View source for TXX-2867, Supplemental Deficiency Rept Re Misclassification of safety- Related Equipment.Initially Reported on 780718.Engineering Safety Implication Analysis Determined That Item Not Reportable Under 10CFR50.55(e)

{{Adams
| number = ML20235B930
| issue date = 07/28/1978
| title = Supplemental Deficiency Rept Re Misclassification of safety- Related Equipment.Initially Reported on 780718.Engineering Safety Implication Analysis Determined That Item Not Reportable Under 10CFR50.55(e)
| author name = Gary R
| author affiliation = TEXAS UTILITIES ELECTRIC CO. (TU ELECTRIC)
| addressee name = Seidle W
| addressee affiliation = NRC OFFICE OF INSPECTION &amp; ENFORCEMENT (IE REGION IV)
| docket = 05000445, 05000446
| license number = 
| contact person = 
| case reference number = FOIA-87-508
| document report number = TXX-2867, NUDOCS 8709240284
| package number = ML17198A319
| document type = DEFICIENCY REPORTS (PER 10CFR50.55E &amp; PART 21), TEXT-SAFETY REPORT
| page count = 1
}}

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                                                                                           ,                  j A               TEXAS UTIL TIES GENERATING COMIMNY 2, . .. ..,,, e n ,,, u. . . . s u. ~ , :s  ,w,,                       J July 28, 1978-              j TXX-2867
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Mr. W. C. Seidle, Chief Reactor Construction & Engineering                                                        i Support Branch U. S. Nuclear Regulatory Commission Office of Inspection and Enforcement                                                      l 611 Ryan Plaza Dr., Suite 1000                                Docket Nos. 50-445 Arlington, Texas ;76011                                                    50-446          ;
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COMANCHE PEAK STEAM ELECTRIC STATION'                                        !
1981-83 2300 MW INSTALLATION                          .
4 MISCLASSIFICATION OF SAFETY-RELATED EQUIPMENT FILE NO. 10110 l
Dear Mr. Seidle-This will supplement our letter of July 18, 1978 logged TXX-2860, wherein we contitted to advise you-by August 31, 1978 of the                              ;
deportability of the interface breakdown, which resulted in +he                           ;
misclassification of safety-related equipment foundations by our architect engineer.
The engineering safety implication analysis has been completed.                            ;
We have concluded that this item is not reportable under the pro-                          l visions of 10 CFR 50.55(e).
l The identified problems are being dispositioned in accordance with                        I our established procedures.                                                               !
Very truly yours, R. J. Gary p 1 RJG:dla                                                                                   '
cc: Director, Office of Inspection and Enforcement (15)                                   :
Director, Office of Management Information and Program Control (1)
U. S. Nuclear Regulatory Commission Washington, D. C. 20555                      -
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8709240284 870921 PDR     FOIA WILLIAMSB7-508 PDR i
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b               TEXAS UTILITIES GENERATING CO.ilI%NY MtM)I HH) AN tt 5% 6.lt D 41J. 4% lia W 71!O6 November 1, 1978
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Mr. W. C. Seidle, Chief Reactor Construction & Engineering Support Branch U. S. Nuclear Regulatory Consnission Office of Inspection and Enforcement 611 Ryan Plaza Dr., Suite 1000                              Docket Nos. 50-445   j Arlington, Texas 76011                                                   50-446    g i
i COMANCHE PEAK STEAM ELECTRIC STATION 1981-83 2300 MW INSTALLATION                                 I I
SERVICE WATER PUMP SEISMIC RESTRAINT INTERIM RESPONSE                                    l FILE NO. 10110 i

