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See also: [[see also::IR 07100130/2012004]]


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ENCLOSURE 1 NOTICE OF VIOLATION Georgia Power Company                                            Docket No. 50-424 Vogtle                                                            License No. NPF-68 During the Nuclear Regulatory Commission (NRC) inspection conducted on November 30    -
                                                ENCLOSURE 1
December 4, December 14 - 18, 1987, and January 5,        1988, violations of NRC requirements were identified.            In accordance with the "General Statement of Policy and Procedure for NRC Enforcement Actions," 10 CFR Part 2, Appendix C (1988), the violations are listed below:
                                            NOTICE OF VIOLATION
A. 10 CFR 50.49(a) requires that each holder of a license establish a prog am for qualifying electric equipment.          10 CFR 50.49(b)(3) lists certain post-accident monitoring system equipment as being important to safety.
          Georgia Power Company                                            Docket No. 50-424
10 CFR 50.49 paragraphs (f), (k), and (j), NUREG-0588, and IEEE 323-1974 require that:
          Vogtle                                                            License No. NPF-68
: 1. This equipment be installed in a manner and position equivalcat to the as tested /as analyzed condition and;                                !
          During the Nuclear Regulatory Commission (NRC) inspection conducted on
: 2. Documentation be maintained to verify the equipment is qualified for i
          November 30    -
its application for the entire period during which the covered item is installed in the Nuclear Power Plant.
                              December 4, December 14 - 18, 1987, and January 5,        1988,
Contrary      to the above,    a Core Exit Thermocouple Junction Box (post-accident monitoring instrumentation) in containment was left in an unqualified environmental condition following system maintenance. This condition was identified on April 13, 1987, on MWO 18704972 which stated that no documentation could be located to verify irsta'.lation of the environmental seal for the junction box. The condition was not corrected until October 10, 1987, following six months of power operation.
          violations of NRC requirements were identified.            In accordance with the
This is a Severity Level IV violation (Supplement I).
          "General Statement of Policy and Procedure for NRC Enforcement Actions," 10 CFR
B. 10 CFR 50 Appendix B Criterion V, and the licensee's accepted QA program, Final Safety Evaluation Report (FSAR) Section 17.2.5, require that activities affecting quality shall be prescribed by documented procedures and shall be accomplished in accordance with these procedures.            The
          Part 2, Appendix C (1988), the violations are listed below:
  ;              licentec Deficiency Control Procedure, 00150-C, Revision 6, Sections 1 and 1.2,  require that conditions adverse to quality be identified and processed oer this procedure.
          A.   10 CFR 50.49(a) requires that each holder of a license establish a prog am
Contrary to the above, problems involving main steam, chemical and volume control, main feed, power operated relief valves, and post-accident monitoring instrumentation systems were not identified as conditions adverse to quality.      They were processed via the maintenance work order    '
              for qualifying electric equipment.          10 CFR 50.49(b)(3) lists certain
program rather than the approved deficiency control program. The specific work orders are:
              post-accident monitoring system equipment as being important to safety.
8802100223 080211 PDR ADOCK 05000424 0                  DCD
                10 CFR 50.49 paragraphs (f), (k), and (j), NUREG-0588, and IEEE 323-1974
              require that:
                1.   This equipment be installed in a manner and position equivalcat to
                      the as tested /as analyzed condition and;                                !
              2.     Documentation be maintained to verify the equipment is qualified for
i
                      its application for the entire period during which the covered item
                      is installed in the Nuclear Power Plant.
              Contrary      to the above,    a Core Exit Thermocouple Junction Box
                (post-accident monitoring instrumentation) in containment was left in an
                unqualified environmental condition following system maintenance. This
              condition was identified on April 13, 1987, on MWO 18704972 which stated
                that no documentation could be located to verify irsta'.lation of the
                environmental seal for the junction box. The condition was not corrected
                until October 10, 1987, following six months of power operation.
              This is a Severity Level IV violation (Supplement I).
          B.   10 CFR 50 Appendix B Criterion V, and the licensee's accepted QA program,
                Final Safety Evaluation Report (FSAR) Section 17.2.5, require that
                activities affecting quality shall be prescribed by documented procedures
                and shall be accomplished in accordance with these procedures.            The
  ;              licentec Deficiency Control Procedure, 00150-C, Revision 6, Sections 1 and
                1.2,  require that conditions adverse to quality be identified and
                processed oer this procedure.
                Contrary to the above, problems involving main steam, chemical and volume
                control, main feed, power operated relief valves, and post-accident
                monitoring instrumentation systems were not identified as conditions
                adverse to quality.      They were processed via the maintenance work order    '
                program rather than the approved deficiency control program. The specific
                work orders are:
    8802100223 080211
    PDR ADOCK 05000424
    0                  DCD


