ML20059L592
| ML20059L592 | |
| Person / Time | |
|---|---|
| Site: | Fort Saint Vrain  |
| Issue date: | 09/13/1990 |
| From: | PUBLIC SERVICE CO. OF COLORADO |
| To: | |
| Shared Package | |
| ML20059L585 | List: |
| References | |
| EE-DEC-0033, EE-DEC-0033-RB, EE-DEC-33, EE-DEC-33-RB, NUDOCS 9009270150 | |
| Download: ML20059L592 (41) | |
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L EE-DEC-0033 Rev. B Determination of Upper Bounds on Radiation Exposure Rates at the Refueling Floor Above.a Defueled Region with CRDOA Radiation Shielding Removed
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i Prepared by: - signature b(- bM. M.tle 9 12
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Verified by:: h h f ** r ['/I-9# sigdhture Title Date-Approved by: . leg 4 M ddil db34 9-11 90
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signature fitle Date 90o9270150 900914 gDR ADOCK0500g7
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iy. I CONTENTS Page 1.0 PURPOS.E... . . . . . . . . . . . . . . 1 2.0.
SUMMARY
... . . . . . . . . . . . . 1 3.0 SCOPE. . . . . . . . . . . . . . . 1 4.0. APPROACH . . . . . . . . . . . . . . 3 5.0 EVALUATION . . . . . . . . . . . . 3 6.0 C.QNCLUSIONS . . . . . . . . . . . . 3
7.0 REFERENCES
.. . . . . . . . . . . . . 4 b.0 ATTACHMENTS. . . . ... . . . . . 4 L 4 t I i
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{ J< l y 1 l s 1.O PURPOSE I
=This EE will establish upper bounds for the potential j personnel radiation exposure rates at the refueling floor ;
level with the radiation shielding portion of the control Rod i Drive ' and Orifice Assembly (CRDOA) removed from a refueling penetration.above a defueled region in the PCRV core. [ The conclusions from this EE will' be used to support the i
, applicable portion of the Safety Analysis being written as ~'
, part of-the proposal to amend FSV Technical Specification DF 6.1 with respect to removal of the radiation shielding i portions of the CRDOAs from above defueled regions. t 2.0
SUMMARY
Based on earlier' measured radiation dose rates, calculations were performed to determine the dose rates at the refueling floor above a refueling penetration with the CRDOA radiation shielding removed. Two situations were evaluated: (A) the i secondary cover installed over the refueling penetration, and : (B) the secondary cover removed. The results for the two t situations are 10 mR/hr and 156 .mR/hr, respectively. ' considerable conservatism is present in these results in that i they are based on the core region below the refueling penetration containing fuel, whereas, in the actual case, it will contain only defueling - blocks - (i.e. , will be in a , defueled state). The' final conclusion is that expected dose rates at the refueling floor above a defueled region with the CRDOA shielding removed-Will not prohibit personnel access to that ! area. l 3.J -SCOPE ' Note: The relevant portion of all drawings referenced
- hereafter are included in Attachment A.
In cenjunction with defueling, the CRDOAs, or certain portions ' thereof, above defueled regions only may be removed; the CRDOAs above fueled regions will remain intact as full ; assemblies. In the refueling penetrations above each of the defueled regions, one of three optional configurations will exist prior ' to the completion of defueling: Configuration 1: A complete CRDOA will be installed; I' f
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t configuration 2: All subassemblies of the CRDOA inclusive ; of the shielding container _ assembly ') (D1201-100, Item 11) and below are absent ! from the refueling penetration; i.e., .! only the housing assembly (D1201-100,
- Item 10, typ.) and the enclosed control !
rod drive gear- and pulley assembly (D1201-100, Item 4, typ.) and orifice drive motor and gearbox (D1201-100, Item ,
- 8) remain installed in the refueling ;
penetration; or '
.(
Configuration 3: The complete CRDOA has been removed- and :i replaced with an alternate sealing device ! L at the primary seal location. h This EE will establish an upper bound for potential radiation [ i exposure at'the refueling floor above a defueled region:for ' the following situations A and B. For each of these two ! situations, one of the above three refueling penetration configurations will exist. { 4 Situation At The refueling penetration cover plate (R1103- l 101), or " secondary cover", is installed over l the region of interest. (R1101-110 shows a ! typical penetration cover plate installed. L the hold-down plates are-not installed during .! L l defueling; therefore, they will not be ; included in any situation to be analyzed by~ i this EE.)
