ML19322C838
| ML19322C838 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear, Crane  |
| Issue date: | 11/27/1979 |
| From: | Cauanaugh W, Creswell J ARKANSAS POWER & LIGHT CO., NRC - NRC THREE MILE ISLAND TASK FORCE |
| To: | |
| References | |
| TASK-TF, TASK-TMR NUDOCS 8001280562 | |
| Download: ML19322C838 (23) | |
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Transcript of Proceedings nv NUCLEAR REGULATORY COMMISSIOf1 TMI SPECIAL INQUIRY GROUP l
INTERVIEW 0F WILLIAM CAVANAUGH PART I l
6 i
(THIS TRANSCRIPT WAS PREPARED FROM A TAPE RECORDING)
PLACE:
Little Rock, Arkansas DATE:
Tuesday, 27 November 1979 l
ACE - FEDERAL REPORTERS,INC.
OfficialReponers AM North Capitol Street Washingten. D.C. 20001 NATIONWIDE COVERAGE DAILY T***" "*j 7
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1 TMI SPECIAL INQUIRY GROUP 2
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l 6l Little Rock, Arkansas l
7 Tuesday, 27 November 1979 8
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13 14 15 (THIS TRANSCRIPT WAS PREPARED FROM A TAPE RECORDING) 16 17 18 l
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20 21 0
23 24 Ace Federal Reporters, Inc.
25 l
6030 01 01 2
NRCmte i
Ilerr Vw 's:
Okay, we can get started.
2 Today is November 2 7,
.v79.
It is 9:06, and we 3
are in the conterence room on the eighth floor of the
,m
(_)
4 Arkansas Power & Light of fices in Little Rock, Arkansas.
5 Present f or this in terview are Mr. William 6
Cavanaugh, Vice President, Generation and Construction, 7
Arkansas Power & Light, and Stephen Riggs, of Hou se, Holmes, 6
and Jewell, representing Arkansas Power & Light.
Present 9
from the Special Inquiry Group are James Creswell and 10 Frederick Hurr.
11 Mr. Cavanaugh, we have given you a copy of a 12 document enti tloo "NRC Special Inquiry Group Witness 13 Notification."
Have you read the document?
I4 Cavanaugh VOI CE:
Yes. I have, gk/
15 Herr VOI CE:
Do you understand the information lo contained in it?
I/ Cavanaugh VOICE:
Yes.
16 Herr VOI CE:
Okay.
Mr. Cavanaugh, we could start with lY
-- maybe you could give us a brief history of your 20 nuclear-rela ted e lucation and experience up to the present 21 time.
22 Cavanaugh VOI CE:
Well, l e t's see.
Related to nuclear, my 23 ex perience goes back to 1962, I believe it was, when I was 24 selec ted to -- while in the Navy as a naval officer, I was
,o k) 25 selected to go into the Naval Nuclear Power Program.
8630 01.02 3
NRCm te i
Basically, from that point until 1969 I was in the naval 2
nuclear program, qualified as a chief engineer on the S5N t
3 naval nuclear plant.
And 1969 to the present I have been
< ()
4 with -- I have been with Arkansas Power & Light and involved 5
with its nuclear program in various capacities.
i 6
Creswell VOICE:
This is Jim Creswell speaking.
'7 Mr. Cavanaugh, I believe you told us that you are i
8 presently Vice President, Generation and Construction.
How l
Y long have you served in that capacity?
10 Cavanaugh VOICE:
Since January of this year.
f 11 Creswell.
VOICE:
Jim Creswell again.
i 12 What are your responsibilities in that posi tion ?
j 13 Cavanaugh VOICE:
Well, my responsibilities in genera tion j
14 and construction are basically over six cepartments.
We I
15 have a generation operations department which has in it both t
16 the fossil and the nuclear operations, as well as the 17-main tenance.
18 The next department is the project management I
19 de par tmen t, which has responsibility a t the present time for 20 three or our f ossil pro je c t s..
f 21
.The next de partment is the generation engineering, 22 which has the various disciplines in it responsible for 123 providing the various engineering support for both the 24 operating plants as well as the projects.
I 25 We have a (Inautible) environmental services l
~
l
t-8630 01 03' 4
NRCm te i
depar tmen t, which has in it quality a ssurance, nuclear fuel 2
management, licensing, and technical analysis, which is 3
basically chemistry and the environmental support.
