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  . r DUKE POWER GoMPANY P.O. D O X 3 318 0 CHAnLOTTE, N.O. 20242 HALD.TUCKEH                                                                   TELEPHONE vwn rematpart
r DUKE POWER GoMPANY P.O. D O X 3 318 0 CHAnLOTTE, N.O. 20242 HALD.TUCKEH TELEPHONE vwn rematpart
                                                                                  @O4) GD4531 pt'0 LEAR PSODUCetON November 2, 1987                                                                             )
@O4) GD4531 pt'0 LEAR PSODUCetON November 2, 1987
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U. S. Nuclear Regulatory Commission                                                         i Attention: Document Control Desk                                                             l Washington, D. C. 20555                                                                     j i
U. S. Nuclear Regulatory Commission i
Subj ect:           Catawba Nuclear Station, Units 1 and 2                                 ,
Attention: Document Control Desk l
Docket Nos. 50-413 and 50-414                                           8 Technical Specification 4.6.1.9.4 - VQ Valves D.ar Sir:
Washington, D. C. 20555 j
i Subj ect:
Catawba Nuclear Station, Units 1 and 2 8
Docket Nos. 50-413 and 50-414 Technical Specification 4.6.1.9.4 - VQ Valves D.ar Sir:
This letter is in response to your correspondence dated July 31, 1937 concerning Technical Specification Surveillance Requirement 4.6.1.9.4 for the Containment Air Release and Addition (VQ) System valves.
This letter is in response to your correspondence dated July 31, 1937 concerning Technical Specification Surveillance Requirement 4.6.1.9.4 for the Containment Air Release and Addition (VQ) System valves.
Your letter discussed certain requirements which "...were established in response to test data which revealed that in a number of instances large butterfly                     I containment purge system isolation valves failed the Type C test at successive refueling outages". Your letter also noted that " Excessive leakage... is typically caused by severe environmental conditions.or wear due to frequent use".
Your letter discussed certain requirements which "...were established in response to test data which revealed that in a number of instances large butterfly I
Please be advised that the VQ valves at Catawba are 4-inch, gate valves (the example contained in the Standard Technical Specifications references an 8-inch valve), not "large butterfly ... valves".
containment purge system isolation valves failed the Type C test at successive refueling outages". Your letter also noted that " Excessive leakage... is typically caused by severe environmental conditions.or wear due to frequent use".
The temperatures that these valves are subject to experience are not extreme (Technical Specification limit for upper containment temperature is 120 degrees F) compared to their design temperature (260 degrees F). The pressures these valves may see are much less than the design pressure of 150 psig. Additionally, these valves are normally cycled twice daily. This results in less than 1000 cycles yearly, which, given the manufacturer's recommended changeout of every 20,000 cycles, does not appear to indicate excessive use.
Please be advised that the VQ valves at Catawba are 4-inch, gate valves (the example contained in the Standard Technical Specifications references an 8-inch valve), not "large butterfly... valves".
Attached is additional test data for the Catawba VQ valves (testing done subsequent to the November 17, 1987 letter) and also test data for similar valves at the McGuire Nuclear Station. The McGuire data covers a period of up to 6 years and also demonstrates that these valves are not prone to excessive leakage even over a long period of time.
The temperatures that these valves are subject to experience are not extreme (Technical Specification limit for upper containment temperature is 120 degrees F) compared to their design temperature (260 degrees F).
The pressures these valves may see are much less than the design pressure of 150 psig. Additionally, these valves are normally cycled twice daily.
This results in less than 1000 cycles yearly, which, given the manufacturer's recommended changeout of every 20,000 cycles, does not appear to indicate excessive use.
Attached is additional test data for the Catawba VQ valves (testing done subsequent to the {{letter dated|date=November 17, 1987|text=November 17, 1987 letter}}) and also test data for similar valves at the McGuire Nuclear Station.