- 1 Situation B: The secondary cover is absent'from>above the .
region of interest, t When a complete CRDOA is installed (Configuration 1) , the i normal radiation shielding provided by the lead shield and' ; boronated graphite contained in the CRDOA shielding container. t assembly (D1201-100, Item 11) will exist. This is the normal [ configuration and therefore does not require further i evaluation. ; For both Configurations 2 and 3, the CRDOA shielding assembly ' will be removed from the penetration. For Configuration 2, the CRD housing assembly (D1201-100, Item 10, typ.) includes ! a closure housing (D1201-276) installed at its upper end. > This closure housing incorporates a 3-inch carbon-steel thickness for which radiation shielding credit may be taken. , For Configuration 3, the alternate sealing device will incorporate a minimum 3-inch carbon-steel thickness.
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3 I Therefore, from the standpoint of radiation exposure at the l refueling floor above a defueled region, Configuration 2 i represents the worst case scenariot i.e., configuration 3 is ! , bounded by Configuration 2. Situations A and B, secondary cover installed and not installed, respectively, for. , Configuration 2 only will therefore be the scope of this . evaluation. ; 4.0 APPROACH : I ; A recent T-test, T-421 (Ref. 1), was performed to measure the j radiation dose rate above a completely vacant (i.e. , complete ' CRDOA, penettation cover plate and hold-down plate removed) t
- , refueling penetration. For this T-test all core regions were >
. fueled. -
This EE will utilize the results of T-421. For Situation A, by taking. radiation shieldin; credit for the existing 3-inch
'l carbon-steel thickness as part of the closure housing.(D1201-276) . installed in the top and of the CRD housing assembly. !
(D1202-100-10, typ.) plus .the 4-5/16-inch carbon-steel thickness of an installed secondary cover plate (R1103-101), this EE will, based on the results of T-421, analytically-determine the dose rate at the refueling floor level above the refueling penetration. . For Situation B, the dose rate will be calculated by taking radiation-shielding credit for only the 3-inch carbon-steel .i thickness mentioned above. , l 5.0 EVALUATION L i calculations have been performed to determine upper bounds on , radiation exposure rates at the refueling floor level for l Situations A and B with Configuration 2 (see Sect. 3.0 and : 4.0) based on the dose rate measured previously via T-421. These calculations are presented in Attachment B. , The results are as follows: For Situations A and B with configuration 2, the calculated upper bound dose rates at the refueling floor above the defueled region are 10 mR/hr and ! 156 mR/hr,respectively.
6.0 CONCLUSION
S The radiation exposure rates calculated in Attach. B represent upper bounds. Significant (on the order of a factor of 10 to 1000) conservatism exists in the fact that the calculations were performed based on fuel being in all core regions; i.e., T-421 measurements were taken with fuel in the core. In the l actual case, when the CRDOA, or portions thereof, are removed i a--- .- - - - - _ . _ _ . - - - - - - - - . _ . . _ . _ _ _ - - - - - - - - - - - - - - - - - - - -- - - - --,.---s- = +we --
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e from a' refueling penetration, that region will have been ! defueled (i.e., defueling blocks installed); any surrounding j regions with fuel will have a CRDOA installed with its normal ; included radiation shielding or will be in the process of l being defueled. No significant radiation contribution from adjacent fueled or defueled regions at the refueling floor' : above- any given defueled region for Situation A or B with i Configuration 2 can be expected. Normal Health Physics administrative controls should be used to limit personnel access or provide additional temporary I shielding as required above a defueled region under Situation - A or B based'on actual radiation measurements taken at the > time access is desired. In all likelihood, the required ; controls will be very modest. l The final conclusion is that expected radiation exposure estr,s at the refueling floor above a defueled region with the 7RDOA shielding removed will not prohibit personnel ~ access to that area. ! 4
7.0 REFERENCES
i
- 1. PPS-90-1435, PSC M'emo from R. L. Talbott to T-421 File, dated June 12, 19'40. t 8.0 ATTACHMENTS L i
( A. Drawings' D1201-100 t~ t R1103-101 l R1101-110 D1201-276 : D1200-100 R1103-213 R1101-101 B. Upper-Bound Radiation Exposure Rate Calculations for Situations A and B with Configuration 2 .! l I 9 E
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r? c Upper-Bound:: Radiation Exposure Rate. Calculations for' Situations'A and;B-with configuration'2 oa f t i
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, i_ . ;TO : ~ File FROM:i Les~Hutchins, Health Physicist SUBJ: CALCULATED = RADIATION EXPOSURE RATES ON. THE TOP HEAD D'IE TO THE .