()
4
'A generation technology de partment, that has in it 5
availability engineering, plant ' perf ormance evaluation, and 6
generation research and development.
7 The last de partment is administrative services and 8
project support, which provides contract administration, 9
administrative services, planning and scheduling, cost 10 control.and training, generation training.
11 Creswell VOICE:
Jim Creswell again.
12 In your present position, how do you interface 13 with the vendor f or your Arkansas Nuclear Plant Unit 1, B&W, 14 Babcock & Wilcox?
IS
.Cavanaugh VOICE:
Well, I am not the key interf ace wi th 16 Babcock & Wilcox.
We have interf aces with B&W through our 17 licensing section, through our nuclear operations section, 18 of course Arkansas Nuclear I i tsel f.
And there may be an 19 o ccasional in terf ace -- well, the fuel management sec tion 20 would have interf ace.
And then there may be occasional I
21 interf ace with the other groups.
22 Creswell.
VOICE:
Mr. Cavanaugh -- Jim Creswell. speaking --
23 who do you re port to in the Arkansas Power & Light 24 organization?
l 26
,Cavanaugh VOICE:
I report to the president and chief l
r 6630 Cl 04 5
NR Cm te i
execu tive of ficer, Mr. Ge rry Malden.
2 Creswell.
VOICE:
I see.
Now, I believe you said in January 3
1978 you started serving in your present capa ci ty.
()
4 Cavanaugh VOICE:
January '79.
5 Creswell VOICE:
January '79.
Excuse me.
6 Prior to that time, what was your position with 7
the company?
6 Cavanaugh VOICE:
Prior to that time, I was executive 9
director of generation construction, having been appointed 10 to that position in August of '77.
Il Creswell.
VOICE:
In the time period of a pproximately August 12 of 1974 until May of 1975, what would your position have 13 been with Arkansas Power & Light?
14 Cavanaugh VOICE:
Manager of nuclear services, primarily --
[_s}
15 at that time, the organization that was set up to support 16 the operating plant, as well as continue the support and 17 management of the Arkansa s Unit 2, Arkansas Nuclear 1, Unit 16 2 Project.
19 Creswell VOI CE:
Okay.
What were your primary 20 responsibilities in your position at that time as manager of 23 nuclear operations?
22 Cavanaugh VOICE:
Well, at that time I had the 23 responsibility for the technical support of Arkansas Nuclear 24 1, Unit I and 2.
I had under me a licensing group, f uel k>
25 management group.
In the project group, we had the
=
b G630 01 05 6
NRCmte I
mechanical and electrical groups that were supporting 1
2 primarily Unit I and Unit 2.
Let's see.
3 I believe tha t those were the key elements of that
()
4 4
organization at that time.
l 5
CresWell.
VOICE:
What responsibilities did you have for 6
interf acing with Babcock & Wilcox Company at that point in 7
time?
i 6
Cavanaugh VOICE:
Well, at that time I was -- I was one of 1
Y the key interf aces with B&W on items related to the support 10
-- at that time, let's see, '74?
Unit I was still in 11 startup testing, and so as a result I was a key interface 12 with B&W on the project tha t was still in eff ect at that 13 time.
And of course, Unit I went commercial December '74, 14 and we then continued -- I continued my involvement as an 15 interf ace with B&W through -- you said May of '75?
16 Creswell VOICE:
Yes.
17 Cavanaugh VOICE:
Through that time.
Where I was the key 16 con ta c t.
Of course, there were other contacts with B&W from IV our company.
- 20 Creswell
VOICE:
Would it be a f air characterization that, j
21 regarding technical issues.that developed during startup 22-testing of Unit I, that you would have been the primary 23 interf ace with Babcock & Wilcox Company?
24 Cavanaugh VOICE:
No, not necessarily.
B&W had on site a
.O
-25 startup support group, and really the key interf ace l
L L
l l
G630 01 06 7
l NRCmte i
related to the test program was between the plant staf f and 2
the B&W support group on site.
3 t.reswell.
VOICE:
Was that centralized in any one
(')
4 individual, that contact with B&W7 l
5 Cavanaugh.
VOICE:
AP&L's contac t?
j 6
Creswell' VOICE:
Yes.
7 Cavanaugh, VOICE:
Well, of course,- the pl a n t -- I guess we E
8 would call him the plant superintendent at that time would 9
have been the contact.