==Dear Mr. Seidle:==

On October 6,1978 we notified you by' telephone that a question on the design of the Seismic Restraint for the Service Water                      !
Pump might be potentially reportable under 10 CFR 50.55(e). The engineer has conducted an evaluation of the design and has noti-fied us that had the deficiency gone undetected it would not have
                     < adversely affected the safety of the plant. However, we are still evaluating his response, and will report to you our final detenni-nation by November 17, 1978.
Very truly yours, l
l R.i . Gary RJG:dla                                                                           ,
                     < cc: Director, Office of Inspection and Enforcement (15)
Director, Office of Management Information and Program Control (1)-         l U. S. Nuclear Regulatory Commission                                        ,
Washington, D. C. 20555                                                    !
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Mll Ryan Plaza Drive, Salte 10Q0                                                                                              Docket llos 50-445                                      -
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                                                                                                                                                                                         .50-4/5 C0MACHE PEA [S'EAM ELhCTRfC STATION
                                 ' ' ~ .'                                            1981 SL 33Cd MW IKsiaLLATION
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==Dear Mr. .%yfrit:==
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'                             ' On Octcoer 4,1978, we verbiOly. ii.formd youniir.E fi. G. "ayW/ CPSLS                                                                                                                                                         i Resioeit Inspector, of a stap?.c failure.fcJ.Anj'(Mallet <,ydytWsledve                                                                                                                                    -                 o j orn Nod & reir.furcing steel forlihuxtericr wail ci tM Unit No. /1 containment strJcture that we were Wlunt99 m u %entially" ?cpcrbble                                                                                                                                                           j deficiency witM4@ definition of -10 :CFrz M.5He). We havE completed                                                                                                                                                           ;
e in-depth instigation of exposed cadwelu 3pitees performd: by the                                                                                                                                           --
l individual ersitsman'involvedand othera work 19 to the sarre, procedures                                                                                           -
and 4iave concluded tbt the incident waFan fitleted case. 3 Additionally engi6eering                  analys,es cleahly indicate th7%had'the single inctdent1gone ? U'                                                                                                                             'l un@tected, the matter would not he ve beert roxrtable under N ~CFR 50.55(e).
j Recteds supripeting these dcirminetWns                                                      '
art av41hble for'your; insgctor's                                                                          -1 revfedat tr.c CPSES site l                                                                                                                                                                                                                                                          ''
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                              ~ Hcwet/er, as dDicusse' wit); yor, en OctoNr 11/19M, we have racognisd, d                   .
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;                               as the rewit of our evahaMonf tte need for corrective action in the mnagement o'f our ovqrall cadwelo brogram The following items have'been or 'will be implemented to correct these .qh,ngenhngdeficienciesi                                                                                                                ,
1.
                   >                            Construction by     0;tder 20,3978.      pr ocedures,J                          ah     6eing 6.fised and will, be fully imMemy.ed
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: 2. Cadwelde rs and their foredLElli beJctr'ainst tith'a revised                                                                                                                procedures                       -
                                            .by Octoter 20, W8, $1th' 9;pnasis placed op eraftsmen inspecting thei.e
                                            -own Work.\ , ?                          g [                                                                                    ,
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: 3.            Each foreran will dac$ ists11denti'ying mark on edsry splice m3do by h3s cw and will furnish to %c rebar superinthdentt i daily' list of1siMces fs crew.
made tiya enrny @thg elapse With no defective caules.%1s act.c will -cdinin effect
: 4. ' All afie, &d cadweld : inspectors weu retraved 'sy October,16,1 1976.
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TXX-2896 Page 2      .
                    -Comanche Peak Cadwelding l                    S. Each cadweld inspector whose inspections were determined to be suspect during our investigation has been counseled at length by-the TUGC0 site QA Supervisor.- This counseling emphasized that-anything'less-than 100% will.not be tolerated.
: 6. Senior TUGC0 QA/QC staff personnel will monitor cadweld inspection on a daily basis until. adequate confidence level in our inspection-effort is restored, then periodically' to maintain this level. of confidence.
If you have any further questions, please advise.
Very truly yours, t
A.
R. J. Gary RJG:dla cc:       L. F. Fikar l
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TEXAS UTILITIES GENERATING COMI%NY 2001 BRYAN TOWER DALLAfs.TICX AH 76201 l
l a s o*=v September 18, 1980        '
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Mr. W. C. Seidle, Chief Reactor Construction & Engineering                                                   i Support Branch U. S. Nuclear Regulatory Commission Office of Inspection & Enforcement 611 Ryan Plaza Dr., Suite 1000                            Docket Nos. 50-445 Arlington, Texas 76012                                                 50-446 i
COMANCHE PEAK STEAM ELECTRIC STATION 1981-83 2300 MW INSTALLATION CLASS V PIPING SUPPORTS FILE N0: 10110

