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| document type = CORRESPONDENCE-LETTERS, OUTGOING CORRESPONDENCE
| document type = CORRESPONDENCE-LETTERS, OUTGOING CORRESPONDENCE
| page count = 4
| page count = 4
| project = TAC:MA0191, TAC:MA0192
| stage = Approval
}}
}}


=Text=
=Text=
{{#Wiki_filter:. _ -              -.                  -    _ -              -                -
{{#Wiki_filter:. _ -
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    *              '}               NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 30MHept
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      '+,         /[                            January 22, 1998
NUCLEAR REGULATORY COMMISSION f
.          Mr. D. N. Morey Vice President Farley Project Southem Nuclear Operating                                                                                   ;
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Company, Inc.
WASHINGTON, D.C. 30MHept
Post Office Box 1295 Birmingham, Alabama 35201 1295                                                                               :
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January 22, 1998 Mr. D. N. Morey Vice President Farley Project Southem Nuclear Operating Company, Inc.
Post Office Box 1295 Birmingham, Alabama 35201 1295


==SUBJECT:==
==SUBJECT:==
RELIEF REQUESTS RELATED TO THE REMOVAL OF INSULATION ON ASME CODE CLASS 1 SYSTEMS DURING INSERVICE INSFECTION FOR                                   r JOSEPH M. FARLEY NUCLEAR PLANT, UNITS 1 AND 2 (TAC NO3. MA0191 AND MA0192)                                                                                 j
RELIEF REQUESTS RELATED TO THE REMOVAL OF INSULATION ON ASME CODE CLASS 1 SYSTEMS DURING INSERVICE INSFECTION FOR r
JOSEPH M. FARLEY NUCLEAR PLANT, UNITS 1 AND 2 (TAC NO3. MA0191 AND MA0192) j


==Dear Mr. Morey:==
==Dear Mr. Morey:==
 
By {{letter dated|date=November 18, 1997|text=letter dated November 18,1997}}, Southem Nuclear Operating Company, Inc., submitted requests for relief (RR 27) for the Joseph M. Farley Nuclear Plant, Units 1 and 2, from certain provisions of Section XI to the American Society of Mechanical Engineers (ASME) Boller and Pressure Vessel Code (ASME Code). Specifically, you requested relief from the requirements of the 1989 Edition of the ASME Code, Section XI, paragraph IWA 5242(a) for Class 1 systems borated for the purposes of reactivity control. Paragraph IWA-5242(a) requires that the aforementioned Class 1 systems have insulation removed from pressure retaining bolted connections prior to perfonning visual examinations. These visual examinations are performed each outage during startup with the piping and components at normal operating pressure and at near normal operating temperature. This Code requirement became effective for Farley on December 1,1997, with the implementation of the 1989 Code. You based this request on the belief that the proposed altomate examinations provide an acceptable level of quality and safety.
By letter dated November 18,1997, Southem Nuclear Operating Company, Inc., submitted requests for relief (RR 27) for the Joseph M. Farley Nuclear Plant, Units 1 and 2, from certain provisions of Section XI to the American Society of Mechanical Engineers (ASME) Boller and Pressure Vessel Code (ASME Code). Specifically, you requested relief from the requirements of the 1989 Edition of the ASME Code, Section XI, paragraph IWA 5242(a) for Class 1 systems borated for the purposes of reactivity control. Paragraph IWA-5242(a) requires that the aforementioned Class 1 systems have insulation removed from pressure retaining bolted connections prior to perfonning visual examinations. These visual examinations are performed each outage during startup with the piping and components at normal operating pressure and at near normal operating temperature. This Code requirement became effective for Farley on December 1,1997, with the implementation of the 1989 Code. You based this request on the belief that the proposed altomate examinations provide an acceptable level of quality and safety.
The staff has completed its review of the relief requests and has determined that for RR 27, the /
The staff has completed its review of the relief requests and has determined that for RR 27, the /
proposed altomative for Code Class 1 systems provides a reasonable approach for ensuring                 j the leak tight integrity of systems borated for the purpose of controlling reactivity, in addhion,     /
proposed altomative for Code Class 1 systems provides a reasonable approach for ensuring j
the leak tight integrity of systems borated for the purpose of controlling reactivity, in addhion,
/
the proposed altemative provides an acceptable level of quality and safety and is therefore authortred pursuant to 10 CFR 50.55a(a)(3)(i). The basis for this conclusion is described in the $
the proposed altemative provides an acceptable level of quality and safety and is therefore authortred pursuant to 10 CFR 50.55a(a)(3)(i). The basis for this conclusion is described in the $
stafra Safety Evaluation (enclosed).                                                               I'     /
stafra Safety Evaluation (enclosed).
I'
/
E C f u M T Pa C M'Y b
E C f u M T Pa C M'Y b
9901270188 963122 h          ,
9901270188 963122h


