L-83-183, Forwards Schedule Outlining Portions of Initial Test Program That May Be Incomplete by Core Load
| ML17213B197 | |
| Person / Time | |
|---|---|
| Site: | Saint Lucie  |
| Issue date: | 03/25/1983 |
| From: | Robert E. Uhrig FLORIDA POWER & LIGHT CO. |
| To: | Eisenhut D Office of Nuclear Reactor Regulation |
| References | |
| L-83-183, NUDOCS 8303300273 | |
| Download: ML17213B197 (20) | |
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BOX 14000, JUNO BEACH, FL 3340B FLORIDAPOWER & LIGHT COMPANY March 25, 1983 L-83-183 Office of Nuclear Reactor Regulations Attention:
Mr. Darrell G. Eisenhut, Director Division of Licensing U. S. Nuclear Regulatory Commission Washington, D.C.
20555
Dear Mr. Eisenhut:
Re:
ST.
LUCIE UNIT NO.
2 DOCKET NO. 50-389 INITIALTEST PROGRAM Attached please find a
schedule outlining portions of the St.
Lucie Unit No.
2 initial test program which may. not be completed by core, load.
The attachment is arranged in matrii form and identifies the p eoperational
- test, the portion of the test
- delayed, justification for the delay and our new completion date.
If you have any questions regarding this submittal, please contact us.
Very truly yours, Robert E. Uhrig Vice President Advanced Systems and Technology REU/RJS/PPC/rms Attachment cc:
J.
P. O'Reilly, Region II Harold F. Reis, Esquire oJ 8303300273 830325 PDR ADOCK 05000389 A
PDR PEOPLE... SERVING PEOPLE
P REOP ERATIONAL TEST ABSTRACT (section) 1 PORTION DELAYED JUSTIFICATION TEST COt1PLET ION 2-2000083 Hydrogen Recombiners 14.2.12.1.3I T.S 3.6.4.2 See Note (1)
The hydrogen recombiners are only required during modes 1
& 2 Prior to initial criticality 2-2000088 Containment Hydrogen Sample Functional Test 14.2.12.1.3J T.S 3.6.4.1 Entire Test This system monitors the buildup of hydrogen, during power operations, in the containment.
The tech specs do not require this system until mode 2.
Prior to entering mode 2.
The purpose of these systems is to monitor and process contaminated RCS System Leakaae.
No
-contaminated leakage is expected prior to initial RCS pressurization.
During the interim period temporary sump pumps 14.2.12.1.3ft T.S 3.4.6.1 2-0010188 This test will be completed prior to initial RCS pressuriz ation after Coreload.
Reactor cavity portion.
Safeguards sump pumps will be tested.
See Note (1)
Safeguard
& Reactor Cavity Sump Pumps Test P
may be used.
No'te (1) - Testing of this system is in progress and may be completed prior to or immediately following Coreload.
Note (2) - This test/system is not safety related and is not required for Coreload by Technical Specifications.
)I
PREOPERATIONAL TEST ABSTRACT (section)
PORTION DELAYED JUSTIFICATION TEST COHPLETION 2-2000089 In Place Testing of HEPA 5 Charcoal Filters 14.2.12.1.3N T.S 3.7.7 RAB, SBVS and Containment Purge The control room emer-gency cleanup system HEPA's and charcoal train will be tested and oper-able prior to entering mode 6.
HEPA and charcoal testing will be completed prior to entering mode 4.
Prior to entering mode 4 for the initial plant heatup.
2-1130080 Loose Parts Honitor 14.2.12.1. 7B T.S 3.3.3.8 See Note (1)
This test is 90%
complete.
Prior to Coreload there i no flow in the RCS.
Tech Specs require this system to be operable in Hodes 1 5 2 only.
Prior to initial criticality.
(Hode 2) 2-0010187 Reactor Cavity Sump Leak Detector Test 14.2.12. 1. 7F T.S 3.4.6.1 See Note (1)
St. Lucie Unit 2 Techni-cal SPecifications for Reactor Coolant Leakage is applicable to modes 1,
2, 3 5 4 only. Addition-ally at this time no fis-sion products are present in the Reactor Coola ht System.
This test will be completed prior to (mode 4).
Not:e
( 1) - Testing of this system is in progress and may be completed prior to or immediately following Coreload.
Note (2)
This test/system is not safety related and is not required for Coreload by Technical Specifications.
