ML20136G494

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Part 21 Rept Re Cracked Nuts Showing Stress Corrosion Cracking.Caused by Matl & Mfg Problems.Valves Placed in Storage & Not Exposed to Plant Process Chemicals
ML20136G494
Person / Time
Site: Paducah Gaseous Diffusion Plant
Issue date: 03/14/1997
From: John Miller
UNITED STATES ENRICHMENT CORP. (USEC)
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
REF-PT21-97 GDP-97-0036, GDP-97-36, NUDOCS 9703180058
Download: ML20136G494 (7)


Text

United States Enrichment Corporation 9

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2 Democracy Center 6903 Rockledge Drive Bethesda, MD 20817 Tel. (301) S64-3200 Fax: (301) 564-3201 flitted Nates E irieliriierit Corporatiori JAMES H. Miu.ER Dir: (301) 564-3309 VicE PRESIDENT, PRODUCTION Fax: (301) 571-8279 March 14,1997 SERIAL: GDP 97-0036 U.S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, D.C. 20555-0001 Paducah Gaseous DitTusion Plant (PGDP)

Docket No. 70-7001 Initial Notification of 10 CFR 21 Report The purpose of this letter is to provide Initial Notification to satisfy the requirements of 10 CFR 21.21(d)(3)(i) of a reportable defect that has been discovered at the Paducah Gaseous Diffusion Plant (PGDP).

The defect is associated with I inch product cylinder valve packing nuts. The valves are manufactured by Hunt Valve Company, Inc.,1913 State Street, Salem, Ohio,44460.

Attached is the associated 10 CFR 21 evaluation checklist and a copy of pertinent problem reports.

The Portsmouth Gaseous Diffusion Plant has also been apprised of this situation.

Any questions related to this subject should be directed to Mark Lombard at (301) 564-3248.

Sincerely, Mames H. Miller Vice President, Production h

Attachments

-(E2Dp 9703180058 970314

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IgippMMEJIEJI!l5 Ott ces in Paducah, Kentucky Portsmouth, Ohio Washington, DC

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UE2 EG-GE1039, Rev.1 Page 17 of 18 veim on.aq

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10 CPR PART 21 EVAftfATION CHECKLIST Page 1 ofFJ

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iollowing questions provide b criieria' forsvaluation of to CFR Part 21 reportability:

r A.1 NoZ Yu _

Has the NRC alrudy been informed of this condition pursuant to 10 CFR 21 (for example, by a supplier)7 A.2 No__ Yes If yes, has USEC or LMUS been named as a recipien't of the defective item?

A..

Nox Yes _._

Has this condit:on already been reported to NRC in accordance with procedure UE2-MC.RE1C30?

If the wwet to Ques'. ions A.! and A.2 are "Yes', or the answer to Question A.3 is "Yes', the condition need not be reported under 10 CPR 21. Attach objective evidence of notification of the NRC and complete Part F.

If the answers to Questions A.1, A.2, and A.3 are 'No', continue with the evaluation.

B.1 No_

Yes.c Is the identified condition a deviation or failure to comply associated with a basie +%-"t (including design, analysis, inspection, testing, fabrication replacement parts, or consahing

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setvices)?

If the answer to Question B.1 is "No', the conditionis not reportable under 10 CFR 21; attack basis for conclusions and proceed to Secaon E. If b enswer to Question B.1 is "Yes", continue the evaluation.

No._. Yes g If the answer to Question B.1 is 'Yes', has the basic component been delivered to USEC/LMUS i

and accepted for une in the plant or an activity (includes USEC. dedicated commercial gsmie leems)?

If the answer to Question B.2 is 'No', the condition is not reportable under 10 CFR 21; attach basis for conclusions sod proceed toSecoco E.

If the answer to Question B.2 is 'Yes", condition is potentially reportabic. Continue with the evaluation.

i C.

