ML20085D261
| ML20085D261 | |
| Person / Time | |
|---|---|
| Site: | Saxton File:GPU Nuclear icon.png |
| Issue date: | 06/10/1963 |
| From: | Hetuck D, Langford F WESTINGHOUSE ELECTRIC COMPANY, DIV OF CBS CORP. |
| To: | |
| Shared Package | |
| ML20083L048 | List:
|
| References | |
| FOIA-91-17 308.3, NUDOCS 9110150375 | |
| Download: ML20085D261 (4) | |
Text
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e CIIEMICAL SilIM TEST 308 3 -
Title:
Chemical Shim Control Under Nucle 4te Boil $ng Conditions l
l Approvals Procedure Date 6-10-63 Technical Approval I I. ut, d ,{p rAldenda Accepted for Saxton No. Date Approva). ,
Experimental Progra j,
v 1 6-13-63 SE' Approval d /d i l," / p- [,3 f311 Dh,01,0.01 A0375 ofo424
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CHD'ICAL SHIM Tim 308 3 J Title rhemical Snim Control Under Nucleate Boiling Conditions orge M 7o providt power reactor demonstration of etem shim control under local nucleate bc1? lng conditions.
'II. Conditiens 2 This test vill start upon completion of test 308.1, therefore:
Beactor power 15 Mdt T ave $1kOF to $230F Pressurizer Pressure 2100 pal
- 2. The boric acid mix tank contains a solution of the same boron content at the main coolant system.
, The purification demineralizers are by-passed.
- V. Frecautions
- 2. The plot of control rod position vill be evntinued. The same
- iethod of determining the unexpiatned reactivity loss vill be used no was used in 308.1. A senior operator should be present any time that the rate of corrected rod withdravsl is equal to or greater them 1/2" per e16ht hour shift.
- 2. For thin test, attention vill be- concentrated on plate out of boron an a scale forming on the ooilirs surface. This vould be I
a power reversible hide-out. N lovance is to be made for the '"
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voids formed in the core excep the cor ection already incorporated l during the pre'uous unborated power measurements as the void p coefficient is not firmly known. The void effect vill be a part g {F,j/
of the unexplained reactivity. ,e p/
f V. procedure 1, Return the pressurizer operating pressure to its normal value of 2000 psi as rapidly as possible (spray with heaters cut-off). Do not move control rods if possible but follnv on decreasing T avg.
Obtain data and plot the corrected rod position (See Appendix A).
- 2 3eturn 7 avg. to ' )30 CT. Obtain dsta and plot the corrected rod por.ti on , (See A1.pendix A.) Place control rod in auto.
3 Increase reactor power to 20 MWt (100%).
Not e The following vill be conducted throughout the test:
n Co*y arisons of the meneured vs. predicted core reactivity. A rerj es of curves will be available to determine when the u: .12ained reactivity loss is being approached or exceedeL (see Aliendix A.) The reactitity vill be checked every half j - y hour, b- Each chift the charging and letdovn system vill be operated long enough to at least re-circulate one volume of the purifi-cation surge tank or for the required time to obtain scraples.
- c. Main coolant sampler, vill be taken immediately prior to starting nnd rtopping letdown flow.
- d. Main ecolant and pressurizer samples will be te. ken in accordance with Appendix B to 303.1.
- e. Conduct a heat balance on the primttry and secondary system on an hourly basis and set nuclear instrumentaion as required. /
- f. The purificaticn surge tank hydrogen overpressure vill not be7 ?
reduced belov 7 psi. Upon reachin6 7 pai, gradually increase <
the hydrogen overpressure to a pressure alightly above 7 psi.'
- g. Make-up will be added to the purification surge tank when the level is reduced to 20%. Return the tank level to 80% full.
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C. Continue power operation, providing the unexy ned reactivity limit is not exceeded, until there is suffici t confidence in the experimental results to varrant proceeding to the next step. (Order
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of a week.) Make peri.> die measurements in accordance with the attached schedule.
$. Beset power range scram set points to 115% full power. Remain in coincidence and adjust only one channel at a time. Also adjust the gain to make 23 5 Mdt equal to 100%. [,
- 6. Increase rmetor power to 22.0 }Mt. Remain at this level until a f , s' flux vire irradiation has been made and the results s'aov that further power increase is feasible. Continue reactivity plot as per step 4.
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Westinghouse DC-372 r=ou j tmTc~'P6 der T vision .-
ATOMIC POWER DIVISION W SAXTON SITE $ ave June 24, 1963, -
V. E. Abbott R. ombo (3) e act Sax.t< Procedure 3083 S. Bartnoff E. A. Hooper '
R. J. Creegan S. Pekar F. Frarth R. J. French SNEC - SAXTON J. M. Gallagher H. W. Gravec I. Finfrock P.'B. Haga D.E.Retrick(1 A. J. Impink W. H. Layman F. L f,an6 ford H. J. Williams C. F. Obermesser D. Howard ..
L. S. Tong /Efferding J. Roth D, Beatty (3)
H. J. von Hollen SNEC - READING '
R. A. Wiesemann V. Rt.,ja6 opal D. R. Rees J. P. Cunningham P. Cohen W. D. Fletcher D. Hanlen - WREC
- 0. N. Hamilton (2) - WREC
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Attsched please find the poreedures for chem shim test 308 3 which is now underway at Saxton. These prociidures have been previously distributed at the Saxton site but lack of reproduction facilities at Saxton prevented the pro-duction of enough copies to meet the full distribution list.
f) .
Atomic Power Division - Development Coordination' -- J. Weisman
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. Attachment t
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- f. cc u
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