PREOP ERATIONAL TEST ABSTRACT (section) 3 PORTION DELAYED JUSTIFICATION TEST COMPLETION 2-1200081 Incore Instrumentati 14.2.12.1. 7I T.S 3.3.3.2 Incore detecters have been installed in the UGS. The cables that are pulled and terminated have been tested.
The remaining cables will be tested prior to use of the incore system during
. the low power physics program.
This system has construc-tion problems due to the late delivery of the HI cable.
Cable resistance has been measured for thos cables installed and ter-minated.
Due to its phy-sical location (in the UGS the system is not operable prior to or during Core-load.
Tech specs do not require this,system-in food 6 or 5.
The first use of this system will be the approach to criticality.
Pri or to initi al'ri tica 1 ity 2-0510081 5 81 Liquid Haste Management 14.1.12.1.8A See Note (1)
This test verifies proper operation of the waste concentrator and liquid waste storage/transfer facilities. The waste concentrator portion of this test is in progress even though it is not used during normal plant opera-tions. Liquid waste storage/transfer facilit-ies. are presently avail-able for use.
See Note (2)
Prior to initial crit'ical ity.
Note (1) - Testing of this system is in progress and may be completed prior to or immediately following Coreload.
Note (2) - This test/system is not safety related and is not requi'red for Coreload by Technical Specification.
PREOP ERATIONAL TEST ABSTRACT (section) 4 PORTION DELAYED JUSTIFICATION TEST CO>DEPLETION'-0520080 Waste Compactor and Drumming Station 14.1.12 F 1.8D Entire Test The Solid Waste Handling System is contracted and is not available for use prior to Coreload (See FSAR 11.4)
Prior to use.
Waste compactor is not needed until after solid radioactive wastes are generated.
Prior to Initial Critical ity.
2-0620080 Circulating Water 14.2.12.1.10C measurement of System Hydraulic Gradient See Note (1)
The Unit 1 refueling outage intake canal work prohibits running of the circulating water pumps.
See Note (2)
Prior to mode l.
P REOP ERATIONAL TEST ABSTRACT (section) 5 PORTION DELAYED JUSTIFICATION TEST COMPLETION 2-1730080 Secondary Sampling Initial Startup an Functional 14.2.12.1.10J Sampling of feedwater while feed system is in operation.
The water quality will be examined prior to feeding the steam generators from the condenser.
Feedwater system is not tested until after Core-load, therefore sampling cannot be done.
See Note (2)
Prior to increasieq power above the 50K plateau.
2-1110083 2-1110080 2-1110092 Radiation Monitoring 2-1120080 Area Monitor 14.2.12.1.10L 14.2.12.1.10M See Note (1)
See Note (1)
Tables 11.5-1 and 12.3.253 of the FSAR list the Area and Process Monitors in the plant.
The monitors circled are required to be operable in Mode 6.
In paren-theses are the appropriate Tech Spec Table 8. The remainder will be tested prior to initial criticality.
Prior to initial criticality.
Note (1) - Testing of this system is in progress and may be completed prior to or immediately following Coreload.
Note (2) - This test/system is not safety related and is not required for Coreload by Technical Specifications.
TARLF 11.5-1 PROCESS AHD EFFLUFtcT RADIATIOt> Hnt>ITARS Honiiors L
~T(()
L 2'2)
Contgot Function I-I"-CC-227 1-1"-Cc-231 Close surge ck vent b)
Chemical and I
SSL Volume Control Letdoun I"-Ckc-432 'one a)
Component 2
SSL Cooling Water Pover
~gu I
Safety AC hus Honsafety Ar tus Range
( Ci/cc)
-7
-2 10 to ln
-4 4
=In co tn k<inieus Sensitivit (3) 1.3xln cpn/pci/cccsl37 1.3xln cpn/pri/ccCsl37 Typical Alarms 6
Control Set oint 1.4xlO pci/cc 2
lxln.
pci/cc At Detector 2.5 mR/hr Ill IO mR/hr I I I c)
Stean Cenrrator 2
SSI.
Ptovdo(cn
~~ 7()EL 3,3-Q Close hlnu-doun valves I-Frv-Zs,-s, s> -7>
4 -9 HnnSafety AC lux
-7
-7 IA tn Ic) 1.3xln cpn/pCi/ccCsl37 R
-5 5x In c(ci /cc I nR/hr
) ll d)
I inuid l'astr I
SSI.
