ML19343B780: Difference between revisions

From kanterella
Jump to navigation Jump to search
(Created page by program invented by StriderTol)
 
(Created page by program invented by StriderTol)
Line 17: Line 17:
=Text=
=Text=
{{#Wiki_filter:<
{{#Wiki_filter:<
    ..%
.
d f/g-[]%ss            cU e.
d f/g-[]%ss            cU e.
                                           .. d hi
                                           .. d hi
                                 ,es.we.eea 1        i        , \ 90GCi
                                 ,es.we.eea 1        i        , \ 90GCi
                          '
           .(Dp/$                            g                                      James W Cook
           .(Dp/$                            g                                      James W Cook
                       /      puN5
                       /      puN5
                                 ,,,,ll,,yi,d b 8 y                                  Vice President - Pro, sects, Engvreenng and Construction General offkes: 1945 West Parnall Road, Jackson. MI 43201 * (5171 783-0453 December 18, 1980
                                 ,,,,ll,,yi,d b 8 y                                  Vice President - Pro, sects, Engvreenng and Construction General offkes: 1945 West Parnall Road, Jackson. MI 43201 * (5171 783-0453 December 18, 1980 l                                                                                                                t Mr J G Keppler, Regional Director                                                                      !
.                                                                                                            .
l                                                                                                                t Mr J G Keppler, Regional Director                                                                      !
Office of Inspection & Enforcement US Nuclear Regulatory Commission Region III                                                                                                        _
Office of Inspection & Enforcement US Nuclear Regulatory Commission Region III                                                                                                        _
799 Roosevelt Road                                                                                                  -
799 Roosevelt Road                                                                                                  -
Line 33: Line 28:
reported by telephone call to Ray Sutphin USNRC Region III, Glen Ellyn, IL, on November 17, 1980. The purpose of this letter is to more fully describe the problems identified and to state that, as of now, we classify the item as potentially reportable due to the extensive analysis that will'be required to make a definitive determination of reportability.
reported by telephone call to Ray Sutphin USNRC Region III, Glen Ellyn, IL, on November 17, 1980. The purpose of this letter is to more fully describe the problems identified and to state that, as of now, we classify the item as potentially reportable due to the extensive analysis that will'be required to make a definitive determination of reportability.
The conditions found include: (a) specific errors found in the Bechtel and B&W analyses (eg, a mathematical error in a moment of inertia calculation, and keypunch errors in input data to the seismic analysis), (b) instances of4nis application by one company of input data generated by the other company related to lack of a clear understanding of the data basis, (c) a case of failure to transmit updated input data and (d) questions as to modeling assumptions. The conclusion drawn from these conditions'is that the primary system seismic and LOCA analysis to date must be considered indeterminate as to the adequacy of the results. Based on the preliminary assessment of the impact of these items, it is not exper ced at this time that the actual hardware will be affected, nor has ic been confirmed that a reportable condition exists.
The conditions found include: (a) specific errors found in the Bechtel and B&W analyses (eg, a mathematical error in a moment of inertia calculation, and keypunch errors in input data to the seismic analysis), (b) instances of4nis application by one company of input data generated by the other company related to lack of a clear understanding of the data basis, (c) a case of failure to transmit updated input data and (d) questions as to modeling assumptions. The conclusion drawn from these conditions'is that the primary system seismic and LOCA analysis to date must be considered indeterminate as to the adequacy of the results. Based on the preliminary assessment of the impact of these items, it is not exper ced at this time that the actual hardware will be affected, nor has ic been confirmed that a reportable condition exists.
Design inputs were provided by Bechtel for the B&W reactor coolant system (RCS) seismic and LOCA analyses. B&W used this input for B&W component stress analysis. These analyses were used by B&W to determine seismic responses for l        B&W components and piping, B&W component support nozzle loads, and i        displacements of the primary system at support attachment points and at attached piping locations. Bechtel then used these B&W results in the design
Design inputs were provided by Bechtel for the B&W reactor coolant system (RCS) seismic and LOCA analyses. B&W used this input for B&W component stress analysis. These analyses were used by B&W to determine seismic responses for l        B&W components and piping, B&W component support nozzle loads, and i        displacements of the primary system at support attachment points and at attached piping locations. Bechtel then used these B&W results in the design O\
                                                                            -
O\
of component supports and in Class 1 stress analysis for Bechtel-supplied                                                g piping and components. A number of these analyses had been completed.
of component supports and in Class 1 stress analysis for Bechtel-supplied                                                g piping and components. A number of these analyses had been completed.
However, the supportinC system for the reactor pressure vessel (RPV) is being
However, the supportinC system for the reactor pressure vessel (RPV) is being oc1280-0085a102
!
oc1280-0085a102
                                                               ~
                                                               ~
S        som.meo ~
S        som.meo ~


