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=Text=
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                                                            *
      Mr. D. M. Smith                                                                  l
      Senior Vice President -                                                          ,
          Nuclear
      PECO Energy                                                                      ,
                                                                                        !
,
,
      Nuclear Group Headquarters
j
      Correspondence Control Desk                                                      l
*
                                                                                        l
Mr. D. M. Smith
      P. O. Box 195
Senior Vice President -
      Wayne, PA 19087-0195
4      SUBJECT:      LIMERICK MOTOR-OPERATED VALVE INSPECTION 95-19
,
,
        Dear Mr. Smith:
Nuclear
        This letter transmits the results of an inspection performed between
PECO Energy
        November 20 - December 1, 1995, by Mr. D. Dempsey and others at the Limerick
,
        Generating Station (LGS). The inspection focused on issues important to
Nuclear Group Headquarters
        public health and safety, specifically your program implemented in response to
,
        NRC Generic Letter (GL) 89-10, " Safety-Related Motor-0perated Valve Testing
Correspondence Control Desk
        and Surveillance." The )reliminary inspection findings were discussed with
P. O. Box 195
        Mr. W. MacFarland and ot1er members of your staff on December 1, 1995.
Wayne, PA 19087-0195
        The NRC concludes that you have implemented a program that verifies the
SUBJECT:
        design-basis capability of the safety-related motor-operated valves (HOVs) at
LIMERICK MOTOR-OPERATED VALVE INSPECTION 95-19
4
Dear Mr. Smith:
,
This letter transmits the results of an inspection performed between
November 20 - December 1, 1995, by Mr. D. Dempsey and others at the Limerick
Generating Station (LGS). The inspection focused on issues important to
public health and safety, specifically your program implemented in response to
NRC Generic Letter (GL) 89-10, " Safety-Related Motor-0perated Valve Testing
and Surveillance." The )reliminary inspection findings were discussed with
Mr. W. MacFarland and ot1er members of your staff on December 1, 1995.
The NRC concludes that you have implemented a program that verifies the
design-basis capability of the safety-related motor-operated valves (HOVs) at
Limerick. Detailed program specifications and useful self-assessments
'
'
        Limerick. Detailed program specifications and useful self-assessments
reflected strong management support, and component engineering staff
        reflected strong management support, and component engineering staff
involvement in valve maintenance has been effective.
        involvement in valve maintenance has been effective.
The limited amount of site-specific, dynamic test data at Limerick underscores
        The limited amount of site-specific, dynamic test data at Limerick underscores
your need to utilize the best data available from other industry sources in a
        your need to utilize the best data available from other industry sources in a
technically sound manner. With respect to MOV Family 19 (a group of twelve
        technically sound manner. With respect to MOV Family 19 (a group of twelve
risk-significant gate valves), we understand your intent is to obtain
        risk-significant gate valves), we understand your intent is to obtain
additional dynamic test results for statistical significance in accordance
        additional dynamic test results for statistical significance in accordance
with the recommendations of Supplement 6 to GL 89-10. New information on
        with the recommendations of Supplement 6 to GL 89-10. New information on
,
,
        valve performance, such as: (1) GL 95-07 on pressure locking and thermal
valve performance, such as:
        binding of gate valves; and (2) the results of the Electric Power Research
(1) GL 95-07 on pressure locking and thermal
i        Institute's MOV testing program also will need to be assessed to ensure that
binding of gate valves; and (2) the results of the Electric Power Research
i       safety-related MOVs remain capable of performing their design-basis functions. j
Institute's MOV testing program also will need to be assessed to ensure that
        We are not determining the acceptability of your current program for
i
        periodically verifying the design-basis capability of safety-related MOVs at   i
safety-related MOVs remain capable of performing their design-basis functions.
        this time, since the NRC is preparing a generic letter to address this issue.   l
j
        You should review your plans in light of the now generic letter when issued,   l
i
        and consider any appropriate adjustments to your program. The NRC will review   l
We are not determining the acceptability of your current program for
                                                                                        !
periodically verifying the design-basis capability of safety-related MOVs at
        your responses to these issues and other additional information on MOV
this time, since the NRC is preparing a generic letter to address this issue.
        performance as part of future staff activities.
You should review your plans in light of the now generic letter when issued,
                                                                                        l
and consider any appropriate adjustments to your program. The NRC will review
                                                                                        l
your responses to these issues and other additional information on MOV
            230080                                                      \l  1
performance as part of future staff activities.
                                      "
230080
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      PDR    ADOCK 05000352                                                           l
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9602230387 960215
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PDR
ADOCK 05000352
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    .
.
  ..-
. . -
    .
.
      Mr. D. M. Smith                       2
Mr. D. M. Smith
      No response to this letter is requested. Your cooperation in these matters
2
      was appreciated, and we would be pleased to discuss any questions you may have
No response to this letter is requested.
      concerning our conclusions.
Your cooperation in these matters
                                                Sincerely,
was appreciated, and we would be pleased to discuss any questions you may have
                                                (original signed by)
concerning our conclusions.
                                                Eugene M. Kelly, Chief
Sincerely,
                                                Systems Engineering Branch
(original signed by)
                                                Division of Reactor Safety
Eugene M. Kelly, Chief
      Docket Nos. 50-352; 50-353
Systems Engineering Branch
      Enclosure: Inspection Report No. 50-352 and 353/95-19
Division of Reactor Safety
      cc w/ encl:
Docket Nos. 50-352; 50-353
      G. A. Hunger, Jr., Chairman, Nuclear Review Board and Director - Licensing
Enclosure:
      W. MacFarland, Vice President - Limerick Generating Station
Inspection Report No. 50-352 and 353/95-19
      J. L. Kantner, Regulatory Engineer - Limerick Generating Station
cc w/ encl:
      Secretary, Nuclear Committee of the Board
G. A. Hunger, Jr., Chairman, Nuclear Review Board and Director - Licensing
      Nuclear Safety Information Center (NSIC)
W. MacFarland, Vice President - Limerick Generating Station
      Commonwealth of Pennsylvania
J. L. Kantner, Regulatory Engineer - Limerick Generating Station
Secretary, Nuclear Committee of the Board
Nuclear Safety Information Center (NSIC)
Commonwealth of Pennsylvania
,
,


