ML20138D140: Difference between revisions

From kanterella
Jump to navigation Jump to search
(StriderTol Bot insert)
 
(StriderTol Bot change)
 
Line 18: Line 18:


=Text=
=Text=
{{#Wiki_filter:- . - -                   ..- - - - - .                   __ - -                   - -.- .           . -. - . _ _- _. ...--
{{#Wiki_filter:- . - -
                                                                                                                                                    .. - -.-.,
..- - - - - .
                *
__ - -
                                                                                                                                                              I
- -.- .
                                                                                                                                                              '
.
    ..
-. - . _ _- _. ...--
                                                                        April 25, 1997
.. - -.-.,
i                  Mr. S. A. Patuiski
*
                  Site Vice President
                  Point Beach Nuclear Plant                                                                                                                  l
                  6610 Nuclear Road
                  Two Rivers, WI 54241                                                                                                                        {
                                                                                                                                                              1
                                                                                                                                                              I
                                                                                                                                                              i
                  SUBJECT:                NRC INSPECTION REPORT 50-266/97002(DRS); 50-301/97002(DRS)                                                          l
                  Dear Mr. Patuiski:                                                                                                                          !
                  On March 4,1997, the NRC completed an inspection at your Point Beach Nuclear Plant,
                  Unit 2, including an inspection at your corporate engineering offices. The focus of this
j                  inspection was on assumptions used in the containment fan cooler operability evaluation.                                                    .
:                  At the conclusion of the inspection, the findings were discussed with those members of                                                      )
'
'
                  your staff identified in the enclosed report.                                                                                               '
..
i                  During this inspection, the inspector noted discrepancies between the initial assumptions
April 25, 1997
i
Mr. S. A. Patuiski
Site Vice President
Point Beach Nuclear Plant
6610 Nuclear Road
{
Two Rivers, WI 54241
1
i
SUBJECT:
NRC INSPECTION REPORT 50-266/97002(DRS); 50-301/97002(DRS)
Dear Mr. Patuiski:
On March 4,1997, the NRC completed an inspection at your Point Beach Nuclear Plant,
Unit 2, including an inspection at your corporate engineering offices. The focus of this
j
inspection was on assumptions used in the containment fan cooler operability evaluation.
.
:
At the conclusion of the inspection, the findings were discussed with those members of
)
'
your staff identified in the enclosed report.
'
During this inspection, the inspector noted discrepancies between the initial assumptions
i
!
!
                  used in the containment fan cooler operability evaluation, and those used in Technical
used in the containment fan cooler operability evaluation, and those used in Technical
                  Specification Change Request (TSCR) 192. However, of more concern, was not                                                                 i
Specification Change Request (TSCR) 192. However, of more concern, was not
                  considering the throttled service water valves in determining the effect of the delayed                                                     I
i
                  containment spray and containment fan cooler start times and the lack of an original
considering the throttled service water valves in determining the effect of the delayed
                  design basis calculation to support the bases for Technical Specification 15.3.6.B. Within
I
                  45 days, please provide the formal calculations quantifying the delayed start times for the
containment spray and containment fan cooler start times and the lack of an original
                  containment spray pumps and containment fan cooler assumed in the containment
design basis calculation to support the bases for Technical Specification 15.3.6.B. Within
                  integrity evaluation supporting TSCR 192.
45 days, please provide the formal calculations quantifying the delayed start times for the
                  In accordance with 10 CFR 2.790 of the Commission's regulations, a copy of this letter -
containment spray pumps and containment fan cooler assumed in the containment
                  and the enclosed inspection report will be placed in the NRC Public Document Room.
integrity evaluation supporting TSCR 192.
                  We will gladly discuss any questions you have concerning this inspection.
In accordance with 10 CFR 2.790 of the Commission's regulations, a copy of this letter -
                                                                          Sincerely,
and the enclosed inspection report will be placed in the NRC Public Document Room.
                                                                                                                                                              i
We will gladly discuss any questions you have concerning this inspection.
                                                                          /s/ J. A. Grobe
Sincerely,
                                                                        John A. Grobe, Deputy Director
i
                          *]00035                                       Division of Reactor Projects
/s/ J. A. Grobe
                                                                                                                                            I
John A. Grobe, Deputy Director
                                                                                                                                                              ,
*]00035
                  Docket Nos. 50-266, 50-301
Division of Reactor Projects
                  License Nos. DPR-24, DPR 27                                                                                                 /
,
                  Enclosure: Inspection Report 50-266/301/97002(DRS)
I
Docket Nos. 50-266, 50-301
/
License Nos. DPR-24, DPR 27
Enclosure: Inspection Report 50-266/301/97002(DRS)
!
!
See Attached Distribution
,
,
                  See Attached Distribution
i
i                                                          SEE ATTACHED CONCURRENCES
SEE ATTACHED CONCURRENCES
l                 DOCUMENT NAME: G:\DRS\ pol 97002.REV
l
                  To receive a copy of this document. Indicate in the box *C' = Copy w/o attach /enot T = Copy w/ attach /enci *N* = No copy
DOCUMENT NAME: G:\\DRS\\ pol 97002.REV
{
{
To receive a copy of this document. Indicate in the box *C' = Copy w/o attach /enot T = Copy w/ attach /enci *N* = No copy
i
i
OFFICE
Rill:DRS
l
Rill:DRS
l
Rill:DRP
l
Rill;DQP a l
'
NAME
O'Dwyer/kjc
Ring
Mc-Barger
GrabgtMGT
DATE
04/
/97
04/
/97
04/
/97
04 pts /97
OFFICIAL RECOR D COPY
llll! ln
I H I I
I
I ill ll
l l
l l ll
11
9705010046 970425
'
'
                    OFFICE              Rill:DRS    l            Rill:DRS        l          Rill:DRP          l              Rill;DQP a l
ll
                    NAME                O'Dwyer/kjc              Ring                      Mc-Barger                        GrabgtMGT
ll
                    DATE                04/    /97              04/    /97                04/    /97                        04 pts /97
PDR
                                                                    OFFICIAL RECOR D COPY
ADOCK 05000266.
              9705010046 970425
* * **** * *
            PDR
G
              G
PDR
                  ADOCK 05000266.
_ _ _
                                                        '                                                ll
;_
                                                                                                          ll! ll ln
_ _ _
                                                                                                          * * **** * *
.
                                                                                                                        I ill ll
_ _
                                                                                                                        I HII I
.
                                                                                                                                ll l
__
                                                                                                                                            11
.
                                                                                                                                      l ll ll
          _ _ _
                                          PDR        ;_                                                                                    .
                                                                  _ _ _                      .                 __                              __
                                                                                                                                                      .


