ML19322A628

From kanterella
Jump to navigation Jump to search
Discusses Util 710513 Response to AEC Noting Noncompliance W/Fsar Sections Re QA Program.Response Unsatisfactory as Util Had Adequate Info on Cable Diameters to Obtain Properly Sized Cable Trays
ML19322A628
Person / Time
Site: Oconee Duke Energy icon.png
Issue date: 05/27/1971
From: Seidle W
US ATOMIC ENERGY COMMISSION (AEC)
To: Henderson J
US ATOMIC ENERGY COMMISSION (AEC)
Shared Package
ML19322A606 List:
References
NUDOCS 7911210699
Download: ML19322A628 (3)


Text

.

0

).

We L

2g...

~

.s.

m' r

J.

... g. g.

.!

  • E.

-*f

,,.*$7

. s

  • 3 A,,.-..

. *;g y;,7,;-

<%**.~

i..

.,r,

.y..

7 a,4 O,._e,s.. @)

.r.. a

....e,...,w...3..e, r.a,..,.

e.

..s..

.~

.~........

..w

.w

.../. s 4 p.

wP re.,

4... -

ww.y. 4 ca e,.. 3.s y.. s c..,

e

). w.

f e j.i.

.s

.v.--

.a

,.. ~.,

A --.

.se wva*.V.f gww.n..

.r. w.Q; w

,., f-e,,,g

., s v.....i.. = p g*, -

..w.

w...

,3 f

.9

..,..--. w..--. p W : n m. m.,. e. v.

-n

.. v s..

. e..:.e..(..,d..

...s.3..

........ a. %.,a.3.s..

....s...,4.. s t.e.

.s.a...

g.O. %.e.

.g 4,.

,j t.

y.....

g..,.

s. 1..r.._.,4..s

. ';,.c........

.s...

4.,

,w

.,, e

.s. ; :. s.,

. 34..

-..s.n t v"

.s -,..... s.... e :., e..s...,

m.,s.

m.

fg o,,

yf.,

.i,.. L,...a.

a...

. y #.......,.,

.e,,,,.

. s.....e....

.u. s w.

4..-

.fu..

,,,c,-

wv....

.4

.3....

a

..... >.e.s,..C., f.

,.u a.

4

%e....om.a a,.e gc..

3.,.

.Q

.w

.a v.

  • ,.a,

.e

,.,.,a.4.

. u.

we

.,...~

'n...

..cJ...a....%.,,

.3...,

J..,.,.

e.

s a.

.cw.e j

..y g....r. s. o. a,..

. w a ~.. a.

.a..

..a 4.....

,s.:. s....

2

.,s

.O......,,.a.

.w c,

s.

.T.-..- s'jd--..'..b#-

y'O*^**'-*-*'

A '- *-

'--*--*-'.*s"*

  • O.

t..

3. 1
2..... v-.a

,.,/

e..-

3.. e,.. *13 0 4

.. a. e.a..,.. a..,,., v

...,.2

...w.

.... i,

.a e.

..a-2.,....

...w..

.m..

,ws.

~..,4.i.,

  1. .,,* Ts.

.,aw

,...,. w

.a

,s,

.v,,

f w.,

y 4.e......

u,.. 4 l.. s,a v..

....., - -,,,.f.

~g s.,,

_y.j, L*,

  • w,

_3i,,,.

..t

. 6ay

_%..-a

...,.g. 3 e f.e.s e., 3

.w..... oa3 s.e.~.,. w.a w.. e. a...,.e

,3.7g.,,o

.i. e

,s 7w.

w.

..s.~

w

,v ySo. Cp. oum. Sed %.;..'.

.e.,.i m....,.. e c..,r.,,,/

.T

. e.#. 4.+ 7,..,

7

~

.j.

. f.

p

,r } gn

.... %...a.

w a u..s

.+

s

.. a s_,,,

. m.,,..e...s L. a 4..,4...e,.,., wy, n

w.

w

..p

..: s.

w w.

w 3

..w

.../ w a.4 6./... e C 4..,... S S w.

.a.

- a..a y w w

.O.

r.*4. @.e.4,...

., P.L.e.

5

-.,. -..........C.. >.

.*9.s.

..,.. >,...,.w...w..

.41 o.../.19 aa. 2./.s..g.

2......

.a.

o

%..~.

a...

s*

v.. n 4..,... % u.

w

..e s.a. s.g... e, * %.. s.

e.e...,,,

e C1...

iV,.

w

.a

.. *. s.. s.. g a,

,a

.a a f g 3. 4.#4 o..,

4. r.,
  • w c...e. 7.w.

,.s,e.4 c

.o.u.,.

s.2 :.~...e.a..c.

..e..

w s.

j...-

.g

.,Cy.**/

- - ^ -

n.. s..

w e

2s. i.e....

