ML18019A804
| ML18019A804 | |
| Person / Time | |
|---|---|
| Site: | Harris  |
| Issue date: | 05/02/1986 |
| From: | Zimmerman S CAROLINA POWER & LIGHT CO. |
| To: | Harold Denton Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 8605060226 | |
| Download: ML18019A804 (20) | |
Text
RE(:ULAT INFORVATION DISTR IBUTIO YSTEV (R IDB)
ACCESSION NBR: 8605060226 DOC. DATE: 86/05/02 NOTARIZED:
NO DOCKET I FACIL:50-400 Shearon Harris Nuclear Power Plant>
Unit i. Carolina 05000400 AUTH. NANE AUTHOR AFFXLIATION ZXNNERNAN>S.
Carolina Power 5 Light Co.
RECIP. NANE, RECIPIENT AFFILIATION DENTON>H. R.
Office of Nuclear Reactor Regulation>
Director (post 851125
SUBJECT:
Forwards response to 860106 request for addi info re description of initial test program in facility FSAR.
Recommended editorial changes to test prerequisite will be incor orated in future FSAR amend.
p DXSTRIBUTION CODE:
B001D COPXEB RECEIVED: LTR ENCL SIZE:
TITLE: Licensing Submittal:
PSAR/FBAR Amdts 5 Related Correspondence NOTES: Application for permit renewal filed.
'05000400 RECIPIENT COPIEB ID CODE/NANE LTTR ENCL PWR-A ADTS PWR-A EICBB 2
2 PWR-A PD2 LA 1
1 BUCKLEY>B 01, 2
2 PWR-A RBB 1
1 RECIPIENT ID CODEJNANE PWR-A EB PWR-A FOB PWR-A PD2 PD PWR-A PSB COPIES LTTR ENCL 1
1 1
1 1
1 INTERNAL: ADN/LFNB IE FILE IE/DGAVT/GAB 21 NRR PWR-A ADTB NRR ROE> N. L NRR/DHFT/NTB RQN2 EXTERNAL: 24X DMB/DSS (ANDTS)
NRC PDR 02 PNL GRUEL> R 1
0 1
1 1
0 1
1 1
3 3
1 1
1 1
1 1
ELD/HDS1 IE/DEPER/EPB 36 NRR BWR ADTB NRR PWR-B ADTB J)BFT/HFIB EG 04 RN/DDANI/NIB BNL(ANDTB ONLY)
LPDR 03 NSIC 05 1
0
.1 0
0 1
1 1
1 0
1 1
1 TOTAL NU>BER OF COPIES REGUIRED:
LTTR 34 ENCL 28
'.> 'U a', r aa a 4(
)Ig,
+a r I alia l(mal) ea 0 g )
'V<) i'4'.)'a '.4
. ~:" ~('<<6$
'-34 a',G
- SH
>",~OC'40<("hP k Cl)(J 4'<)li)a fj
'ir344')l0
~atria) 5. r)UP) ea 4 ', '>(at ri 'l)0 T )9 l ~ ~
rflQi')"! 1 jf 4 'a."S ".'mllVh
, vD 0)aP,
.)
4"
'I".l>>ta) 'm f, t f 0'v" )
"';9"
~ A.,(3 f~
i Y K~IT:)')H
~'<t) t,,a rr ra a 0,',,",
'709, a 99
'a
~ <<'4 X 'a l)f) '<<)
') ) J j lU a)t'.!,'a Yg)I.
'3'>.)0 fa 9th:",H
'"." <Vw
",t ti -.<,'a,aalu,.',"I.
t a,,(<i' l~i".JO
) rg
>y'$)a 4,"
g))r+g ',;
fr~ r ggpay 4a f')5IQgl>
aqua
',>ra?)ygqa~9ag,~&'a('ala)'4 0
'J
,Nf':)
l4 t 4, E 2 gFar'a ll <
')'6 f j)O a',
fr~ 9a)
La"lit'kZHX
'11 6 aTA < 0'4'4).
