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See also: [[see also::IR 07100019/2011029]]


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{{#Wiki_filter:._          _        --        __      _ _ _      . .. _ . _ . . _                ,_ _ _._ _ . _ . . -. _
{{#Wiki_filter:._          _        --        __      _ _ _      . .. _ . _ . . _                ,_ _ _._ _ . _ . . -. _
:.7          m              v                                                                                                                        q a
            :.7          m              v                                                                                                                        q
i
                                                                                                                                                                  a
                                                                                                '
                                                                                                                                                                    i
                     ;                                                N0TICE OFl VIOLATION
                     ;                                                N0TICE OFl VIOLATION
                                 < Southern Nuclear Operating Company -                Docket Nos.:      50-348 and 50 364 Farley Nuclear Plant,: Units:1 and 2-              License:Nos.: - NPF-2 and.NPF-8
                                                                                                                                                                "
                                                                    .
                                                                                                                                                _
                      '
                                 < Southern Nuclear Operating Company -                Docket Nos.:      50-348 and 50 364
    >
                                    Farley Nuclear Plant,: Units:1 and 2-              License:Nos.: - NPF-2 and.NPF-8
        -              -
                                                                                                         ; EA 97-557;                            --
                                                                                                         ; EA 97-557;                            --
EA 97-571                                              j During an U.S. Nuclear Regulatory Commission (NRC)' inspection conducted during'                                                l the period October 19 through November.29, 1997.' violations of'NRC .
                                                                                                                                                                    .
requirements were identified. In accordance with the " General Statement of:                                                  1 Policy and Procedures'for NRC Enforcement Actions." NUREG-1600 the violations                                                  >
                                                                                                        <
                                                                                                          EA 97-571                                              j
                                    During an U.S. Nuclear Regulatory Commission (NRC)' inspection conducted during'                                                l
                                    the period October 19 through November.29, 1997.' violations of'NRC .
                                    requirements were identified. In accordance with the " General Statement of:                                                  1
                                    Policy and Procedures'for NRC Enforcement Actions." NUREG-1600 the violations                                                  >
                                 'are listed below:
                                 'are listed below:
10 CFR Part 50. Appendix- B. Criterion XVI: Updated Final Safety Analysis'
                                            10 CFR Part 50. Appendix- B. Criterion XVI: Updated Final Safety Analysis'
                         ~
                         ~
                                   'A.-                                                                                                                              f Report.: Section 17.2; and the J. M. Farley Plant Operations- Quality l                                                '
                                   'A.-                                                                                                                              f
Assurance Policy Manual. Chapter 16, require that the-licensee take measures to assure that conditions adverse to quality are-promptly identified and corrected. Such measures are to be taken to assure that the cause of the condition is determined ~and corrective actions are.
                                            Report.: Section 17.2; and the J. M. Farley Plant Operations- Quality l                                                '
taken to preclude repetition.                                                                                          ,
                                            Assurance Policy Manual. Chapter 16, require that the-licensee take
Contrary to the-above as-early as June 1985 the licensee identified
                                            measures to assure that conditions adverse to quality are-promptly
                                           . degradation of the cork seal between the containment and auxiliary a                                          building walls.-a condition adverse to cuality, and foiled to promptly correct it. Furthermore, on June 22 anc -December. 10. 1996, the licensee                                              o~
