ML20151U043: Difference between revisions

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#REDIRECT [[U-600422, Interim Deficiency Rept 55-85-15 Re Classification of Instrument Lines Connected to Rcpb.Initially Reported on 851227.Sargent & Lundy Performing Evaluation.Final Rept Expected within 30 Days]]
| number = ML20151U043
| issue date = 01/25/1986
| title = Interim Deficiency Rept 55-85-15 Re Classification of Instrument Lines Connected to Rcpb.Initially Reported on 851227.Sargent & Lundy Performing Evaluation.Final Rept Expected within 30 Days
| author name = Hall D
| author affiliation = ILLINOIS POWER CO.
| addressee name = Keppler J
| addressee affiliation = NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
| docket = 05000461
| license number =
| contact person =
| document report number = 55-85-15, U-600422, NUDOCS 8602100449
| document type = DEFICIENCY REPORTS (PER 10CFR50.55E & PART 21), TEXT-SAFETY REPORT
| page count = 3
}}
 
=Text=
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U- 600422
                                                                                            ~ L14-86 ( 01-25 )-L _
IA.120 NLLINOl8' POWER COMPANY
                                                                                        ^
CLINTON POWER STATION, P.O. BOK 678. CLINTON. ILLINOIS 61727 .
                        ~
Docket No. 50-461-Mr.! James':G. Keppler Regional' Administrator-Region III U.S.: Nuclear Regulatory Commission
:799 Roosevelt Road
                      ; Glen Ellyn, Illinois        60137
                      . Subj ect :  Potentially Reportable 10CFR50.55(e)
Deficiency 55-85-15:    Classification of Instrument Lines Connected to the                                        ,
Reactor Coolant Pressure Boundary De'ar Mr. Keppler:
On December 27, 1985, Illinois Power Company (IP)-
notified Mr. Guldenmond, NRC Region III (Ref: _IP Record'of.
Coordination.Y-32700 dated December-27, 1985) of a
                      -potentially reportable deficiency _under~the provisions.of
                      .10CFR50.55(e):concerning the_ instrument-lines connected to the reactor coolant pressure boundary that are ASME Class 3 instead.of ASME~ Class 2 as= required by the Final Safety.
Analysis Report (FSAR). Our investigation of.this issue                            is-continuing.      This letter represents an' interim report in accordance with the" requirements of110CFR50.55(e).
                      ~ Attachment A:provides the-details'of our investigation to date.
                              'We-: trust that this. interim. report provides you sufficient. background information to perform a general .
assessment of'this potentially reportable' deficiency and adequately describes our overall approach to resolve ~tiis
                      -issue.
Sincerel        yours, 1
                                                              .-    . Hall Vice President RLC/ckc Attachment-cc:    NRC Resident Office
                              ~ Director, Office of I&E, US NRC, Washington, DC                        20555 Illinois Department of Nuclear Safety INPO Records Center l
8602100449 e60123 5"                                                    JAN 2 8.1986      #
                          'PDR    ADOCK 05000461                                                                          1
    --                    S                  PDR  2                                                                        ,
w l__ - - _ _ - - -_ -                      _ - - _ _'_ - _ _ __ _ -                                    k_ A
 
e    a v .
Ll4-86( 01-25 )-L -
1A.120 ATTACHMENT A3 Illinois' Power Company Clinton Power Station Docket No. 50-461
:Potentially Reportable 10CFR50.55(e) Deficiency 55-85-15 cClassification of Instrument. Lines Connected-to the~ Reactor Coolant Pressure Boundary Interim Report Statement of Reportable Deficiency / Background
                      ' Illinois Power. Company Nuclear Station Engineering Department--(NSED): identified a deficiency with the design
: classification'of instrument.. lines connected to the reactor coolant-pressure boundary.- The instrument' lines are
                -classified as ASME Class 3.instead of ASME Class 2 as required by-the Final: Safety Analysis Report (FSAR).
Investigation Results/ Corrective Action IllinoisLPower (IP) prepared,and implemented an.
                .itwestigation plan to determina .tha axtent ef ' thic preblem at-the.Clinton Power Station (CPS). 13ue results' of our
                ~ investigation to date are discussed below.-
A review'was performed by-NSED and Illinois. Power
_ Quality Assurance (IPQA)--to determine the differences in
                . requirements regarding the two ASME Classes. The results          of this review determined that nondestructive examinations l(NDE) would~havesto be performed on the instrument line-
                ? welds'in order'to upgrade these lines-to ASME Class.2..
A review was performed of the line lists, P& ids, and
                . isometric drawings-to. identify'the. instrument lines.which
                'had been incorrectly. classified.        As a result of this review.
2,702 instrument line welds were identified which. require
                ' nondestructive examination for upgrading to ASME Class 2.
The NDE is currently being performed and identified
                -deficiencies-are being documented on nonconformance reports
                .(NCRs) for resolution in accordance with approved site procedures.
Sargent & Lundy (S&L) has reviewed the design requirements and issued necessary design documentation that provides for upgrading of the instrument lines to ASME Class 2.
Page 1 of 2
 
1 U 600422 :
L14-86( 01-25 )-L 1A.120 ATTACHMENT A (continued)
Root Cause-A review and evaluation is being performed by S&L of the design activity associated with classification of instrument lines. Following completion of S&L's review and evaluation, a determination will be made concerning the root cause_and_ required. corrective action needed to preclude recurrence.
Safety Implications / Significance Illinois Power's investigation of this matter is continuing. The safety implications and significance will be addressed after further background information and NDE
:r'esults have been obtained'and evaluated. It is_ anticipated that approximately thirty (30) days will ie required to complete our investigation, determine reportability and submit a final report on the matter.
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