) ')" ) ~
'4 <)g )')'1 'fr,a far, 0 OS 4-g pnr. F(,c K('raa for ),,4 4)gb)agl'at<)a
r).l:'Z.4)~
PrAd') 9'l')
4 0 1f 4)')i1'Cr '6 q ')'O.)4" ~
~) lrll Qt,a arb
'4"a 4 )
GHVI.-i3'9R GBKROQ Ji()():,l
='lQOQ j;()Ti, ) tl)kgb(i',4:(
>> <<ii;4>;~ 1 4.'+b~.h HAGR'>AAGR
.-)',l4 a i '.~fuP.
p))'..4)..>> i l
'U0 =lsrra r l 1 t) t)9...jt."4'cL'atl9'4'
) "
)aalu ad.a iY(a 4,'(~ ) f' q;ftfi ',a',') 4'<
<<":"'3 L'A').)
ta)< l
'-'a'))
a 1 aU.U4 f<. 7"a)~i
'0 "<
<<Ji a4, Cj.-a~)
IH a>'".>>>
"Af;NX'"'0< )
())'.
<<f!>> f 6-H~ "al
',)/Q(J>$
ih>'tr
'r~a(')~a JL
~
a
~ l ~ J.;
Ga,
~
~fill' Of Al g(44 ~
4
'v'"Q rrll'i
1aa) rf fit% 'alia) lYgaia
l SRK Carolina Power 8 Light Company MAY 2~
SERIAL: NLS-86-068 Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation United States Nuclear Regulatory Commission Washington, DC 20555 SHEARON HARRIS NUCLEAR POWER PL'ANT UNIT NO.
1 DOCKET NO.50-000 INITIALTEST PROGRAM REQUEST FOR ADDITIONALINFORMATION
Dear Mr. Denton:
This letter provides Carolina Power R Light Company's (CPdcL) response to your 3anuary 6, 1986 request for additional information regarding the description of the Initial Test Program in CPRL's Shearon Harris Nuclear Power Plant (SHNPP) Final Safety Analysis Report (FSAR).
Each request for information and the corresponding CPRL response is provided in the enclosure to this letter. Marked-up FSAR pages are included at the end of the enclosure for those responses which require changes to the SHNPP FSAR. These changes willbe incorporated into a future amendment of the FSAR.
If you have any further questions regarding this matter, please contact Mr. 3. D.
Kloosterman at (919) 836-8055.
Yours very truly, CGL/Ijs (3055CGL)
Enclosure
. R. Zi erman nager Nuclear Licensing Section CC:
Mr. B. C. Buckley (NRC)
Mr. B. Clayton (NRC)
Mr. G. F. Maxwell (NRC-SHNPP)
Dr. 3. Nelson Grace (NRC-Rll)
Mr. Travis Payne (KUDZU)
Mr. Daniel F. Read (CHANGE/ELP)
Wake County Public Library Mr. Wells Eddleman Mr. 3ohn D. Runkle Dr. Richard D. Wilson Mr. G. O. Bright (ASLB)
Dr. 3. H. Carpenter (ASLB)
Mr. 3. L. Kelley (ASLB) 8605060226 860502 PDR ADOCN, 05000400 A
PDR 411 Fayettevilte Street
~ P. O. Box 1551
~ Raleigh, N. C. 27602
~
g Enclosure to NLS-86-068 RESPONSE TO 3ANUARY6, 1986 REQUEST FOR ADDITIONALINFORMATION NRC Re est No.
1 600.5 O.t (open Item 202)
The following FSAR sections should be modified to conform with the Westinghouse Revised Special Low Power Testing Program as described in the letter from E. P. Raha (Westinghouse) to H. R. Denton (NRC) dated 3uly 8, 1981:
(1)
Subsection 10.2.12.2.22 (Pressur izer Heaters and Spray Valves Capability Test Summary).
(a)
Prerequisites 3 and 0 (regarding charging flow variations and RCS cooldown) should be rewritten as part of the test method.
