ML20206G429

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SER Supporting Employee Concern Element Rept Co 10703-SQN, Bending Equipment/Matl
ML20206G429
Person / Time
Site: Sequoyah  Tennessee Valley Authority icon.png
Issue date: 11/04/1988
From:
NRC OFFICE OF SPECIAL PROJECTS
To:
Shared Package
ML20206G037 List: ... further results
References
NUDOCS 8811220276
Download: ML20206G429 (3)
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  1. y*"c..,'% UNITED STATES i

! NUCLE AR REGULATORY COMMISSION

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%.... l SAFETY EVALVAT'ON REPORT BY TFE OFFICE OF SPECIAL PROJECTS EMPLOYEE CONCERN ELEMENT REPORT C0 10703-SCN, i

"EENDING EQUIPMENT /FATERI AL" ,

TENNESSEE VALLEY AUTHORITY l i SEQUC) AP NUCLEAR F0WER PLANT UNITS 1 & P i

00CKET h05. 50 327 AND 50-328 \

e i I. Subject i Category
Constru: tion (10000)

Subcategory: Instrueent Tubing (10700) j Empleyee Con: erns: Bending Equipment / Material (10703)

Employee Concerns: IN 85 707-002, IN BS-740 002, IN 85 740 003, t l IN 85 773-0C2, and IN 85-831-001 1

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r j Elevent Report CO 10703 SQN, Rev. 4 dated December 19, 1986 is based on the following Employee Concerns: [

t IN 85 707-002 which states: "Tubing cracked when bent with hand i tender. Was located in Reactor Building 2, through hatch, up spiral  !

staircast, on 1st landing-3/8" copper tubing. Has been replaced  !

, with acceptable tubing. Cracked tubing hadn't been inspected at i

time that it was discovered and fixed. C/1 has no more detail. L Note
C/I has no more information. He raplaced cracked tubing f whenever he found it- knows of no more." [

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IN-85 740 002, which states
"All hand benders ar* the "Imperial" i

brand, and all bend the same. The benders work OK for stainless  !

j steel but they crack and "egg shape" copper tubing. CI declined i I to provide fertner inforeation. Construction Cept. Concern."

j IN-85 740-003 which states: "Hand made tubing benders used to bend ,

j radiation monitoring tubing (1" and 1 1/2") camage tubing. Senders l j

located 729' of turbine building (14" and 20" radius). Tubing  !

10:ste: in 30:itional equipment building, Go in crane bay c0er  !

0' . t tait e';*t nan: 00ce. 1 := te iad ieg -all ePr :" I j lA ~ i *. sC*t 5'as. C0~lstructi;"i Cept, C *i: e r 'i . ll Ot*liae to O'Cvice fWrt*er information,"

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SG1122O276 SS1104 5

POR ADOCK 05000327  !

j P PDC  !

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IN-85 773-002 which states: "Cepper tubtig creaks or squeezes Material or bencer is defectiv,,

together . hen tending 90 tegrees.

N: . mere informati:n availaple."

IN 25-831-001 which states: Copper instrumertation tubing is con-1' sistently "creakieg" when bsnt using the necranical (hand ocerstec) '

teactrg tools. Because of tt,t consistency St which the "breakage" cccurs, there is a concern that +he "good" tends may violate minimum

.all oc otherwise weaken the copper tuting. Problem may te tre c:rdition cf the tencing tools. (No specifics given)."

Inese Watts Bar concerns were evaluated by TVA to be potentially nuclear safety-related and c tentially applicable to Sequoyah (generic).

II. S.--ary of Issue The pecblem, as defined ty TVA, is that programmatic deficiencies resulting frem inadequate implementation of Division of Nuclear E gineering (CNE) recuire.ents concerning the qualification and centrol o' teaciag equipment may allcw cuestionable cuality tends to be prc:wcec, are on-aged or 9efective tending equipment may remain undetected. In acciticn, ;roci,re ent scecifications may have been inadequate by not clearly s:ecifying "Bending Quality" tuDing in the cepper tucirg description.

.i III. Evaluatio9 The NRC inspectors revie.ed Element Reoort CO 10703 SQN, Rev. 4 and the related E*:loyee Concern Task Group (ECTG) file and discussed the Element Repcrt aitn tre ECTG evaluator and other TVA personnel, In aceition to reviewing tne relevant Watts Bar recorts, the ECTG f evaluator revie.ed Secuoyah procedures and specifications, interviewed i

responsible Secuoyah QA, Medificatic'.is and Maintenance per onnel, TVA perso,1rel esamined bending tools, cualified tools, and byJrotested bend j >

samples at the Sequoyah Nuclear Plant.

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TVA determired that at Sequoyah bending tools had not been preserly segregated or Qualified, that bending tools were damaged, that qualifica-tion records .ere missing, and that site procedures did not adecuately address the pregram recuirements or specifications. Additionally, it .35 1 determined that non bendable Quality c0pper tuti*g had been procured'and issued for bending situatlons.

IkA had ;erfor-ed an extensive field inspection and engiretring evaluation i of i95talles pipe tercs at the hatts Bar site (sa ple inspection program). [

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Because tre tenders, procedures and personnel were often identical to l i

those used at SCN, TVA c:ncluded that the kBN stu:y results were relevant to SON.  ;

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t I ',' . Conclusien t TVA concluded that site procedures did not adequately control the pipe and tubing bending crocess at Sequoyah. In addition, TVA concluded that i hard dra.n copv," tuting had been improperly procured and issued for l An 69gineering installations awe d "bending quality" tubing was required.

r evaluation of inspection and test results and operating history determired l that instalite bends were acceptable as is. It was also catcemined that t

the hard dra.n copper tubing always failed during attempted tending such [

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that none would have been installed in the plant. .

Corrective actions initiated by TVA include segregation and qualification {

l of tencers and revisions to procedures and specifications to better control bending tool segregation, qualification and inspection, and tubing l procurement. Although a separate sample inspection program of installed {

f tends was not conducted at SeQuoyah the present corrective actions request TVA's Division of Nuclear Engineering (ONE) to evaluate wretter additional corrective actions are required to verify the quality of existing Secuoyan installations, hone of these corrective actions were i j

evaluated by TVA as restart items, ,

The NRC staf f concludes that TVA's investigation and resolution of thege concerns as descrited in Element Report CO 10703-SQN, 'ev. 4, is adequate. l

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No further NRC action is recuired.  ;

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