But'of course, ne also, for 10 in s tanc e, had representatives.
We had a test working i
. 11 group.
There were AP&L and B&W people on that, as well as i
j 12 probably Bechtel.
1 13 Creswell VOICE: -Well, I still don't quite understand.
Is 14 it a picture of anyone on the staff contacting B&W regarding O
15 issues that would develop, or was there a management control 16 over it?
17 Cavanaugh VOICE:
Well, of course, it all funneled.
On the 4
16 plant staff, it funneled to the plant superintendent.
He 19 was then -- of course, he delegated various responsibilities 20 to members of his staf f.
And of course, he was the key j
21 individual.
22 Crfsvell' VOICE:
A t w ha t point would you have become 23 involved in these communications?
24
-Cavanaugh.
. VOICE:
I would.become involved if there was, 25.
let's say, an item that could not be resolved, an item that
d630 01 07 8
I NRCmte i
I had to have interf ace through the Little Rock support 2
group to B&W.
3 Creswell.
VOICE:
Okay.
If I unoerstand what you're saying, iO 4
tr there wes ea issee thet erese d"rlov t e testino greare-4 5
at ANU-l that the plant superintendent could not resolve in i
6 discussions with site B&'i personnel, that issue would be 1
7 followed -- would be forwarded to you for further U
resolution?
y Cavanaugh VOICE:
That's correc t.
10 Creswell' VOICE:
Okay.
Who did you report to?
.11 Cavanaugh-VOICE:
At that time I reported to the director of 12 power production.
13 Creswell VOICE:
When I say report to at tha t time, tha t i s 14 f rom approximately August of 1974 to May of 1975.
And your O
15 10 Cavanaugh VOICE:
Director of power production.
17 Creswell VOICE:
Who was he?
l 18 Cavanaugh VOICE:
Mr. James H. Woodward.
19 Creswell VOICE:
Mr. Woodward.
I 20 (Pause.)
J 21 Creswell VOI CE:
Mr. Cavanaugh, now I'd like f or you to, if i
22 you ' would, describe any pre ssurizer level problems that
-23 you're aware of that occurred at Arkansas Nuclear One, i '
24 starting as f ar back as you knew it could be a problem.
1
-25 Cavanaugh VOICE:
Well, I think the one that became I
4 i
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'8630 01 08 9
NRCm te i
evident and caused us to have extensive discussions with B&W 2
. occurred in, I-believe, in the f all of '74, subsequen t to
'3.
some reactor trips, where we lost pressurizer level
()
4 indication for a.short period of time.
And of course, we, 5
as a follow-up to that, had extensive discussions with B&W o
related to why, of course, we were losing level, what was 7
diff erent about Arkansas Nuclear One than previous -- I say 8
" previous"; previous B&W plan ts tha t had gone into 9
commercial operations and was in fact there an unreviewed 10
~saf e ty question involved here.
.31 These I believe first occurred in the fall of 12
'74.
13 Creswell VOICE:
How was the problem resolved?
1 14 Cavanaugh VOICE:
Well, the problem was finally resolved 15 with some basic operating -- to the best cf my recollection, lo i t was resolved primarily with, one, to establish that there 17 was not a saf ety, unreviewed safety question, and this was 4
18 demonstrated at a point in time in these discussions by 19 B&W, who had done some extensive analyses and comparisons to 20 other plants and similar trips and plant characteristics 21 after-the. trip.
22 It was also resolved f rom the standpoint of 23 maintaining pressurizer level indication within the 24 indicating band by. changes basically in our operation and in y
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25 our control systems.
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8630 01 09 10 NRCm te 1
0 VOICE:
Okay.
Was this i ssue re solved to your 2
satisfaction?
3 Cavanaugh VOICE:
Yes, it was resolved to our satisfaction I
')
4 and it took a while to be resolved, but yes, it was resolved
,a S
to our satisfaction.
o Creswell VOICE:
This is Jim Creswell speaking again.
7 Mr. Cavanaugh, I'm going to show you a document c
here.
This document is a memorandum to a Mr. Ole s wi th the 9
Babcock & Wilcox Corporation, who was a senior projec t 10 manager at that time.
The subjec t is Arkansas Nuclear Unit
.11 1, pressurizer level set poin t.
