ML20211N008: Difference between revisions

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=Text=
=Text=
{{#Wiki_filter:. .                                  .    -                    .
{{#Wiki_filter:.
I p%g p             1"                            UNITED STATES s*                              NUCLEAR REGULATORY COMMISSION                                               4 WASHINGTON, D.C. 30006 0001
p%g p
          *****                                          September 2, 1999-
1 UNITED STATES s
        , Mr. Otto L. Maynard                                                                                       l
NUCLEAR REGULATORY COMMISSION 4
        ~ President and Chief Executive Officer                                                                     )
WASHINGTON, D.C. 30006 0001 September 2, 1999-
Wolf Creek Nuclear Operating Corporation Post Office Box 411 Burlington, KA ' 66839 l
, Mr. Otto L. Maynard
~ President and Chief Executive Officer Wolf Creek Nuclear Operating Corporation Post Office Box 411 Burlington, KA ' 66839


==SUBJECT:==
==SUBJECT:==
. GENERIC LETTER 95-07," PRESSURE LOCKING AND THERMAL BINDING OF
. GENERIC LETTER 95-07," PRESSURE LOCKING AND THERMAL BINDING OF
{
{
SAFETY-RELATED POWER-OPERATED GATE VALVES" - WOLF CREEK                                   j GENERATING STATION, UNIT 1 (TAC NO. M93540)
SAFETY-RELATED POWER-OPERATED GATE VALVES" - WOLF CREEK j
GENERATING STATION, UNIT 1 (TAC NO. M93540)


==Dear Mr. Maynard:==
==Dear Mr. Maynard:==
1
1
          . On August 17,1995, the NRC issuea Generic Letter (GL) 95-07, " Pressure Locking and Thermal Binding of Safety-Related Power-Operated Gate Valves," to request that licensees               -
. On August 17,1995, the NRC issuea Generic Letter (GL) 95-07, " Pressure Locking and Thermal Binding of Safety-Related Power-Operated Gate Valves," to request that licensees take actions to ensure those safety-related power-operated gate valves that are susceptible to pressure locking or thermal binding are capable of performing their safety functions. In your letter of October 11,1995 (ET-95-0111), you stated that the requested actions of the GL would be implemented for Wolf Creek Generating Station, Unit 1 (WCGS) and that the 180-day
take actions to ensure those safety-related power-operated gate valves that are susceptible to           '
)
pressure locking or thermal binding are capable of performing their safety functions. In your letter of October 11,1995 (ET-95-0111), you stated that the requested actions of the GL would be implemented for Wolf Creek Generating Station, Unit 1 (WCGS) and that the 180-day response would be provided by February 14,1996.-                                                         )
response would be provided by February 14,1996.-
In a letter of February 14,1996 (WO-96-0023), you submitted the 180-day response to the GL for WCGS. The staff reviewed the submittal and requested additional information in its letter
In a letter of February 14,1996 (WO-96-0023), you submitted the 180-day response to the GL for WCGS. The staff reviewed the submittal and requested additional information in its letter
          ~ dated May 30,1996. You responded to that request in your letter of July 3,1996 (WO           0107) ~and provided the additional information. By its letter of April 1,1999, the NRC issued a second request for information and you provided the additional information in your letter of
~ dated May 30,1996. You responded to that request in your letter of July 3,1996 (WO 0107) ~and provided the additional information. By its letter of April 1,1999, the NRC issued a second request for information and you provided the additional information in your letter of
        . August 3,'1999 (ET-99-0034).
. August 3,'1999 (ET-99-0034).
          ' In the letter of August 3,1999, you committed to complete certain long-term corrective actions for 18 valves by the Spring 2002 refueling outage. This is addressed in Section 3.2.a of the             J enclosed safety evaluation. Because we are relying on you meeting this commitment, you are requested to submit a letter stating the corrective actions have been completed within 3 months         i of completing the work.
' In the letter of August 3,1999, you committed to complete certain long-term corrective actions for 18 valves by the Spring 2002 refueling outage. This is addressed in Section 3.2.a of the J
The staff has reviewed your submittals and conclude that you have adequately addressed the           O actions requested in GL 95-07 for WCGS. This conclusion is partly based on the use of the thrust-prediction methodology _ developed by Commonwealth Edison Company (Comed).
enclosed safety evaluation. Because we are relying on you meeting this commitment, you are requested to submit a letter stating the corrective actions have been completed within 3 months i
Because this' methodology may be revised in the future, the staff considers that you must       /)Dk control the use of this methodology, to demonstrate that safety-related valves can overcome     $g r
of completing the work.
9909100019       990902 A'        fh
The staff has reviewed your submittals and conclude that you have adequately addressed the O
(
actions requested in GL 95-07 for WCGS. This conclusion is partly based on the use of the thrust-prediction methodology _ developed by Commonwealth Edison Company (Comed).
PDR P.       ADOCK    05000482 pm
/)Dk Because this' methodology may be revised in the future, the staff considers that you must control the use of this methodology, to demonstrate that safety-related valves can overcome
$g A'
fh 9909100019 990902 r(
PDR ADOCK 05000482 P.
pm