The McGuire data covers a period of up to 6 years and also demonstrates that these valves are not prone to excessive leakage even over a long period of time.
Given this new information, it is requested that our previous amendment request be granted.
Given this new information, it is requested that our previous amendment request be granted.
Pursuant to 10 CFR 50.91 (b) (1) the appropriate South Carolina State Official is being provided a copy of this supplement to our previous amendment request.
Pursuant to 10 CFR 50.91 (b) (1) the appropriate South Carolina State Official is being provided a copy of this supplement to our previous amendment request.
t 8711100383 871102 DR         ADOCK 0500           $                                                        g
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            .U. S'vNuclear Rsgulatory Commission,-
(
                    ,                                        J.   .I
.U. S'vNuclear Rsgulatory Commission,-
(    ,
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November.2,'.1987 Page'Two
.I November.2,'.1987 Page'Two
                                                                                                                    )
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'This letter supplements.the information'which was submittedLNovember 17, 1986.
            'This letter supplements.the information'which was submittedLNovember 17, 1986.
J As such, no. additional fee-,is required.-
J As such, no. additional fee-,is required.-
Very thuly yours                                   ,
d Very thuly yours d
d
j/A Q.
                #                          .                                                                              l i                              j/A Q .               '
i Hal-B. Tucker-1
d Hal-B. Tucker-                                                                                           1
..j RWO/151/sbn 1
                                                                                                                  ..j RWO/151/sbn 1
1 Attachment j
1 Attachment                                                                                         j i
i d
xc:                                                                                       'I Dr. J. Nelson Grace, Regional Administrator'                                                 d U. S. Nuclear Regulatory. Commission Region II 101 Marietta Street, NW,' Suite 2900'                                                         ..
'I xc:
Atlanta, Georgia 30323 i
Dr. J. Nelson Grace, Regional Administrator' U. S. Nuclear Regulatory. Commission Region II 101 Marietta Street, NW,' Suite 2900' Atlanta, Georgia 30323 i
Mr. Heyward Shealy, Chief Bureau of Radiological Health South Carolina Department of Health &
Mr. Heyward Shealy, Chief Bureau of Radiological Health South Carolina Department of Health &
Environmental Control 2600 Bull Street Columbia, South Carolina 29201
Environmental Control 2600 Bull Street Columbia, South Carolina 29201
                                                                                                                      ]
]
American Nuclear Insurers                                                                           I c/o Dottie Sherman, ANI Library The Exchange, Suite,245 270 Farmington Avenue Farmington, CT 06032 M&M Nuclear Consultants                                                                             1 1221 Avenue of the Americas                                                                       l New York, New York 10020 INPO Records Center                                                                                 l Suite 1500                                                                                         '
American Nuclear Insurers c/o Dottie Sherman, ANI Library The Exchange, Suite,245 270 Farmington Avenue Farmington, CT 06032 M&M Nuclear Consultants 1221 Avenue of the Americas New York, New York 10020 INPO Records Center Suite 1500 1100. Circle 75 Parkway Atlanta, Georgia 30339
1100. Circle 75 Parkway                                                                           -
- Mr. P. K. Van Doorn NRC Resident Inspector Catawba Nuclear Station-
Atlanta, Georgia 30339
.h
                    - Mr. P. K. Van Doorn
* NRC Resident Inspector Catawba Nuclear Station-
                                                                                                                    .h


