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{{#Wiki_filter:-
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                    #                     611 RY AN PL AZA oRIVE, Suff E 400
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                                              AR LINGToN. T r x AS 76011 8064
NUCLEAR REGULATORY COMMISSION -
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                                                  November 21,1997--
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        lEA 97 523
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        William T. Cottle, Group Vice
#
              President, Nuclear
611 RY AN PL AZA oRIVE, Suff E 400
          Houston Lighting & Power Company
%,
          P.O. Box 289 -
#
        Wadsworth, Texas 77483
AR LINGToN. T r x AS 76011 8064
                                                                                                            I;
''
          SUBJECT: NRC INSPECTION REPORT 50 498/97-24; 50-499/97 24
-
          Dear Mr. Cottle:
*'***
          From September 15 through November 12,1997, the NRC inspected your design control
-
          program and the adequacy of calculations used to develop the design and licensing basis
November 21,1997--
            for your South Texas Project Electric Generatlng Station Units 1 and 2, reactor facilities.
lEA 97 523
          The team reviewed the history and corrective actions ass:iated with previously identified
William T. Cottle, Group Vice
          weaknessos related to the process instrument setpoint and scaling program. The team also
President, Nuclear
          reviewed 10 CFR Part 50.59 saf ety evaluations and 10 CFR Part 50.59 applicability
Houston Lighting & Power Company
            screening evaluations,
P.O. Box 289 -
          We have concluded that t,nreviewed safety question evaluations and screenings were
Wadsworth, Texas 77483
          generally logical and of good quality. However, we identified design and licensing control
I
          concerns, which are discussed below. We noted that, as time permitted, your staff
SUBJECT: NRC INSPECTION REPORT 50 498/97-24; 50-499/97 24
          initiated and plaaned corrective actiuns for the weaknesses identified by the team.
Dear Mr. Cottle:
          We have concluded that your current setpoint guidance procedure was technically
From September 15 through November 12,1997, the NRC inspected your design control
            adequate. However, a random sampling of existing calculations for safety-related plant
program and the adequacy of calculations used to develop the design and licensing basis
          process values indicated that appropriate uncertainty calculations had not always been
for your South Texas Project Electric Generatlng Station Units 1 and 2, reactor facilities.
            accomplished through the end of 1996. The team selected 6 safety related process valucs
The team reviewed the history and corrective actions ass:iated with previously identified
            from the Updated Final Safety Analysis Report and found that calculations associated with
weaknessos related to the process instrument setpoint and scaling program. The team also
          4 of the 6 p'rocess values were incorrect and required revision. We also continued to
reviewed 10 CFR Part 50.59 saf ety evaluations and 10 CFR Part 50.59 applicability
          identify problems with the basis for setpoints. Three of 20 setpoints, which had been
screening evaluations,
          identified by your contractor in 1995 as potentially having no basis, still had weak-
We have concluded that t,nreviewed safety question evaluations and screenings were
                                                                                                        )
generally logical and of good quality. However, we identified design and licensing control
            calculation bases. The unresolved item related to our review of the safety impact of your
concerns, which are discussed below. We noted that, as time permitted, your staff
            decision to defer planned setpoint program improvements was left open for additional
initiated and plaaned corrective actiuns for the weaknesses identified by the team.
            review. The NRC plans to evaluate the calculations, which address team concerns, but
We have concluded that your current setpoint guidance procedure was technically
            were not complete at the conclusion of the inspection. The specific technicalissues are
adequate. However, a random sampling of existing calculations for safety-related plant
            discussed in Section E8.2 of the enclosed report.
process values indicated that appropriate uncertainty calculations had not always been
                                              -
accomplished through the end of 1996. The team selected 6 safety related process valucs
                                    1                                         * * * ' '   '
from the Updated Final Safety Analysis Report and found that calculations associated with
              971129016397h493
4 of the 6 p'rocess values were incorrect and required revision. We also continued to
              gDR      ADOCK 05
identify problems with the basis for setpoints. Three of 20 setpoints, which had been
                                  PDR
)
                -
identified by your contractor in 1995 as potentially having no basis, still had weak-
                                                a
calculation bases. The unresolved item related to our review of the safety impact of your
                                *                                       m   ,-
decision to defer planned setpoint program improvements was left open for additional
review. The NRC plans to evaluate the calculations, which address team concerns, but
were not complete at the conclusion of the inspection. The specific technicalissues are
discussed in Section E8.2 of the enclosed report.
971129016397h493
-
1
* * * '
'
'
gDR
ADOCK 05
-
PDR
a
*
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,-