__                ._            _                                              _
                                                                                                  .
_ _ _          _        . _      m.,
_ _ _          _        . _      m.,
                                .
i Serial 10085                                                                                                  2 modified as a result of problems experienced with the reactor vessel bolting.
$
i
                  '
Serial 10085                                                                                                  2
      ..
modified as a result of problems experienced with the reactor vessel bolting.
As a result, appropriate NSSS seismic and component loading documents will be revised using corrected input and the revised RPV support design. The current project design will then be verified or revised, as necessary, using the results of corrected RCS analyses.
As a result, appropriate NSSS seismic and component loading documents will be revised using corrected input and the revised RPV support design. The current project design will then be verified or revised, as necessary, using the results of corrected RCS analyses.
Consumers Power, B&W, and Bechtel are implementing a corrective action program which will assure that all specific anomalies are adequately dispositioned and that any required process corrective actions are in place to provide confidence in the new analysis. An additional review is being undertaken to confirm that intercompany interface controls are adequate.
Consumers Power, B&W, and Bechtel are implementing a corrective action program which will assure that all specific anomalies are adequately dispositioned and that any required process corrective actions are in place to provide confidence in the new analysis. An additional review is being undertaken to confirm that intercompany interface controls are adequate.
Line 59: Line 42:
1981.
1981.
[0&d/            '
[0&d/            '
i
i WRB/re CC Director of Office of Inspection & Enforcement Att Mr Victer Stello, USNRC (15)
.
V,/ Director, Office Management Information & Program Control, USNRC (1)
WRB/re CC Director of Office of Inspection & Enforcement Att Mr Victer Stello, USNRC (15)
:
V,/ Director, Office Management
,
Information & Program Control, USNRC (1)
RCook, USNRC Resident Inspector
RCook, USNRC Resident Inspector
,                        Midland Nuclear Plant (1) 2 i                          CBechhoefer, ASLB Panel
,                        Midland Nuclear Plant (1) 2 i                          CBechhoefer, ASLB Panel
;                          GAlinenberger, ASLB Panel                                                                      ,
;                          GAlinenberger, ASLB Panel                                                                      ,
FPCowan, ASLB Panel
FPCowan, ASLB Panel AS&L Appeal Panel                                                                                  ',e MMCherry, Esq l                        MSinclair l                        CRStephens, USNRC l
'
AS&L Appeal Panel                                                                                  ',e MMCherry, Esq l                        MSinclair l                        CRStephens, USNRC l
WDPaton, Esq, USNRC FJKelly, Esq, Attorney General SHFreeman, Esq, Asst Attorney General GTTaylor, Esq, Asst Attorney General WHMarshall i
WDPaton, Esq, USNRC FJKelly, Esq, Attorney General SHFreeman, Esq, Asst Attorney General GTTaylor, Esq, Asst Attorney General WHMarshall i
'
GJMerritt, Esq, TNK&J Great Lakes QA Managers
GJMerritt, Esq, TNK&J Great Lakes QA Managers
(
(
'
,
I I
I I
,
l
l
!
;
;
;
;
i S
i S
          '
i                  oc1280-0085a102 l                                          .
i                  oc1280-0085a102
                                                                    -
l                                          .
                                                                                                                                              -
w -  -  .- - , m    ,,~,  e  +          --4-.. , , - . - , -- , - , -n._ .- , , ,e-, -- -,-v  -y ,    ,  .ew- - , --
w -  -  .- - , m    ,,~,  e  +          --4-.. , , - . - , -- , - , -n._ .- , , ,e-, -- -,-v  -y ,    ,  .ew- - , --
                                                                                                                --
e ,%}}
e ,%}}

Revision as of 07:29, 31 January 2020

Deficiency Rept,Originally Reported on 801117,confirming Anomalies Identified in NSSS Seismic & LOCA Analysis of Primary Sys.Reactor Pressure Vessel Supporting Sys Being Modified Due to Reactor Vessel Bolting Problems
ML19343B780
Person / Time
Site: Midland
Issue date: 12/18/1980
From: Jackie Cook
CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.)
To: James Keppler
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
References
10085, 10CFR-050.55E, 10CFR-50.55E, NUDOCS 8012300460
Download: ML19343B780 (2)
v • d • e


Text

<

d f/g-[]%ss cU e.