                                                                                        -a h'
-a h'
CATAWBA LEAKAGE HISTORY IVQ2A-                                           IVQ16A             i 01/16/87             2.0 SCCM                     '01/12/87         45.8 SCCM   ;
CATAWBA LEAKAGE HISTORY IVQ2A-IVQ16A i
03/15/87             5.3 SCCM                     03/06/87           8.7 SCCM
01/16/87 2.0 SCCM
      . 03/18/87-           6.1 SCCM                     05/22/87           3.5 SCCM 06/04/87             2.6 SCCM 2VQ2A                                             2VQ16A           ,!
'01/12/87 45.8 SCCM 03/15/87 5.3 SCCM 03/06/87 8.7 SCCM
      ~06/08/85             56.0 SCCM                     06/12/85         24.0 SCCM 04/07/86           72.0'SCCM                     03/23/86         36.5 SCCM 07/17/86             1.0 SCCM                     07/19/86         10.0 SCCM   l 11/04/86             2.0 SCCM                     11/11/86-         2.0-SCCM q' 01/09/87             7.0 SCCM                     01/09/87           1.0'SCCM   :
. 03/18/87-6.1 SCCM 05/22/87 3.5 SCCM 06/04/87 2.6 SCCM 2VQ2A 2VQ16A
03/29/87             2.6 SCCM                     '04/03/87-         11.0 SCCM l 07/14/87             3.0 SCCM                     07/16/87         83.4 SCCM ^'
~06/08/85 56.0 SCCM 06/12/85 24.0 SCCM 04/07/86 72.0'SCCM 03/23/86 36.5 SCCM 07/17/86 1.0 SCCM 07/19/86 10.0 SCCM l
i 10/06/87           369.0 SCCM*
11/04/86 2.0 SCCM 11/11/86-2.0-SCCM q'
01/09/87 7.0 SCCM 01/09/87 1.0'SCCM 03/29/87 2.6 SCCM
'04/03/87-11.0 SCCM l
07/14/87 3.0 SCCM 07/16/87 83.4 SCCM i
^'
10/06/87 369.0 SCCM*
l
l
* HIGHER MEASURED LEAKAGE DUE TO A LEAKING TEST VOLUME BLOCK VALVE.               !
* HIGHER MEASURED LEAKAGE DUE TO A LEAKING TEST VOLUME BLOCK VALVE.
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Line 89: Line 98:
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MCGUIRE LEAKAGE HISTORY (6-INCH DIAPHRAGM VALVES)
MCGUIRE LEAKAGE HISTORY (6-INCH DIAPHRAGM VALVES)
IVQ1                                       1VQ2 09/26/80       20 SCCM                     09/26/80       20 SCCM 03/02/82       93 SCCM                     03/02/82       93 SCCM 03/28/84       2 SCCM                     03/28/84       290 SCCM     :
IVQ1 1VQ2 09/26/80 20 SCCM 09/26/80 20 SCCM 03/02/82 93 SCCM 03/02/82 93 SCCM 03/28/84 2 SCCM 03/28/84 290 SCCM 06/01/85 20 SCCM 06/01/85 20 SCCM l
06/01/85       20 SCCM                     06/01/85       20 SCCM     l 05/27/86       20 SCCM                     05/27/86       20 SCCM     !
05/27/86 20 SCCM 05/27/86 20 SCCM IVQ5 IVQ6 03/01/82-20 SCCM 03/01/82 20 SCCM 03/02/82 93 SCCM 03/02/82 93 SCCM.
IVQ5                                       IVQ6 03/01/82-     20 SCCM                     03/01/82       20 SCCM 03/02/82       93 SCCM                     03/02/82       93 SCCM. i l               03/28/84       2 SCCM                     03/28/84         2 SCCM     ]
i l
06/08/85       20 SCCM                     06/08/85       20 SCCM   f 05/30/86       4 SCCM                     05/30/86         4 SCCM i
03/28/84 2 SCCM 03/28/84 2 SCCM
2VQ1                                       2VQ2 08/24/82       20 SCCM                     08/24/82       30 SCCM     3 01/11/84       2 SCCM                     01/11/84       47 SCCM     I 02/cs/85       60 SCCM                     02/08/85       20 SCCM 03/20/86       20 SCCM                     03/20/86       20 SCCM 05/23/87       5.5 SCCM                   05/23/87       32 SCCM 2VQ5                                       2VQ6 09/20/82       35 SCCM                     09/20/82       35 SCCM U1/05/84       2 SCCM                       01/05/84       2 SCCM 03/14/85       2 SCCM                     03/14/85         2 SCCM 03/21/86       24 SCCM                     03/21/86       24 SCCM 06/13/87       2 SCCM                       06/13/87       2 SCCM I
]
06/08/85 20 SCCM 06/08/85 20 SCCM f
05/30/86 4 SCCM 05/30/86 4 SCCM i
2VQ1 2VQ2 08/24/82 20 SCCM 08/24/82 30 SCCM 3
01/11/84 2 SCCM 01/11/84 47 SCCM I
02/cs/85 60 SCCM 02/08/85 20 SCCM 03/20/86 20 SCCM 03/20/86 20 SCCM 05/23/87 5.5 SCCM 05/23/87 32 SCCM 2VQ5 2VQ6 09/20/82 35 SCCM 09/20/82 35 SCCM U1/05/84 2 SCCM 01/05/84 2 SCCM 03/14/85 2 SCCM 03/14/85 2 SCCM 03/21/86 24 SCCM 03/21/86 24 SCCM 06/13/87 2 SCCM 06/13/87 2 SCCM I
I:}}
I:}}