And this memo was 12 a pparently f rom you to Mr. Oles.
Would you tako a look a t 13 it to ref resh your memory?
14 (Pause.)
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15 Cavanaugh VOICE:
Yes, sir.
16 Creswell VOICE:
In this memorandum, you note that in 17 another letter -- this was a le tter of J. Kaylin to 16 J. Anderson, dated September 26th, 1974 -- t ha t a req ue s t lY had been made tha t the operating procedures at ANO-1 be 20 modified to increase the normal operating pressurizer level 21 from 180 inches to 210 inches.
22 You point out that if this change is made, that 23 some operating experience a t TMI-l has shown that, wi th the 24 level increases being experienced during a transient there, n
I h
(s' 25 that you might lose pressurizer level indica tion high.
You
G630 01 10 11 NRCm te I
further state that you cannot implement the change un til 2
f urther justifica tion and resolution of_ the following 3
comments is provided.
Those comments are s
()
4 That no analysis has 'been provided to AP&L to L
5 verify that this change will not cause the pressurizer to 6
fill solid, resulting in loss of level indication l
7 (Inaudible) without reactor trips 6
Two, no analysis results have been provided which
/
9 indicate the accident analysis contained in the FSAR would 10 not be affecteds
.ll Three, by basing the recommendation on a transient 12 including one turbine bypass valve partially open, it is not 13 valid since the turbine bypass system is not (Inaudible) and 14 --
more than one valve may stick open, resulting in a more
~
15 severe transients 16 And four, explain the reason for the difference in 17 the location of the level tap at ANO versus TMI-l and Oconee 18 1, 2 and 3.
19 Were you ever provided with an analysis by B&W to 20 Justify that level increase?
21 Cavanaugh VOICE:
I believe, to the best of my recollection, 22 that af ter subsequent discussions with B&W, tha t they 23 changed their recommendation on changing that particular 24 level change.
'2S Creswell VOICE:
To your knowledge, did B&W ever do an
'8630 01.11 12 NRCmte l-analysis -before making the recommendation to justify the 2
increased level?
3 Cavanaugh VOICE:
I don't know tha t.
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4 g
VOICE:
Were you ever provided an analysis s
5 regarding more than one turbine bypass valve malf unctioning?
6 Cavanaugh VOICE:
I can't recall at this time whether we did 7
or not.
8 Q
VOI CE:
Were you ever provided an explana tion for 9
the reason for the difference in the location of the level 10 tap a t ANO versus TMI-I and Oconee I, 2 and 3?
11 Cavanaugh VOICE:
I know that we had discussions with B&W 12 about that.
In my understanding, it had something to do, I 13 believe, with the manufacturing.
But I don't recall the 14 exact B&W reason for the change.
\\-
15 Creswell VOI CE:
Mr. Cavanaugh -- Jim Creswell speaking 16 again -- I'm going to show you a copy of a figure out of the 17 FSAR for ANO-l.
It's entitled " Pre ssurizer Outline," and 18 the figure number is 4-6.
Would you take a look at that, 19 please, sir.
20 (Pause.)
21 Creswell VOICE:
In your opinion and your prof e ssional 22 judgment, is that tap shown properly located on that i
23 drawing?
24
.Cavanaugh VOICE:
I don't know that I could make that O
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25-determination right now.
I would say that the level
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k 8630-01 12 13 sensing' nozzle says typical of three,.and I gue ss I'd have NRCmte' ll 2
to go back to the point in time --- I a ssume that this was in 3
. the. original - we11, I'm not sure whether it was in the (h
Did you say what the --
5 Creswell
. VOI CE :
I believe that's the FSAR.
6 Cavanaugh. VOICE:
I guess I'd have to go back and compare it
=7 to the as-built drawings.
f 6
Creswell VOICE: - Would you say that that drawing shows.the 9
tap to be located at the tangent line bet :.n the 1
10 cylindrical body and the hemispherical. lower head of the f'
11' pressurizor?
12 Cavanaugh Vo!CE:
Yes, it shows i t to ha in that region.
Of i
13' course, i t says " typical. "
I'm not sure tha t tha t's meant f
14 to indicate an exact location, seeing as how there are no N
15-
' dimensions on thi s outline.
Creswell 16 VOICE:
Okay..