  . _ - . . - - ..                 -.       . - - -           -               .               _         ~ . - - -       .-           -. . . . _ -
. _ - . .
- - ..
-.
. - - -
-
.
_
~ . - - -
.-
-. . . . _
-
i
i
  .
.
l
l
!
!
Line 103: Line 157:
l
l
t
t
l                  Mr. S. A. Patutski
l                  Site Vice President
l                  Point Beach Nuclear Plant                                                                                                        I
;                  6610 Nuclear Road
[                  Two Rivers, WI 54241
l
l
l                 SUBJECT:           NRC INSPECTION REPORT 50-266/97002(DRS); 50-301/97002(DRS)
Mr. S. A. Patutski
                  Dear Mr. Patuiski:
l
l                                                                                                                                                   l
Site Vice President
l
Point Beach Nuclear Plant
;
6610 Nuclear Road
[
Two Rivers, WI 54241
l
l
SUBJECT:
NRC INSPECTION REPORT 50-266/97002(DRS); 50-301/97002(DRS)
Dear Mr. Patuiski:
l
On March 4,1997, the NRC cnmpleted an inspection at your Point Beach Nuclear Plant,
!
!
                  On March 4,1997, the NRC cnmpleted an inspection at your Point Beach Nuclear Plant,                                              '
;                  Unit 2, including an inspection at your corporate engineering offices. The focus of this                                        j
'
'
                  inspection was on assumptions used in the containment fan cooler operability evaluation.                                         l
;
                  At the conclusion of the inspection, the findings were discussed with those members of
Unit 2, including an inspection at your corporate engineering offices. The focus of this
                  your staff identified in the enclosed report.
j
'
inspection was on assumptions used in the containment fan cooler operability evaluation.
At the conclusion of the inspection, the findings were discussed with those members of
your staff identified in the enclosed report.
l
;
During this inspection, the inspector noted discrepancies between the initial assumptions
!
used in the containment fan cooler operability evaluation, and those used in Technical
Specification Change Request 192. However, of more concern, was the use of an
informal calculation to support the delayed containment spray and containment fan cooler
start times and the lack of a design basis calculation to support the bases for Technical
j
l
l
;                  During this inspection, the inspector noted discrepancies between the initial assumptions
Specification 15.3.6.B.
!                  used in the containment fan cooler operability evaluation, and those used in Technical
,
                  Specification Change Request 192. However, of more concern, was the use of an
                  informal calculation to support the delayed containment spray and containment fan cooler                                        ;
                  start times and the lack of a design basis calculation to support the bases for Technical                                        j
l                  Specification 15.3.6.B.                                                                                                         ,
                                                                                                                                                    !
I
I
I                 In accordance with 10 CFR 2.790 of the Commission's regulations, a copy of this letter                                           ,
I
In accordance with 10 CFR 2.790 of the Commission's regulations, a copy of this letter
,
'
'
                  and the enclosed inspection report will be placed in the NRC Public Document Room.                                               !
and the enclosed inspection report will be placed in the NRC Public Document Room.
i                 We will gladly discuss any questions you have concerning this inspection.                                                       i
i
!                                                                                                                                                  !
We will gladly discuss any questions you have concerning this inspection.
                                                                      Sincerely,                                                                   ;
i
!
Sincerely,
!
!
l
l
l                                                                    John A. Grobe, Deputy Director
l                                                                    Division of Reactor Projects
l
l
                  Docket Nos. 50-266, 50-301
John A. Grobe, Deputy Director
l
Division of Reactor Projects
l
Docket Nos. 50-266, 50-301
License Nos. DPR-24, DPR-27
'
'
                  License Nos. DPR-24, DPR-27
Enclosure: Inspection Report 50-266/301/97002(DRS)
                  Enclosure: Inspection Report 50-266/301/97002(DRS)
See Attached Distribution
<                  See Attached Distribution
<
                  DOCUMENT NAME: G:\DRS\ pol 97002.REV
DOCUMENT NAME: G:\\DRS\\ pol 97002.REV
                  To receive a copy of thle document, Indicate in the box "C" = Copy w/o attach / encl T = copy w/ attach /enci"N" = No copy
To receive a copy of thle document, Indicate in the box "C" = Copy w/o attach / encl T = copy w/ attach /enci"N" = No copy
                    OFFICE           Rlll:DRS       lE.       Rill:DRS_         lc.   Rill:DRP                 lg Rlll:DRP             l
OFFICE
                    NAME             O'Dwyer/kjc A Ring MF                             Mc-Bargerfi4 k fo             Grobe
Rlll:DRS
                    DATE             04/W/97                 04/ g/97                 04/g /97                     04/     /97
lE.
,                                                               OFFICIAL RECORD COPY
Rill:DRS_
lc.
Rill:DRP
lg
Rlll:DRP
l
NAME
O'Dwyer/kjc A
Ring MF
Mc-Bargerfi4 k fo
Grobe
DATE
04/W/97
04/ g/97
04/g /97
04/
/97
,
OFFICIAL RECORD COPY
l
l
r
r