I'ischarge
~. -a6h xs-I~
3"-t(kc-F19 I'Iosc t'nngalrty discharge Ac hus valves FCV-6677 X 6 V
ln' tn ln 1.3xln P
cpe/pCi/ccCs.'37
-6 4xlO pci/cc 2
5 mR/hr
( 11 e)
Gaseous Waste I
SSC Discharge
.'.vah/e 3.~-i3
-I 4
7 2"-I!8-D40 Clnsr t'ongafrty ln tn ln 4.3xln cpm/pni/ccXel33 500 pci/cc.
2 5 mR/hr
) 11 discharge Ar hus Valve V656S f)
Condenser A'ir I
SSC I"-AF.-45 Hone Ejector tlnnSafety Ac hus In-7 t, 10-2 4.3xln 7 cpe/pCi/ccXel33 3xln pCi/cc I mR/hr I 11 g)
Plant Vent 2
P-I-C
>z~h/e a.s-is tlone Safety AC hus
,ln 0 Co 10 P
-12
-7 I
to I" I
ln Cn In C
p.ax~n4 I x ln I.ln'pn/pci/"ccsl37 pm/pCi/cc1131 cpm/pci /ccye I 33
-7 lxln 7 Sxln 6 5x1 0 pCi/cc pCI/cc pCi/cc I mR/hr i ll h)
Fuel lland I inp I
P-I-C slag.
Stack
'; sahje 4i~hk= 3.3-/3 i)
ECCS Area 2
HSG Ventilation System Fxhsust 2PVF-9 Honr Pone HonSafrry AC hns gafrtv AF hns ln 0
c In I'O tn Ict I In"7 cn In 2 r.
-7
-2 ln tn ln IA to IIn I.n tn IA p-c)xnan I x ICc 2. I I n 7 4.32xin 7 Z.R4 In 1.19xln cpn/( ri/ccns 137 cpe/pli/cc1131 cpm/c(ci/ccyrl33 cpnlpri/cc cpm/Hei /cc c pe/pc'-i lcc
-7 lxln Ixln 5
lxln
'c(/cc pci/cc pCi/cc
-6 lxln 3 PCi/cc Ixln pCi/cc Ixln pci/c>>
I eR/hr 2.5 mR/hr noma I (IOOO mR/hr accident t>ot ra:
(I) ssL single stage I.iouid, sso
> single steer c'asc ons, "Fc'culci-stagr rasrnws, p-I-c:
particulate, indine and noble gas (refer to subsection
[ 5 11.5.2.1.3)
(2)
All monitors (except for e and I) are off-line type.
Incatinn indicatrr. sn>>rtr linc tat(r-off.
(3)
Sc nsitivitv listed is for counting tine and background states In a(tdirinn, nll ennitnrs ec'c'c thr srnsitivicies indicated in Subsection II>5.2 1.3.
(4)
One detector ls required for background subtracclon.
(5)
Detectors vieu the main stcam line.
TAP(F. II.S-I (Cont'd)
Monitors I'
~TI I I i) auric Acid snd I
Paete Poldup Condensate
'Tank location(7)
I"-CR-9 Control I
t'nnr power Snnnlv t'nnsafety AC hus i'ange Pinimum (II Ci/cc)
Srnsitivicv(3)
-7
-7 P
IA tn IA l.3xlO cpm/PCi/ceps l 37 Tvpical Alarms 6
Control Srt oint Ix)0 Ci/cc At Detector 2
5 mR/hr I II I )
Plant Vent (high Range Noble Cae Monitor)
I)
Atmospheric 3 (4)
Steam AurIP Exhaust HFC C-M tube t>ain Steam (5)
Treat lr t'nnr None Ponssfetv AC hiis (on sero load block)
Pon safety with unin-trrruptihlr backup IA 7 tn In2 IA'n Ig I.A tn-IO IO'o IA 4 ~ 12xlA cpm/>>Ci /cc 7
2.>>4xlA cpr/pri/cc I. I9xlA cpm/>>Ci/cc
'2 IO cpm/mR/hr
-6 Sx IA PCI/cc
-3 I,IA pci/cc I.A
> Ci/cc
-I Ixln
>ICi/cc I mR/tir normal II 20 mR/hr accident 0.25 mR/hr normal
( IOAO mP/hr accident n)
Post-Accident I
SSI.
