 90.265 90.256 RTD 31 DEG F 89.405'9.330 89.287 89.229 89.191 89.160 89'28 89.082 89.041 89'21 88.974 88.945 88'13 88.706 88.695 RTD 32 DEG F 91'153 91.056 91.003 90.978 90.917 90.863 90.863 90.794 90.767 90.702 90.677 90.617 90.592 90.547 90.538 97 CLRT Data Sample Number 118 119 120 121 122 123 124 125 126 127 128 129 130 131'32 TEST TIME 38~817 39.150 39.483 39'17 40.150 40.483 40.817 41'50 41.483 41.817 42.150 42.483 42~817 43.150 43'17 RTD 33 DEG F 91.297 91.266 91.212 91.111 91.019 90.955 90.890 90.854 90.901 90.836 90.769 90.719 90.692 90.630 90.618 RTD 34 DEG F 91.272 91'07 91.153 91.129 91.057 91.034 90.992 90.944 90.895 90.852 90.805 90.767 90~731 90.709 90.688 RTD 35 DEG F 89.832 89.778 89.639 89.580 89 520 89.435 89.423 89.356 89.276 89.222 89'52 89'29 89.002 88.982 88'71 RTD 36 DEG F 90.898 90.833 90.802 90.755 90.705 90.672 90.618 90.571 90.533 90.501 90'54 90'14 90.378 90.335 90.324 Sample Number 118 119 120 121 122 123 124 125 126 127 128 129 130 131 132 TEST TIME 38'17 39.150 39'83 39'17 40.150 40.483 40'17 41'50 41.483 41 817 42.150 42.483 42.817 43.150 43'17 RTD 37 DEG F 91.079 91.025 90.983 90.947 90'06 90.864 90.810 90.785 90.725 90.694 90'58 90.629 90.593 90'50 90.550 RTD 38 DEG F Deleted Deleted Deleted Deleted Deleted Deleted Deleted Deleted Deleted Deleted Deleted Deleted Deleted Deleted Deleted RTD 39 DEG'89.486 89.432 89.390 89.354 89'05 89'62 89'08 89.184 89'32 89.101 89.054 89.016 88.989 88.946 88.946 RTD 40 DEG F 90.738 90.702 90.649 90.606 90.557 90.492 90.456 90.418 90.364 90.322 90.-283 90.252 90'14 90.187 90'78 98 I I I I I I CLRT Data Sample Number 118 119 120 121 122 123 124 125 126 127 128 129 130 131 132 TEST TIME 38.817 39.150 39.483 39'17 40.150 40.483 40.817 41.150--41.483 41.817 42.150 42.483 42.817 43.150 43.217 RHD 1 RH 62.01 62.19 62.35 62.53 62.73 62.92 63.08 63.28 63.42 63.64 63.76 63.95 64'4 64.38 64.42 RHD 2 RH 71~04 71.13 71.27 71.39 71.52 71.66 71.75 71~89 71.98 72.11 72.23 72'3 72.46 72.67 72.70 RHD 3 RH 70.78 70.89 71'4 71'1 71.37 71.50 71.67 71.88 71.96 72'2 72.22 72.37 72.54 72.77 72'6 RHD 4 RH 80.33 80.39 80.13 80.30 80.07 80.12 80.11 79.89 79.83 79.90 79.81 79.48.79.73 79.56 79.65 Sample Number 118 119 120 121 122 123 124 125 126 127 128 129 130 131 132 TEST TIME 38.817 39.150.39.483 39 817 40.150 40'83 40.817 41.150 41.483 41.817 42.150 42.483 42.817 43'50 43'17 RHD 5 RH 83.33 83.29 83'7 83.24 83.22 83.12 83.02 82.92 82.78 82.69 82.55 82.43 82.39 82.50 82.52 RHD 6 O'H 79.48 79.45 79.47 79.37 79.34 79.31 79.21 79.13 79.06 78.98 78.96 78.92 78'0 78.97 79.00 RHD 7 RH 78.15 78.22 78.43 78.42 78.39 78.35 78.46 78.29 78.03 77'0 77.98 78.15 77.98 78.35 78.40 RHD 8 RH 102.31 102.25 102.62 102.38 101.99 103.04 102.58 102'1 102.26 102.70 101.91 101.27 100.70 99.75 100.70 99
