ML19253A525
| ML19253A525 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 05/22/1979 |
| From: | Vollmer R Office of Nuclear Reactor Regulation |
| To: | Stello V Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 7909100211 | |
| Download: ML19253A525 (5) | |
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UNITED STATES o,
NUCLEAR REGULATORY COMMISSION
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"Fange out sh:uli :egia on 3/:L wit'
^ pleti:n instalIed 'n tha t a n '< #ar 3
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clushine and byfr, testing o' t e line #-en the spr:y pump h
and the Tank carr sFould ac co pleted today, h.
'3'nti1g 0F th
~'100P system s " o u l ; a.? cm pieteu today.
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5/22/79 AGENDA TECIC;ICAL WORKING GROUP 0900 5/22/79 1.
Radioactive Releases hW i
a.
748, 219, Auxiliary Building Fans
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Point Sources - Waste Gas Vent Header Leak Check 2.
Plant Status a.
RCS Profile b.
Plant Operations Schedule Replacement of "B" train FH3 charcoal filters
&l l'3G., lA Y ye-i 0 Pressurizer Sample Results - a 9 w u
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h,,,, g,f[pyf Pressurizer Solid - 5/22 C#
Reactor building heise gauge co=p rison it nsole - h"9 N V.),1 oh qwye9-Sk ET.
~b Reactor building sump level measure =ent - evaluate need k N hweh w"ks% - d 3.
Prestations bm.w k % P,.2 3 b ). Mvk,
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a.
Use f o g-term coo stem"p"OTSG cethod of tie-in pw - e. m
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b.
Radioactive l' quid w.ste =anagement plans Es, 9lll 14 Gr EftA.LT wp
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Analvsis a.
Reevaluation of existing reco==endation to draw a bubble F l &.'$,t 2Aba,/l_ y +ey s o I..
vs. solid operation j/
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b.
Procedure for verification of Solid PER during solid opera-tions at 300 psi c.
Reduction to 300 psig - increase in loss of pressure protec-tion?
d.
Reevaluate the curve supplied for throttling steam bypass based upon present te=perature and pressure condttions N
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5/22/79 5.
Construction Status Estimated Completion a.
Tank Farm (Zero Leak Testing) 5/23
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OTSG "B" Long-Term Cooling EPICOR (CAP-GUN II)q Q Q g, Qg, 5/23 c.
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RCS Pressure /Vol' e Control Turnover for testing eM,
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Alternate Decay Heat Re= oval Syste= tie-ins 6/20 h *Tlpl h Y 80 W
60s P00R ORNK
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i REL'ASES 1100 (5/20/79) 1700 (5/21/79) 0500 (5/22/79)
-8 748 4.8 x 10-9 8.51 x 10-9 5.00
- 7. 10
-11
-12 219
- 7. 4 x ' 0 9.45 x 10-11 3.79 x 10 Inlet 9.2 x 10-9 4.77 x 10-9 3.80 x 10-9 Train #1*
9.0 x 10 9.02 x 10-12 5.44 x 10-12
-12' Train #2*
6.6 x 10 1.03 x 10-11 5.60 x 10-12
-12 Train #3*
1.1 x 10-12 1.02 x 10-11 9.86 x 10-11 Train #4*
6.1 x 10-12 4.67 x 10-13 5.50 x 10-13 REACTOR COOLANT SYSTEM PROFILE PLANT STATUS 1100 (5/20/79) 1700 (5/21/79) 0500 (5/22/79)
A B
A B
A B
Th 169.2 170.2 168.3 170.1 167.2 169.5 Tc 156.5 102.4 15h. 8 100.2 156.5 100.5 T
12.7 67.8 l1 5 69.9 10.7 69.0 Tstm 155.6 131.0 154.8 129.7 153.8 127.3 PZR Level Cal.
373 379 DVM LT-3 227.6 R.C. Press.
PT-398 - 286 PT-398 - 276 PT-398 - 268 PT-399 - 233 PT-399 - 215 Recorder - 285 S/G Level 410" 95%
430" 99%
430" 96%
Turb. B/P 57%
Closed 57%
Closed 56%
Closed I.C.T.
High 299.7 303.5 303.4 n
Avg.
194.9 192.8 193.3 H.U.
Temp.
128 128 128
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