,4.,

e L..n

..t..,

a -

, n.....:

.n.o,,,.. s...u.

w yg, -....

.' '.' a..a.s ee aculd. '. '. e ' * '- "w*. '.~. v..". a.- ". a. '..date.e a-

".w-"i'.. ^ ~..=

w

.w

.y a,,,4...,

+4

.., 4, _,..a.e.

......w.

.m.

.. w. j,...

.w,.

4.

....,......,,..s

...../ 4. s <. z~...

..w

'/

v-c.y,.c, cy.

-C r.e.co.=.,.o.

..i

'/

o CO ?.epor',, NO. 5C-M9/'TC-3

2.,.,

s.

-,....ecor, o.

0occ e-c 4

7911210 N f

(m J. 3. Henderson Xay 27, 1971 3.

In an inspection on Septe=ber 28 - Cet:ber 2, 1970,./ C. E. Murphy, Reactor Inspector, discussed the need to Observe cable tray rcuting and tray fill limits vish C. 3. Ayecek, Field Engineer, Electrical.

At that time, only a very few saft.t/-related cables had teen installed.

Aycock was advised at that time that C: ;11ance vould 20.e a elese in-spection of this feature.

4 7ne cable and tray installaticn van discussed vi.h the licensee durir,g inspections conducted en @ t:ber 26-23, 1970,2/ 7,3c3 3 37 ;_,,, 197c,;j

+

sad en January 5-8, 1971.1' A cen.:tr =tien deficiency notice v a issued at the conclusien of tha inspection en C :cber 26-25, 19~0.1 Ihis OLN questioned the adequacy cf the cable and tray design re fiev.

The inspector again expressed cen:arn abcut the ader,ua:7 of desigr.

re'rievs in discussicas with C.

1. irlie, Cuhe's Princi;al Electrical Ingineer, during the inceection :.:, anus.ry. Wylie implied at that time that smother review vculd
  • .e.: ale and agreed that additienc1 trays vould be installed tc sur;rt and protect the cable.

5 Insufficient dete.is of the uccis alluded tc in the licensee's recponse are given to subst:ntiate the licensee's clai that cvar-nesting vill act be a probles.

6.

Insufficient details are given in the li:ensee's respense to sup;cr the licensee's statement that physical overicading is not a prcble=,

7.

The statement that "The s.ddi:1cn of cables in the everfilled trc/c has been stopped and additional cabic trays have been adden where necessary and practical" is c biguous and risles. ding. Tr27s have nct teen added at many places where the everfill ;r:ble: exists. Overfilling should have been stopped nuc' aa 'ier to te effective since essen.1 ally all of the cable for Unit 1 has nov been incialled.

8.

The addition of,rsy rails, tea,4-e y, could pu. :he licencee in conformance with the FSAR but in a fev osses vould result in a ton since the cable in sc e tracts a: e filled n; to the point cf alt:st rea:hing the tra/ above. Additien cf higher trsct rails vculd net solve the'proble: but veuld result in an inferior installation since

, air circulatica veuld be reduced. Vertical separation of trays at present is only five inches.

9 Che require ent of the FSAR is not being re:. 7ais fact overrides.the other censideratiens. It is the c;inien of Region II that the pri=ar/-

/ CO Repcrt No. 50-269/70-10 UC0 Report No. 50-269/70-11 t/

1 00 Report No. 269/70-12

.,/

' 1 00 Report No. 50-269/71-1 I CON dated November.25,1970

y J. 3. Hendersen May 27, 1971 reascn for the violaticn is that design reviews were inadequate even though the licensee was cautiened abcut the possibility of the problem.

Duke's response regar:iing the veliing red contrcl is considered to be un-satisfactory. Tne reasons for this position are as folleva:

1.

Se centrol of red had been discussed with the licensee by C. E.

Murphy, Reactor Inspector, on three succeeding incpections. Each time the licensee inferred that steps vculd be taken to 1: prove contrci.

Se inspector for Units 2 and 3 hai also diccussed velding red centrol with the licensee and had teen told that steps vould be taken *o cor-rect the problem.

2.

2ecause of the lack of centrol in recent conths, tha licensee cannot identify with any degree of certc_inty the source of the reds used in any velds.

If, at a later date, a particular heat of veli rods is found to be defective, then the licensee vill be unable to identiff the velds in which the red vas u;ed. Se identity cf the red in a system cust be considered to te ac important as the identity of the pipe in the system.

,lf V~ %

l W. C. Seidles CO: I:CEM Senicr Reacter Inspecter

Enclosure:

Ltr to Davis fr. S ies dtd 5/13/71 cc w/ encl:

A. Giambusso, CC:HQ

1. Ko: nblith, Jr., 00:EQ R. E. Ingelken, CO:EQ a'.
3.. C 9 3..e.i i.f, C^. U. A, d

o..

C. E. Murphy, CO:II "o

s e

t i