(b)
The test method and acceptance criteria should be modified to address the effects of auxiliary pressurizer spray on pressurizer pressure.
(c)
The test method and acceptance criteria should be modified to address the effects of charging flow and steam from variations on subcooling.
(d)
Acceptance Criteria 3 should be clarified.
(2)
Subsection 10.2.12.2.26 (Natural Circulation Test Summary).
(a)
The test objective should be modified to reinstate the demonstration of the effects of loss of pressurizer heaters on margin to saturation temperature.
(b)
The test method should be modified to reinstate the observation of the core power distribution as it remains part of the acceptance criteria.
CPRL Res nse No. 1 CPRL willincorporate the recommended changes as well as an editorial change to the Test Prerequisite (shown on the attached mark-ups) into a future FSAR amendment.
(3455CGL/Ijs
)
Enclosure to NLS-86-068 NRC Re est No. 2 600.9 FSAR Subsection 10.2.12.1.16 (Emergency Diesel Generator Test Summary) should be modified to reinstate the following acceptance criteria in accordance with FSAR Subsection 8.3.1.2.0:
(1)
The recovery of within 10 percent of nominal voltage and two percent of nominal frequency within 00 percent of each load sequence time interval.
(2)
The diesel generator speed shall not exceed 107.5 percent of nominal speed (050 rpm) upon disconnection of the largest single load.
CPRL Res nse No. 2 The criteria stated in FSAR Section 10.2.12.1.16 are consistent with the current revision of Regulatory Guide 1.9 (Revision 2) which represents the current practice in the operation and testing of emergency diesel generators; FSAR Sections 1.8 (Regulatory Guide 1.9) and 8.3.1.2.0 willbe revised in a future FSAR amendment to update the SHNPP commitment to Revision 2 of Regulatory Guide 1.9 and change data to conform to Revision 2.
NRC Re est No. 3 600.21 FSAR Subsection,10.2.1.25 (Safety Injection System Performance Test Summary) should be modified to reinstate the recording of CSIP system pressure, temperature, chemistry and duration of testing, or appropriate justification should be provided in response to this item.
CPRL Res nse No. 3 Preoperational Test 1-2080-P-Ol, HHSI Pumps Performance and Flow Balance Test was completed and approved by the 3oint Test Group on 3uly 3, 1985.
CPRL recorded the CSIP system pressure, temperature, chemistry and duration of testing where appropriate and these records are located in site files.
The following summarizes this effort:
(1)
The charging and safety injection pumps (CSIP) used water from the Reactor Water Storage Tank (RWST) throughout the test.
Test prerequisites verified that the RWST had demineralized quality water as defined in the SHNPP Start-Up Manual.
(2)
CPRL recorded CSIP fluid pressure and temperature on applicable data sheets for system performance tests, pump curve verifications and flow adjustments.
(3)
The actual differential pressure across critical valves which were tested under flow conditions can be obtained from plant configuration as determined from procedure steps.
(0)
The duration of testing can be obtained from the Test Comment Sheet, which contains documentation of the dates and times of significant events.
In conclusion, CPRL considers revision of FSAR Subsection 10.2.1.25 unnecessary due to the completion of the test and adequate recording of the parameters in question.
( 3l 55 (XL/I is)
0 V
Enclosure to NLS-86-068 NRC R est No. 0 lOA FSAR Figure 10.2.11-1 and Figure 10.2.11-2 should be modified to include all test summaries contained in FSAR Subsection 10.2.12.
CPRL Res nse No. 0 Figures 10.2.11-1 and 10.2.11-2 are intended to provide an overview of the startup and test program and a general guide to testing sequence.
The inclusion of each test would place unnecessary restrictions upon the test program by rigidly specifying the sequence of testing.
A footnote to this effect willbe added to these figures in a future FSAR amendment.