REMOVAL'OF ORIFICE VALVES AND BIOSHIELDS n '" UThe calculsted radiationfexposare rates on the Refueling Floor;(RFF)
-above the core v'ith the bioshields and orifice valves removed.from.the CRDOA are listed below. (attached -is the methodology.and assumptions-used to perform-this: assessment).
I With Secondary Without Secondcry
~ Covers Installed Covers Installed Dose Rate Above Each' -10 mr/hr 156 mr/hr Region'-
Please note- that the . initial ' dose- rate assumed in these calculations is, based upon a' fully fueled region being exposed. The proposed change to:
' Technical Specifications would, apply to onlyothose regi~ons which:-have
.been fully defueled. The expected radiation levels:would accordinolv be.
reduced-L, a g minimum of a -factor _ of- -10'and in all-likelihood'by a factor of 100 to 1000. . Perfprc;ed by: it A%
.Les Hutchins ieviewed by: //S /. AA/'3 h
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Bill Woodard
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4, t , n- y s 9 CALCULATION 8/ ASSUMPTIONS i In ordar-to perform-the requested exposure rate estimations at the Top Head of'the PCRV' with the orifice- valve assemblies and bioshields-removed'from.the CRDOA's, the following assumptions are made:
- 1. - The' actual dose rate without these items will not'. exceed the values as measured in T-Test T-421.
I
- a. A !maximum' radiation ~ level of.630 mr/hr was encountered -through a 1/4 -inch thick plexiglass plate-(350 mr/hr through a 3/4 inch carbon steel. plate).
- b. This test was performed with an RIV being opened above the core without == CRDOA in place. Hence this was the dose rate- with spent fuel and reflectors being directly exposed to the environment.
- c. The actual exposure rates will be significantly less than these measured rates since there will not be any opent fuel underneath-a CRDOA with the bioshield and orifice valve removed,
- d. The radiation levels- during this test were. determined at a-distance of 48 inches above the floor level.
- e. The effective height'from the uppermost. activated components in the core to the floor level is 23' 5" (Ref. D-1200-100).
- f. All calculated dose rates are- rounded to the nearest whole number to be ' consistent with current survey instrumentation sensitivities.
2.- The closure housing of the CRDOA will remain present at all times in this configuration. This assembly has a thickness of 3 inches and is constructed of carbon steel (Ref D-1201-276). 3 ~. Calculations wi'11 be performed for 2 conditions:
- a. With. the secondary covers in place. These covers are made of carbon steel with a thickness of 4 5/16 inches (Ref, R-1103-101). -
- b. With the secondary covers removed.
- 4. Each' penetration will ,2t as a plane (surface) source with a diameter of 22.75 inchea (Ref. R-1103-213).
- 5. The effective gamma energy to be shielded will be conservatively estimated to be 1.5 MeV.
- 6. Carbon steel is assumed to be equivalent to iron for shielding with a density of 7.86 g/cm3 (hence p = . 37 8 cm- 2 ) .
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- 7. The equations used to calculate the expected dose rates are:
- a. For a plane source (from Introduction to Health Physics, Cember):
DRi = In f(Rt + hi t ) /hi
- 1 DRs In [(R + h: 2 ) /h: 8 ]
Where: DRs = Dose rate at point of interest DR = Dose rate as measured at point 2 R = radius of the plane source ha = distance from the plane source to the point of interest ha = distance from the plane source to the point of measured dose rate
- b. To calculate the effects of shielding (from The Heal th Physics and Radiological Health Handbook):
I = b Io e-u5 Where I = the dose rate (or flux) after shielding b = t. auildup factor Io = ti initial, unshielded flux p = the linear absorption coefficient x = the shielding thickness
- 8. The unshielded flux at a height of 48 inches (taking into account the effects of the 3/4 inch carbon steel plate is therefore calculated to be 397 mr/hr (b = 1.81). Since this ; less than the dose rate through the plexiglass, the plexiglass .e rate will be used as the unshielded dose rate.
- 9. Correcting the dose rate to the floor level this unshielded dose rate becomes 863 mr/hr.
- 10. The dose rate taking only the effects of the upper closure housing will therefore be 156 mr/hr (b = 3.23).
- 11. The dose rate with the secondary covers in place is calculated to be 10 mr/hr (b = 4.17).
- 11. An evaluation of the effects of shine through an adjacent fueled region with the CRDOA removed in preparation has been performed.