                                                          -                                              -
  r:  ;, .
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                                                                                                                                                1
                                                                                                                                                1
-
-
                Mr. D. M. Smith                                                 3
-
                Distribution w/ encl:
r:
                'J.   Wiggins, DRS                                                                                                             i
;, .
, ;
Mr. D. M. Smith
3
-
Distribution w/ encl:
'J. Wiggins, DRS
P. Fredrickson (RII)
J. Jacobson_(RIII DRS)
'-
'-
                  P. Fredrickson (RII)                                                                                                          l
C. Vandenburgh (RIV)
                                                                                                                                                l
T. Scarbrough (NRR)
                J. Jacobson_(RIII DRS)
Region I Docket Room (with concurrences)
                  C. Vandenburgh (RIV)
                T. Scarbrough (NRR)
'
'
                  Region I Docket Room (with concurrences)                                                                                      l
K. Gallagher, DRP
                  K. Gallagher, DRP                                                                                                             l
,
,
D. Screnci, PA0 (2)
                  D. Screnci, PA0 (2)
3
3
                  NRC Resident Inspector
NRC Resident Inspector
;                PUBLIC-
PUBLIC-
:                 DRS Files (2)
;
$               ' Distribution w/ encl: (Via E-Mail)
:
                  W. Dean, OEDO
DRS Files (2)
                  F. Rinaldi, NRR
$
                  J. Stolz, PDI-2, NRR
' Distribution w/ encl: (Via E-Mail)
                  R. Borchardt, NRR (PIPB)
W. Dean, OEDO
1
F. Rinaldi, NRR
J. Stolz, PDI-2, NRR
R. Borchardt, NRR (PIPB)
                                                                                                                                                 1
                                                                                                                                                 1
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DOCUMENT NAME: A:LM951919. INS
      DOCUMENT NAME: A:LM951919. INS
Ta secahe a copy of tiis document, indicate in tie box: "C" = Copy without attachment
      Ta secahe a copy of tiis document, indicate in tie box: "C" = Copy without attachment losure T = Copy witn attachment / enclosure "W = No
losure T = Copy witn attachment / enclosure "W = No
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      NAME         DDEMPSEY 3 D                   EKELLY4W.( M             WPASCI%6 )             TCHAN bj7@h
/
      DATE-       02/09/96                       02/ 9 /96 M               02/Q /9F               02/09 /96 %             02/     /96
OFFICE
                                                                '4FFICIAL RECORD COPY
RI/DRS
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#
NRR/EMEB
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NAME
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EKELLY4W.( M
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TCHAN bj7@h
DATE-
02/09/96
02/ 9 /96 M
02/Q /9F
02/09 /96 %
02/
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'4FFICIAL RECORD COPY
1
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Latest revision as of 08:53, 11 December 2024

Forwards Insp Repts 50-352/95-19 & 50-353/95-19 on 951120-1201.No Violations Noted
ML20149L189
Person / Time
Site: Limerick  Constellation icon.png
Issue date: 02/15/1996
From: Eugene Kelly
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
To: Danni Smith
PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC
Shared Package
ML20149L192 List:
References
GL-89-10, GL-95-07, GL-95-7, NUDOCS 9602230387
Download: ML20149L189 (3)


See also: IR 05000352/1995019

Text

2.^

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l

i.