                                            identified and corrected. Such measures are to be taken to assure that
identified that sections of the cork seal in the Unit 1 and Unit 2 Main ESteam Vaive Room (MSVR) floor were'missings The significance of the condition was not recognized and corrected 'until April 21. 1997 for-Unit 2 and until June 1997 (during the scheduled outage) for Unit 1.
                                            the cause of the condition is determined ~and corrective actions are.
                                            taken to preclude repetition.                                                                                          ,
,
                                            Contrary to the-above as-early as June 1985 the licensee identified
                                           . degradation of the cork seal between the containment and auxiliary
a                                          building walls.-a condition adverse to cuality, and foiled to promptly
'
                                            correct it. Furthermore, on June 22 anc -December. 10. 1996, the licensee                                              o~
                                            identified that sections of the cork seal in the Unit 1 and Unit 2 Main
                                          ESteam Vaive Room (MSVR) floor were'missings The significance of the
                                            condition was not recognized and corrected 'until April 21. 1997 for-
                                            Unit 2 and until June 1997 (during the scheduled outage) for Unit 1.
.                                          Consequently, due to the missing MSVR floor cork seal, the plant
.                                          Consequently, due to the missing MSVR floor cork seal, the plant
,4                                          operated outside its design basis for a main feedwater line break in the MSVR for an extended period of time before being corrected.
,4                                          operated outside its design basis for a main feedwater line break in the
This 1s.a Severity Level IV violation (Supplement I).
                                            MSVR for an extended period of time before being corrected.
                                 'B.        10 CFR Part 50. Appendix B. Criterion-III, requires that applicable regulatory requirements and design basis are correctly translated into-                                                ;
                                  This 1s.a Severity Level IV violation (Supplement I).
drawings, procedures and instructions.
'
          ,
                                 'B.        10 CFR Part 50. Appendix B. Criterion-III, requires that applicable
                                            regulatory requirements and design basis are correctly translated into-                                                ;
                                          drawings, procedures and instructions.
F                        ,                  10 CFR Part 50. Appendix A. Criterion 2. requires that structures.
F                        ,                  10 CFR Part 50. Appendix A. Criterion 2. requires that structures.
.                                          systems, and components.important to safety shall be designed to withstand the effects of. natural phenomena such as tornados F hout the'                                                o Lloss of crpability to perform their safety functions.-
.                                          systems, and components.important to safety shall be designed to
                                          withstand the effects of. natural phenomena such as tornados F hout the'                                                o
                                          Lloss of crpability to perform their safety functions.-
                                     ~
                                     ~
.
                 ,                        1Thel Licensee's 0)erations-Ouality Assurance-Program. Updated Final
                 ,                        1Thel Licensee's 0)erations-Ouality Assurance-Program. Updated Final
                                           'Sifety' Analysis Report (UFSAR) 17.2;3, states that measures-are established to assure that applicable regulatory requirements.' quality standards, and-desien bases are properly translated inte specifications.
                                           'Sifety' Analysis Report (UFSAR) 17.2;3, states that measures-are
Ldrawings.Tproceduresr'and instruct 1ons, e
  ,
Enclosure 1 a                          :                ,    .
              -
                                          established to assure that applicable regulatory requirements.' quality
                                          standards, and-desien bases are properly translated inte specifications.
    "
                                          Ldrawings.Tproceduresr'and instruct 1ons,
e
.                .
                                  '
                                                                                                                                  Enclosure 1
  a                          :                ,    .
      _'
t
t
                 .,u                            ,.              .
                 .,u                            ,.              .
                                                                         -,e--<%e esA    ,43-        e        ic-.--,'  ,. + - -  . ,,v-- m ,      e , . . - .
                                                                         -,e--<%e esA    ,43-        e        ic-.--,'  ,. + - -  . ,,v-- m ,      e , . . - .