  .
.
    4
4
    .
.
      Houston Lighting & Power Company               2-
Houston Lighting & Power Company
      Based on the results of this inspection seven apparent violations were identified and are
2-
      being considered for escalated enforcen.ent action in accordance with the " General
Based on the results of this inspection seven apparent violations were identified and are
      Statement of Policy and Procedure for NRC Enforcement Actions" (Enforcement Policy),
being considered for escalated enforcen.ent action in accordance with the " General
      NUREG-1600. The team identified one apparent violation of 10 CFR Part 50, Appendix B,
Statement of Policy and Procedure for NRC Enforcement Actions" (Enforcement Policy),
      Criterion XVI, " Corrective Action," five apparent violations of 10 CFR Part 50, Appendix B,
NUREG-1600. The team identified one apparent violation of 10 CFR Part 50, Appendix B,
      Criterion lil, " Design Control," and one apparent violation of 10 CFR 50.59, " Changes,-
Criterion XVI, " Corrective Action," five apparent violations of 10 CFR Part 50, Appendix B,
      Tests and Experiments." No Notice of Violation is presently being issued for these
Criterion lil, " Design Control," and one apparent violation of 10 CFR 50.59, " Changes,-
      inspection findings, in addition, please be advised that the number ano characterization of
Tests and Experiments." No Notice of Violation is presently being issued for these
      apparent violations described in the enclosed inspection report may change as a result of
inspection findings, in addition, please be advised that the number ano characterization of
      further NRC review.
apparent violations described in the enclosed inspection report may change as a result of
      The NRC is concerned about the apparent corrective action violation because it appeared           I
further NRC review.
      that your threshold for determining that calculation deficiencies are conditions (iverse to
The NRC is concerned about the apparent corrective action violation because it appeared
      quality was too high. As a result, you did not take corrective action in a time frame
I
      commensurate to the safety significance of design deficienc'es first identified in 1992. The
that your threshold for determining that calculation deficiencies are conditions (iverse to
      NRC is concerned about the apparent design control violation related to the control of
quality was too high. As a result, you did not take corrective action in a time frame
      amendments because your enginers may not have been provided with the tools required to
commensurate to the safety significance of design deficienc'es first identified in 1992. The
      adequatoly maintain thc design of tu f acility. As a result, in some cases calculations were
NRC is concerned about the apparent design control violation related to the control of
      amended so many times, that the bu ding design values were not readily apparent. The
amendments because your enginers may not have been provided with the tools required to
      NRC is concerned about these violatio.is, the remaining apparent design control violations
adequatoly maintain thc design of tu f acility. As a result, in some cases calculations were
      and the 10 CFR 50.59 violation, because the causes appear to be programmatic. As such,
amended so many times, that the bu ding design values were not readily apparent. The
      the team has probably not identified all of the examplea ano may not have identified the
NRC is concerned about these violatio.is, the remaining apparent design control violations
      most safety significant examples.
and the 10 CFR 50.59 violation, because the causes appear to be programmatic. As such,
      A predecisional enfercement conference to discuss these apparent violations has been
the team has probably not identified all of the examplea ano may not have identified the
      scheduled for December 8,1997. The decision to hold a predecisional enforcement
most safety significant examples.
      confereme does not mean that the NRC has determined that a violation has occurred or
A predecisional enfercement conference to discuss these apparent violations has been
      that enforcement action will be taken. This conference is being held to obtain 3. formation
scheduled for December 8,1997. The decision to hold a predecisional enforcement
      to enable the NRC to make an enforcement decision, such as a common understanding of
confereme does not mean that the NRC has determined that a violation has occurred or
      the facts, root causes, mined opportunities to identify the apparent violation sooner,
that enforcement action will be taken. This conference is being held to obtain 3. formation
      corrective actions, significr :e of the issues, and the need for lasting and effective
to enable the NRC to make an enforcement decision, such as a common understanding of
      corrective action. During the predecisional enforcement conference, we expect you to
the facts, root causes, mined opportunities to identify the apparent violation sooner,
      describe your current plan and schedule for identifying and correcting any remaining
corrective actions, significr :e of the issues, and the need for lasting and effective
      calculation deficiencies, in addition, this is an opportunity for you to point out any errors in
corrective action. During the predecisional enforcement conference, we expect you to
      our inspection report and for you to provide any information conceming your perspectives
describe your current plan and schedule for identifying and correcting any remaining
      on 1) the severity of the violations,2) the application of the f actors that the NRC considers
calculation deficiencies, in addition, this is an opportunity for you to point out any errors in
      when it determines the amount of a civil penalty that may be assessed m accordance with
our inspection report and for you to provide any information conceming your perspectives
      Section VI.B.2 of the Enforcement Policy, and 3) any other application of the Enforcement
on 1) the severity of the violations,2) the application of the f actors that the NRC considers
      Policy to this case, including the exercise of discretion in accordance with Section Vll.
when it determines the amount of a civil penalty that may be assessed m accordance with
      This coc!erence will be open to public observation in accordance with a recent change to
Section VI.B.2 of the Enforcement Policy, and 3) any other application of the Enforcement
      the enforcement policy (61 FR 65088).
Policy to this case, including the exercise of discretion in accordance with Section Vll.
      You will be advised by separate correspondence of the results of our deliberations on this
This coc!erence will be open to public observation in accordance with a recent change to
the enforcement policy (61 FR 65088).
You will be advised by separate correspondence of the results of our deliberations on this
matter. No response regarding these apparent violations is required at this time,
,
,
      matter. No response regarding these apparent violations is required at this time,
j
                                                                                                      j