Mr. D. N. Morey                                   2-i i
Mr. D. N. Morey 2-i i
if you have any questions regarding this response to your requests, please have your representative contact Jeoob 1. Zimmerman at (301) 415 2426.                                                                                           ;
if you have any questions regarding this response to your requests, please have your representative contact Jeoob 1. Zimmerman at (301) 415 2426.
Sincerely,                                                                                 !
Sincerely,
;                                                                                      )
)
i 1
i 1
rbert N. Berkow, Director                                                           ,
rbert N. Berkow, Director roject Directorate ll 2 Division of Reactor Projects -1/ll Office of Nuclear Reactor Regulation i
roject Directorate ll 2 Division of Reactor Projects -1/ll                                                         .
Docket Nos. 50-348 and 50 364
Office of Nuclear Reactor Regulation                                                       i Docket Nos. 50-348 and 50 364


==Enclosure:==
==Enclosure:==
- Safety Evaluation cc w/ encl: See next page                                                                                                                               j 4
- Safety Evaluation cc w/ encl: See next page j
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                                                      . . _ .                                    . _ .      - - . . - , - . . - . . - . . . . ,      , , . , - ~ . , - -
,,., - ~., - -


O     O' Mr. D, N. Morey                                 2-                     January 22, 1998             ,
O O'
If you have any quest 6ns regarding this response to your requests, please have your representative cont: bet Jacob 1. Zimmerman at (301) 415-2426.
Mr. D, N. Morey 2-January 22, 1998 If you have any quest 6ns regarding this response to your requests, please have your representative cont: bet Jacob 1. Zimmerman at (301) 415-2426.
Sincerely, ORIGINAL SIGNED BY:
Sincerely, ORIGINAL SIGNED BY:
Herbert N, Berkow, Director Project Directorate ll 2 Division of Reactor Projects 1/il Office of Nuclear Reactor Regulation
Herbert N, Berkow, Director Project Directorate ll 2 Division of Reactor Projects 1/il Office of Nuclear Reactor Regulation
                  ' Docket Nos. 50-348 and 50-364                                                                         !
' Docket Nos. 50-348 and 50-364