CLRT Data TEST TIME RHD 9 RH RHD 10 RH 38'17 39.150 39.483 39'17 40.150 40.483 40'17 41.150 41.483 41.817 42.150 42.483 42.817 43.150 43'17 102.6 102.61 102.63 102.66 102.70 102.79 102.76 102.76 102.82 102.89 , 102.87 102.91 102.87 102.89 102.92 101.19 101.29 101-.31 101.47 101.44'01.41 101.46 101.47 101.63 101.49 101.80 101.43 101.53 101.69 101'1 100
CLRT Data Sample Number 118 119 120 121 122 123 124 125 126 127 128 129 130 131 132 TEST TIME 38.817 39.150 39.483 39'17 40'50 40.483 40.817 41'50 41.483 41.817 42.150 42.483 42.817 43.150 43.217 VAPOR PRESSURE PSIA 0.6068 0.6062 0.6060 0.6054 0.6042 0.6048 0.6038 0.6027 0.6020 0.6018 0.6007 0.5989 0.5978 0.5970 0'981 CONT.PRESSURE PSIA 57.000 56.994 56.987 56.981 56.975 56.969 56.963 56.957 56.951 56.945 56'40 56.934 56.928 56.923 56.922 , AIR MASS 692753 692734 692694 692668 692657 692615 692595 692574 692552 692512 692502 692491 692471 692455 692433 LEAK FIT 4'/DAY 0'152 0.2845 0.2924 0.2888 0.2827 0.2763 0.2787 0.2743 0.2666 0.2600 0.2534 0.2529 101
FITTED TOTAL TIME ILRT LEAKAGE RATE Lam CONTAINMENT DESIGN LEAKAGE RATE La SUPERIMPOSED CLRT LEAKAGE RATE Lo FITTED CLRT TOTAL TIME LEAKAGE RATE Lc-0.010 4/DAY 0.500 4'DAY 0.264 4/DAY 0.253 4'DAY Lo+Lam-La/4<=Lc<=Lo+Lam+La/4 0.264+-0.010-0.125<=0.253<=0.264+-0.010+0.125 0.129<=0.253<=0.379 102 I I I I I CLRT Containment Abso ute Pressure St.Lucie Unit 2 1992 PslG 57.'i 57.05 l C: O CA 56.95 56.9 38 40 4't Test Time Containment Absolute Pressure psia 0.615 CLRT Weighted Vapor PressUre St.Lucie Unit 2 June 1992 0.61 0.605 0.6 0.595 0.59 0.585 38 40 41 Test Time Vapor Pressure I I I I CLRT Weighted Average Temperature St.Lucie Unit 2 June 1992 Deg F 90 89.8 89.6 89A Z)89.2 O Q 89 88.8 88.6 40 41 Test Time Containment Average Temperature I I I I I I Lbs 692,800 692,750 692,700 692,650 692,600 692,550 692,500 692,450 692 400 38 CLRT CalcUlated Air Mass St.Lucie Unif 2 June 1992 40 41 Test Time Air Mass I I I I I I I I CLRT Bn-Top Rates Relative to Limits St.Lucie Unit 2 June 1992 wt.r./Day Oo5 0.4 0.3%%%%%%%%%aaaa
%%%%%%%%%%%%%%
%%%%%%%%%%%%%%%%%%%