A

,

j

Mr. D. M. Smith

Senior Vice President -

,

Nuclear

PECO Energy

,

Nuclear Group Headquarters

,

Correspondence Control Desk

P. O. Box 195

Wayne, PA 19087-0195

SUBJECT:

LIMERICK MOTOR-OPERATED VALVE INSPECTION 95-19

4

Dear Mr. Smith:

,

This letter transmits the results of an inspection performed between

November 20 - December 1, 1995, by Mr. D. Dempsey and others at the Limerick

Generating Station (LGS). The inspection focused on issues important to

public health and safety, specifically your program implemented in response to

NRC Generic Letter (GL) 89-10, " Safety-Related Motor-0perated Valve Testing

and Surveillance." The )reliminary inspection findings were discussed with

Mr. W. MacFarland and ot1er members of your staff on December 1, 1995.

The NRC concludes that you have implemented a program that verifies the

design-basis capability of the safety-related motor-operated valves (HOVs) at

Limerick. Detailed program specifications and useful self-assessments

'

reflected strong management support, and component engineering staff

involvement in valve maintenance has been effective.

The limited amount of site-specific, dynamic test data at Limerick underscores

your need to utilize the best data available from other industry sources in a

technically sound manner. With respect to MOV Family 19 (a group of twelve

risk-significant gate valves), we understand your intent is to obtain

additional dynamic test results for statistical significance in accordance

with the recommendations of Supplement 6 to GL 89-10. New information on

,

valve performance, such as:

(1) GL 95-07 on pressure locking and thermal

binding of gate valves; and (2) the results of the Electric Power Research

Institute's MOV testing program also will need to be assessed to ensure that

i

safety-related MOVs remain capable of performing their design-basis functions.

j

i

We are not determining the acceptability of your current program for

periodically verifying the design-basis capability of safety-related MOVs at

this time, since the NRC is preparing a generic letter to address this issue.

You should review your plans in light of the now generic letter when issued,

and consider any appropriate adjustments to your program. The NRC will review

your responses to these issues and other additional information on MOV

performance as part of future staff activities.

230080

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1

"

i

9602230387 960215

PDR

ADOCK 05000352

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-

-

-

- -

- -

- -

\\

.

. . -

.

Mr. D. M. Smith

2

No response to this letter is requested.

Your cooperation in these matters

was appreciated, and we would be pleased to discuss any questions you may have

concerning our conclusions.

Sincerely,

(original signed by)

Eugene M. Kelly, Chief

Systems Engineering Branch

Division of Reactor Safety

Docket Nos. 50-352; 50-353

Enclosure:

Inspection Report No. 50-352 and 353/95-19

cc w/ encl:

G. A. Hunger, Jr., Chairman, Nuclear Review Board and Director - Licensing

W. MacFarland, Vice President - Limerick Generating Station

J. L. Kantner, Regulatory Engineer - Limerick Generating Station

Secretary, Nuclear Committee of the Board

Nuclear Safety Information Center (NSIC)

Commonwealth of Pennsylvania

,

-

-

r:

, .

, ;

Mr. D. M. Smith

3

-

Distribution w/ encl:

'J. Wiggins, DRS

P. Fredrickson (RII)

J. Jacobson_(RIII DRS)

'-

C. Vandenburgh (RIV)

T. Scarbrough (NRR)

Region I Docket Room (with concurrences)

'

K. Gallagher, DRP

,

D. Screnci, PA0 (2)

3

NRC Resident Inspector

PUBLIC-

DRS Files (2)

$

' Distribution w/ encl: (Via E-Mail)

W. Dean, OEDO

F. Rinaldi, NRR

J. Stolz, PDI-2, NRR

R. Borchardt, NRR (PIPB)

1

i

e

a

DOCUMENT NAME: A:LM951919. INS

Ta secahe a copy of tiis document, indicate in tie box: "C" = Copy without attachment

losure T = Copy witn attachment / enclosure "W = No

'

Copy

/

OFFICE

RI/DRS

lM RI/DRS

/ E RI/DRJfd

NRR/EMEB

lE

NAME

DDEMPSEY 3 D

EKELLY4W.( M

WPASCI%6 )

TCHAN bj7@h

DATE-

02/09/96

02/ 9 /96 M

02/Q /9F

02/09 /96 %

02/

/96

'4FFICIAL RECORD COPY

1

4

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