Failed Fiirl PAR(6) m)
Laundry I
PIC 2IIVE-5 and Not Change Area None Pone tlon-safety AC gus t>on-safety IU rII I>i I'n 7
rn in 20 In to IA t
R.6xl( cpm/>>Ci/ccCs I 37 Ixl0 7cpe/uCi/I I I I3I 2 ~ lxI0 cpm/>ICi/ccXel 33 I.3xlA cpn/ppi/ccpsl31
-9 5XIA.RpCi/cc IxlO 6pCi/cc 5
IO 6 Ci/cc I.n i I/cc lmR/hr 20mR/hr Is Notes:
(I)
SSL Single Stage l.iquid, SSC
~ Single Stage
II.5.2.I.3)
I5 (2)
All monitors (except for e and I) are off-linc type (ncation indicates sample line take-off-(3)
Sensitivity listed is for counting time and background stntre.
In ad>litinn, all monitors mort thI. srnsitivities indicat>d in Snbeection II.S.2. I.3.
(4)
One detector is required for background subtraction.
(5)
Detectors view the main steam line.
(6)
Detector to view primary coolant sample linr..
SL2-FSAR TABLE 12. 3-2 AREA RADIATION MONITORS Item Detector Tag Number Honitored Area Safety Classification RD-26-1 Control Room Non-Sa fe ty 2
RD-26-3 CIAS A TS 1((bh ~~
IE 3
RD"26&
CIAS B
RD-26-5 CIAS C IE RD-26-6 CIAS D
IE RD-26-7 Spent RD-26-8 Spent 8
RD-26-9 Spent Fuel Pool A, 5 Fuel Pool 8
" 3.3-4 Fuel Pool C
~4 RD-26-10 Spent Fuel Pool 0
IE 10 RD-26-11 Spent RD-26-12 Spent Fuel Pool E
Fuel Pool F
IE 12 13 RD-26"38 Containment Post Accident A
IE RD-26"39 Containment Post Accident 8
IE 15 16
!7 n
18 19 RD-26-32 Personnel Lock Area RD-26-33 Refueling Canal Area RD-26-34 Fuel Pool Pump Area RD-26 "35 Boric Accid Precon-centrator Filter Area RD-26-36 Waste Filter Area RD-26-37 ECCS Equipment Area Non-Safety Non-Safety Non-Safety Non-Sa fe ty Non-Safety Non-Safety v
20 Q
21 22 23 RD-26-14 Charging Pump Area RD-26-15 Holdup Drain Pump Area RD-26-16 Sample Room Area Non-Safety Non-Safety Non-Safety RD-26-13 Waste Cas Compressor brea Non-Safety Range (mR/hr) 10
-10 10
-10 10
-10 10
-10 10
-10 10
-10
-I 4
10
-10
-I 4
10 "10
-I 4
10
-10 10
-10 10
-IO 10 10 10-10 10
-10
-]
4 10
-10 10
-10 10
-10 10
-10 10
-10
-I 4
10
-10
-I 4
10 "10 10
-10 10
-10 Sensitivity (mR/hr)
-2 10 10 10 10 10 10 10 10 10 10 10 10 10 10 10 10 10 10 10
-I IO 10 10 10 Accuracy (Z)
+15Z
+15X
+152
+15Z-
+152
+15X
+152
+15Z
+15X
+ I 52 iI5X
+ I 5X
+15X
+15X
+15X
+15Z
+15X
+152
+152
+15Z
+15X
+15X
+152 Ty pi ca I Ala rm Set oint (mR/hr) 1,0 10 10 10 10 10 10 10 10 10 10 30 30 10 IO 10 IO 80 10 40 40 20 Monitor Locatron RAB el 67.5'AB el 25'AB el 25'AB el 25'AB el 25 FHB el 68'HB el 68'HB el 68'HB el 68'HB el 68'HB el 68'AB el 64.5 RAB el 67.5 C~n)~ident FHB el 68'etector Location RAB el 67.5 Containment el 90'ontainment el 90'ontainment el 90'ontainment el 90'HB el 61
'HB el 61'HB el 61
'HB el 61
'HB el 61'HB el 61'elou FHB roof at el 85'bove RAB roof at el 85'ontainment el 35.5'HB el 67.5'AB el 5'AB el 5'AB el 5'AB el 10'AB RAB el 5.5'AB el 4.5'AB el 25'AB el 5'AB el 5.5'AB el 9.5'AB el 10.