%%%%aaa aaa%a%@a%a@a%a%~aa Oo2 0.1~oooosoo~~~~so~ooooo Qo~~~~~oQoo~~oo~oOooo~~~oQo~oooo+sos~~ooQooo~oooQo~~~~o Qo~ooo~oQo~~oooo'os~ooQo~~~~~oQo~~oosOooooo~o(iP~~s~~0 38 40 41 Test Time CLRT~Up er Limit Fitted l eqkage Rate aaa CLRT Lovter Limit~oooooQo bassos I I I I I I I I APPENDIX C LOCAL LEAKAGE RATE TESTING CONDUCTED SINCE 1989 108 I I I I I I TYPE B TESTING BETWEEN REFUELING OUTAGES SINCE 1989 REFUELING DESCRIPTION PERSONNEL AIR LOCK EMERGENCY ESCAPE HATCH DATE 09-11-89 02-20-90 08/20/90 11-17-90 05-07-91 10-31-91 06-11-92 09-11-89 02-20-90 08-20-90 02-12-91 08-07-91 06-06-92 AS FOUND SCCM 46000 20000 20000 20000 70000 57000 22000 3000 160 3000 2000 3000 2000 AS LEFT SCCM REMARKS 3000 160 3000 2000, 3000 2000 6500 See Section VI 20000 20000 20000 37000 See Section VI 22000 See Section VI 17000 See Section VI Maintenance Hatch 01-12-90 20 20 109 TYPE C TESTING BETWEEN REFUELING OUTAGES SINCE 1989 REFUELING DESCRIPTION DATE AS FOUND AS LEFT SCCM SCCM REMARKS MAIN PURGE VALVES P-10 EXHAUST 06-05-89 08-30-89 11-28-89 01-05-90 02-16-90 03-29-90 07-08-90 10-01-90 11-12-90 01-17-91 04-03-91 10-09-91 04-21-92 06-13-92 3, 171, 840 20 908,970 2,500 122,000 60,000 2200 10,000 1500 3000 17'2800 4500 800 200 20 400 2500 400 400 2200 10,000 1500 3000 17.9 2800 4500 800 See Section VI See Section VI See Section VI See Section VI P-11 INLET 06-05-89 08-30-89 11-28-89 02-15-90 08-15-90 10-01-90 01-17-91 07-01-91 01-07-92 04-22-92 06-11-92 20 20 20 20 20 20 9000 300 600 110 200 20000 20 20 20 20 20 20 9000 300 20000 600 200
TYPE C TESTING BETWEEN REFUELING OUTAGES SINCE 1989 REFUELING DESCRIPTION DATE AS FOUND SCCM AS LEFT SCCM REMIGES HYDROGEN PURGE VALVES 06-06-89 P-56 INLET BYPASS LEAKAGE 08-28-89 11-27-89 02-21-90 05-16-90 08-15-90 11-20-90 02-07-91 05-22-91 08-06-91 11-08-91 02-04-92 06-13-92 HYDROGEN PURGE VALVES 06-09-89 P-57 EXHAUST BYPASS LEAKAGE 08-28-89 400 250 700 820 880 800 5,000 8,400 9,600 10,900 20,000 20,000 600 20 20 400 250 700 820 880 800 5,000 8,400 9,600 10,900 20i000 20,000 600 20 20 11-27-89 02-21-90 05-16-90 08-15-90 11-07-90 02-07-91 20 20 20 20 20 20 20 20 20 20 20 20 05-22-91 130 130 08-06-91 11-08-91 02-04-92 06-07-92 100 20 300 20 100 20 300 20 111 I I I I I I I I I I I TYPE C TESTING BETWEEN REFUELING OUTAGES SINCE 1989 REFUELING DESCRIPTION DATE AS FOUND AS LEFT SCCM SCCM REMAMCS P-48A H~Sample 08-22-89 20 20 Replace FSE-27-10 P-26 Letdown 01-06-90 55 25 Repack V2516 112 REFUELIHG OUTAGE TYPE 8 TESTING SINCE 1989 REFUEL IHG 1990 REFUELING PEH.HO.TYPE SERVICE VALVE HO.DATE AS FOUND SCCN NIH.PATH AS LEFT SCCN NIH.PATH AS FOUND AS LEFT SCCN SCCN NAX.PATH NAX.PATH RENARKS 25 50 HAIN STEAN BELL 2A HAIN STEAN BELL 28 FEEDNATER BELL 2A FEEDNATER BELL 2B FUEL TRAHS BELL FUEL TRANS TUBE OUTAGE AUX PEN NAINT