    -         -.       -
-
      ..:
-.
            Houston Lighting & Power Company             -3
-
            In accordance with 10 CFR 2.790 of the NRC's " Rules of Practice," a copy of this letter -
..:
            and its enclosure will be placed in the NRC Public Document Room (PDR).
Houston Lighting & Power Company
          - Should you have any que:tions concerning this inspection, we will be pleased to discuss
-3
            them with you.-
In accordance with 10 CFR 2.790 of the NRC's " Rules of Practice," a copy of this letter -
                                                        Sincerely,
and its enclosure will be placed in the NRC Public Document Room (PDR).
                                                                                                        -l
- Should you have any que:tions concerning this inspection, we will be pleased to discuss
                                                        [
them with you.-
                                                      l           h             k
Sincerely,
                                                        Arthur T. Howell lil, Director                     '
-l
                                                        Division of Reactor Safety
[
            Docket Nos.: 50 498;50-499
l
            License Nos.: NPF 76; NPF 80
h
k
Arthur T. Howell lil, Director
'
Division of Reactor Safety
Docket Nos.: 50 498;50-499
License Nos.: NPF 76; NPF 80
- Enclosure:
<
<
          - Enclosure:
NRC Inspection Report
              NRC Inspection Report
50-498/97-24; 50 499/97 24
                  50-498/97-24; 50 499/97 24
i
                                                                                                          i
cc w/ enclosure:
            cc w/ enclosure:
Lawrence E. Martin, General Manager
            Lawrence E. Martin, General Manager
Nuclear Assurance & Licensing
            Nuclear Assurance & Licensing
Houston Lighting & Power Company
            Houston Lighting & Power Company
P.O. Box 289
            P.O. Box 289
Wadsworth, Texas 77483
            Wadsworth, Texas 77483
Mr. J. C. Lanier/Mr. M. B. Lee
            Mr. J. C. Lanier/Mr. M. B. Lee
~ City of Austin
          ~ City of Austin
- Electric Utility Department
          - Electric Utility Department
721 Barton Springs Road
            721 Barton Springs Road
A~ustin, Texas 78704
            A~ustin, Texas 78704
Mr. K. J. Fiedler/Mr. M. T Hardt
            Mr. K. J. Fiedler/Mr. M. T Hardt
City Public Service Board
            City Public Service Board
P.O. Box 1771
            P.O. Box 1771
San Antonio, Texas 78296
            San Antonio, Texas 78296                                                                     3
3
            -Jack R. Newman,- Esq.
-Jack R. Newman,- Esq.
            Morgan, Lewis & Bockius
Morgan, Lewis & Bockius
            1800 M. Street, N.W.                                                                         1
1800 M. Street, N.W.
            Washington, D.C. 20036 5869
1
Washington, D.C. 20036 5869
,
,
  .-                                                                                                   -
.-
-