17:
Next I'm going to show -you a copy of Table 7.11, 18 which is entitled "Information Readouts Available to the 19 Operator for Moni toring Conditions in the Reactor, Reactor 20 Coolant System, and in the Containmen t."
This is on page
' 2l 7-56 of 'the FSAR and I t's Amendment No. 36 dated April 6th, 22
-1973.
{
23 ~-
Would you take a look at t ha t, pl ea se ?
24
-(Pause.)
p i
V
'25
.Cavanaugh -VOICE:
I couldn't. v9rify that this is from our W
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18630'Ol'13 14 NRCmte-l __
FSAR without looking at it.
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2 Creswell VOICE:
Sure.
3 (Pause.)
Creswell VOICE:
As an item in this table, a major 4
5 parameter, pressurizer level is indicated, and the i
o indication range or indicator range is specified as zero to 7
4 C0 inc he s.
To your knowledge, is that.informa tion correct?
8 Cavanaugh VOICE:
I don't know that I could say right now.
9 I would assume that it was deemed to be correct when we put 10-it in the FSAR.
t Creswell VOICES-To your knowledge, has it ever been 12 reviewed or changed?
13 Cavanaugh VOICE:
I can't say that.
I don't know.
I don't 14
-remember, since i t wa s some time ago.
That was 1973.
15' Creswell VOICE:
Okay.
Let me ask you this.
Could I ask
_16 you to review your FSAR, the copy tha t you have here, the il 7 control copy, and see If 1 t has 'been changed?
IU Cavanaugh VOICE:
Yes, I could do that.
19 0
VOICE:
Why don't we go of f the record, then.
20 Cavanaugh VOICE:
Okay.
21
-(Discu ssion of f the record.)
22 Cavanaugh VOICE:
These are the same table and figure that's L
23-in there, my FSAR.
- 24
~Creswell
_ VOICE:
Is your FSAR a control copy?
25 Cavanaugh VOI CE:
Yes.
i f
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i 8630 01 ~l4
'15 NRCmte i
Q VOICE:
It is?
So tha t from that I would assume,
[
2
.unle ss there is an error' in your control FSAR documen t, that 3
L these would be the latest 1up to date information?
'()
Cavanaugh VOICE:
To my knowledge.
4 5
Creswell VOICE:
Okay.
Next I'm going to show you a o
document here which is a piece of correrpondence from the 4
7 Babcock & Wilcox Company directed to you, dated November.
6 18th, 1974, f rom Mr. Bowe s, the senior project manager --
9 but the memo was sent out, was signed by H. A. Baker, the 10 project manager.
The subject of this memorandum is Arkansas
.11 Nuclear One pressurizer level set po in t, B&W reference 12 NSS-8.
13 I'd like for you to take a look at thi s 14 memorandum.
i t
15 (Pause.)
~
10 Creswell VOICES-In reading this memorandum, I note tha t 17 the recommendation for increasing the pressurizer level f rom 16 180 to 210. inches was discu ssed.
Ba si cally, if IJunderstand 19
'the memo-correctly -- and if I'm wrong, would you correct me 20
-- t ha t they_ were withdrawing the recommendation.
21-Cavanaugh VOICE:
Yes, tha t's correc t.
I 22 Creswell-VOICE:
They f urther suggested that your operators 23-be instructed to secure letdown flow and increase makeup 24.
flow.immealately following a reactor trip, to help maintain 25 pre ssurizer ' level.
1 l
l I
i
8630 01 15 16 NHCm te I
What did you do 'with this information that B&W 2-sent to you?
i 3
Cavanaugh VOICE:
That was then forwarded on to the plant l():
4 for their evaluation.
I believe also that this situation 5
was presented to continue the review by the plan t saf e ty 6
committee and also the safety review, the corporate saf ety 7
review committee.
l 6
I can't recollect about the letdown flow, but I 9
can -- I do remember the tact that in fact we were manually 10 initiating high pressure injection in order to maintain the
'll level.
12 VOICE:
Approximately when did you start that?
13 Cavanaugh VOICE:
I don't recall the exact time.
It may 14 have been bef ore that le tter.
15 Q
VOICE:
Would you have initiated that change 16 without a B&W recommendation?
Would you have initiated it 17 on your own?
By "your own," I'm saying the management 18 structure of Arkansas Power & Light.
l 19 Cavanaugh VOICE:
Which change?