5'AB el 4.5'AB el 26'HB el 25.5'HB el 25'
SL2-FSAR TABLE 12.3-2 (Cont'd)
Detector Tsg Iten Number Safety Honitored brea Classification Range (mR/hr)
Sens itivity (nR/hr)
Accuracy (Z)
Typical Alarm Set oint (mR/hr)
Honitor Location Detector Location 24 RD-26-17 Ion Exchanger Corridor Hon-Safety 26 RD-26-20 Purification Filter Area Non-Safety 25 RD-26-18 Flash Tank Pumps Corridor Non-Safety 10
-10 IO
-10 IO
-10 10 10 10
+152
+15Z
+15Z 20 20 RAS el 25'AB el 25'AB el 25'AB el 26'AB el 26<
RAB el 35.5'7 RD-26"21 Spent Resin Corridor brea Non-Safety
-I 4
10
-10
-I 10
IIV 30 RD-26-24 31 RD-26-25 I
32 RD-26-26 HVAC Roon brea Chemical Drain Pump brea Volume Control Tank Corridor
'8 RD-26-22 ECCS Equipment brea 29 RD-26-23 Decontanination Ares Hon-Safety Non-Safety Non-Safety Non-Safety Non-Safety
-I 4
10
-IO 10
-10 10
-10 10
-10 10
-10 10' 10 10 10 10
+152
+15X
+I 5Z
+15X
+152 20 IO 10 20 20 RAB el 5'AB el 5'AB el 48'AB el 5'AB el 25'AB el 4'AS el 26'AB el 49'AB el 12'AB el 26'3 RD"26-27 34 RD-26-28 35 RD-26-29 36 RD-26-30 Borononeter Enclosure Ares Nev Fuel Storage Area V:a. iajjr* k3-Q berate Haste torage Area Boric Acid Concentrator Ares Non-Safety Non-Safety Hon-Safety Non-Safety 10
-10 10
-10 10
-10 10
-10 10 10 10 10
+15X
+15X
+ I SZ
+15Z 10 10 10 10 RAB el 26'AB el 26'AB el 5'AB el 5'AB el 25'AB el 28'HB el 67.5'HB el 53.5' O
38 RD-26-2 Operating Deck brea 37 RD-26-31 Fuel Pool Filter Area Non-Safety Non-Safety
-I 4
10
-10 4
10 "IO 10 10
+ISZ
+152 20 10 FHB el 25'ontainment el 35.5'HB el 26'ontainnent el 85'a 0
39 RD-26"19 40 RD-26-40 41 RD-26-41 Notes Drunming Station brea Containment High Range Containment High Range Non-Safety IE IE 10
-10 1.0 -10 I.O -10 10 10 10
+15Z
+I 5X
+15X 20 10 10 RAS el 25'AB el 65'AB el 65'AB el 25 RCS el 90'CB el 90'I)
Canna sensitive detector.
Heasurement is in Rad/hr SL2-FSAR TABLE 12.3-3 AIRBORNE RADIATION HONITORS t4 I
~4 Honitor/Location of Sam le Pt.
Containment Atmosphere, multiple sample Control Room Outside Air Intake~, w~hh pp-g ECCS Area Vents Hob ile Particulate Iodine Noble Cas B-Yscint u/
bkgrd Subtraction Hoble Cas Particulate Iodine Noble Cas Number of Channels Safety Classification lE 1E lE IE 1E Non-Safety Hon-Safety Non-Safety Range (sci/cc)
IO "-ln
'O
'0-iO 5
10-7 10-2 IO-B-IO-3 10
-10 10
-10 lo-10-lo-5 lo '-lo 2 Sensitivity
~('I
)
10 12 10 IO
'O-B ioy 10 12 IO io
'ccuracy
~(n Typical Alar)s
~)*c ~e(
')
)
10 io'O' x 10 6
5 x 10 Variable Variable Variable 0
9o n
0
PREOPERATIONAL TEST ABSTRACT (Section)
PORTION DELAYED
-- JUSTIFICATION TEST COMPLETION 2-0540081 Boric Acid Concentrators' 14.2.12.1.100 Actual Concentration of Boron See Note (1)
The boric acid concentra-tors have been tested to the extent possible using unborated water.
When heat tracing is completed final testing shall begin See Note (2)
Prior to initial
~ criticality.