Due to the relative locations of the penetrations, it would be impossible for shine from a fueled region to measurably contribute to the radiation levels above an adjacent region. The associated gammas would first be attenuated by a minimum of 282 inches of concrete which reduces the flux by a factor of 2.3 E-38.
- 13. Each region will act as a radiation source to another region. This will be due to shine from the cylindrical beam exiting the region.
The radiation from surrounding regions is actually traveling in a tight bean directly upwards from the region and the exposure to an l
- f. , ,
4- ' #" vs . i . adjacent region :is:..due. to secondary: cover and the air,- scatter from. interactions with-the. i The cumulative effects of the scatterc from adjacentiregions'on the-primary region of interest (i.e. the region.above which the maximum dose rateris being-evaluated) is considered to bet negligible.:This is due to the.following; reasons: a) The- adjacent' regions,- if' fueled,'will-have~a complete'CRDOA, including the bioshit,1d, installed or= e
'b) If'the' adjacent' region'(s) are defueled " iib the CRDOA[bioshield
-and, possibly, the secondary covers removem, the' expected actual ,
3 dose. rates from-these regions will be-sufficiently 'smalli such.
. that' the - 'effect on. the dose rate at t.he primary region'of- l f
interest due to scatter from-- these adjacent ' regions willi be negligible, g l 9 4 1 i l l l I i l I,I F
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7^ , 1pummuuuuuuuuuumana . w$ Linteroffice. . Memos N lPPS-90-1435; : y v. Masasnesecompeiratosamens ' g ~DATE: . June 12,.1990 ., t q y TO:- T 421'FILEz },, FROM:" lussell L.- Talbott, Sr. System Engineer,' FSV 'i 3
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SUBJ: -T-TEST 421 RESULTS EVALUATION E'. y
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* -test' f T-421 : was performed t' provide quantitative . information i j* .egarding the.. potential radiation. streaming, from the:: reactor core .I
, 'through an open .RIV. This information was: valuable.in' determining q the viable-options and design requirements for .the development of-alternate _means of: removing ~the reserve. shutdown boron balls.from the r \ reactor core.
E 7
- The..- test- was performed with no difficulties. The test provided the.
.following .results: streaming- for the . core through , an - open penetration- and -:RIV . resulted - in 630 MR/Hr ~through.1/4-inch . hick
, r clear plastic and 350 MR/Hr through 3/4-inch thick carbon' steel.
These levels were detected directly aboveLthe penetration with very
, little' scattering. ,
i 3; ' l Attached for information are:the drawings of.the' penetration plugging ~ tool utilized during performance of the test.-
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, ATTACHMENT 6 TO-P-90273 I i,
O< ' GENERAL ATOMICS EVALUATION.FOR REMOVAL OF ORIFICE l-CONTROL MECHANISMS- ,
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[ ; e i.e. m swi pau 22gg ISSUE / RELEASE
SUMMARY
'e o ano - Arevt Doc, oa uvs6 wen sYS DOC. TYPE PROACT DOCUMENT NO. REV o mes - LEVEL I FSV I easteo -' 868CTIWCAL 2 M. pgy I;- 18 CFL 1900- 910144 N/C.
N/A Ym.E: CORE OPERATION DURING DEFUELING NO ORIFICES OR PLENUM ELEMENTS APPROVA48) REVI8 SON CM' APPROVAL / PREPARED DESCRIPTIOf6'
-OATE REV SY- EN0mEERING QA PRCUECT W.O. NO.
][ hib/C R ernick R.vollman- R.F xwelh F.C.D hae Initial Release y- ,13/
. 2970647-JUN t 11990 ,(Oh l:
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CONTINUE ON GA FORM 1486.1 NEXT DOENTURED
*See Liec of Effective Pages PG-1930
~
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.b n
ti j Q GA PROPftETARY INFORMATION THIS DOCUMENT 18 THE PROPERTY OF GEP ERAL ATOMICS, ANY TRAN8MITTAL OF THIS DOCUMENT OUT8IDE GA WILL BE IN ' CONFIDENCE. EXOEPT Y4TH THE WRITTEN CONSENT OF GA, (1) THIS DOCUMENT MAY NOT BE COPIED IN WHOLE OR IN PART AND WILL BE RETURNED UPON REQUEST OR WHEN NO LONGER NEEDED BY RECIPIENT AND (2) INFORMATION CONTAINED HEREIN MAY NOT BE COMMUNICATED TO OTHER8 AND MAY BE USED BY RECIP'ENT ONLY FOR THE PURPOSE FOR WHICH ff
' WA8 TRAN8MITTED.