                                                  ]
]
O
O
  Houston Lighting & Power Company-         -4-
Houston Lighting & Power Company-
  Mr. G . E. Vaughn/Mr. C. A. Johnson
-4-
  Central Power & Light Company
Mr. G . E. Vaughn/Mr. C. A. Johnson
  P.O. Box 289.
Central Power & Light Company
  Mail Code: N5012
P.O. Box 289.
  Wadsworth, Texas 77483
Mail Code: N5012
  INPO
Wadsworth, Texas 77483
  Records Center
INPO
  700 Galleria Parkway
Records Center
  - Atlanta, Georgia 30339-5957
700 Galleria Parkway
  Dr. Bertram Wolfe
- Atlanta, Georgia 30339-5957
    15453 Via Vaquero
Dr. Bertram Wolfe
  Monte Sereno, California 95030
15453 Via Vaquero
  Bureau of Radiation Control
Monte Sereno, California 95030
  State of Texas
Bureau of Radiation Control
    1100 West 49th Street
State of Texas
  Austin, Texas 78756
1100 West 49th Street
  Mr. G!enn W. Dishong
Austin, Texas 78756
  Texas Public Utility Commission
Mr. G!enn W. Dishong
  7800 Shoal Creek Blvd.
Texas Public Utility Commission
  Suite 400N
7800 Shoal Creek Blvd.
  Austin, Texas 78757-1024
Suite 400N
  John Howard, Director
Austin, Texas 78757-1024
  Environmental and Natural Resources Policy
John Howard, Director
  Office of the Governor
Environmental and Natural Resources Policy
  P.O. Box 12428 -
Office of the Governor
  Austin, Texas 78711
P.O. Box 12428 -
  Judge, Matagorda County
Austin, Texas 78711
  Matagorda County Courthouse
Judge, Matagorda County
    1700 Seventh Street
Matagorda County Courthouse
  Bay City, Texas 77414
1700 Seventh Street
  Licensing Representative
Bay City, Texas 77414
  Houston Lighting & Power Company
Licensing Representative
  Suite 610
Houston Lighting & Power Company
  Three Metro Center
Suite 610
    Bethesda, Maryland 20814
Three Metro Center
                                                  ')
Bethesda, Maryland 20814
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                          ' Houston Lighting & Power Company.-                               -5 '
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                                      .,
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                                            *
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        ;     &
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                            : Rufus S.4 Scott, Associate'-
, - .
                              ; General Counsel
&
                              Houston Lighting & Power Company-:
*
                          .; P.O. Box 61867 '                 ~
;
                              Houston, Texas 77208
Rufus S.4 Scott, Associate'-
                          -' Joseph R. Egan, Esq.
:
                              Egan & Associates,- P.C. .
; General Counsel
                  -
Houston Lighting & Power Company-:
                            - 2300 N Street, N.W.
P.O. Box 61867 '
                          -- Washington, D.C.- 20037
.;
                    ,                                                                                   .
~
                        .-
Houston, Texas 77208
                                                                                                                  ;
-' Joseph R. Egan, Esq.
                                                                                                                  i
Egan & Associates,- P.C. .
                                                                                                                  a
-
                                                                                                              ..
- 2300 N Street, N.W.
Washington, D.C.- 20037
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      Houston Lighting & Power Company                             6
e
      E Mail report to T. Frye (TJF)
d
      E Mail report to T. Hiltz (TGH)
Houston Lighting & Power Company
      E Mail report to NRR Event Tracking System (IPAS)
6
      E Mail report to Document Control Desk (DCCDESK)
E Mail report to T. Frye (TJF)
      bec to DCD (IE01)
E Mail report to T. Hiltz (TGH)
      bec distrib. by RIV:
E Mail report to NRR Event Tracking System (IPAS)
      Regional Administrator                                   Resident inspector
E Mail report to Document Control Desk (DCCDESK)
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Latest revision as of 04:22, 8 December 2024