       >      ~ _ .. _ _ _ _ _ _                          _ _ . _                  _ . _ . -        -        _    _    _    __ _ . .
       >      ~ _ .. _ _ _ _ _ _                          _ _ . _                  _ .     _ . -        -        _    _    _    __ _ . .
v      w r
      v      w
a
                                                                                                                                                r
                                                                                                                                                *
                    a
[m
[m
                           . Notice _of Violation                          2                                                                    1 10FSAR Section-~3.5.4 states that Category I equipment and-' piping outsidet containment are either housedLin Category I structures-or-buried _ _                                      <
,                    .
underground. -UFSAR Sections 6.5.1, 3.2.1.3, 3.2.1.5 and Table 3,2-1 _
                        _
identify the Auxiliary Feedwater_ equipment as Category I.                                                >
                                                                                                                  _
                                                                                                                                                .
            ,
                           . Notice _of Violation                          2                                                                    1
                                  10FSAR Section-~3.5.4 states that Category I equipment and-' piping outsidet
                                      containment are either housedLin Category I structures-or-buried _ _                                      <
                                      underground. -UFSAR Sections 6.5.1, 3.2.1.3, 3.2.1.5 and Table 3,2-1 _
-
                                      identify the Auxiliary Feedwater_ equipment as Category I.                                                >
                                                                                                                                             ~
                                                                                                                                             ~
                                   -Contrary to the above. as'of March 14,1997.o the 'above regulatory requirements and design bases were not correctly translated-into drawings, procedures and instructions in that the TDAFW pump vent stadk                                  ;
                                   -Contrary to the above. as'of March 14,1997.o the 'above regulatory
was installed on the roof of the auxiliary building and was not designed and installed to withstand the effects of tornados.
                                    -
                                      requirements and design bases were not correctly translated-into
                                      drawings, procedures and instructions in that the TDAFW pump vent stadk                                  ;
                                      was installed on the roof of the auxiliary building and was not designed
                                      and installed to withstand the effects of tornados.
                       <  Thisiis a. Severity Level IV Violation-(Supplement I).
                       <  Thisiis a. Severity Level IV Violation-(Supplement I).
iPursuant.to the provisions ~of 10 CFR 2.201, Southern Nuclear Operating Company                                          ,
                      iPursuant.to the provisions ~of 10 CFR 2.201, Southern Nuclear Operating Company                                          ,
is hereby required to submit a written statement or explanation to the'U.S.
'
Nuclear Regulatory Commission. ATTN: Document Control Desk. Washington. DC
                          is hereby required to submit a written statement or explanation to the'U.S.
                         . 20555, with a copy to the' Regional Administrator Region II. and a copy to the-NRC Resident Inspector, Farley. Nuclear Plant, within-30 days of the date of                                        +
                          Nuclear Regulatory Commission. ATTN: Document Control Desk. Washington. DC
the letter transmitting this Notice of Violation (Notice). This reply should' be clearly marked as a " Reply to a Notice of Violation" and should include for each violation: (1) the reason:for.the-violation, or, if contested . the basis for disputing the violation (2) the corrective steps-that have been taken and the results achieved. (3)'the corrective steps that will be taken to avoid further violations, and (4) the date_when full compliance will be achieved.                                            '
'
Your response may reference or-inctde previous docketed correspondence if
                         . 20555, with a copy to the' Regional Administrator Region II. and a copy to the-
'.                        the correspondence adequately 'addrf aes the recuired res?onse. -If an adequate-reply is not_ received within the time specifiec in this 40tice, an order or a
                                          -
:                      - Demand for Information may be issued as to why the license shoald not be modified, suspended, or revoked, or why such other action as may be 3 roper should not be taken. Where good cause is shown, consideration will 3e given to extending the response time.
                          NRC Resident Inspector, Farley. Nuclear Plant, within-30 days of the date of                                        +
Because your res:rnse will be placed in the NRC Public Document Room (PDR), to
                          the letter transmitting this Notice of Violation (Notice). This reply should'
                          be clearly marked as a " Reply to a Notice of Violation" and should include for
                          each violation: (1) the reason:for.the-violation, or, if contested . the basis
                          for disputing the violation (2) the corrective steps-that have been taken and
                          the results achieved. (3)'the corrective steps that will be taken to avoid
                                                                            -
                          further violations, and (4) the date_when full compliance will be achieved.                                            '
                          Your response may reference or-inctde previous docketed correspondence if
'.                        the correspondence adequately 'addrf aes the recuired res?onse. -If an adequate-
                          reply is not_ received within the time specifiec in this 40tice, an order or a
:                      - Demand for Information may be issued as to why the license shoald not be
                          modified, suspended, or revoked, or why such other action as may be 3 roper
>-
                          should not be taken. Where good cause is shown, consideration will 3e given
                          to extending the response time.
                          Because your res:rnse will be placed in the NRC Public Document Room (PDR), to
.                        the extent possi]le, it should not include any personal privacy, 3roprietary.
.                        the extent possi]le, it should not include any personal privacy, 3roprietary.
                       . or safeguards _information so that it can be placed in the PDR witlout
                       . or safeguards _information so that it can be placed in the PDR witlout
                         -redaction. However, if you find it necessary to include such information. -you should clearly indicate the specific information that you desire not to be placed in the PDR.- and provide the legal basis to support your request .for withholding the_information from the public.
                         -redaction. However, if you find it necessary to include such information. -you
Dated at Atlanta, Georgia this 29th day of December 1997-4 e
                          should clearly indicate the specific information that you desire not to be
o                                                                                                                    ' Enclosure 1 e
                          placed in the PDR.- and provide the legal basis to support your request .for
i f
                          withholding the_information from the public.
   ''ly  .;_            e er    y Pt  o      e ~a-        **--W re&  4    --'rt*    e- *we    -=waww  e" w-                          " "}}
.
                          Dated at Atlanta, Georgia
                          this 29th day of December 1997-
                                                                                                                                                4
e
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Latest revision as of 10:47, 8 September 2023