20 Q'
VOICE:
Tha t i s, to decrease or stop letdown flow 21 and increase charging flow, starting --
-22 Cavanaugh VOICE: 'Well, that would work, that would be a t
23 change to a procedure.
It would be reviewed by the plant ~
24 saf ety committee, and then if they f elt that it presented an 25 unreviewed safety question or felt that they wanted the t
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safety review co mmi t t ee to review i t, then i t would be sent 2
to the saf e ty review committee for their review.
3 Q
VOICE:
But to your recollection, was tne decision
,\\(,)
4 tha t was made to do this based upon this B&W recommendation S
at this point of time?
6 Cavanaugh VOICE:
I can't say that.
7 Q
VOICE:
Was that ul tima tely the corrective action 6
taken regarding the pressurizer level problem, that is, an 9
operator ac tion?
10 Cavanaugh VOICE:
I don't believe tha t was the ultimate, the 11 ultimate correction.
The ultimate correction, I believe, 12 involved some changes in the control systems so tha t we 13 would not lose level indica tion.
We had a concern, as I 14 recall, about getting too many cycles on the high pre ssure
(
)
lb injec tion nozzles, and we wanted to get into a mode, I 16 believe, where we did not have to do that.
17 Q
VOICE:
And that was done primarily by changes to 18 con trol systems?
19 Cavanaugh VOICE:
Right.
Wh'n I say control systems, I mean 20 I believe that we made, for instance, a change in the 21 in tegra ted control system.
The basic goal was to reduce the 22 pressurizer level decrease and those things that would cause 23 it, for instance, excessive blowback on the steam dump and 24 bypass system and steam saf ety valves.
p
\\ Y 25 Creswell VOICE:
Next I'm going to show you a document
8630 01 17 18 NRCmte i
dated December 6th, 1974, f rom William Cavanaugh to 2
G.M. Bowles, senior projec t manager at B&W.
The subject is 3
" Arkansas Nuclear One, Uni t I, pre ssurizer level set point."
()
4 Would you take a look at that to refresh your memory?
S (Pause.)
6 Creswell VOICE:
In revieving the text of this memorandum, 7
you state that previous correspondence had not addressed the 6
f ac t that the ANO lower level tap is 40 inches above the ta p 9
on Oconee and Three Mile Island.
You further stated that 10 you haa problems with this arrangemen t, ands 11 I tem one, the FSAR Figure 4.6 shows the lower taps 12 located below the heater bundles, near the bottom of the 13 pressurizer, which is in conflict with the actual location.
14 Now, I've previously shown you Figure 4.6.
In g
(_)
Ib reading your statement here, it would tend to indicate t ha t
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16 you did have a problem with the way that tap was illustrated 17 on the figure.
16 Cavanaugh VOICE:
Well, I do not remember the specific 19 reference about that being above or below the heater 20 bundle.
I do recall that, of course, that we did note that 21 our lower level sensing nozzle was in f act 40 inches above 22 the -- wha t wa s, I gue ss, on TMI-I and on Oconee; and we 23 wanted f urth ;r explanation of t ha t.
24 Creswell VOICE:
I'm going to jump ahead in time a little.
g-~3
(_)
2S There wa s a telephone call apparently on the 12th of
f 6630 02 01 19 NHQn te l
December, 1974, between yourself and Mr. Baker, who I assume 2
was with Babcock & Wilcox, and Mr. Rui ter, H-u-i-t-e-r.
Do 3
you recall what the substance of that telephone conversation
()
4 was?
5 Cavanaugh VOICE:
Not right of f hand, no, I oon' t.
o Creswell VOICE:
Do you recall whether or no t the location 7
of the lower taps on the pressurizer were discussed during 6
that conversation?
Y Cavanaugh VOICE:
No, I don't.
10 Creswell VOICE:
In the two memorandum that I presented to 11 you here today, the one da ted 1)ecember 6th and the one dated 12 Oc tober 16th, you nave asked questions or showed concern 13 about the location of the lower level taps.
I'd like to 14 again ask yous Were you ever told by B&W or anyone why
,(J l
k IS those taps were 40 inches higher?
10 Cavanaugh VOICE:
I'm sure - well, I'm sure we were.
Our 17 main concern was not t ha t t he tap was diff erent s our main 16 concern was to ensure tha t we did not have an unsaf e 19 condition.