NRC Re est No. 5 10D FSAR Subsection 10.2.12.1.36 (Fuel Pool Cooling and Clean-up System Test Summary) should be modified to reinstate the test methods and acceptance criteria regarding operability and leak tests on sectionalizing devices and drains and leak tests on gaskets and bellows, or FSAR Subsection 10.2.7 should be modified to provide technical justification for exception to Regulatory Guide 1.68, Appendix A.l.m(3).
CPRL Res nse No. 5 CPRL willincorporate the recommended changes (as shown on the attached mark-ups) into a future FSAR amendment.
NRC Re est No. 6 ICE FSAR Subsection 10.2.12.2.12 (Control Rod Reactivity Worth Test Summary) should be modified to provide clarification regarding the location and position of the greatest worth control rod.
CPRL Res nse No. 6 CPRL willincorporate the recommended change (as shown on the attached mark-ups) into a future FSAR amendment. (3455CGL/I js )
SHNPP FSAR Regulatory Guide 1.9 SELECTION OF DIESEL GENERATOR SET CAPACITY FOR STANDBY POWER SUPPLIES (REV. A z
The SHNPP project complies with Regulatory Guide 1.9, as presented in FSAR Sections 8.3.1.2.4 and 14.2.12.1.16.
1.8-16 P
Amendment,No. P1
SHNPP FSAR 8.3.1.2.4 g)
Each standby power source consists of a single generator driven by a single prime mover.
'2 Ppq-... Iji~fl>(
Regulatory Guide 1.9 (Revision -~arch 1~)
The intent of Regulatory Guide 1.9 is met as follows:
a)
The diesel generators are each rated as shown in Table 8.3.1-1.
The maximum automatically started load on each diesel generator is within the continuous rating of 6500 kW.
The total maximum load, including manually started
- loads, is also within the continuous rating of the diesel generators.
b)
Preoperational tests are discussed in Chapter 14.
c)
Preoperational tests will verify the capability of each diesel generator set to start and accelerate to rated speed.all of the needed safety related loads in the required sequence.
26
)
d)
The diesel generator sets will be capable of reaching full speed and voltage within 10 seconds after receiving a signal to start.
The engine will be capable of starting, accelerating and supplying the above Loads in the sequence shown in Table 8.3.1-2 without exceeding five percent speed
- drop, maximum, at any time.
A Load sequencing test has been performed reflecting the Shearon Harris diesel generator loading condition, as per FSAR TabLe 8.3.1-2 with margin.
The test results indicate that at no time during the load sequencing does the frequency and voltage decrease to Less than 95 percent of the nominaL and 75 percent of the nominal respectivel,y.
The generator will be capable of starting, accelerating, and supplying the above loads in their proper sequence without exceeding 25 percent voltage drop at the generator terminals.
(g/, 2.a The speed of the diesel generator set will not exceed 4~ percent of nominal speed (450 rpm) during recovery from transients caused b
disconnection of the
> ~
Largest single load.
The engine trip setpoint is~ rpm percent nominal) to ensure that the unit will not trip on rejection of the largest single loads.
The recovery of the diesel generator from transients, to within 10 percent of nominal voLtage and two percent of nominal frequency, will be within~&~
percent of each Load sequence time interval.
The recovery from transients will be verified during preoperational testing.
Qualification data (as described in Section 3.11) will be submitted and preoperational tests will be performed to confirm the suitability of the diesel generator set.
8.3.1.2.5 Regulatory Guide 1.29 (Revision 3, September 1978)
For a listing of the seismic classification of electrical equipment important to safety, refer to Section 3.2.
8.3.1-26 Amendment No.
SHNPP FSAR b)
P'rerequisites 1)
The fuel, pools and transEer
- canals, and PLant Reactor Cavity are filled with demineraLized water as required.
I23 c) 2)
The general prerequisites of Section 14.2.12.1 are met.
Test Method 1)
Operate the FueL PooL Cooling Pumps at various flow rates to verify the pump performance curves.
I23 2)
Operate the Fuel.
PooL and Refueling Water Purification Pumps at various flow rates to verify the pump performance curves.