i      .
  _ _ _ _ _ _ _  _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _
Georgia Power Company                                                                  2                                                                                                        Occket No. 50-424 Vogtle                                                                                                                                                                                          License No. NPF-68 MWO 18705430 MWO 18706938 MWO 18701732 MWO 18702035 MWO 18704972 This is a severity Level V violation (Supplement I).
                                                                                                                                                          _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ .___ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ - _ _ - _ _ .
C.                                            10 CFR 50 Appendix B Criterion XI, and the licensee's accepted QA program, FSAR Section 17.2.11, collectively require that a test program be estab-li'J.ed to assure that all testing required to demonstrate that systems will perform satisfactorily in service is performed in accordance with written test procedures. Additionally, Procedure SUM 22, Maintenance Work Orders, Revision 16, Section 6.7.1, states that where applicable (dering the preoperational phase), a functional test is required after maintenance work to verify that systems are capable of performing their intended function.
        i      .
Contrary to the above, following preoperational modifications to the turbine driven auxiliary feedwater (AFW) pump turbine speed indication circuit under MWO 18620139, a functional test was not performed to verify that this system would perform satisfactorily in service. The modifica-tion placed an oversized resistor in the circuit which resulted in a loss of AFW turbine speed indication in the control room and shutdown Panel C.
                                                            Georgia Power Company                                                                  2                                                                                                        Occket No. 50-424
This condition was discovered three months later and was not repaired until after two months of power operations.
                                                            Vogtle                                                                                                                                                                                          License No. NPF-68
This is a Severity Level V violation (Supplement I).
                                                                                                                          MWO 18705430
Pursuant to the provisions of 10 CFR 2.201, Georgia Power Company is hereby required to submit a written statement or explanation to the 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, within 30 days of the date of the letter transmitting this Notice.
                                                                                                                          MWO 18706938
This reply should be clearly marked as a "Reply to a Notice of Violation" and should include [for each violation]: (1) admission or denial of the violation, (2) the reason for the violation, if admitted, (3) the corrective steps which I
                                                                                                                          MWO 18701732
                                                                                                                          MWO 18702035
                                                                                                                          MWO 18704972
                                                                                                              This is a severity Level V violation (Supplement I).
                                                              C.                                            10 CFR 50 Appendix B Criterion XI, and the licensee's accepted QA program,
                                                                                                              FSAR Section 17.2.11, collectively require that a test program be estab-
                                                                                                              li'J.ed to assure that all testing required to demonstrate that systems
                                                                                                              will perform satisfactorily in service is performed in accordance with
                                                                                                              written test procedures. Additionally, Procedure SUM 22, Maintenance Work
                                                                                                              Orders, Revision 16, Section 6.7.1, states that where applicable (dering
                                                                                                              the preoperational phase), a functional test is required after maintenance
                                                                                                              work to verify that systems are capable of performing their intended
                                                                                                              function.
                                                                                                              Contrary to the above, following preoperational modifications to the
                                                                                                              turbine driven auxiliary feedwater (AFW) pump turbine speed indication
                                                                                                              circuit under MWO 18620139, a functional test was not performed to verify
                                                                                                              that this system would perform satisfactorily in service. The modifica-
                                                                                                              tion placed an oversized resistor in the circuit which resulted in a loss
                                                                                                              of AFW turbine speed indication in the control room and shutdown Panel C.
                                                                                                              This condition was discovered three months later and was not repaired
                                                                                                              until after two months of power operations.
                                                                                                              This is a Severity Level V violation (Supplement I).
                                                                                                                                                                                                                                                                                '
                                                                Pursuant to the provisions of 10 CFR 2.201, Georgia Power Company is hereby
                                                                  required to submit a written statement or explanation to the 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, within 30 days of the date of the letter transmitting this Notice.
                                                                This reply should be clearly marked as a "Reply to a Notice of Violation" and
                                                                    should include [for each violation]: (1) admission or denial of the violation,
                                                                  (2) the reason for the violation, if admitted, (3) the corrective steps which
!
I