==Enclosure:==
==Enclosure:==
Safety Evaluation-
Safety Evaluation-
                  . cc w/ encl: See next page                                                                             >
. cc w/ encl: See next page Distnbution:
Distnbution:                                                                                           ;
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PD ll 2 Rdg.                                               g PSkinner, Ril       ,
THarris (e-mail TLH3 SE only)
GHill(4)
THarris (e-mail TLH3 SE only)                                                                           .
ACRS.
ACRS.
MTschitz JJohnson,Ril BBoger                                                                                                 >
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RCarrion, Ril                                                                                           t OGC DJackson, RES                                                                                           .-
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Joseph M. Farley Nuclear Plant l
Joseph M. Farley Nuclear Plant l
cc:
cc:
I
I Mr. R. D. Hill, Jr.
;      Mr. R. D. Hill, Jr.
General Manager-Southem Nuclear Operating Company Post Office Box 470 Ashford, Alabama 36312 Mr. Mark Niuni, Licensing Manager i
General Manager-                                                             ,
Southem Nuclear Operating Company Post Office Box 1295 Birmingham. Alabama 35201 1295 Mr. M. Stanford Blanton Balch and Bingham Law Firm Post Office Box 306 1710 Sixth Avenue North Birmingham, Alabama 35201 Mr. J. D. Woodard Executive Vice President Southem Nuclear Operating Company Post Office Bor 1295 Birmingham, Alabama 35201 i
Southem Nuclear Operating Company                                           !
Post Office Box 470 Ashford, Alabama 36312 Mr. Mark Niuni, Licensing Manager                                           i Southem Nuclear Operating Company Post Office Box 1295 Birmingham. Alabama 35201 1295 Mr. M. Stanford Blanton Balch and Bingham Law Firm                                                   !
Post Office Box 306 1710 Sixth Avenue North Birmingham, Alabama 35201 Mr. J. D. Woodard Executive Vice President Southem Nuclear Operating Company Post Office Bor 1295 Birmingham, Alabama 35201 i
State Health Officer Alabama Department of Public Health 434 Monroe Street Montgomery, Alabama 36130-1701 Chairman-Houston County Commission Post Office Box 6406 Dothan, Alabama 36302 Regional Administrator, Region ll U.S. Nuclear Regulatory Commission Atlanta Federal Center 61 Forsyth Street, S.W., Sune 23T65.
State Health Officer Alabama Department of Public Health 434 Monroe Street Montgomery, Alabama 36130-1701 Chairman-Houston County Commission Post Office Box 6406 Dothan, Alabama 36302 Regional Administrator, Region ll U.S. Nuclear Regulatory Commission Atlanta Federal Center 61 Forsyth Street, S.W., Sune 23T65.
Atlanta, Georgia 30303 Resident inspector-U.S. Nuclear Regulatory Commission 7386 N. State Highway g5 Columbia, Alabama 3631g}}
Atlanta, Georgia 30303 Resident inspector-U.S. Nuclear Regulatory Commission 7386 N. State Highway g5 Columbia, Alabama 3631g}}

Latest revision as of 08:52, 10 December 2024

Forwards SE Accepting Request for Relief (RR-27) for Plant, Units 1 & 2 from Certain Provisions of Section XI to ASME Boiler & Pressure Vessel Code.Relief Will Remove Insulation on ASME Code Class 1 Sys During Insp
ML20199A337
Person / Time
Site: Farley  Southern Nuclear icon.png
Issue date: 01/22/1998
From: Berkow H
NRC (Affiliation Not Assigned)
To: Dennis Morey
SOUTHERN NUCLEAR OPERATING CO.
Shared Package
ML20199A341 List:
References
TAC-MA0191, TAC-MA0192, TAC-MA191, TAC-MA192, NUDOCS 9801270188
Download: ML20199A337 (4)
v • d • e


Text

. _ -

p.~r k

UNITED STATES ye

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NUCLEAR REGULATORY COMMISSION f

u*

WASHINGTON, D.C. 30MHept

/[

'+,

January 22, 1998 Mr. D. N. Morey Vice President Farley Project Southem Nuclear Operating Company, Inc.

Post Office Box 1295 Birmingham, Alabama 35201 1295

SUBJECT:

RELIEF REQUESTS RELATED TO THE REMOVAL OF INSULATION ON ASME CODE CLASS 1 SYSTEMS DURING INSERVICE INSFECTION FOR r

JOSEPH M. FARLEY NUCLEAR PLANT, UNITS 1 AND 2 (TAC NO3. MA0191 AND MA0192) j

Dear Mr. Morey:

By letter dated November 18,1997, Southem Nuclear Operating Company, Inc., submitted requests for relief (RR 27) for the Joseph M. Farley Nuclear Plant, Units 1 and 2, from certain provisions of Section XI to the American Society of Mechanical Engineers (ASME) Boller and Pressure Vessel Code (ASME Code). Specifically, you requested relief from the requirements of the 1989 Edition of the ASME Code,Section XI, paragraph IWA 5242(a) for Class 1 systems borated for the purposes of reactivity control. Paragraph IWA-5242(a) requires that the aforementioned Class 1 systems have insulation removed from pressure retaining bolted connections prior to perfonning visual examinations. These visual examinations are performed each outage during startup with the piping and components at normal operating pressure and at near normal operating temperature. This Code requirement became effective for Farley on December 1,1997, with the implementation of the 1989 Code. You based this request on the belief that the proposed altomate examinations provide an acceptable level of quality and safety.