Latest revision as of 01:13, 3 December 2024

Forwards Addl Test Data of Vq Valves for Facilities in Support of Util Application for Amends to Licenses NPF-35 & NPF-52,changing Tech Spec Surveillance Requirement 4.6.1.9.4.Previous Amend Requested to Be Granted
ML20236L514
Person / Time
Site: Mcguire, Catawba, McGuire, 05000000
Issue date: 11/02/1987
From: Tucker H
DUKE POWER CO.
To:
NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
References
NUDOCS 8711100383
Download: ML20236L514 (4)
v • d • e


Text

&

]

r DUKE POWER GoMPANY P.O. D O X 3 318 0 CHAnLOTTE, N.O. 20242 HALD.TUCKEH TELEPHONE vwn rematpart

@O4) GD4531 pt'0 LEAR PSODUCetON November 2, 1987

)

l i

U. S. Nuclear Regulatory Commission i

Attention: Document Control Desk l

Washington, D. C. 20555 j

i Subj ect:

Catawba Nuclear Station, Units 1 and 2 8

Docket Nos. 50-413 and 50-414 Technical Specification 4.6.1.9.4 - VQ Valves D.ar Sir:

This letter is in response to your correspondence dated July 31, 1937 concerning Technical Specification Surveillance Requirement 4.6.1.9.4 for the Containment Air Release and Addition (VQ) System valves.

Your letter discussed certain requirements which "...were established in response to test data which revealed that in a number of instances large butterfly I

containment purge system isolation valves failed the Type C test at successive refueling outages". Your letter also noted that " Excessive leakage... is typically caused by severe environmental conditions.or wear due to frequent use".

Please be advised that the VQ valves at Catawba are 4-inch, gate valves (the example contained in the Standard Technical Specifications references an 8-inch valve), not "large butterfly... valves".

The temperatures that these valves are subject to experience are not extreme (Technical Specification limit for upper containment temperature is 120 degrees F) compared to their design temperature (260 degrees F).

The pressures these valves may see are much less than the design pressure of 150 psig. Additionally, these valves are normally cycled twice daily.

This results in less than 1000 cycles yearly, which, given the manufacturer's recommended changeout of every 20,000 cycles, does not appear to indicate excessive use.

Attached is additional test data for the Catawba VQ valves (testing done subsequent to the November 17, 1987 letter) and also test data for similar valves at the McGuire Nuclear Station.

The McGuire data covers a period of up to 6 years and also demonstrates that these valves are not prone to excessive leakage even over a long period of time.

Given this new information, it is requested that our previous amendment request be granted.

Pursuant to 10 CFR 50.91 (b) (1) the appropriate South Carolina State Official is being provided a copy of this supplement to our previous amendment request.

t 8711100383 871102 DR ADOCK 0500 g

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.U. S'vNuclear Rsgulatory Commission,-

J.