M NO GA PROPMETARY INFORMATION PAGE 1 OF
.,7.. 7
[ ' Mi-22 '90!C9iB2 ' ID: GEN AT0t11C5 5DGi sTEL tom 94554174 3 :uC2A P02 - I f+, ' ' ' 7, - , a -
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'Pese Number Page Count: ' Revision 1 through 10 10 N/C I
. Microfiche * '17 ,N/C- >
A-1'through A-6 6 .N/C-L a Total Pages. d 33 M
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*Microhicheinottobedistributed .
POKE run' ~ Pg Reafons Decay 3,eg. Orifices . Plenums-l L '
'ST9138? 0.28 W 1.' 2 'l out in in.
, 2.. '876527 2 1 out~ O.28 W out in L
b
- 3. .ST7704 2 ) out 0.28 W out out --,
4.. :872420 2- -1 out - 0.08 W- out-' out ! 5.- 878339 2 :all in 0.28 W ' . in - in . . L
- 6. ' '875339 2 .all:in ' O.28 W out .in- e,
'7-. 875916 '2 all-in ' 0.28 W out- out
.' 8. 876322 2 .all in- 0.08 W . out- out-f
*,., 1
' 9. .878837 1 all in ' 10 08 W . out out 17 -
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. . , - , . - , _ . , ,. . . . . . _ . _ , _ _ , _ _ __________.________________._______________________________________..______________1
, ' 2 __ .3JR22 '90 09:52 lD GEN ATOMIC 5 'SDG .TEL NO:6194554174 n024 P02 !
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- 1. A 3
L aq, t 910144 N/C- 3 l
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i CONTENT 8 i 4 1 1 1.- St49%RT.......-.......-'..'.. .....-......
- 4' a
-2. INTRODUCTION:-. . . . . . . . . .,. .,. . . . . . . . . . . . . 4 i
- 3. DISCUSSION . - . ... . .. . . . . . . . . . . . . . . . - . . - . ,
5 - 4. 8 POKE CODE VALIDATION . . .. . . . . . . . . . . . . . . . . _ - . . l 1; 3. CIRCULATOR OPERATION . .. .. . . . . . . . . . . . . . . . ... 8- , i.,
.l 6. REFERENCES =.-. . . . . . . . . . . . . . . . . . . - . . . .. . ...
9 Calculation Review Report . . . . .................. 10 , , ,. i l-
- 1. ~
FIGURE 8 .e . l. I
- 1. LCO 4.1.9 Core Flow Requirement, No Regione Removed, AT=350'F. . :6
, 2. LCO 4.1.9 Core Flow Requirement,' one Region Removed, AT=350'F. . . 7 31 I
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4 7, . JUN-22 '90 08:53 !D: GEN G.TOMICS SDG TEL lO:6'.91554174 #024 PO4 i.-: 910144 N/C
- 1. Sth9%RY With the region control rod drives und orifices installed and at a core decay heat value of 0.28 W, a core flow rate of 1,66 lbm/s is required to meet the LCO 4.1.9 limit throughout the defueling operation.
If the control rod drive /orificing assemblies are not reinstalled on the - regione after they are defueled, the required core flow increases to 1.82 lbm/s. If, additionally, the metall plenum elements are not reinstalled, the maximum flow rate increases to 1.91 lbm/s. Currently, the decay heat is 0 08 W, considerably less than the . value of 0.28 W. Wfch this lower decay heat, the flow required to meet LCO 4.1.9 reduces to ( .7$ lbm/s for the case where both the control rod drive /orificing assemblies and metallic plenum elements have been removed from defueled regions. The analysis performed shows that the core can be operated at these flow rates without reverse flow occurring in any of the regions. How-ever, there is some concern with circulator stall, and if the core flow is reduced to the low values permitted at 0.08 W decay heat, it is recommended that the onset of stall be monitored and the circuletor speed be adjusted to ensure operation outside of the stall region. F l
- 2. INTRODUCTION 3 l
During defueling the maximum region temperature rise is limited to 350'F, per LC0 4.1.9 of the Technical Specificatione. Calculations were performed earlier (Ref. 1) that show a core flow rate of 1.66 lbm/s is I required to meet this limit. In these calculations, a core power of I l 0.28 W was used at d the core power distribution was taken to be that at l the time of shut de m of the reactor (Ref. 2). Further, it was assumed l 4
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-I the metallic: elements.and control rod drive /orificing assemblies were; j.B inet'alled on the defueledLregions.1
. ~
PSC is considering removing the control; rod drive /orfficing"csson- . y blies and metallic plenum elements from all defueled regions in the ; core. .which would necassitate' en operational limit to be imposed to ;