s O. Maynard                                                 September 2, 1999
's O. Maynard September 2, 1999
_ pressure locking conditions, by the requirements in' Appendix B to 10 CFR Part 50 because the
_ pressure locking conditions, by the requirements in' Appendix B to 10 CFR Part 50 because the
          ' methodology is being used to show that safety-related valves will meet their safety functions during accidents. -This is also addressed in Section 3.2.a of the enclosed safety evaluation.
' methodology is being used to show that safety-related valves will meet their safety functions during accidents. -This is also addressed in Section 3.2.a of the enclosed safety evaluation.
        ' This completes the staff's efforts on TAC No. M93540.
' This completes the staff's efforts on TAC No. M93540.
Sincerely, ORIG. SIGNED BY Jack N. Donohew, Senior Project Manager, Section 2 Project Directorate IV & Decommissioning Division of Licensing Project Management Office of Nuclear Reactor Regulation
Sincerely, ORIG. SIGNED BY Jack N. Donohew, Senior Project Manager, Section 2 Project Directorate IV & Decommissioning Division of Licensing Project Management Office of Nuclear Reactor Regulation
                                                                                                            ]
]


==Enclosure:==
==Enclosure:==
Safety Evaluation cc w/ encl: See 'next pa9e                                                                   -
Safety Evaluation cc w/ encl: See 'next pa9e 1
1 DISTRIBUTION EDocket File '
DISTRIBUTION E ocket File '
PUBLIC                                                                                         l PDIV-2 Reading                                                                                 ,
D PUBLIC PDIV-2 Reading SRichards(clo)
SRichards(clo)
OGC ACRS' i
OGC                                                                                             !
DTerso TScarborough' STingen (SE dated 8/18/99)
ACRS'                                                                                           i DTerso TScarborough' STingen (SE dated 8/18/99)
RScholl(e-mail SE)
RScholl(e-mail SE)
DGraves, RGN-IV                                                                                 ;
DGraves, RGN-IV
        - *For previous concurrences see attached ORC '
- *For previous concurrences see attached ORC '
To receive a copy or trus cocument, Inoicate v in tne cox OFFICE -   PDly-2(ppl       C PDIV-2/LA       C EMEB*             PDIV-2/SC _
To receive a copy or trus cocument, Inoicate v in tne cox OFFICE -
NAME       JMS:rb dedn'                           STingen         SDembek[ k DATE       9 / L 199           9 / l'/99'         9 / 1'/99         9 / / /hh DOCUMENT NAME: G:\PDIV-2\WolfCreeMLTR93540.wpd                                                   ,
PDly-2(ppl C PDIV-2/LA C EMEB*
OFFICIAL RECORD COPY 4:
PDIV-2/SC NAME JMS:rb dedn' STingen SDembek[ k DATE 9 / L 199 9 / l'/99' 9 / 1'/99 9 / / /hh DOCUMENT NAME: G:\\PDIV-2\\WolfCreeMLTR93540.wpd OFFICIAL RECORD COPY 4:
1
1


c;.      .          .
c;.
c I
c I
G. Randolph                                                 pressure locking conditions, by the requirements in Appendix B to 10 CFR Part 50 because the methodology is being used to show that safety-related valves will meet their safety functions during accidents. This is also addressed in Section 3.2.a of the enclosed safety evaluation.
G. Randolph pressure locking conditions, by the requirements in Appendix B to 10 CFR Part 50 because the methodology is being used to show that safety-related valves will meet their safety functions during accidents. This is also addressed in Section 3.2.a of the enclosed safety evaluation.
This completes the staff's efforts on TAC No. M93540.
This completes the staff's efforts on TAC No. M93540.
Sincerely, Jack N. Donohew, enlor Project Manager, Section 2 Project Directorate IV & Decommissioning Division of Licedsing Project Management Office of Nu ear Reactor Regulation Docket No. 50-482
Sincerely, Jack N. Donohew, enlor Project Manager, Section 2 Project Directorate IV & Decommissioning Division of Licedsing Project Management Office of Nu ear Reactor Regulation Docket No. 50-482