            -
-
                                                                                                                I
.
  .
I
I
!                     S. A. Patuiski                                   2                         April 25, 1997   l
!
l                                                                                                                 l
S. A. Patuiski
2
April 25, 1997
l
l
l
I
I
                                                                                                                  l
l
l                    cc w/ encl:         R. R. Grigg, President and
cc w/ encl:
l                                         Chief Operating Officer, WEPCo
R. R. Grigg, President and
I                                       A. J. Cayia, Plant Manager
l
                                        Virgil Kanable, Chief, Boiler Section
Chief Operating Officer, WEPCo
                                        Cheryl L. Parrino, Chairman,
I
                                          Wisconsin Public Service Commission
A. J. Cayia, Plant Manager
                                        State Liaison Officer                                                   l
Virgil Kanable, Chief, Boiler Section
                                                                                                                  !
Cheryl L. Parrino, Chairman,
Wisconsin Public Service Commission
State Liaison Officer
!
!
                      Distribution:
Distribution:
                      Docket File w/ encl               Rlli PRR w/enct             Rlll Enf. Coordinator w/encI {
Docket File w/ encl
                  ['"PUBLIC IE-01;w/enci .,           SRI, Pt. Beach w/enci       TSS w/enci                   l
Rlli PRR w/enct
                      OC/LFDCB w/ encl                 LPM, NRR w/ encl           CAA1 w/ encl
Rlll Enf. Coordinator w/encI
                      DRP w/ encl                       A. B. Beach, Rlll w/enci                                 l
['"PUBLIC IE-01;w/enci .,
l                    DRS w/enci                       C. D. Pederson, Rtil w/enci                             j
SRI, Pt. Beach w/enci
          *
TSS w/enci
                                                                                                                  \
OC/LFDCB w/ encl
                                                                                                                i
LPM, NRR w/ encl
CAA1 w/ encl
DRP w/ encl
A. B. Beach, Rlll w/enci
l
DRS w/enci
C. D. Pederson, Rtil w/enci
j
\\
*
i
i
i
l
l
Line 192: Line 301:
,
,
!
!
T
T
4
4
$
$
l __ __ _ _ _ _ _ _ _ _ ____ _ _ _ _ _ _
l
.
.
_
-
}}
}}

