ML20059B637
| ML20059B637 | |
| Person / Time | |
|---|---|
| Site: | Big Rock Point File:Consumers Energy icon.png |
| Issue date: | 08/22/1990 |
| From: | Eddy J CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.) |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| TASK-***, TASK-OR GL-90-04, GL-90-4, NUDOCS 9008290201 | |
| Download: ML20059B637 (8) | |
Text
-
~ /*~ '
.e:
-a
. s.
H l
1s
-. {
s 4 >:
' Consumers:
Power powrams MKMGAN'S PROGRs55 General of ficest 1946 West Parnell Road, Jackson, MI 49201 * (517) 788-0550 AEgust: 22', 1990'
~
7..
. Nuclear Regulatory Commission Document' Control Desk
. Washington, DC '20555-i 1
l
. DOCKET 50-155 - LICENSE DPR BIG ROCK POINT PLANT -
L CORRECTION TO GENERIC LETTER 90-04 RESPONSE - STATUS OF GENERIC SAFETY ISSUES i
1 Consumers Power Company letter dated June-28, 1990,' transmitted the Big-Rock
' 3 J
Point response to Generic Letter 90-04 concerning the status of Generic 1'
Saiety Issues. That letter contained some errors in that some Palisades Plant related information was inadvertently substituted into the Generic Safety l
Issue status tables for Big Rock Point. This letter provides the corrected version of the tables as they should have orginally appeared. The i
I
, corrections are indicated by slashes."/" in the right-hard margin. This subject has been discussed with the Big Rock Point Project Manager. Please contact us if you have any further questions.
.i 7
J Daniel Eddy i
i Plant Licensing Engineer f,J
.CC ~ Administrator, Region III, USNRC NRC Resident Inspector - Big Rock Point 1
1 i
02130 t
^
9008290201 900G'22 PDR ADOCK 05000155 P
{
OC0890-0393-NLO2 1
g 1
A C%iS ENE72GYCO/V!PANY t
w" 2
..l;'./~ *1%. - o v
m
@Myq ;A vi%
v m'",
i N ' '
s y'
t.v6%' ~ =, e.W* '
. ; G.
M m,
n'
> > 3~
7r' 4 0, ym:;mlW ui.'s v
. -y
?
p N ;% ruse M;: u m
w":,= - -
4.
w
,m, d
W-
!ig! :
u,-
> iibri
.- s -w ya 7
- c.c
- f.4 g,+ 4L2 e;,e r
p%u
~ < c. M.L.W O 'c z-y
.9
- " =,'
- mX-~
y c.
ss 1 nja ?
+ p':
p:
n.
n w
wy n-3,.
- 7 "j
-w.
s v.
s
.=1;..
py r,s3 sj+.
i
- Tc
-y y' ! 4 f +*f, W " p(
- w4..
' ' s F' j
-I.,,'
c ;.r.
f-@g s
'i'
.m z.
3 jg M - A;;
d-u i
p,911
- n -
g~
>x w..,. w; m w a.y,. m,,
y;~
o y'. 4
' q f > > aiA,.
- 1 e
r g._
'-.i:
'p:7:ap " ( -d ' *,
<+qp p'
43; vh,.
2 r
s w:
, ~
c it,
, s t
y:.
,t
(
~ i
.-},.-
4-Y s
b, 4
7
- iv m;i. fb
_m us t4 1 *!..
4 i
S' m,;d 15_
..T?
di
- i. l ?
j ~ V I.
y
- q. d k, >
s n
8 ws
-.1-
.'5-e
+
- w q a
-. P,;
p 9 4., ;,.g pw i
m, m
e 9
+
g[ f _ q,e f : i 5
/
u,
- v, _s2
%pl} ; +
-9,-
't
- }.
l 1
p.. o #
4 R
t
' y..,
'( ? '
v, s, Wgg g m]u r, y M,/(
? -lATTACHMENTL 2
9--
.z t; e
w fl o,
i si >
p p 1
"e Consumers t Powerf Company ?
~ ' ' '
F_ C, ',
m
- BigTRock: Point Plant?
N
- m.
m pW
? Docket:50-155:
L xi px z '
d {)* S
'I
-i-r a
A. ;
'\\
A n..
p_fy u
- y
\\
h
\\
t t
.-gv.,
4
-rq t
i 0_?
' hl{
n > ~,
s,._..,
w s
m b ] r-E..
t..
E - t ';,,
('
,A
.i 1
U ';j '.