==Enclosure:==
==Enclosure:==
Safety Evaluation l           cc w/ encl: See next page l
Safety Evaluation l
DISTRIBUTION Docket File PUBLIC PDIV-2 Reading l           SRichards(clo) l           OGC l
cc w/ encl: See next page l
ACRS l           DTerao l           TScarborough         IS STingen (SE dated 8/5/99)
DISTRIBUTION Docket File PUBLIC PDIV-2 Reading l
RScholl(e-mail SE)                                                                           !
SRichards(clo) l OGC l
DGraves, RGN-IV                                                                               I To receive a copy of this document, indicate "c" in the box OFFICE     PqlVM         C PDIV-2/LA         C EMEB         (; PDIV-2/SC NAME        J h w:rb           EPSytoE           STingenSuf       SDembek DATE       9 / i /99         9/I /99           9 / I/99         9/   /99                 I DOCUMENT NAME: G:\PDIV-2\WolfCreek\LTR93540.wpd OFFICIAL RECORD COPY 1
ACRS l
l
DTerao l
TScarborough IS STingen (SE dated 8/5/99)
RScholl(e-mail SE)
DGraves, RGN-IV I
To receive a copy of this document, indicate "c" in the box OFFICE PqlVM C PDIV-2/LA C EMEB
(;
PDIV-2/SC J h w:rb EPSytoE STingenSuf SDembek NAME DATE 9 / i /99 9/I /99 9 / I/99 9/
/99 DOCUMENT NAME: G:\\PDIV-2\\WolfCreek\\LTR93540.wpd OFFICIAL RECORD COPY


1 O. Maynard                                         pressure locking conditions, by the requirements in Appendix B to 10 CFR Part 50 because the methodology is being used to show that safety-related valves will meet their safety functions during accidents. This is also addressed in Section 3.2.a of the enclosed safety evaluation.
1 O. Maynard pressure locking conditions, by the requirements in Appendix B to 10 CFR Part 50 because the methodology is being used to show that safety-related valves will meet their safety functions during accidents. This is also addressed in Section 3.2.a of the enclosed safety evaluation.
This completes the staffs efforts on TAC No M93540.
This completes the staffs efforts on TAC No M93540.
Sincerely,
Sincerely,
                                        )       eau Qt ac   . DonohWw, Senior Project ManaCer, Section 2 Project Directorate IV & Decommissioning Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket No. 50-482
)
Qt eau ac
. DonohWw, Senior Project ManaCer, Section 2 Project Directorate IV & Decommissioning Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket No. 50-482


==Enclosure:==
==Enclosure:==
Safety Evaluation ec w/ enc!: See next page i
Safety Evaluation ec w/ enc!: See next page i
i l
i
l
)
                                                                                                  )
i
i


F.
F.
l l         Wolf Creek Generating Station cc:
l l
Jay Silberg, Esq.                   Vice President & Chief Operating Officer Shaw, Pittman, Potts & Trowbridge   Wolf Creek Nuclear Operating Corporation       j 2300 N Street, NW                   P. O. Box 411
Wolf Creek Generating Station cc:
: Washington, D.C. 20037             Burlington, Kansas 66839
Jay Silberg, Esq.
                                                                                              )
Vice President & Chief Operating Officer Shaw, Pittman, Potts & Trowbridge Wolf Creek Nuclear Operating Corporation j
Regional Administrator, Region IV   Superintendent Licensing l         U.S. Nuclear Regulatory Commission   Wolf Creek Nuclear Operating Corporation L         611 Ryan Plaza Drive, Suite 1000     P.O. Box 411                                 -
2300 N Street, NW P. O. Box 411
Arlington, Texas 76011 ~             Burlington, Kansas 66839 Senior Resident inspector           U.S. Nuclear Regulatory Commission U.S. Nuclear Regulatory Commission   Resident inspectors Office-P. O. Box 311                       8201 NRC Road Burlington, Kansas 66839             Steedman, Missouri 65077-1032 Chief Engineer Utilities Division Kansas Corporation Commission 1500 SW Arrowhead Road Topeka, Kansas 66604-4027 Office of the'Govemor.
)
l         State of Kansas l         . Topeka, Kansas 66612                                                           -
: Washington, D.C. 20037 Burlington, Kansas 66839 Regional Administrator, Region IV Superintendent Licensing l
l Attomey General                                                                     !
U.S. Nuclear Regulatory Commission Wolf Creek Nuclear Operating Corporation L
Judicial Center 301 S.W.10th 2nd Floor Topeka, Kansas 66612 County Clerk .
611 Ryan Plaza Drive, Suite 1000 P.O. Box 411 Arlington, Texas 76011 ~
Burlington, Kansas 66839 Senior Resident inspector U.S. Nuclear Regulatory Commission U.S. Nuclear Regulatory Commission Resident inspectors Office-P. O. Box 311 8201 NRC Road Burlington, Kansas 66839 Steedman, Missouri 65077-1032 Chief Engineer Utilities Division Kansas Corporation Commission 1500 SW Arrowhead Road Topeka, Kansas 66604-4027 Office of the'Govemor.
l State of Kansas l
. Topeka, Kansas 66612 l
Attomey General Judicial Center 301 S.W.10th 2nd Floor Topeka, Kansas 66612 County Clerk.
Coffey County Courthouse Burlington, Kansas 66839
Coffey County Courthouse Burlington, Kansas 66839
          ~ Vick L. Cooper, Chief Radiation Control Program Kansas Department of Health and Environment Bureau of Air and Radiation Forbes Field Building 283 Topeka, Kansas 66620}}
~ Vick L. Cooper, Chief Radiation Control Program Kansas Department of Health and Environment Bureau of Air and Radiation Forbes Field Building 283 Topeka, Kansas 66620}}