==Dear Mr. Seidle:==

In accordance with 10 CFR 50.55(e) we are submitting the attached report of actions taken to correct discrepancies involving installation and inspection requirements for Class V non-nuclear safety-related piping supports. We previously made a verbal report to Mr. R. G. Taylor on j
November 20, 1979 and submitted interim reports logged TXX-3127 and                 j TXX-3162 dated April 21, 1980 and July 14, 1980, respectively.                      J l
Supporting documentation is available at the job-site for your inspector's           )
review.
If we can provide any additional information, please advise,
                                                                                                      ]
Very truly yours,            l R.    . Gary RJS:dk Attachment cc: NRC Region IV - (0 + 1 copy)
Director, Inspection & Enforcement - (15 copies) c/o Distribution Services Branch, DDC, ADM.
U. S. Nuclear Regulatory Conrnission Washington, D. C. 20555                --
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A TXX-3195                          Attachment               September 18, 1980 CLASS V PIPING SUPPORTS Description of the Deficiency Various sections of the FSAR establish the pertinent requirements for the design fabrication, installation, and inspection of seismic supports for Class V piping systems.     ~.ne applicable project specification 2323-MS-46B does not clearly define the applicable quality requirements for the supports.
Consequently, there is insufficient positive assurance that the FSAR com-mitments have been satisfied.
l Safety Implications As a result of the stated deficiency, there is no documented assurance that the supports would satisfy the design conditions and withstand the postulated seismic loadings. Therefore, this deficiency could possibly reduce the functioning of a Seismic Category I system or component to an unacceptable safety level.
Corrective Actions To address the stated deficiency, the following corrective actions h< ave been completed:
A) FSAR changes have been instituted to more clearly delineate the requirements for Seismic Category II piping supports for Class V piping systems.
B) Changes to project specification 2323-MS-46B have been issued to detail and clarify the quality requirements and pertinent provisions of 10 CFR 50, Appendix B, to be applied during design, fabrication and installation and inspection.
C) Implementing construction and inspection instructions have been prepared and are being used for ongoing work activities. Previously installed hangers are being
                           . reworked as necessary and inspected on a system basis.

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TEXAS UTILITIES GEVERATING COMI'ANY e'i(
COOL #1MVAN TOW $ R .?A!J d84,1*ftw AM 7mmos n ,, . .m                                                              October 10, 1980
               'I'Jt;,*:,1,';;".;;'                                                              TXX-3217 i
Mr. W. C. Seidle, Chief Reactor Construction & Engineering
                                     . Support Branch
, :                              U. S. Nuclear Regulatory Commissioa L                                Office of Inspection & Enforcement 611 Ryan Plaza Dr., Suite 1000                                  Docket Nos. 50-445 Arlington, Texas 76012                                                       50-446.          ,
COMANCHE PEAK STET 4 ELECTRIC STATION 1981-83 2300 F1 INSTALLATION UPPER INTERNALS 30TO-LOCK INSERT FILE NC: 10110
: l.                               naar Mr. Spidla:
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On September 13 1980, we verbally iaformed your Mr. Ray Hall that wo                                !
Were evaluating,a deficiency with tt
* Roto-lock Insert locking tab                                 l as a potentially reportable deficier cy within the definitions of                                   '
10 CFR bO.bb(e),
We have completed our invest 1gaticn :nd have cuncludvfd that the matter                              j is not reportable under 10 CFR 50.5!(e). Records supporting this                                      j determination are available for ycui Inspector's review at the CPSES                                  I site.
Very truly yours,                     ;
                                                    \
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: a. ear, RJG:dk cc: NRC Wegion IV - (0 + 1 copy)
Director. Inspection & Enforcel ent - (15 copies) c/o Distribution Services Bron h, 000, ADM.
U. S. Nuclear Regulatory Convii sion Washington, D. C. 20555
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:..     .    ...                         R                                         R TEXAS UTILITIES GENERATING COMPANY K                                          2003 DRYAN 'N)WER DALLAE TEXAS 76208
            .som                                                           October 29, 1980
        " M;'Jf':""J.' '                                                   TXX-3229 Mr. W. C. Seidle, Chief Reactor Construction & Engineering Support Branch U. S. Nuclear Regulatory Commission Office of Inspection & Enforcement 611 Ryan Plaza Dr., Suite 1000                          Docket Nos. 50-445 Arlington, Texas 76012                                                      50-446 COMANCHE PEAK STEAM ELECTRIC STATION PLASITE 7122 C0ATING FILE N0: 10110