123 3)
Operate the Fuel PooL Skimmer Pumps at various flow rates to verify the pump performance curves.
123 4)
Simul.ate high fuel pool temperatures and low fuel pooL cooling flows and verify proper aLarm annunciation.
I 23 d) 5)
Vary levels in fuel. pooLs and demonstrate proper operation of Euel pools level instrumentation and al.arms.
I 23 0 )
Frcc.
r<<<.<.
r'c<'~>
A s +ac =~gucY rc rirrrtlr=
u Arced ce
'.'J 5i8c-c r=
AccePtance Criteria Pc< c 6Al< 5 8>> +r+ c'J
~ <<<-
cr<<FR r rc
<>rnlrn'.Srel72.
1Hcr rhfl'C'6r lf dr'HE 5~br IW"IAl48I7~~>>A ~P+r CNey Hrird~ 4C-~r<86r=
1)
The Fuel PooL CooLing, Fuel Pool and Refuel.ing Water c."'rCt"46 Purification, and Fuel Pool Skimmer Pumps operate in accordance with the specific pump performance curves.
23 2) 14.2.12.1.37 Syscem controls and aLarms Eunction properly in FueL Pool. Cooling Cleanup and Skimmer Systems.
I 8 p gQc-<.
PGC C.
8 r+TF5 5HP c-C ZSor rfTP VSF, Vlr'rc'<4~ Sc:.c'ygprq~
T/gP P<rgc. +Dg, lA/P/ de'4 f Ale'df-'A.LWKHbZ.
Component Cooling 'dater System Tesc Summary 23 a) l'est Objectives To verify the characteristic performance of the component cooLing water pumps.
2)
To veri fy that each train of che Component Cooling 'dater System is capable of providing adequate cooLing
.bracer co supplied components.
.4)
'l'o verify <<larms and contr()l setpoincs.
l'o verify system activation with safety injection signaL
~
14.2.12-39 Amendment No.
23
SHNPP FSAR 14.2.12.2.12 Control Rod Reactivity Worth Test Summary a)
Test Objective 26 b) 1)
To determine the Integral Rod Reactivity Worths of the control rods and shutdown rod banks, and to verify by analysis that the Rod Insertion limits will be adequate to ensure a shutdown margin consistent with accident analysis assumptions with the greatest worth control rod stuck out of the core.
( Q g
iZCs w:"cc (:; ~ c(2.2-t~ 8><)
Prerequisites c) 1)
The reactor is critical at zero power.
2)
The general prerequisites are met.
Test Method 26 1)
The integraL control rod worths will be determined and compared to design predictions by utilizing the boron dilution or the Rod Swap technique.
2)
Verify by calculation that a shutdown margin consistent with the accident analyses exists assuming the greatest worth rod remains in the full out position with the control rods previously inserted to their maximum Rod,Insertion Limits.
3)
With the greatest worth control rod in the full out position, determine the minimum boron concentration required to maintain the reactor shutdown.
d)
Acceptance Criteria 26 1)
The rod worths are determined to be within the Limits of FSAR Table 4 '.2-3.
2)
The calculated shutdown margin is greater than 1.77X hk/k.
14.2.12.2.13 Boron Reactivity Worth Test Summary a)
Test Objective 1)
To determine the boron reactivity worth over the boron concentration ranges in which the reactor may be taken critical.
b)
Prerequisites c) 1)
The reactor is critical at "zero power.
2)
The general prerequisites are met.
Test Method 1)
Determine the reactivity worth of the boron in soLution by diluting the boron concentration and compensating for the reactivity effect by movement of controL rods.
I
SHNPP FSAR
'3)
The RHR System is operated from outside the Control Room and.will reduce the RCS temperature 50F without exceeding the cooldown rate.