- n>
==
,s:-
'+t,
=.
l '
_3 s 3
,6 i -
?#t
.. 4 y';:
s.
^
47 t g
4, s
& q
. A.
.:q..-
r, o
& Wl L v g:
-L(
t-
..fd,i Uw (j "%
-ENCLOSURE'IDFROM GENERIC LETTER 90,
@l " ',cE m
t STATUS OF. GENERIC SAFETY' ISSUES:
' O. u M..*
1
., L%
CORRECTED VERSION i
e&.,
. m.
' August 22h 1990 j.ji ;
- n
- .
.n 0"
e s
)
i
,"9'.
1 p
la 4"
l 4[.;
\\
)
s f
Y?O
, ! hi :.
J. '1j. i-Y r :4
,Q
.},^
,. g gl...
b
[ N 2-:
i..
I' t
t*
,l
.f
'z g k
I'
l
,n
- .,1 4
s
- \\.
v,'
H
.;yy,!--!
1 y
i
.O
- ... [z' i
.i
..p it i +
n b
I y
g 3r
.m.
y bh yj I
-:1 1
6 Pages 3
OC0890-0393-NLO2-s 1
i i
'h k
A
+
.- - z
- =-
=
e
- . -. - V;
- - -- r..
- :=2 6
3-7 ~ y '~
= =" 273FXa1 myy
~
..~ y
_c.
.g -...
y
- -) ;- wz
-~ ~
?. 5 Q Ye l
'.jf
,c a, ~
' ~ ' '
.g.,
s
{-]
.x
.~.
. :l
' " A. l.
2
.x FACILITY NAME: BIG ROCK. POINT-DOCKET NO:
50-155:
LICENSEE:
CONSUMERS POWER CO.
STATUS OF LICENSEE 1hM EMENTATION OF GENERIC SAFETY ISSUES-RESOLVED WITH' IMPOSITION OF REQUITIMENTS OR CORRECTIVE ~ ACTIONS GSI/(MPA No)
TITLE APPLICABILITY STATUS
' COMMEPTTS ~
40 (B065)
Safety Cohcerns Associated With lAll BWRs-LNC-NRC'SER 7/8/82.
' /.;
Pipe: Breaks.in'.the BWR Scram System 41 BWR Scram Discharge Volume Systems
-.~ All' BWRs.
NC-
~ NRC Ltr: 9/21/84 :
43 (B107)
Reliability of Air Systems All Plants' I
l Projected (complete 12/31/90 /i J CPCo Letter.2/20/89 p-
[ 4/
51 (L913)
Improving the Reliability of All Plants.
_C_
Projec.ted completeJ12/31/90)
'~~
Open-Cycle Service Water Systems
- 2 CPCo Letter'1/29/90T 1 -
~
n.~
67.3.3 (A017)
Improved Accident Monitoring All-Plants.
C Awaiting NRC SER
~
/ l~
75** (B076)
Item 1.1 - Post-Trip' Review-
,All Plants
.C
.NRC SER 11/5/85-
./:
(Program Description and Procedure) 75 (B085)
Item 1.2 - Post-Trip Review All Plants' C'
NRC'SER in Concurrence
~ ~ /[
Data and Information Capability Projected 9/1/90
- Status column completed ~per attached.. guidance.
OC0890-0393-NLO2L "s%.
.-,w...
gy-g
-+.'**+w N -% h-wy
+pm. e-r-
--i +.i.
.9--v..m gry
,.4 4
g.
sep
.9fe.%-.,.m e,,y
+g y p.pns
_%,y.rg.,p.y 7
..--e p.mp.,y.
~. - -
- p. g ~:-
w; 5
ig
-3
==&
g3
- :n c -
>- m m-s:g:
_ =.
pm, -
~
---n
=
" = = = =
- =l
'^ =~~ ~ '
}_
~
L fjf f=
A g
==, [.
.,y y. ~ 2 9=, p g g3. n y Q +
a} g=:...
.:7 g;_
3m3
- ,y yne - g,
=?
~ Jj% :
.=
. 7-Jri ~ -f up g4
]E
- :;3;;;.w-1
- -L yg-g.]
r sn w.
~
.x-
~
g@mV-GS7/(MPA No)
TITLE APPLICABILITY.