Latest revision as of 21:42, 5 December 2024

Informs That NRC Staff Has Reviewed Submittals & Concluded Util Adequately Addressed Actions Requested in GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power- Operated Gate Valves
ML20211N008
Person / Time
Site: Wolf Creek 
Issue date: 09/02/1999
From: Donohew J
NRC (Affiliation Not Assigned)
To: Maynard O
WOLF CREEK NUCLEAR OPERATING CORP.
Shared Package
ML20211N012 List:
References
GL-95-07, TAC-M93540, NUDOCS 9909100019
Download: ML20211N008 (5)


Text

.

p%g p

1 UNITED STATES s

NUCLEAR REGULATORY COMMISSION 4

WASHINGTON, D.C. 30006 0001 September 2, 1999-

, Mr. Otto L. Maynard

~ President and Chief Executive Officer Wolf Creek Nuclear Operating Corporation Post Office Box 411 Burlington, KA ' 66839

SUBJECT:

. GENERIC LETTER 95-07," PRESSURE LOCKING AND THERMAL BINDING OF

{

SAFETY-RELATED POWER-OPERATED GATE VALVES" - WOLF CREEK j

GENERATING STATION, UNIT 1 (TAC NO. M93540)

Dear Mr. Maynard:

1

. On August 17,1995, the NRC issuea Generic Letter (GL) 95-07, " Pressure Locking and Thermal Binding of Safety-Related Power-Operated Gate Valves," to request that licensees take actions to ensure those safety-related power-operated gate valves that are susceptible to pressure locking or thermal binding are capable of performing their safety functions. In your letter of October 11,1995 (ET-95-0111), you stated that the requested actions of the GL would be implemented for Wolf Creek Generating Station, Unit 1 (WCGS) and that the 180-day

)

response would be provided by February 14,1996.-

In a letter of February 14,1996 (WO-96-0023), you submitted the 180-day response to the GL for WCGS. The staff reviewed the submittal and requested additional information in its letter

~ dated May 30,1996. You responded to that request in your letter of July 3,1996 (WO 0107) ~and provided the additional information. By its letter of April 1,1999, the NRC issued a second request for information and you provided the additional information in your letter of

. August 3,'1999 (ET-99-0034).

' In the letter of August 3,1999, you committed to complete certain long-term corrective actions for 18 valves by the Spring 2002 refueling outage. This is addressed in Section 3.2.a of the J

enclosed safety evaluation. Because we are relying on you meeting this commitment, you are requested to submit a letter stating the corrective actions have been completed within 3 months i

of completing the work.

The staff has reviewed your submittals and conclude that you have adequately addressed the O

actions requested in GL 95-07 for WCGS. This conclusion is partly based on the use of the thrust-prediction methodology _ developed by Commonwealth Edison Company (Comed).

/)Dk Because this' methodology may be revised in the future, the staff considers that you must control the use of this methodology, to demonstrate that safety-related valves can overcome

$g A'

fh 9909100019 990902 r(

PDR ADOCK 05000482 P.

pm

's O. Maynard September 2, 1999

_ pressure locking conditions, by the requirements in' Appendix B to 10 CFR Part 50 because the

' methodology is being used to show that safety-related valves will meet their safety functions during accidents. -This is also addressed in Section 3.2.a of the enclosed safety evaluation.