The staff has completed its review of the relief requests and has determined that for RR 27, the /

proposed altomative for Code Class 1 systems provides a reasonable approach for ensuring j

the leak tight integrity of systems borated for the purpose of controlling reactivity, in addhion,

/

the proposed altemative provides an acceptable level of quality and safety and is therefore authortred pursuant to 10 CFR 50.55a(a)(3)(i). The basis for this conclusion is described in the $

stafra Safety Evaluation (enclosed).

I'

/

E C f u M T Pa C M'Y b

9901270188 963122h

Mr. D. N. Morey 2-i i

if you have any questions regarding this response to your requests, please have your representative contact Jeoob 1. Zimmerman at (301) 415 2426.

Sincerely,

)

i 1

rbert N. Berkow, Director roject Directorate ll 2 Division of Reactor Projects -1/ll Office of Nuclear Reactor Regulation i

Docket Nos. 50-348 and 50 364

Enclosure:

- Safety Evaluation cc w/ encl: See next page j

4 k

O E

,,., - ~., - -

O O'

Mr. D, N. Morey 2-January 22, 1998 If you have any quest 6ns regarding this response to your requests, please have your representative cont: bet Jacob 1. Zimmerman at (301) 415-2426.

Sincerely, ORIGINAL SIGNED BY:

Herbert N, Berkow, Director Project Directorate ll 2 Division of Reactor Projects 1/il Office of Nuclear Reactor Regulation

' Docket Nos. 50-348 and 50-364

Enclosure:

Safety Evaluation-

. cc w/ encl: See next page Distnbution:

gesNgMiqlos PUBLIC PD ll 2 Rdg.

g PSkinner, Ril GHill(4)

THarris (e-mail TLH3 SE only)

ACRS.

MTschitz JJohnson,Ril BBoger RCarrion, Ril t

OGC DJackson, RES Y

.Va,

$fh// /

DOCUMENT NAME:G:\\FARLEY\\MA0191.REL

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N h DB P DllS/Q t PDil.2h PDil-M OGC OFFICE PDil-2/PM '

f.71tdC 0.dBAGCHI B

NAME WGLEben LBER ERMAN b/

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/ If 7 /97 l/T/99, M/ h Il N/97 DATE II/ $9 /97 1

/hEs>NO h NO YES NO YES NO YES NO)

COPY'

[E NO v'

OFFICIAL;1tECORD COPY y

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Joseph M. Farley Nuclear Plant l

cc:

I Mr. R. D. Hill, Jr.

General Manager-Southem Nuclear Operating Company Post Office Box 470 Ashford, Alabama 36312 Mr. Mark Niuni, Licensing Manager i

Southem Nuclear Operating Company Post Office Box 1295 Birmingham. Alabama 35201 1295 Mr. M. Stanford Blanton Balch and Bingham Law Firm Post Office Box 306 1710 Sixth Avenue North Birmingham, Alabama 35201 Mr. J. D. Woodard Executive Vice President Southem Nuclear Operating Company Post Office Bor 1295 Birmingham, Alabama 35201 i

State Health Officer Alabama Department of Public Health 434 Monroe Street Montgomery, Alabama 36130-1701 Chairman-Houston County Commission Post Office Box 6406 Dothan, Alabama 36302 Regional Administrator, Region ll U.S. Nuclear Regulatory Commission Atlanta Federal Center 61 Forsyth Street, S.W., Sune 23T65.

Atlanta, Georgia 30303 Resident inspector-U.S. Nuclear Regulatory Commission 7386 N. State Highway g5 Columbia, Alabama 3631g

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