14.2.12.2.21 Loss of Offsite Power Test Summary a)
Test Objective To demonstrate that the necessary equipment,
- controLs, and indication are available following the isolation of the offsite power distribution system to remove decay heat from the core using only emergency power supplies.
b)
Prerequisites 1)
The plant is at a steady state power level between 10 and 20 percent.
c) 2)
The general prerequisites are met.
Test Method 1)
Simulate a
Loss of offsite power coincident with a loss of turbine-generator.
2)
Using approved operating procedures, bring the plant to a hot standby condition and maintain the plant in a hot standby condition for at Least thirty (30) minutes using only emergency on-site power sources.
d)
Acceptance Criteria 1)
The hot'standby condition is achieved and maintained for at least thirty (30) minutes using only emergency on-site power sources.
2)
The emergency dieseL generators start and sequence Loads when off-site power is not availabLe.
L4.2.12.2.22 Pressurizer Heaters and Spray Valves Capability Test Summary a)
Test Objective 1)
To determine the capabiLity of the pressurizer heaters and spray vaLves.
2)
To measure the effect of auxiliary pressurizer spray on pressurizer pressure.
3)
To measure the etfects of charging flow and steam flow on subcooli.ng.
Prerequisties 1)
The plant is in hot standby conditi.on with three reactor coolant pumps running and system pressure and temperature at approximately 2235 psig and 5/7 F.
14 '.12>>93 Amendment No. 23
SHNPP FSAR 2)
The generaL prerequisites are met.
T<~a. t le+M l9)
Vary charging flow to allow a 5 percent increase in pressurizer Level and obtain subcooling data.
gP)
Initiate an RCS cooldown of 10F/hour to 552F and obtain subcooling data.
~ 2)
With the pressurizer spray valves closed, all heaters are energized, and the time to reach a 2300 psig system pressure is measured and recorded.
d)
$ 2)
With alL pressurizer heaters de-energized, both spray valves are
- opened, and the time to reach a 2000 psig system pressure is measured and recorded 0<':toe Iii>o'z.c'b'r 4<<Mrs ze ~im <y'z<$(, p~<cc-"
g ) b~
.Wvwilie v~ >pea ~ i~ 'sec@ i(.e 4 Rcc eke(/~~8
~i'<+~'~~i~Q Zaaa p>> > RCS y,~
Acceptance Criteria 1)
The pressurizer pressure
- response, as the heaters are energized, is within the alLowable range graphed in the Westinghouse NSSS Start-up Manual.
23 2)
The pressurizer pressure
- response, as the spray valves
- open, is within the aLlowable range graphed in the Westinghouse NSSS Start-up Manual.
~z-cs GIB'p p~g>
pgspes(>
gg Ogive lloyd Cpa cL~ '6 pl&(c.(L<<<0 '.~ ~+c i6 mi4Hiiw~ <<1(o~&e. g~)c.
(@Aped (t. i'~ vgc&vec&awc~ H5Gw merci&-~~1 l&&wa.l ~
ar-pcessv re-wi cbees pect-to-the ndMGS-tempera tare-change-i~
@et t-ural-ei-rcpt.ia t ion--date.-
4 4K ci&wc:R~
ci~ c'<He'ic l4.2.12..
Fai Led Fuel Detection System Test Summary a)
Test Objective l)
To verify proper operation of the Gross Failed Fuel Detection System during power ascension.
b)
Prerequisites c) 1)
Power l.evel i.s estabLished to meet the test requirements.
2)
The generaL prerequisites are met.
Test Method l)
At steady state po~er levels of 25 and 100 percent. verify that detector H.V. is at the setting determined during the initiaL preoperational setup.
2)
At a power Level ot'00 percent, set the high alarm to 2
X 10 CPM above the Level estabLished by the plant chemistry section, to be'ithin technical specitications.
14.2.12-94 Amendment No.