     %    0 Georgia Power Company                                        3                  Docket No. 50-424 Vogtle                                                                            License No. NPF-68 (2) the reason for the violation, if admitted, (3) the corrective steps which have been taken and the results achieved, (4) the corrective steps which will be taken to avoid further violations, and (5) the date when full compliance l              will be achieved. Where good cause is shown, consideration will be given to l
                                                                                _____
extending the response time. If an adequate reply is not received within the i                time specified in this Notice, an order may be issutd to show cause why the l                license should not be modified, suspended, or revoked or why such other action as may be proper should not be taken.
                                                .
1 FOR THE NUCLEAR REGULATORY COMMISSION
              ..
                                                                               ])W? W/lUbb Caudie A. Ju ian, Chief'lt Operations Branch Division of Reactor Safety Dated at Atlanta, Georgia, this lith day of February 1988 1
            _
     %    0
              Georgia Power Company                                        3                  Docket No. 50-424
              Vogtle                                                                            License No. NPF-68
                (2) the reason for the violation, if admitted, (3) the corrective steps which
                have been taken and the results achieved, (4) the corrective steps which will
,
                be taken to avoid further violations, and (5) the date when full compliance
l              will be achieved. Where good cause is shown, consideration will be given to
l
                extending the response time. If an adequate reply is not received within the
i                time specified in this Notice, an order may be issutd to show cause why the
l                license should not be modified, suspended, or revoked or why such other action
'
                as may be proper should not be taken.
1
                                                                            FOR THE NUCLEAR REGULATORY COMMISSION
                                                                               ])W? W/lUbb
                                                                            Caudie A. Ju ian, Chief'lt
                                                                            Operations Branch
                                                                            Division of Reactor Safety
                Dated at Atlanta, Georgia,
                this lith day of February 1988
1
i
i
   --    -                                              . - - . - - - - - -}}
      .
                                                                                                                  ;
   --    -                                              . - - . - - - - - -
}}

Latest revision as of 18:22, 9 September 2023

Notice of Violation from Insp on 871130-1204 & 14-18 & 880115.Violations Noted:Core Exit Thermocouple Junction Box in Containment Left in Unqualified Environ Condition After Maint & Problems Not Identified as Adverse to Quality
ML20149G318
Person / Time
Site: Vogtle Southern Nuclear icon.png
Issue date: 02/11/1988
From: Julian C
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
To:
Shared Package
ML20149G314 List:
References
50-424-87-69, NUDOCS 8802180223
Download: ML20149G318 (3)


See also: IR 07100130/2012004

Text

s . .

ENCLOSURE 1

NOTICE OF VIOLATION

Georgia Power Company Docket No. 50-424

Vogtle License No. NPF-68

During the Nuclear Regulatory Commission (NRC) inspection conducted on

November 30 -

December 4, December 14 - 18, 1987, and January 5, 1988,

violations of NRC requirements were identified. In accordance with the

"General Statement of Policy and Procedure for NRC Enforcement Actions," 10 CFR

Part 2, Appendix C (1988), the violations are listed below:

A. 10 CFR 50.49(a) requires that each holder of a license establish a prog am

for qualifying electric equipment. 10 CFR 50.49(b)(3) lists certain

post-accident monitoring system equipment as being important to safety.