-STATUS
~ COMMENTS 1
- -:7 -
7 IM 75 (B077 Itu 2.1 - Equipment Classification All Plants:
~ C NRC SERi6/6/88
~
and Vendor Interface(Reactor. Trip System Components) 75 (B086)
Item 2.2.1 Equipment Classifica-All Plants
.C ~
NRC SER 6/3/83..
tion for Safety-Related Components 75 (LOO 3)
Item 2.2.2 - Vendor Interface All-Plants E
Response due 9'/24/90 for Safety-Related Components 75 (B078)
Item 3.1.1 & 3.1.2 - Post-All Plants C-NRC SER 11/19/85-Maintenance Testing'(Reactor
~
Trip System Components)-
75 (B079)
Item 3.1.3 - Post-Maintenance All Plan'ts-C NRC SER 11/19/85 Testing-Changes to. Test Require-ments (Reactor Trip System Components)
F a
75 (B087)
Items 3.2.1~& 3.2.2:- Post-All Plants C:
NRC'SER-11/19/85~
Maintenance Testing (All 0ther
^
~
Safety-Related Components) y.
75 (B088)
Item 3.2.3 - Post-Maintenance All Plants C
NRC SERL11/19/851 Testing-Changes to, Test Require-7 ments-(All Other' Safety-Related Components) 75 (B080)
Item 4.1 -- Reactor: Trip System -
All Plants.
NA~
-See GL 83-28.
Reliability (Vendor-Related Modifications) 2
.g
,w.
' ~
OC0890-0393-NLO2-x
...,, ~ - -
~..,w
-.n.n.,
<:,.m ;; Q,
- --j fQ., &4,_,-s,Y;'
__ ~;l . :,:::,;;-'* -^..,,.- -.,4.
- e.,.,,..
'T."'
,,,;L, *, u,, ; n :,;, %,,;,, ; f.,. c
y.
pg:-
, ~
y3
- p_
.w
- A+ y yy m v-
= -
g y
r
-m
, 7. ;p ; ~, -3 3
, v.
a rg
- :~
....y '..
om m
,..49 :
.;,.} g
, :*: _ ;, f:( '
.*-,./
c.
'A GSI/(MPA No)
TITLE APPLICABILITY STATUS:
COMMENTS-~
~
-+:
75 (B081)
Items 4.2.1 & 4.2.2 -: Reactor?
All PWRs-NA' Trip System Reliability -
- a-Maintenance-'and Testing (Preventative Maintenance and Surveillante Program for i
Reactor Trip Breakers)
_.=.
75 (B082)
Item 4.3;- Reactor Trip l System _
-'All W and B&W NA t._
-Reli sbilit y' - Design' Modifications
~ W ", E'
~ '
(A6tomatic-Actuation of Shunt Trip Actachment for Westinghouse and B&W-
-J Plants).
' ~
J
- i 75 (B090)
Item 4.3 - Reactor Trip System All W & B&W.
NA-Reliability - Tech Spec. Changes.
- ~
' (Automatic Actuation of Shunti
~
Trip Attachment for Westinghouse and B&W Plants)-
75 (B091)
Item'4.4 - Reactor Trip.Systea LAll;B&W Plants-NA
~
~
-Reliability.(Impro'taents'in
~
Maintenance.and Te,c Procedures L - --
- ~
for B&W Plants)
.m
- W 1
_.~+-
A.
OC0890-0393-NLO2 y
,am-wamp't'--
.-h_m.
w-
-me ryg 4 yseem ge-M'u---i h'*
h.-";
>a.
.hM.h.
-m
,,h
y.
3; 3 3 3-- - ;- g--,,
---;- =5-_ ;.
=-
._,y p:;.g
,,9:.; p _ g y,
g, g.
...n=' v..
g e.
- 2 - _,n,.
v-3 n:
m3 y-w.,_
1., _ g39
^
u.% ;A-m -
2
, ~ } g=f
. + -
2:
G p.. '
]
'q H
E 3,~ ;.
~'y
~
4:2_~~
? %;
GSI/(MPA No)
TITLE-
. APPLICABILITY
' STATUS '
' COMMENTS-. ~
75 (B092)
Item 4.5.1
- Reactor Trip Sys' em All Plants-C
.NRC;SER.11/19/85s
+
t Reliability-Diverse Trip ~ Features
~~
J --
~'
O-(System Functional' Testing)j 75 (B093)
Items 4.5.2. & 4.5.3. -' Reactor Trip All Plants C-
'NRC SER.'2/13/89 System Reliability ' Test:Alterna.
NRC.: SER,8/10/89 :
tives and'IntervalsL.(System.