. ensure the intent of LCO 4.1.9 of the Technical Specifications is. met. $
-In support of this, operational limit, an analysis has been performed to-determine.the flow required to limit the maximum region coolant temper- .r
- sture rise to 350'F, with 'the' control rod drive /orificing assembly; l
. removed and with both the control rod drive /orificing assembly and'-
T' metallic plenum elemente removed from defueled regions. .(
- 3. DISCUSSION : }
a Core flow analyses were performed'using the POKE code (Ref. 3), I using the operating conditions requested in Ref. 4: ? r
- 1. Inlet Temperature 100'F
]
- 2. Inles Pressure 12 3 psia
'3. RPF Distribution - from Ref. 1 ' <
- 4. Orifice Positions Uniform flows 172 open/.101 opm Decay. Heat-S. 0.13 W (Case-1) 0.08 W' (Case 2) ,
For each of the two decay heat values, calculations were done for H- . the two extreme conditions during.defuelings (1).at the start of defuel. I
- ing of a region and (2) when all the fuel has been removed from a region but the defueling blocks have not been installed. These calculat. ions were repeated.for each region, following the selected defueling sequence ,
(Sequence 6). The results are presented in Figs. I and 2. x Consistent with earlier analysis, the curves show the core flow requirement is greatest for condition (2) above, due to the core flow that is shunted through the empty region cavity. Also, there is a S _._m._.__ mom .._.m._______.__ _ _ _____m_ _ _ _ . _ _ _ _ ___. __ ._. -
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Fig. 2. LC0 4.1 9 Core Flow Requirement, One Region Removed, AT = 350'r
. I
bN. 1. - ._ M 22 '90 08 95 ID: GEN ATOMICS SDG :TELLNoi6194554174 n024.P09 1 7g: 2 _ , ,; 910144 N/C c;
~ general increaseiin~ti.e-required core flow as_more' regions'are defuelor'..
$ This occurs, despite the f act- that the defueled regions have f ewer-coolant holes, because:the coolant flow through the defueled regions la
.only.very slightly heated through the core.- Note that there is a. step-
-reduction when-region 13 is removed (the nineteenth region to be defueled),"since this is the highest RPF in:the power distribution-used in the analysis. .
The P0KE code achieved stable, downwasd flow in all regions for all o ' cases analysed,: indicating reverse flow will occur even for these very low core power conditions.
- " 4. POKE CODE VALIDATION As noted in Ref. 1, POKE is a validated code for FSV core analysie'.
Minor changes were made to the code to create plot' filee Snd to iterate'. cn the core flow to achieve the desired maximum region tempirature rise-of 350'F. Listings of the code changes are included in the microfiched POKE calculation'resulte. None of these-changes affected the analysis w ' performed by POKE.
-4
- 5. CIRCULATOR OPERATION A check was made to ensure the calculated core operating conditione
-are within the circulator performance envelope. -Based on this check (see Appendix A), there is adequate torque from the Pelton wheel and stall does not appear to be a problem for the higher flow requirements attendsat to the 0.28 MW decay heat value.- There is a concern with circulator stall for the lower flow requirement at the 0.08 MW decay heat value. If it is desired to operate et those very low flow rates, it' is reconumended that the onset of stall be monitored and that a speed be maintained that avoids this region.
8
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' 70ti-32 '90f 08:56 .!D GEN 4T0rilCS'SDG TEL NO:6194594171 .u324 P09.I
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- 6. REFERENCES- -l 5
- 1. Kapernick, R.' J.,-" Core operation During Defueling': Revised Sequence,"-
'GA Document 1910057 N/C, December 7, 1989.-
f
- 2. Letter:1D./Alberstein'tolD.Warembourg,"CorePerformanceInformation for 3rd Quarter of_1989--(End of Cycle 4)",'GP 3368, September 12,:-1989.
- 3. Munos, S., "Va11detion of the FSV Version of the POKE Code,"
s GA Document' 906762/A June 13,_1983. 4 '. Letters D;-Warembourg to F. Dahms, " Removal,of CRD0A's From Defueled. Regions," PG-1930, May 24, 1990.- 'I
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APPENDIX ~A
- w:s i
,, . CIRCUI.ATOR PERFORMANCE EVAL!!ATION
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