Latest revision as of 19:53, 11 December 2024

Forwards Insp Repts 50-266/97-02 & 50-301/97-02 on 970113-0304.No Violations Noted
ML20138D140
Person / Time
Site: Point Beach  NextEra Energy icon.png
Issue date: 04/25/1997
From: Grobe J
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
To: Patulski S
WISCONSIN ELECTRIC POWER CO.
Shared Package
ML20138D146 List:
References
NUDOCS 9705010046
Download: ML20138D140 (3)


See also: IR 05000266/1997002

Text

- . - -

..- - - - - .

__ - -

- -.- .

.

-. - . _ _- _. ...--

.. - -.-.,

'

..

April 25, 1997

i

Mr. S. A. Patuiski

Site Vice President

Point Beach Nuclear Plant

6610 Nuclear Road

{

Two Rivers, WI 54241

1

i

SUBJECT:

NRC INSPECTION REPORT 50-266/97002(DRS); 50-301/97002(DRS)

Dear Mr. Patuiski:

On March 4,1997, the NRC completed an inspection at your Point Beach Nuclear Plant,

Unit 2, including an inspection at your corporate engineering offices. The focus of this

j

inspection was on assumptions used in the containment fan cooler operability evaluation.

.

At the conclusion of the inspection, the findings were discussed with those members of

)

'

your staff identified in the enclosed report.

'

During this inspection, the inspector noted discrepancies between the initial assumptions

i

!

used in the containment fan cooler operability evaluation, and those used in Technical

Specification Change Request (TSCR) 192. However, of more concern, was not

i

considering the throttled service water valves in determining the effect of the delayed

I

containment spray and containment fan cooler start times and the lack of an original

design basis calculation to support the bases for Technical Specification 15.3.6.B. Within

45 days, please provide the formal calculations quantifying the delayed start times for the

containment spray pumps and containment fan cooler assumed in the containment

integrity evaluation supporting TSCR 192.

In accordance with 10 CFR 2.790 of the Commission's regulations, a copy of this letter -

and the enclosed inspection report will be placed in the NRC Public Document Room.

We will gladly discuss any questions you have concerning this inspection.

Sincerely,

i

/s/ J. A. Grobe

John A. Grobe, Deputy Director

  • ]00035

Division of Reactor Projects

,

I

Docket Nos. 50-266, 50-301

/

License Nos. DPR-24, DPR 27

Enclosure: Inspection Report 50-266/301/97002(DRS)

!