.. d hi

,es.we.eea 1 i , \ 90GCi

.(Dp/$ g James W Cook

/ puN5

,,,,ll,,yi,d b 8 y Vice President - Pro, sects, Engvreenng and Construction General offkes: 1945 West Parnall Road, Jackson. MI 43201 * (5171 783-0453 December 18, 1980 l t Mr J G Keppler, Regional Director  !

Office of Inspection & Enforcement US Nuclear Regulatory Commission Region III _

799 Roosevelt Road -

Glen Ellyn, IL 60137 MIDLAND NUCLEAR PLANT UNITS 1 AND 2, DOCKET NOS 50-329, 50-330 NSSS ANALYSIS FILE 0.4.9.44 UFI 73*10*01, 02000(S) SERIAL 10085 This letter confirms the 50.55(e) item concerning anomalies identified in the NSSS seismic and LOCA analysis of the primary system. This condition was.

reported by telephone call to Ray Sutphin USNRC Region III, Glen Ellyn, IL, on November 17, 1980. The purpose of this letter is to more fully describe the problems identified and to state that, as of now, we classify the item as potentially reportable due to the extensive analysis that will'be required to make a definitive determination of reportability.

The conditions found include: (a) specific errors found in the Bechtel and B&W analyses (eg, a mathematical error in a moment of inertia calculation, and keypunch errors in input data to the seismic analysis), (b) instances of4nis application by one company of input data generated by the other company related to lack of a clear understanding of the data basis, (c) a case of failure to transmit updated input data and (d) questions as to modeling assumptions. The conclusion drawn from these conditions'is that the primary system seismic and LOCA analysis to date must be considered indeterminate as to the adequacy of the results. Based on the preliminary assessment of the impact of these items, it is not exper ced at this time that the actual hardware will be affected, nor has ic been confirmed that a reportable condition exists.

Design inputs were provided by Bechtel for the B&W reactor coolant system (RCS) seismic and LOCA analyses. B&W used this input for B&W component stress analysis. These analyses were used by B&W to determine seismic responses for l B&W components and piping, B&W component support nozzle loads, and i displacements of the primary system at support attachment points and at attached piping locations. Bechtel then used these B&W results in the design O\

of component supports and in Class 1 stress analysis for Bechtel-supplied g piping and components. A number of these analyses had been completed.

However, the supportinC system for the reactor pressure vessel (RPV) is being oc1280-0085a102

~

S som.meo ~

_ _ _ _ . _ m.,

i Serial 10085 2 modified as a result of problems experienced with the reactor vessel bolting.

As a result, appropriate NSSS seismic and component loading documents will be revised using corrected input and the revised RPV support design. The current project design will then be verified or revised, as necessary, using the results of corrected RCS analyses.

Consumers Power, B&W, and Bechtel are implementing a corrective action program which will assure that all specific anomalies are adequately dispositioned and that any required process corrective actions are in place to provide confidence in the new analysis. An additional review is being undertaken to confirm that intercompany interface controls are adequate.

I Another report, either interim or final, will be sent on or before~ March 12,.

1981.

[0&d/ '

i WRB/re CC Director of Office of Inspection & Enforcement Att Mr Victer Stello, USNRC (15)

V,/ Director, Office Management Information & Program Control, USNRC (1)

RCook, USNRC Resident Inspector

, Midland Nuclear Plant (1) 2 i CBechhoefer, ASLB Panel

GAlinenberger, ASLB Panel ,

FPCowan, ASLB Panel AS&L Appeal Panel ',e MMCherry, Esq l MSinclair l CRStephens, USNRC l

WDPaton, Esq, USNRC FJKelly, Esq, Attorney General SHFreeman, Esq, Asst Attorney General GTTaylor, Esq, Asst Attorney General WHMarshall i

GJMerritt, Esq, TNK&J Great Lakes QA Managers

(

I I

l

i S

i oc1280-0085a102 l .

w - - .- - , m ,,~, e + --4-.. , , - . - , -- , - , -n._ .- , , ,e-, -- -,-v -y , , .ew- - , --

e ,%

Retrieved from "https://kanterella.com/w/index.php?title=ML19343B780&oldid=2350500"