23
t
~
g) 4 cc~q4w cm Wi~vic o) M~ ASS-a~m
~5( w~ ~rm.~ d'ee~c (~~.~ W(a;a)
Qm 8( 5 5 VOc~l<~a, IR IZQ(088(6. CIE48VIYYI'iv>8'5><-R<. i8 MM-Cohvp<~blq'pic N+sk@C c4'imam~ (
o tW km<>c V C,i,~ Fc.el<<,etc:Q
- 5) "PV e)4<<<
oR Cgavzc~~m~~ 'j-lo~Q vaeio+or~s (i~c&cisc) g m P<S S~ <<~ <>
Q (S ~ggggQg/Q+~g~ v,g<g,g,~g.-ti C
pe..<<l"(w c~ec ca~pcMa.'~lp 4:-~~[~~ c4.~ig~~ (h<
i~+v A~ii"=i q/'. Q
~~qy, ~.g y Fc<P IE.'~
WkC.)
J
SHNPP FSAR 14.2.12.2.26 Natural. Circulation Test Summary a)
Test Objective 1}
To confirm that design heat removaL capability exists under natural circulation conditions')
To verify that flow (without pumps} and temperature data are comparabLe to prototype designs for which equivaLent tests have been successfully completed.
3)
To obtain a data base for simulator training in natural circuLation operation.
0)
I 0 c1~rn~W@
44@. 8 Lc ~So ~
I<55 o~ pb2.~scAs~%4v.>
o~ AAa,ajar ~ ~ ~4uec-%c~ ~~~<M~.
b)
Prerequisites 1)
Plant is stabLe at approximately 3 percent and parameters are at no-load values.
2)
Three reactor coolant pumps are running.
3)
The general prerequisites are met.
c)
Test Method 1)'rip the reactor coolant pumps.
2)
Verify adequate natural circulation flow to maintain cooling.
23 3)
Demonstrate the effects of loss of pressurizer heaters by de-energizing all heater banks.
Maintain naturaL circulation and constant T
whiLe observing the pressure drop.
avg
- 0) oh'+e (L
w ~s a+ gee ",44 l~~)s 4 Qg~o.ng qo<ew G4WKMQons, d)
Acceptance Cri teria L) 1'he heat removal capability, power distribution, ELow data, and temperature data are comparable to those of the prototypes (North Anna) for which equivalent tests have been completed.
2)
Pressurizer pressure remains above 1800 psig.
14.2.12-96 Amendment No.
23
~ '
~
~
I ~
~
~
~
~ '
~ ~
~
~
~
I
~
I
~
~
~
~
~
~ '
~
l
9 MONTHS COMMERCIAL OPERATION FUEL LOAD LOWPOWEII TEST INITIAL CRITICALITY POWE4 ASCENSION IDEE 20'X SIVA AOIE Mtt EEVA 70%
SIVA 90%
I 100'\\
I REACTOR TRIP SYSTEM BORON REACTIVITYWUH s i>a ROD OIICP TESTS PSEUDO 400 EJECTION HEACTUH COOLANT FLUw ISSTS rEACToR coot.ANT F I nw cnASToowN CONTROL ROD D4IVE TEST J HOD PUSII ION INDICA1UHS I
~.."DKF'R TELSP IIEACTIVITYCOEFFICIENT I vnNTnnt Rno RFACTIYITY WORTHS I
I vNCUHL IHtHMuCUUVlt I
I ilHX DISTRIBUTIONMEASUREMENTS I I EMOTE SHUTDOWN CALIBRATIONOF NUCLEAR INSTRUMENTATION RAOIATIONMONITORING EFFLUENT NIONITORING POWER COEFFICIENTS ANDPOWER OEFFCTS MEASUREMENTS LOSS OF OFFSITE POWER TURBINE TRIP CORE PE4FORMANCE EVALUATION UNIT LOADTRANSIENTS HTO FLOW BYPASS VERIFICATION SHEARON HARRIS NUCLEAR POWEII PLANT Carolina Power IL Light Company FINALSAFETY ANALYSISRE+AT INITIALSTART.UP TEST SCHEDULE-ISHNPPI FIGURE T4.2.TT 2
A
~ I ~ 1 I
re AP ft
~
4l.
a