And the location of the tap was just pa rt o f the 20 overall analysis and investigation that we were conducting 21 at the time.
22 Creswell VOICE:
Mr. Cavanaugh, I'm asking i t f rom this 23 pers pec ti ve.
Here you have a component installed in your 24 plant where a design change has been made, a design change
(
_/
25 that has resulted in a '>ncern, a sign 111can t -- a
8630 02 02-20
. NH Cm te I-significant concern,. as indicated by these -memoranda.
Yet'I 2'
don' t' qui te understand -- well, l'could understand why you 3
would want to resolve the concern.
- (),
4 But it would seem to me to be of interest as to S-w hy the taps were changed.
o Cavanaugh VOICE:
I think it's more important as to the
{
7 question of whether or not the condition of the plant on a 8.
subsequent trip
-- it seems to me to be more important than
'9' where a tap was located.
The location of the tap was just 10 one item that was part of an overall big picture thing, the 11 big picture being what happens to pressurizer level, what 12 happens to the reactor coolant system from a trip a t high 13 power levels.
14-Creswell VOICE:
Mr. Cavanaugh, do you have any IS documentation regarding that telephone conversation that was I
16 held on the 12th of December?
I 17 Cavanaugh VOICE:
I don't know if we do or not.
18
.Q VOICE:
I'd like for you, if you would, to conduct 19 a good f aith search --
20-Cavanaugh-VOICE:
What was the date of that?
21 Q
VOICE:
December 12th, 1974.
' 22 A
VOICE:
1974.
A telecom-between --
- 23L Q
VOICE:
The parties indicated here are Baker,
';24 Cavanaugh,~and Huiter.
25
~A VOICE:
Baker, B&W. 'Okay.
4 1
J e
. ~. -
6630 02 03 21 NRCm te I
A VOICE:
We'll check the files and see.
2 (Pause.)
3 Creswell VOICE:
Ge tting back to the December 6th, (j
4 1974, memoranda and your problems with the loca tion of the 5
level taps, i tem 2 states that, following a reactor trip 6
f rom 75 percent full power level, indication was lost for 45 7
seconds.
This indicates that following trips f rom 100 6
percent full power, the level indication could be lost in 9
excess of one minute, which does not s
crespond with the 10
" lost momentarily" statement in reference one -- reference 11 one being the letter, Baker to Cavanaugh, dated November 12 16th, 1974.
13 You f urther s ta te in the ending of the memorandum:
14 Please review the above to determine what actions can be
(^h
\\ s
15 taken to re solve these items and provide us with your
~
16 recommendations and reasons for that level tap discrepancy 17 by Januar 6th, 1975.
18 I t would appear f rom reading this tha t you se t a 19 deadline f or their re spon se to this particular item, your 20 concern about the location of the ta ps.
21 Cavanaugh VOICE:
Well, I don't think it's the location of 22 the taps, again.
Again, it's the concern about pre ssuri zer 23 level indication, pre ssure, the plant's response after a 24 trips not the business of -- not the primary concern of
!q 25 where the ta p is.
No, that was not the primary concern.
G630 02 04 22 NRCmte I
g Vo!CE:
Well, I was -- let me read this sentence 2
again Please review the above to determine what actions 3
can be taken to resolve t he se i tems and provide us wi th your
()
4 recommendations and reasons for the level-tap discrepancy by S
January 6th, 1975.
l o
You speci f i call y addre ss le vel-tap --
7 Cavanaugh VOICE:
That's right, but that's --
u Q
VOICE:
- di sc repant <.
tha t's "and the r easons. "
So I think V
Cavanaugh VOICE:
10 you're taking just that part out of context.
I t was the 11 overall big pic ture that we wanted additional inf orma tion 12 on.
13 Q
VolCE:
Now, obviously they didn't meet that --
14 B&W didn't meet that deadline of January 6th.
15 Cavanaugh VOICE:
I don' t know that.
I can't say tha t they lo didn't today.
I'd ha ve to go back and research all the q7).
17 riles to say that they didn't.
I can' t make that 16 s ta tement.
IV Q
VOICE:
We'd like f or you to conduct that search 20 of your files and determine if that informa tion was or was 21 not provided to you.
22 A
VOI CE:
Tha t memo was what?
23 0
VOICE:
This is December 6th, 1974.
24 A
VOICE:
December 6.
(3 25
( Pau se. )
-