Forwards Insp Repts 50-498/97-24 & 50-499/97-24 on 970915-1112.No Violations Noted.Team Reviewed History & CAs Associated w/previously-identified Weakness Re Process Instrument Setpoint & Scaling Program
ML20199J535
Person / Time
Site: South Texas  STP Nuclear Operating Company icon.png
Issue date: 11/21/1997
From: Howell A
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
To: Cottle W
HOUSTON LIGHTING & POWER CO.
Shared Package
ML20199J541 List:
References
50-498-97-24, 50-499-97-24, EA-97-523, NUDOCS 9711280163
Download: ML20199J535 (7)
v • d • e


See also: IR 05000498/1997024

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November 21,1997--

lEA 97 523

William T. Cottle, Group Vice

President, Nuclear

Houston Lighting & Power Company

P.O. Box 289 -

Wadsworth, Texas 77483

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SUBJECT: NRC INSPECTION REPORT 50 498/97-24; 50-499/97 24

Dear Mr. Cottle:

From September 15 through November 12,1997, the NRC inspected your design control

program and the adequacy of calculations used to develop the design and licensing basis

for your South Texas Project Electric Generatlng Station Units 1 and 2, reactor facilities.

The team reviewed the history and corrective actions ass:iated with previously identified

weaknessos related to the process instrument setpoint and scaling program. The team also

reviewed 10 CFR Part 50.59 saf ety evaluations and 10 CFR Part 50.59 applicability

screening evaluations,

We have concluded that t,nreviewed safety question evaluations and screenings were

generally logical and of good quality. However, we identified design and licensing control

concerns, which are discussed below. We noted that, as time permitted, your staff

initiated and plaaned corrective actiuns for the weaknesses identified by the team.

We have concluded that your current setpoint guidance procedure was technically

adequate. However, a random sampling of existing calculations for safety-related plant

process values indicated that appropriate uncertainty calculations had not always been

accomplished through the end of 1996. The team selected 6 safety related process valucs

from the Updated Final Safety Analysis Report and found that calculations associated with

4 of the 6 p'rocess values were incorrect and required revision. We also continued to

identify problems with the basis for setpoints. Three of 20 setpoints, which had been

)

identified by your contractor in 1995 as potentially having no basis, still had weak-

calculation bases. The unresolved item related to our review of the safety impact of your

decision to defer planned setpoint program improvements was left open for additional

review. The NRC plans to evaluate the calculations, which address team concerns, but

were not complete at the conclusion of the inspection. The specific technicalissues are

discussed in Section E8.2 of the enclosed report.

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Based on the results of this inspection seven apparent violations were identified and are

being considered for escalated enforcen.ent action in accordance with the " General

Statement of Policy and Procedure for NRC Enforcement Actions" (Enforcement Policy),

NUREG-1600. The team identified one apparent violation of 10 CFR Part 50, Appendix B,

Criterion XVI, " Corrective Action," five apparent violations of 10 CFR Part 50, Appendix B,

Criterion lil, " Design Control," and one apparent violation of 10 CFR 50.59, " Changes,-

Tests and Experiments." No Notice of Violation is presently being issued for these

inspection findings, in addition, please be advised that the number ano characterization of

apparent violations described in the enclosed inspection report may change as a result of

further NRC review.

The NRC is concerned about the apparent corrective action violation because it appeared

I

that your threshold for determining that calculation deficiencies are conditions (iverse to

quality was too high. As a result, you did not take corrective action in a time frame

commensurate to the safety significance of design deficienc'es first identified in 1992. The

NRC is concerned about the apparent design control violation related to the control of

amendments because your enginers may not have been provided with the tools required to

adequatoly maintain thc design of tu f acility. As a result, in some cases calculations were

amended so many times, that the bu ding design values were not readily apparent. The

NRC is concerned about these violatio.is, the remaining apparent design control violations

and the 10 CFR 50.59 violation, because the causes appear to be programmatic. As such,

the team has probably not identified all of the examplea ano may not have identified the

most safety significant examples.