Functional' Testing)
~"~
86 (B084)
Long Range-Plan for~ Dealing-All BWRs C
CPCo LetrerL4/25/904 -
with Stress Corrosion
.ICSCC~ Program Rve.2'
~
Cracking in BWR Piping 93-(B098)
Steam Binding of Auxiliary All PWRs
-NA.
Feedwater Pumps
~
99 (L817)
RCS/RHR Suction Line Valve
. All PWRs -
NA-
~
Interlock'on PWRs 124
. Auxiliary Feedwater: System LANO-162, Rancho
. NA..
Reliability.
Seco,' Prairie
- Island.16@,
Crystal River-3
~
1~-
!Ft Calhoun' A-13 (B017)
Snubber' Operability; Assurance.a
.All Plants
'NC.
1NRC, Letter'4/2/82 Hydraulic Snubbers
~
~
7
- p11, J
_ H
, w-y:
OC0890-0393-NLO2 7
_C
,s.
..m.
L.s
..;_.q g_,
JC. _ ; ;,.IU'-j ; ;.., 4.,,,
.;g4
- g. _$. L l,:,.,,,.;_ n, r;;g,,.; ; J'
.._;, ;,,74, ; _gji.,,
.,4_
- .g,.
,4
- ~,
.n f'
'iJ. "
n.n
~
T
' ' " r -
y - -
g n.me
--m..c. m.
w n
.n g=an m 'y"_}m.'-
~
t
_3..
. _ ~.
~
i_
'l,
~ ~
~
Y,- _
,~
^,.
l.,,, -
~
- ~
'^~
n e
- e _.
w
__: q:-
~ ~..
,n 3
m -..
4a
~~e w
GSI/(MPA No)
TITLE' APPLICABILITY
' STATUS-COMMENTS 5 f
A-13 (B022)
Snubber Operability Assurance -
All1 Plants
~
jC Tech Spec Amendil/11/84j y_fg r.
^q
- Mechanical Snubbers INRC' Letter 7/31/841 7/:
~
A-16 (D012)
Steam Effects on BWR Core.
Dyster Creeke NA
! Spray-Distribution?
s & NMP.-l'
~~
~
A-35 (B023)
Adequacy:of.Offsite; Power
-All Plantsur C.
Tech.Spee. Amend and NRC SERi.
Systems
- 3/8/82:
4i~
/
B-10 Behavior of'BWR' Mark III All:BWR Mark III:
~
I2 _
/
Containments tPlants B-36 Develop _ Design, Testing'and
- All Plants'with NA Maintenance Criteria for-OL ' Applications l
AtmosphereTCleanup SystemT y
Jf Air Filtration.and~ Adsorption-Units for Engineered-' Safety'
~
Features Systems and for-
~ %
Normal' Ventilation Systems' H
~
3 B-63 (B045)'
Isolat! ion of' Low Pressure.
All' Plants
- NC
'NRC Letter 8/12/80
$/
Systems Connected;to the Reactor
~ _
^
Coolant. System Pressure: Boundary a
rr-
.4 e
p
.m, OC0890-0393-NLO2
.a g-i e e :aa m-q
-d' KwAyIm am g.
grg.
m -,
-+w
,1g'no.
^f==
.r
'p
.=
p-1sh.='p--'
y q' y qv-,
..g g.
pwg
%q
-p g,.a-^'
g.g.
n mw.g--
s
+
Ric L..*
l','e o
?'
l
-n Attachment to From GL 90-04 GUIDANCE FOR COMPLETING STATUS COLUMN IN ENCLOSURE 1 q-1.
Provide a separate entry for each licensed reactor unit. If the information is identical for multiple units, so state.
2.
If a CSI is not applicable to a unit (s).-enter "NA".
3.
If a GSI is applicable. but nu Euanges were necessary to implement _ the resolution, enter "NC".
If ita CSI 'mplementation was completed prior to issuance of the operating. ilcense, -enter "NC",
as a no post-licensing changes were necessary.
4 if_a GSI is applicable, submittal of information and/or changes were necessary and such submittals were made or changes are complete, enter "C".
Also identify the licensee's document (s) to the NRC which certified completion, and the_ document date(s).
5.
If a GSI is applicabic and changes are necessary but such changes are-not yet fully implemented, enter "1" and the projected month and year of-completion. Provide a brief explanation of the outstanding work in the
" Comments" column.
6,.
If implementation guidance for a resolved GSI was issued recently and the licensee is still evaluating the appropriate response, enter "E" and the projected response date.
7.
The " Comments" column may be used to explain any entry in the " Status" column.
\\
p l
OC0890-0393-NLO2