' This completes the staff's efforts on TAC No. M93540.

Sincerely, ORIG. SIGNED BY Jack N. Donohew, Senior Project Manager, Section 2 Project Directorate IV & Decommissioning Division of Licensing Project Management Office of Nuclear Reactor Regulation

]

Enclosure:

Safety Evaluation cc w/ encl: See 'next pa9e 1

DISTRIBUTION E ocket File '

D PUBLIC PDIV-2 Reading SRichards(clo)

OGC ACRS' i

DTerso TScarborough' STingen (SE dated 8/18/99)

RScholl(e-mail SE)

DGraves, RGN-IV

- *For previous concurrences see attached ORC '

To receive a copy or trus cocument, Inoicate v in tne cox OFFICE -

PDly-2(ppl C PDIV-2/LA C EMEB*

PDIV-2/SC NAME JMS:rb dedn' STingen SDembek[ k DATE 9 / L 199 9 / l'/99' 9 / 1'/99 9 / / /hh DOCUMENT NAME: G:\\PDIV-2\\WolfCreeMLTR93540.wpd OFFICIAL RECORD COPY 4:

1

c;.

c I

G. Randolph pressure locking conditions, by the requirements in Appendix B to 10 CFR Part 50 because the methodology is being used to show that safety-related valves will meet their safety functions during accidents. This is also addressed in Section 3.2.a of the enclosed safety evaluation.

This completes the staff's efforts on TAC No. M93540.

Sincerely, Jack N. Donohew, enlor Project Manager, Section 2 Project Directorate IV & Decommissioning Division of Licedsing Project Management Office of Nu ear Reactor Regulation Docket No. 50-482

Enclosure:

Safety Evaluation l

cc w/ encl: See next page l

DISTRIBUTION Docket File PUBLIC PDIV-2 Reading l

SRichards(clo) l OGC l

ACRS l

DTerao l

TScarborough IS STingen (SE dated 8/5/99)

RScholl(e-mail SE)

DGraves, RGN-IV I

To receive a copy of this document, indicate "c" in the box OFFICE PqlVM C PDIV-2/LA C EMEB

(;

PDIV-2/SC J h w:rb EPSytoE STingenSuf SDembek NAME DATE 9 / i /99 9/I /99 9 / I/99 9/

/99 DOCUMENT NAME: G:\\PDIV-2\\WolfCreek\\LTR93540.wpd OFFICIAL RECORD COPY

1 O. Maynard pressure locking conditions, by the requirements in Appendix B to 10 CFR Part 50 because the methodology is being used to show that safety-related valves will meet their safety functions during accidents. This is also addressed in Section 3.2.a of the enclosed safety evaluation.

This completes the staffs efforts on TAC No M93540.

Sincerely,

)

Qt eau ac

. DonohWw, Senior Project ManaCer, Section 2 Project Directorate IV & Decommissioning Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket No. 50-482

Enclosure:

Safety Evaluation ec w/ enc!: See next page i

i

)

i

F.

l l

Wolf Creek Generating Station cc:

Jay Silberg, Esq.

Vice President & Chief Operating Officer Shaw, Pittman, Potts & Trowbridge Wolf Creek Nuclear Operating Corporation j

2300 N Street, NW P. O. Box 411

)

Washington, D.C. 20037 Burlington, Kansas 66839 Regional Administrator, Region IV Superintendent Licensing l

U.S. Nuclear Regulatory Commission Wolf Creek Nuclear Operating Corporation L

611 Ryan Plaza Drive, Suite 1000 P.O. Box 411 Arlington, Texas 76011 ~

Burlington, Kansas 66839 Senior Resident inspector U.S. Nuclear Regulatory Commission U.S. Nuclear Regulatory Commission Resident inspectors Office-P. O. Box 311 8201 NRC Road Burlington, Kansas 66839 Steedman, Missouri 65077-1032 Chief Engineer Utilities Division Kansas Corporation Commission 1500 SW Arrowhead Road Topeka, Kansas 66604-4027 Office of the'Govemor.

l State of Kansas l

. Topeka, Kansas 66612 l

Attomey General Judicial Center 301 S.W.10th 2nd Floor Topeka, Kansas 66612 County Clerk.

Coffey County Courthouse Burlington, Kansas 66839

~ Vick L. Cooper, Chief Radiation Control Program Kansas Department of Health and Environment Bureau of Air and Radiation Forbes Field Building 283 Topeka, Kansas 66620