See Attached Distribution

,

i

SEE ATTACHED CONCURRENCES

l

DOCUMENT NAME: G:\\DRS\\ pol 97002.REV

{

To receive a copy of this document. Indicate in the box *C' = Copy w/o attach /enot T = Copy w/ attach /enci *N* = No copy

i

OFFICE

Rill:DRS

l

Rill:DRS

l

Rill:DRP

l

Rill;DQP a l

'

NAME

O'Dwyer/kjc

Ring

Mc-Barger

GrabgtMGT

DATE

04/

/97

04/

/97

04/

/97

04 pts /97

OFFICIAL RECOR D COPY

llll! ln

I H I I

I

I ill ll

l l

l l ll

11

9705010046 970425

'

ll

ll

PDR

ADOCK 05000266.

  • * **** * *

G

PDR

_ _ _

_

_ _ _

.

_ _

.

__

.

. _ - . .

- - ..

-.

. - - -

-

.

_

~ . - - -

.-

-. . . . _

-

i

.

l

!

,

i

l

t

l

Mr. S. A. Patutski

l

Site Vice President

l

Point Beach Nuclear Plant

6610 Nuclear Road

[

Two Rivers, WI 54241

l

l

SUBJECT:

NRC INSPECTION REPORT 50-266/97002(DRS); 50-301/97002(DRS)

Dear Mr. Patuiski:

l

On March 4,1997, the NRC cnmpleted an inspection at your Point Beach Nuclear Plant,

!

'

Unit 2, including an inspection at your corporate engineering offices. The focus of this

j

'

inspection was on assumptions used in the containment fan cooler operability evaluation.

At the conclusion of the inspection, the findings were discussed with those members of

your staff identified in the enclosed report.

l

During this inspection, the inspector noted discrepancies between the initial assumptions

!

used in the containment fan cooler operability evaluation, and those used in Technical

Specification Change Request 192. However, of more concern, was the use of an

informal calculation to support the delayed containment spray and containment fan cooler

start times and the lack of a design basis calculation to support the bases for Technical

j

l

Specification 15.3.6.B.

,

I

I

In accordance with 10 CFR 2.790 of the Commission's regulations, a copy of this letter

,

'

and the enclosed inspection report will be placed in the NRC Public Document Room.

i

We will gladly discuss any questions you have concerning this inspection.

i

!

Sincerely,

!

l

l

John A. Grobe, Deputy Director

l

Division of Reactor Projects

l

Docket Nos. 50-266, 50-301

License Nos. DPR-24, DPR-27

'

Enclosure: Inspection Report 50-266/301/97002(DRS)

See Attached Distribution

<

DOCUMENT NAME: G:\\DRS\\ pol 97002.REV

To receive a copy of thle document, Indicate in the box "C" = Copy w/o attach / encl T = copy w/ attach /enci"N" = No copy

OFFICE

Rlll:DRS

lE.

Rill:DRS_

lc.

Rill:DRP

lg

Rlll:DRP

l

NAME

O'Dwyer/kjc A

Ring MF

Mc-Bargerfi4 k fo

Grobe

DATE

04/W/97

04/ g/97

04/g /97

04/

/97

,

OFFICIAL RECORD COPY

l

r

-

.

I

!

S. A. Patuiski

2

April 25, 1997

l

l

l

I

l

cc w/ encl:

R. R. Grigg, President and

l

Chief Operating Officer, WEPCo

I

A. J. Cayia, Plant Manager

Virgil Kanable, Chief, Boiler Section

Cheryl L. Parrino, Chairman,

Wisconsin Public Service Commission

State Liaison Officer

!

Distribution:

Docket File w/ encl

Rlli PRR w/enct

Rlll Enf. Coordinator w/encI

['"PUBLIC IE-01;w/enci .,

SRI, Pt. Beach w/enci

TSS w/enci

OC/LFDCB w/ encl

LPM, NRR w/ encl

CAA1 w/ encl

DRP w/ encl

A. B. Beach, Rlll w/enci

l

DRS w/enci

C. D. Pederson, Rtil w/enci

j

\\

i

i

l

I

l

1

,

i

I

l

!

l

,

!

T

4

$

l

.

.

_

-