.I November.2,'.1987 Page'Two

)l

'This letter supplements.the information'which was submittedLNovember 17, 1986.

J As such, no. additional fee-,is required.-

d Very thuly yours d

j/A Q.

i Hal-B. Tucker-1

..j RWO/151/sbn 1

1 Attachment j

i d

'I xc:

Dr. J. Nelson Grace, Regional Administrator' U. S. Nuclear Regulatory. Commission Region II 101 Marietta Street, NW,' Suite 2900' Atlanta, Georgia 30323 i

Mr. Heyward Shealy, Chief Bureau of Radiological Health South Carolina Department of Health &

Environmental Control 2600 Bull Street Columbia, South Carolina 29201

]

American Nuclear Insurers c/o Dottie Sherman, ANI Library The Exchange, Suite,245 270 Farmington Avenue Farmington, CT 06032 M&M Nuclear Consultants 1221 Avenue of the Americas New York, New York 10020 INPO Records Center Suite 1500 1100. Circle 75 Parkway Atlanta, Georgia 30339

- Mr. P. K. Van Doorn NRC Resident Inspector Catawba Nuclear Station-

.h

-a h'

CATAWBA LEAKAGE HISTORY IVQ2A-IVQ16A i

01/16/87 2.0 SCCM

'01/12/87 45.8 SCCM 03/15/87 5.3 SCCM 03/06/87 8.7 SCCM

. 03/18/87-6.1 SCCM 05/22/87 3.5 SCCM 06/04/87 2.6 SCCM 2VQ2A 2VQ16A

~06/08/85 56.0 SCCM 06/12/85 24.0 SCCM 04/07/86 72.0'SCCM 03/23/86 36.5 SCCM 07/17/86 1.0 SCCM 07/19/86 10.0 SCCM l

11/04/86 2.0 SCCM 11/11/86-2.0-SCCM q'

01/09/87 7.0 SCCM 01/09/87 1.0'SCCM 03/29/87 2.6 SCCM

'04/03/87-11.0 SCCM l

07/14/87 3.0 SCCM 07/16/87 83.4 SCCM i

^'

10/06/87 369.0 SCCM*

l

  • HIGHER MEASURED LEAKAGE DUE TO A LEAKING TEST VOLUME BLOCK VALVE.

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MCGUIRE LEAKAGE HISTORY (6-INCH DIAPHRAGM VALVES)

IVQ1 1VQ2 09/26/80 20 SCCM 09/26/80 20 SCCM 03/02/82 93 SCCM 03/02/82 93 SCCM 03/28/84 2 SCCM 03/28/84 290 SCCM 06/01/85 20 SCCM 06/01/85 20 SCCM l

05/27/86 20 SCCM 05/27/86 20 SCCM IVQ5 IVQ6 03/01/82-20 SCCM 03/01/82 20 SCCM 03/02/82 93 SCCM 03/02/82 93 SCCM.

i l

03/28/84 2 SCCM 03/28/84 2 SCCM

]

06/08/85 20 SCCM 06/08/85 20 SCCM f

05/30/86 4 SCCM 05/30/86 4 SCCM i

2VQ1 2VQ2 08/24/82 20 SCCM 08/24/82 30 SCCM 3

01/11/84 2 SCCM 01/11/84 47 SCCM I

02/cs/85 60 SCCM 02/08/85 20 SCCM 03/20/86 20 SCCM 03/20/86 20 SCCM 05/23/87 5.5 SCCM 05/23/87 32 SCCM 2VQ5 2VQ6 09/20/82 35 SCCM 09/20/82 35 SCCM U1/05/84 2 SCCM 01/05/84 2 SCCM 03/14/85 2 SCCM 03/14/85 2 SCCM 03/21/86 24 SCCM 03/21/86 24 SCCM 06/13/87 2 SCCM 06/13/87 2 SCCM I

I:

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