HATCH TAP¹1 TAP¹2 TAP¹1 TAP¹2 TAP¹1 TAP¹2 TAP¹1 TAP¹2 TAP¹1 FLANGE 0 RIHG BLANK FLANGES GASKET INTER-SPACE 10.03.90 10-03-90 10-03-90 10-03-90 10.12-90 10-04.90 11-09-87 10-01-90 20 35 20 20 20 20 20 20 20 35 20 20 20 90 20 20 20 35 20 20 20 20 20 20 20 35 20 20 20 90 20 20 A-1 THRU E-10 ELEC.PEN.NA 09 29-87 6125 6195 6125 6195 TOTAL TYPE B LEAKAGE (SCCN)6300 6300 6370 113 I I I I I I I E C TESTING EL ING E FUELING SINCE OUTAGE TYP 1989 REFU 1990 REFUEL ING till*1***PEH.NO.llltltlll*111111*llllltl**tliltllllllt*
VALVE HO.TYPE SERVICE DATE 1****11*l*11*t**1***
AS FOUND AS LEFT SCCH SCQI HIH.PATH HIN.PATH~llllltt1111111111**
111111111 AS LEFT SCCH HAX.PATH 1*****i***11*11*it*
AS FOUND SCQI HAX.PATH*llttl**1*
REHARKS**********1 1*1 PRIHARY HAKEUP MATER 8 STATION AIR 9 IHSTRUHEHT AIR V-15-328 HCV-15-1 HCV.18.2 V-18-1270 SH-18-797 V-18.195 HCV-18-1 10.03-90 10-1.90 11.03-90 20 1000 270 20 1000 270 3000 4&00 600 3000 BYPASS 4800 BYPASS 600 BYPASS 14 HITROGEH SUPPLY V.6792 V.6741 10-12-90 20 20 35.7 35+7 BYPASS 23 RCP COOL IHG 24 RCP COOLING 26 LETDOMH LINE 2&A SIT SAHPLE 288 HOT LEG SAHPLE 29A PRESS SAHPLE 298 PRESS SAHPLE HCV.14-1 HCV.14.7 HCV-14.2 HCV.14.6 V-2516 V-2522 I-SE-05.1A I SE.05.18 I SE-05-1C I-SE 05 1D I-SE 05-1E V.5200 V.5203 V.5201 V.5204 V-5202 V-5205 10.26-90 10-26.90 11-08.90 10.10.90 10-05.90 10-08-90 10 05-90 20 20 20 20 20 20 20 20 20 20 20 20 20 20 20 20 200 80 30 55 200 20 BYPASS 20 BYPASS 1500 BYPASS 80 BYPASS 30 BYPASS 55 BYPASS 200 BYPASS 31 RCB VENT HEADER V-6718 V.6750 10-11-90 155 155 200 200 BYPASS 41 SIT TEST LINE I-SE-03 2A 8 I.SE.03.28 V-3463 10.05-90 300 300 300 300 BYPASS 42 CONT SNIP 43 RDT PNIP SUCT RCP BLEED-OFF FUEL POOL CLEANUP FUEL POOL CLEANUP LCV-07 11A LCV.07.118 V-6341 V.6342 V 2524 V-2505 V-7189 V.7206 V-7188 V-7170 10.05-90 11-12.90 10 05 87 10-05-90 10.05.90 20 740 20 20 70 20 740 20 20 20 45 20000 20 100-150 45 BYPASS 20 BYPASS 100 BYPASS 150 BYPASS 200 BYPASS 114 I I I I I I I I I I I
REFUELING OUTAGE TYPE 8 TESTING SINCE 1989 REFUEL IN 1992 REFUELING lltll*ill PEN.NO+1111111111*111111*1111***11*11**11**111 1*1111*11*
AS FOUND SCCH HIN.PATH***1*11111 VALVE NO.TYPE SERVICE DATE tlllt**11*t ll*lltt11111111111*11*11*111 1111111111 AS LEFT SCCN HIN.PATH*1111*1***
