ML19253A621
| ML19253A621 | |
| Person / Time | |
|---|---|
| Site: | Crane |
| Issue date: | 05/19/1979 |
| From: | Vollmer R Office of Nuclear Reactor Regulation |
| To: | Stello V Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 7909100524 | |
| Download: ML19253A621 (4) | |
Text
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UNITED STATES
[G
,l NUCLEAR REGULATORY COMMISSION
$ - ( 'M) $
WASHINGTON, D. C. 20555
- ^ 1;.. -
[
May 19, 1979 MEMORANDUM FOR: Victor St.ello FROM:
Richard H. Vollmer
.i
SUBJECT:
'DII DAILY REPORT A.
Reactor and Plant Status 1.
Operations found a large diameter penetration of the RB near the water on the floor that might be used to insert a probe and measure radiation levels.
Possibility being pursued.
Dome monitor reading has decreased - will look for half life correlation.
2.
Decay Heat Loop A seems leak tight except for bonnet leak on valve. Will fix and try again.
Pressure. decay was ~ 15#
in several hours. DH-V6B seems to be tight based on pressure test and rad surveys.
3.
Status of modifications as indicated in attach =ent.
No major problems but minor ones will likely cause a couple day slip.
These dates correspond to turnover to operations following a functional test.
4.
Reactor Coolant and "A" Bleed Tank samples were taken 5/18 at 9:00 a.m.
Results are as follows:
Feactor Coolant "A" Bleed Tank PH 7.6 8.2 Baron 2870 576 H
11 "/K8 2
N2 ND 02 ND Xe-131m (gas) 0.97 pCi/cc Xe-133 (gas) 0.023 nCi/cc I-131 (liquid) 210 JICi/cc M pei/cc Cs-134 (liquid) 42 uCi/cc 7.7 pCi/cc Cs-136 (liquid) 7.2 pCi/cc 1.4 nCi/cc Cs-137 (liquid) 190 nCi/cc 35 pCi/cc Ba-140 (liquid) 25 pCi/cc j, y 790939g L,
v "l A
Victor Stello.
5.
Reactor Status - At 373# with a bubble and drifting toward 300#. Bypass valve now 567. closed. See attachme.at for details of reactor and releases.
B.
Radwaste and EP 2
1.
On May 18 some workers without respirators entered an Aux Building area requiring respiratory protection after getting
~
lost. After being in the area for approximately two minutes,
they found their way to the Health Physics check point.
Whole body counts revealed a maximum intake of 16 nci of I-131 2.
Met-Ed is trying to operate the compactor 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> per day to rid themselves of the backlog of low-level trash. More druns, approximately 29, were moved to the paint shed en May 19, bringing the inventory to 89.
It is anticipated that Met-Ed may resolve the problems concerning the shipment of solid radwaste and that shipments may resume next week.
C.
Environmene veasurement, 1.
Grounu surveys made between 1200, 5/18/79 and 1200, 5/19/79 on both the east and west side of the river showed no levels above a background of 0.02 mR/hr.
2~
Two milk samples collected on 5/17 and counted on 5/18 showed no I-131 over the MDL of 10.5 picoeuries per liter. A grass sample collected near the south gate showed no I-131 activity over the MDL of LE-4 microcuries per square meter.
3.
The three 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> air senples showed no I-131 above the MDL of 1E-12 microcuries per milliliter.
Three grab samples showed no I-131 above the MDL of 6E-12 microcuries per milliliter.
/
/ Richhrd H. Vollmer Attachments cc:
D. Eisenhut G. Smith, IE R. Vollmer D. Crutchfield J. Collins Silver B. Grimes hO9
( c i,
5/18/79 AGENOA TECHNICAL WORKI 'G GROUP 1300 5/19/79 1.
Radioactive Releases
- 94. ctbI'd a.
748, 219, Auxiliary Building Fans -
b.
Point Sources
,wd '.; o, egg
?
/
Measurement of Fadiation Level Inside Containment./
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c.
-=
Dome Monitor
, 4,_,.
_ _. = _ _ _
2.
Plant Status RCS Pro ile
, m a N A' a.
b.
Plant Operations Schedule
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4' '/' I DHP 'A' Leak
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Leak cMeck of DHV-6B pyw
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, r{
Replacement of a train rno charcom
____ers M
0900 5/19 Results - 5/19 f' b h RCS Sample Results -
Sample Bleed Tank
'A' Pressurizer Sample - 5/19
'giu-r.c 3.
Analvsis Reevaluation of existing reco==endation-to draw a bubble vs.
a.
solid operation
,,y fr.
m b.
Procedure for verificaticrn of Solid PZR during solid operations at 300 psi Reduction to 300 psig - increase in loss of pressure protection?
c.
d.
Use of Long-Term Cooling Systen ' B' OTSG and method of tie-in M
ww '
g 4.
Cons tructicn S tatus Estimated Coroletion a.
Tank Fars 5/23
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I,pW'M ?
b.
OTSG 'B' Long-Term Cooling 5/20
/
/
a,
c.
EPICOR (CAD-GUN II) 5/23s -
d d.
RCS Pressure / Volume Control Turnover 5/25 c//4.
for testing
,/t/
e.
Alternate Decay IIeat Genoval Syste= tie-ins 6/20
" "'N.
en t uJ 4
e
RELEASES 1100 (5/17/79) 1100 (5/18/79) 1100 (5/19/79)
-13
-9
-9 748 1.49 x 10 6.4 x 10 3.2 x 10
-12
-10
-l'-
6.4 x 10 219 4.4 x 10 2.81 x 10
~9
-8 Inlet 1.6 x 10~
5.29 x 10 1.3 x 10
-12 Train #1*
6.6 x 10 ^2 7.65 x 10 1
-l'-
7.4 x 10
-l~'
-l'
-11 1.2 x 10 Train #2*
8.44 x 10 8.8 x 10
-9.4-x 40 13
~ ~ ^
-l'-
- 4. 7 6 x 10
-12
.- ' = _;' -
Train #3*
3.8
.x 10 I
~
~
-l'
-12
" 11
~' -
Train #4*
-- - 3. 66 x 10 7.'24 x 10 1.4~x 1Q
. REACTOR CCOLANT SYSTEM PROFILE PLANT STATUS 1100 (5/17/79) 1100 (5/13/79) 1100 (5/19/79)
A B
A B
A B
Th 169.5 170.6 169.3 170.9 168.0 169.9 Tc 157.7 114.5 156.9 97.7
.27.2 116.2 LT 11.8 56.1 12.4 73.2 10.8 53.7 Tst:
155.7 130.1 155.9 129.1 154.4 132.2 PZR Level Cal.
373 356 DVM LT-3 225 R.
C. Press.
386 PT-398 - 465 PT-398 - 373
/2-399 - 416 PT-399 - 331 S/G Level 420" 96 T.
,30" 967.
420" 96~
Turb. 3/P 60%
Closed 60%
Closed 5 6 *.
Closed I.C.T.
High 304.37 306.5 303.8 Avg.
194.16 193.4 192,7 M.C.
Te p.
213 12S 128 hbU I
. _ _ _