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See also: [[see also::IR 07100019/2011029]] | |||
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; 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 : , . | |||
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> ~ _ .. _ _ _ _ _ _ _ _ . _ _ . _ . - - _ _ _ __ _ . . | > ~ _ .. _ _ _ _ _ _ _ _ . _ _ . _ . - - _ _ _ __ _ . . | ||
v w r | v w | ||
a | r | ||
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[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 | |||
o ' Enclosure 1 | |||
e | |||
i | |||
f | |||
''ly .;_ e er y Pt o e ~a- **--W re& 4 --'rt* e- *we -=waww e" w- " " | |||
}} |
Latest revision as of 10:47, 8 September 2023
ML20198N948 | |
Person / Time | |
---|---|
Site: | Farley ![]() |
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
Text
._ _ -- __ _ _ _ . .. _ . _ . . _ ,_ _ _._ _ . _ . . -. _
- .7 m v q
a
'
i
- 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
- -
- 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 >
'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
,
-
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
.,u ,. .
-,e--<%e esA ,43- e ic-.--,' ,. + - - . ,,v-- m , e , . . - .
> ~ _ .. _ _ _ _ _ _ _ _ . _ _ . _ . - - _ _ _ __ _ . .
v w
r
a
[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. >
~
-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 ;
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-
4
e
o ' Enclosure 1
e
i
f
ly .;_ e er y Pt o e ~a- **--W re& 4 --'rt* e- *we -=waww e" w- " "