HAIN STEAN BELL 2A HAIN STEAN BELL 28 FEEDNATER BELL 2A FEEDNATER BELL 28 TAP¹1 TAP¹2 TAP¹1 TAP¹2 TAP¹1 TAP¹2 TAP¹1 TAP¹2 5-22-92 5-22.92 5-22-92 5-22-92 20 20 20 20 20 20 20 20 20 20 20 20 20 20 20 20 25 FUEL TRANS BELL TAP¹1 5-22-92 20 20 20 20 50 A-1 THRU E-10 FUEL TRANS TUBE OUTAGE AUX PEN HAINT HATCH ELEC.PEN.I FLANGE O.RING BLANK FLANGES GASKET INTER-SPACE NA 4-28-92 4-23.92 4-22-92 4-28-92 20 38 20 20 20 20 7800 20 20 7800 20 20 20 7800 TOTAL TYPE 8 LEAKAGE 8015 116 I I I I I I I I I.I REFUELIHG OUI'AGE TYPE C TESTING SINCE 1989 REFUEL IN 1992 REFUELING**t**t*****ttt*t*ttt*t*tt*ttttt*********tttttt**ttt*ttt*tt*tttt*tt*tt**t*tttt**l**ttt*t*1**tt*ttttttt PEH.HO.TYPE SERVICE VALVE NO.DATE AS FOUND SCCN NIH.PATH AS LEFT AS FOUND SCCH SCCN NIN.PATH HAX.PATH AS LEFT SCCH HAX.PATH*****tt*REHARKS tt*****tt*ttt*
PRIHARY HAKEUP HATER V-15-328 HCV 15 1 4-27.92 400 400 2800 2800 BYPASS STATIOH AIR SH.18-797 HCV-18.2 V-18-1270 6-13-92 1300 1300 16,000 1300 BYPASS 14 24 26 288 29A 298 31 41 42 43 47 IHSTRQLEHT AIR NITROGEN SUPPLY RCP COOLING RCP COOLING LETDOHN LINE SIT SAHPLE HOT LEG SAHPLE PRESS SANPLE PRESS SANPLE RCB VENT HEADER SIT TEST LINE CONT SINP RDT PUHP SUCT RCP BLEED-OFF FUEL POOL CLEANUP FUEL POOL CLEANUP V.18.195 HCV-18-1 V-6792 V-6741 HCV 14-1 HCV 14-7 HCV.14-2 HCV-14-6 V-2516 V.2522 I-SE.05.1A I-SE 05-18 I-SE-05-1C I-SE-05-1D I-SE 05 1E V-5200 V-5203 V-5201 V.5204 V-5202 V-5205 V-6718 V-6750 I-SE-03-2A 8 I-SE-03-2$
V.3463 LCV-07-11A LCV.07-118 V-6341 V-6342 V-2524 V-2505 V-7189 V.7206 V-7188 V.7170 6.11.92 4-25-92 5-1-92 5-19-92 6.12.92 6-14-92 4-24-92'-12-92 4-27-92 4-27-92 4-27-92 4-27-92 5-21-92 5-20-92 4-25.92 4-25.92 650 20 20 20 20 40 20 20 20 20 20 20 350 20 20 20 650 20 20 20 50 20 20 20 20 20 20 20 350 20 20 20 900 50 20 20 185 20 500 20 20 400 20 20 20 900 50 20 20 20 500 20 20 70 400 20 20 110 BYPASS BYPASS BYPASS BYPASS BYPASS BYPASS BYPASS BYPASS BYPASS BYPASS BYPASS BYPASS BYPASS BYPASS BYPASS BYPASS 117
REFUELIHG OUTAGE TYPE C TESTING SINCE 1989 REFUELIHG 1992 R FUELIHG 111111111 AS LEFT SCCH HAX.PATH**1111**1 80 11***1************11 AS FOUND AS LEFT SCCH SCCH HIN.PATH HIN.PATH 11111111111111111111 20 20 111*11111 PEN.NO.111*111111 AS FDUHD SCCH HAX.PATH*111*1*1**
80 F 11111111111111*111111111111*llllll*111 VALVE NO.TYPE SERVICE DATE 11111111 111111*llllllllll 1 1 1*1 1 1 1 1 1 1 48A H2 SAHPLE FSE-27-8 FSE-27-9 FSE-27-10 FSE.27.11 FSE-27.15 5-5.92 1111111*11*111 REHARKS 1***111*1*1**1 488 H2 SAHPLE 51A H2 SAHPLE 51$H2 SAHPLE V-27-101 FSE-27-16 FSE.27.12 FSE 27-13 FSE-27-14 FSE-27-18 V.27-102 V-27-17 5-5.92 5-5.92 5-5-92 20 20 20 20 20 20 3000 60.500 3000 500 528 52C 52E 67 RCB ATHOS RAD HOHITORS RCB ATHOS RAD HOI I TORS RCB ATHOS RAD HONITORS ILRT TEST COHNECTIOH ILRT TEST CNNECT I ON ILRT TEST CNHECT IOI COHTAINHENT VACUUH RELIEF COHTAIHHENT VAml RELIEF FCV-26-1 