==Dear Mr. Seidle:==

On September 18, 1980, we verbally. informed your Mr. R. 'G. Taylor that we were evaluating a condition involving the Plasite 7122 lining in the Service Water System Piping as a potentially reportable deficiency within the definitions of 10 CFR 50.55(e). We previously submitted an interim status. report logged TXX-3218, dated October 13, 1980.
We have completed our investigation and have concluded that the matter.
is not reportable under 10 CFR 50.55(e). Documentation supporting this determination is available for your Inspector's review at the CPSES site.
Very. truly 'yours ,
R. J. Gary RJG:dk cc: NRCRegionIV-(0+1 copy)
Director, Inspection & Enforcement - (15 copies) c/o Distribution Services Branch, DDC, ADM.
U. S. Nuclear Regulatory Commission Washington, D. C. 20555 gf)//nn        ~v- n WR       -
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       .            ".'                                                                               e TEXAS UTILITIES GENERATING COMPANY 2001 DHYAN TOWEH + DALLAN, TEX.AH 76201 October 15, 1980
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TXX-3219 Mr. W.'C. Seidle, Chief Reactor Construction & Engineering Support Branch l                          U. S. Nuclear Regulatory Commission Office of Inspection & Enforcement 611 Ryan Plaza Dr. , Suite 1000                               Docket Nos. 50-445 Arlington, Texas 76012                                                          50-446 COMANCHE PEAK STEAM ELECTRIC STATION 1981-83 2300 MW-INSTALLATION THREAD ENGAGEMENT OF SWAY STRUTS FILE NO:      10110

==Dear Mr. Seidle:==

On September 19, 1980, we verbally informed your Mr. R. G. Taylor that we were evaluating a condition involving sway strut units which do not have threads upset as a potentially reportable deficiency within the definitions of 10 CFR 50.55(e).
We have completed our investigation and have concluded that the matter is not reportable under 10 CFR 50.55(e). Records supporting this deter-l                         mination are available for your Inspector's review at the CPSES site.
1 Very truly yours, 7
1 folkhy R.       Gary RJG:dk cc: NRC Region IV - (0 + 1 copy)                                                        J Director, Inspection & Enforcement - (15 copies)
I                                    c/o Distribution Services Branch, DDC, ADM.
U. S. Nuclear Regulatory Commission l
Washington, D. C. 20555 3~&8 mob g,
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         **X* .'." :::* 2.':"                                                                                        i November 30, 1982                   1 TXX-3594                             ]
Mr. G. L. Madsen, Chief                                                      '
I Reactor Projects Branch 1                                                                             l U. S. Nuclear Regulatory Commission Office of Inspection and Enforcement 611 Ryan Plaza Drive, Suite 1000                                 Docket Nos.:    50-445 Arlington, TX 76012                                                              50-446 COMANCHE PEAK STE.AM Et El TRIC STATION                                      j 0VER-TORQUING OF SAFETY RELIEF VALVES FILE NO. 10.10

==Dear Mr. Madsen:==

              'On September 10, 1982, we verbally infonn;d your Mr. R. G. Taylor of a deficiency regarding the over-torquing of safety rel ef valves. We submitted an interim                          l report logged TXX-3577 on October 6,1982.
We have completed our investigation and c >ncluded that the matter is not report-able under 10 CFR50.55(e). Records suppo ' ting this determination are available for your inspector's review at the CPSES site.
                                                                                                         .           1 Very truly yours,                    ;
R   J. Gary .
RJG:ecq i
cc: NRC REGION IV - (0 + 1 copy)
Uirector. Inspection & Enforcement (15 copies)
U. ,S. Nuclear Regulatory Comission Wash 1ngton. DC 20555 ro Ws%5b8                                         :
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cc:   R. J Gary (?)
R. R. Clements                                                  i D. N. Chapman R. L. Ramsey J. C. Kuykendall                                                 l J. T. Merritt                    *
: 0. Frankum H. C. Schmidt B. S. Dacko                                                      i R. G. Tolson                                                     !
R. G. Taylor F. B. Shant$
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                         .rt              j pa.c.u eve.e ca .          1 October 29, 1982 TXX-3589 NW        31982 Mr. G. L. Madsen, Chief                                                                     . . _ . -       .d Reactor Project Branch 1 U. S. Nuclear Regulatory Commission                                                                           j Office of Inspection and Enforcement                                                                          i 611 Ryan Plaza Drive, Suite 1000                               ' Docket Nos. 50-445                       i Arlington, TX 76012                                                              50-446 COMANCHE PEAK STEAM ELECTRIC STATION AUXILIARY BUILDING CONCRETE FLOOR SLABS FILE N0.: 10110

==Dear Mr. Madsen:==

l                 On October'20,1982, w'e verbally informed your Mr. R. G. Taylor of a deficiency regarding embedded rotafoam and plywood in the Auxiliary Building concrete floor slabs.
l                 We have completed our investigation and concluded that the matter is not l                 reportableunder10CFR50.55(e). Records supporting this determination are l
available for your Inspector's review at the CPSES site.
Very truly yours, c^     -
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                                                                         /
e . J. Gary RJG:eaq cc: NRC Region IV - (0 + 1 copy)
Director, Inspection & Enforcement (15 copies)
U. S. Nuclear Regulatory Commission                                                           {
Washington, DC 20555 i
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