2-0950080 Boric Acid Heat Tracing 14.2.12.1.10P T.S 3.1.2.1 See Note (1)
CVCS Tech Specs require a
certain flow path.to be operable in Modes 5
& 6.
(See Tech Spec 3.1.2.1)
The heat tracing associated with these flow paths will be tested prior to Core-load.
WASTE MANAGEMENT The heat tracing associated with waste management will be tested prior to initial criticality.
Prior to Mode 4.
Prior to initial criticality.
2-0950086 Essential Lighting Systems 14.2.12.1.5H AC Portion.
DC survey in control room is complete.
Lighting is essentially complete.
It is used for emergency shutdown.
It will not be needed until initial critical-ity.
Prior to initia criticality.
Note (1) - Testing of this system is in progress and may be completed prior to or immediately following Coreload.
Note (2) - This test/system is not safety related and is not required for Coreload by Technical Specifications.
PREOP ERATIONAL TEST ABSTRACT (Section) 12 PORTION DELAYED
'USTIFICATION TEST COMPLETION, 2-0540080 Boron Recovery System Function Test 14.2.12.1.100 See Note (1)
Boron recovery testing is approximately 90Ã com-pleted.
The flash tank portion of this test is the only section not completed.
See Note (2)
Prior to initial
'criticality.
2-3400088 Miscellaneous Lifting-Equipment 14.2.12.1.10R T.S 3.9.6 See No'te (1)
Refueling machine (Ma-nipulator) will be tested in accordance with Tech-..
nical Specifications prior to moving fuel, Spent Fuel Cask Crane is not needed until after the first refueling at the earliest.
Miscel-laneous cranes and hoists are put into service to support operations and maintenance as required.
Prior to use.
2-1600080 Fuel Handling in Building Ventilation Functional 14.2.12.1.11C Obtaining negative pres-sure on spent fuel area with Shield Building Ventilation system.
See Note (1)
This test is 90Ã complete.
The remaining portion of the test obtains a nega-tive pressure in spent fuel area.
Only new fuel is presently stored in the spent fuel racks.
Prior to storage of spent fuel in the fuel handling building.
Note (1) - Testing of this system is in progress and may be completed prior to or immediately following Coreload.
Note (2) -'his test/system is not safety related and is not required for Coreload by Technical Specifications.,
PREOPERATIONAL TEST ABSTRACT (Section) 13 PORTION DELAYED JUSTIFICATION TEST COMPLETION'-2000085B Initial Fan Operation and HVAC Balancing 2-1900080 Auxiliary Building Ventilation 14.2.12.1.11F T.S 3.7.8 Final Balancing of the RAB and ECCS area Control Room and containment balancing is complete.
Initial fan operation for the RAB and ECCS areas are complete.
(i.e. 2-2000085A Preliminary balancing in the RAB and ECCS areas are also complete.
These systems are not required till mode 4 of the Tech Specs.
Prior to entering mode 4.
2-2000090 RAB Leak Test 14.2.12.1.11F Smoke Leak Test of RAB (Entire Test)
This test ensures air flows in the RAB from less potentially contaminated areas to more potentially contaminated areas.
Fis-sion product will not be potentially present in the RAB till after initial criticality Prior to criti ity 2-2000082 Shield Building Ventilation Functional Test 14.2.12.1.11G T.S 3.6.6.1 Final Balancing See Note (1)
This system has been functionally tested and preliminary balancing is completed.
This system is not required by Tech Specs since no irradiated fuel is present.
(Leak test is complete)
Prior to entering mode 4.
Note (1)
Testing of this system is in progress and may be completed prior to or immediately following Coreload.
Note (2) - This test/system is not safety related and is not required for Coreload by Technical Specifications.
14 14.2.12.4N OBJECTIVE Baseline Leak Test of Systems Outside Containment Processing Primary Coolant To accumulate preoperational leak rates on systems that contain primary coolant in a post accident or transient condition to be used as a comparison in later checks.
P ERBEII TES The LPSI, HPSI, Containment Spray and Primary Sampling Systems have all open inte-grity items dealing with valves, flanges, and leaky instrument connections cleared and all temporary strainers and test equipment removed.
TEST METHOD With systems operating at normal pressure the piping and equipment is walked down and all unrepairable leakage record.
ACCEPTANCE CRITERIA None.
Baseline data is recorded.