FCV-26-2 FCV-26-3 FCV-26-4 FCV-26-5 FCV-26-6 V-00140 V-00143 V-00139 V-00144 V.00101 V-25-20 FCV-25.7 V-25-21 FCV.25.8 5-1-92 5-1-92 5-1-92 5-6-92 5-6-92 04-24-92 6-6-92 04-24-92 950 110 20 100 20 900 40 20 950 110 20 100 20 900 40 20 1200 130 100 1800 350 200 1200'30 300 100 1800 20 200 BYPASS BYPASS BYPASS BYPASS BYPASS BYPASS TOTAL TYPE C LEAKAGE 5240 5240 29,985 14,030 TOTAL BYPASS TYPE LEAKAGE 5100 5100 25,795 25,465 118 I I I I I I I VI.LOCAL LEAKAGE RATE PROBLEMS SINCE LAST ILRT A.Main Purge Exhaust (FCV-25-5)
During routine testing on June 5, 1989 FCV 25 5 (48" butterfly valve on main purge exhaust P-10)was found to be leaking in excess of the Technical Specification limits, see LERs 389-89-004, 389-89-009, and 389-89-009 Revl.Improper adjustment of valve closure stop was.originally thought to be the cause of the excessive leakage.On November 28, 1989 the valve again failed LLRT.After adjusting the valve closure stop again to stop leakage the testing frequency was increased.
After another LLRT failure a blind flange was installed per Engineering Safety Evaluation JP¹PSL-SEMJ 039.Because the flange is outside the shield building this makes leakage from this penetration now bypass leakage, and plant procedures were changed to correctly account for the Technical Specification limit on bypass leakage.During the 1990 refueling outage repair and root cause determination was not done due to personnel safety concerns over performing maintenance on the 48 inch.butterfly valve without a jacking device for the actuator available to hold the valve open.An Engineering Request has been submitted to make the blind flange permanent.
119 I I l I B.Personnel Air Lock Between the 1989 and 1992 refueling outage the personnel air lock exhibited high leakage during the"overall leakage test" (strong-back test)of Tech Spec 4.6.1.3.b on September 20, 1990.The air lock was repaired by replacing the outer door reach rod shaft packing.Reducing the overall leakage from 46,000 sccm to 6,500 sccm, the limit being 47,250 sccm.After successful tests on February 20, 1990, August 20, 1990, and t, November 17,1990, the personnel airlock failed the strong back test on May 7, 1991.Repairs were again made to reach rod shaft seals before the Limiting Condition for Operation (LCO)3.6.1.3 time limit was exceeded.Similar problems were experienced after the 1990 refueling on October 31, 1991.During the 1992 refueling outage (prior to the ILRT)the reach rod shafts were rebuilt and seal again replaced.120 I I I I I I I I I I I I