10 CFR 50.49 paragraphs (f), (k), and (j), NUREG-0588, and IEEE 323-1974

require that:

1. This equipment be installed in a manner and position equivalcat to

the as tested /as analyzed condition and;  !

2. Documentation be maintained to verify the equipment is qualified for

i

its application for the entire period during which the covered item

is installed in the Nuclear Power Plant.

Contrary to the above, a Core Exit Thermocouple Junction Box

(post-accident monitoring instrumentation) in containment was left in an

unqualified environmental condition following system maintenance. This

condition was identified on April 13, 1987, on MWO 18704972 which stated

that no documentation could be located to verify irsta'.lation of the

environmental seal for the junction box. The condition was not corrected

until October 10, 1987, following six months of power operation.

This is a Severity Level IV violation (Supplement I).

B. 10 CFR 50 Appendix B Criterion V, and the licensee's accepted QA program,

Final Safety Evaluation Report (FSAR) Section 17.2.5, require that

activities affecting quality shall be prescribed by documented procedures

and shall be accomplished in accordance with these procedures. The

licentec Deficiency Control Procedure, 00150-C, Revision 6, Sections 1 and

1.2, require that conditions adverse to quality be identified and

processed oer this procedure.

Contrary to the above, problems involving main steam, chemical and volume

control, main feed, power operated relief valves, and post-accident

monitoring instrumentation systems were not identified as conditions

adverse to quality. They were processed via the maintenance work order '

program rather than the approved deficiency control program. The specific

work orders are:

8802100223 080211

PDR ADOCK 05000424

0 DCD

_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _

_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ .___ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ - _ _ - _ _ .

i .

Georgia Power Company 2 Occket No. 50-424

Vogtle License No. NPF-68

MWO 18705430

MWO 18706938

MWO 18701732

MWO 18702035

MWO 18704972

This is a severity Level V violation (Supplement I).

C. 10 CFR 50 Appendix B Criterion XI, and the licensee's accepted QA program,

FSAR Section 17.2.11, collectively require that a test program be estab-

li'J.ed to assure that all testing required to demonstrate that systems

will perform satisfactorily in service is performed in accordance with

written test procedures. Additionally, Procedure SUM 22, Maintenance Work

Orders, Revision 16, Section 6.7.1, states that where applicable (dering

the preoperational phase), a functional test is required after maintenance

work to verify that systems are capable of performing their intended

function.

Contrary to the above, following preoperational modifications to the

turbine driven auxiliary feedwater (AFW) pump turbine speed indication

circuit under MWO 18620139, a functional test was not performed to verify

that this system would perform satisfactorily in service. The modifica-

tion placed an oversized resistor in the circuit which resulted in a loss

of AFW turbine speed indication in the control room and shutdown Panel C.

This condition was discovered three months later and was not repaired

until after two months of power operations.

This is a Severity Level V violation (Supplement I).

'

Pursuant to the provisions of 10 CFR 2.201, Georgia Power Company is hereby

required to submit a written statement or explanation to the 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, within 30 days of the date of the letter transmitting this Notice.

This reply should be clearly marked as a "Reply to a Notice of Violation" and

should include [for each violation]: (1) admission or denial of the violation,

(2) the reason for the violation, if admitted, (3) the corrective steps which

!

I

_____

.

..

_

% 0

Georgia Power Company 3 Docket No. 50-424

Vogtle License No. NPF-68

(2) the reason for the violation, if admitted, (3) the corrective steps which

have been taken and the results achieved, (4) the corrective steps which will

,

be taken to avoid further violations, and (5) the date when full compliance

l will be achieved. Where good cause is shown, consideration will be given to

l

extending the response time. If an adequate reply is not received within the

i time specified in this Notice, an order may be issutd to show cause why the

l license should not be modified, suspended, or revoked or why such other action

'

as may be proper should not be taken.

1

FOR THE NUCLEAR REGULATORY COMMISSION

])W? W/lUbb

Caudie A. Ju ian, Chief'lt

Operations Branch

Division of Reactor Safety

Dated at Atlanta, Georgia,

this lith day of February 1988

1

i

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