A predecisional enfercement conference to discuss these apparent violations has been

scheduled for December 8,1997. The decision to hold a predecisional enforcement

confereme does not mean that the NRC has determined that a violation has occurred or

that enforcement action will be taken. This conference is being held to obtain 3. formation

to enable the NRC to make an enforcement decision, such as a common understanding of

the facts, root causes, mined opportunities to identify the apparent violation sooner,

corrective actions, significr :e of the issues, and the need for lasting and effective

corrective action. During the predecisional enforcement conference, we expect you to

describe your current plan and schedule for identifying and correcting any remaining

calculation deficiencies, in addition, this is an opportunity for you to point out any errors in

our inspection report and for you to provide any information conceming your perspectives

on 1) the severity of the violations,2) the application of the f actors that the NRC considers

when it determines the amount of a civil penalty that may be assessed m accordance with

Section VI.B.2 of the Enforcement Policy, and 3) any other application of the Enforcement

Policy to this case, including the exercise of discretion in accordance with Section Vll.

This coc!erence will be open to public observation in accordance with a recent change to

the enforcement policy (61 FR 65088).

You will be advised by separate correspondence of the results of our deliberations on this

matter. No response regarding these apparent violations is required at this time,

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Houston Lighting & Power Company

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In accordance with 10 CFR 2.790 of the NRC's " Rules of Practice," a copy of this letter -

and its enclosure will be placed in the NRC Public Document Room (PDR).

- Should you have any que:tions concerning this inspection, we will be pleased to discuss

them with you.-

Sincerely,

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Arthur T. Howell lil, Director

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Division of Reactor Safety

Docket Nos.: 50 498;50-499

License Nos.: NPF 76; NPF 80

- Enclosure:

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NRC Inspection Report

50-498/97-24; 50 499/97 24

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cc w/ enclosure:

Lawrence E. Martin, General Manager

Nuclear Assurance & Licensing

Houston Lighting & Power Company

P.O. Box 289

Wadsworth, Texas 77483

Mr. J. C. Lanier/Mr. M. B. Lee

~ City of Austin

- Electric Utility Department

721 Barton Springs Road

A~ustin, Texas 78704

Mr. K. J. Fiedler/Mr. M. T Hardt

City Public Service Board

P.O. Box 1771

San Antonio, Texas 78296

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-Jack R. Newman,- Esq.

Morgan, Lewis & Bockius

1800 M. Street, N.W.

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Washington, D.C. 20036 5869

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Houston Lighting & Power Company-

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Mr. G . E. Vaughn/Mr. C. A. Johnson

Central Power & Light Company

P.O. Box 289.

Mail Code: N5012

Wadsworth, Texas 77483

INPO

Records Center

700 Galleria Parkway

- Atlanta, Georgia 30339-5957

Dr. Bertram Wolfe

15453 Via Vaquero

Monte Sereno, California 95030

Bureau of Radiation Control

State of Texas

1100 West 49th Street

Austin, Texas 78756

Mr. G!enn W. Dishong

Texas Public Utility Commission

7800 Shoal Creek Blvd.

Suite 400N

Austin, Texas 78757-1024

John Howard, Director

Environmental and Natural Resources Policy

Office of the Governor

P.O. Box 12428 -

Austin, Texas 78711

Judge, Matagorda County

Matagorda County Courthouse

1700 Seventh Street

Bay City, Texas 77414

Licensing Representative

Houston Lighting & Power Company

Suite 610

Three Metro Center

Bethesda, Maryland 20814

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Rufus S.4 Scott, Associate'-

General Counsel

Houston Lighting & Power Company-:

P.O. Box 61867 '

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-' Joseph R. Egan, Esq.

Egan & Associates,- P.C. .

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Washington, D.C.- 20037

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Russ Wise (2)

Branch Chief (DRS/MB)

DOCUMENT NAME: R:\\,_STP\\ST724RP.LJS

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