Notice of Violation from Insp on 971019-1129.Violation Noted:As Early as June 1985,licensee Identified Degradation of Cork Seal Between Containment & Auxiliary Bldg Walls, Condition Adverse to Quality
ML20198N948
Person / Time
Site: Farley  Southern Nuclear icon.png
Issue date: 12/29/1997
From:
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
To:
Shared Package
ML20198N914 List:
References
50-348-97-14, 50-364-97-14, EA-97-557, EA-97-571, NUDOCS 9801210271
Download: ML20198N948 (2)


See also: IR 07100019/2011029

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N0TICE OFl VIOLATION

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< Southern Nuclear Operating Company - Docket Nos.: 50-348 and 50 364

>

Farley Nuclear Plant,: Units:1 and 2- License:Nos.: - NPF-2 and.NPF-8

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EA 97-557; --

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EA 97-571 j

During an U.S. Nuclear Regulatory Commission (NRC)' inspection conducted during' l

the period October 19 through November.29, 1997.' violations of'NRC .

requirements were identified. In accordance with the " General Statement of: 1

Policy and Procedures'for NRC Enforcement Actions." NUREG-1600 the violations >

'are listed below:

10 CFR Part 50. Appendix- B. Criterion XVI: Updated Final Safety Analysis'

~

'A.- f

Report.: Section 17.2; and the J. M. Farley Plant Operations- Quality l '

Assurance Policy Manual. Chapter 16, require that the-licensee take

measures to assure that conditions adverse to quality are-promptly

identified and corrected. Such measures are to be taken to assure that

the cause of the condition is determined ~and corrective actions are.

taken to preclude repetition. ,

,

Contrary to the-above as-early as June 1985 the licensee identified

. degradation of the cork seal between the containment and auxiliary

a building walls.-a condition adverse to cuality, and foiled to promptly

'

correct it. Furthermore, on June 22 anc -December. 10. 1996, the licensee o~

identified that sections of the cork seal in the Unit 1 and Unit 2 Main

ESteam Vaive Room (MSVR) floor were'missings The significance of the

condition was not recognized and corrected 'until April 21. 1997 for-

Unit 2 and until June 1997 (during the scheduled outage) for Unit 1.

. Consequently, due to the missing MSVR floor cork seal, the plant

,4 operated outside its design basis for a main feedwater line break in the

MSVR for an extended period of time before being corrected.

This 1s.a Severity Level IV violation (Supplement I).

'

,

'B. 10 CFR Part 50. Appendix B. Criterion-III, requires that applicable

regulatory requirements and design basis are correctly translated into-  ;

drawings, procedures and instructions.

F , 10 CFR Part 50. Appendix A. Criterion 2. requires that structures.

. systems, and components.important to safety shall be designed to

withstand the effects of. natural phenomena such as tornados F hout the' o

Lloss of crpability to perform their safety functions.-

~

.

, 1Thel Licensee's 0)erations-Ouality Assurance-Program. Updated Final

'Sifety' Analysis Report (UFSAR) 17.2;3, states that measures-are

,

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established to assure that applicable regulatory requirements.' quality

standards, and-desien bases are properly translated inte specifications.

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Ldrawings.Tproceduresr'and instruct 1ons,

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. Notice _of Violation 2 1

10FSAR Section-~3.5.4 states that Category I equipment and-' piping outsidet

containment are either housedLin Category I structures-or-buried _ _ <

underground. -UFSAR Sections 6.5.1, 3.2.1.3, 3.2.1.5 and Table 3,2-1 _

-

identify the Auxiliary Feedwater_ equipment as Category I. >

~

-Contrary to the above. as'of March 14,1997.o the 'above regulatory

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requirements and design bases were not correctly translated-into

drawings, procedures and instructions in that the TDAFW pump vent stadk  ;

was installed on the roof of the auxiliary building and was not designed

and installed to withstand the effects of tornados.

< Thisiis a. Severity Level IV Violation-(Supplement I).

iPursuant.to the provisions ~of 10 CFR 2.201, Southern Nuclear Operating Company ,

'

is hereby required to submit a written statement or explanation to the'U.S.

Nuclear Regulatory Commission. ATTN: Document Control Desk. Washington. DC

'

. 20555, with a copy to the' Regional Administrator Region II. and a copy to the-

-

NRC Resident Inspector, Farley. Nuclear Plant, within-30 days of the date of +

the letter transmitting this Notice of Violation (Notice). This reply should'

be clearly marked as a " Reply to a Notice of Violation" and should include for

each violation: (1) the reason:for.the-violation, or, if contested . the basis

for disputing the violation (2) the corrective steps-that have been taken and

the results achieved. (3)'the corrective steps that will be taken to avoid

-

further violations, and (4) the date_when full compliance will be achieved. '

Your response may reference or-inctde previous docketed correspondence if

'. the correspondence adequately 'addrf aes the recuired res?onse. -If an adequate-

reply is not_ received within the time specifiec in this 40tice, an order or a

- Demand for Information may be issued as to why the license shoald not be

modified, suspended, or revoked, or why such other action as may be 3 roper

>-

should not be taken. Where good cause is shown, consideration will 3e given

to extending the response time.

Because your res:rnse will be placed in the NRC Public Document Room (PDR), to

. the extent possi]le, it should not include any personal privacy, 3roprietary.

. or safeguards _information so that it can be placed in the PDR witlout

-redaction. However, if you find it necessary to include such information. -you

should clearly indicate the specific information that you desire not to be

placed in the PDR.- and provide the legal basis to support your request .for

withholding the_information from the public.

.

Dated at Atlanta, Georgia

this 29th day of December 1997-

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