Further, does the activity or basic component contain any of the following types of conditions? (Deviation means a departure from b technical requirenants included in a procurement document.)

- No._

Yes_ g 1)

The installation, use, or operation of a basic composint containing a deviation?

Nog Yu __

2)

A condition or circumstance involving a baric component that could contribute to exceeding a safety limit as defined in the GDPs Technical Safety Requirements (TSRs)?

Nog Yes _

3)

A failun to comply with any applicabic regulation, order, or certificate issued by the NRC?

If all of the answers in this section are "No', the condition is not reportable; sitsch buis for conclusion and proceed to Se-tion E. If any answers are 'Yes", continue with the evaluation.

,i ii seawevventsseener I

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03/12 '97 15:59 ID:tRA FAX:5024d16798 PAGE

- 4 kJE5Eb GE1039, Rev.1 Page 18 N is 11 3 :41 (t122 94)

Paget of,7 3 Vs/npr Could abo deviation or failure to comply create a substantial afety hazard resulting in any of the following (assues das, no redundant or back up systocas):

No_/ Yes 1)

Exposure in excus of 10 CFR 20.1201 timits No_/ Yes _,,,,

2)

Exposure of an individualin an untutricted area to more than 0.5 rum in one calendar year (10 CFR 20.1301(c))

Nog Yes,,,,,,,,

3)

Release of radioactive material to an unrestricted ans in excess of the limits in 10 CFR 20, Appendix B, Table 2 i

No_ Yes x 4)

A deficiency which seriously compromised the ability of a UF, confinessent system to perform its dwign' ted function a

Noz Yas _

5)

Other (explain) _

If all answers in this mi: tion are 'No*, the condition is not reportable:,coauplete Part E.' If any answer is "Yes", condition u nportable.'

4 Continue with evaluation.

E.

Evaluation nsults and recommendation. Reconuneed condition be reported?

3 No.,

'Yes 2

.If answer is "Yes*, sign this part and continue to follow procedure UE2.RWC1039. Sign the evaluation checklist and forward to the Manager. NRA. If answer is 'No", evaluation is complete. Sign the evaluation checklist and forward to Commitment Management for doeurs of Problem Report.

Attach written summary of evaluation and basis for conclusions.

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03/12 '97 16:00 ID:tRA FAX:5024416798 pAGE 5

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l 10 CFR PART 21 EVALUATION CHECKLIST res,3 ers i

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SUMMARY

OF EVALUATION AND BASIS FOR CONCLUSIONS Crr eking of the nuts has been observed and, in one case, resulted in a reportable release of UF.,

Metallurgical. Analysis of the cracked nuts has shown stress corrosion cracking to be the degradstion mechanism 7 Intergrannular esacking has been detected in cylinder valvo packing nuts which have been used in various stages of the enrichment process, in addition, j

intergrannular cracking of packing nuts has been detected in "new" cylinder valves removed i

from new cylinders to allow receipt inspections. The removed valves were placed in storage and were not exposed to plant process chemicals or handling practiccs affecting the packing nut This indicates that the problem is a material or manufacturing problem with the nuts. Three valve packing nut materials ac: currently used; monel, ASTM B150 613 alloy, and CDA 636 alloy. The cracking problem has been observed only in the 636 alloy nuts on valves supplied by Hunt Valve Co., Inc..

USEC-651. Rev 7, Uranium Hexafloride, A Manual of Good llandling Practices, section 5.4.6, discusses past defects in one inch cylinder valves and the potential adverse effects. One past defect was packing nuts which have split during service. It is identified that this condition could allow the stem packing rings to be forcefully ejected from the valve, resulting in a UF, release.

i Failure of a cylinder valve packing nut and ejection of the valve packing with an open valve on a j

full cylinder would constitute a failure of a UF. confinement system.

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03,12 '97 16:00 ID:WA FAX:5024416798

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118 Buf fness PP;0Pltiretfon Systeet 1

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A51EllMfRf...: PROSLEM R(PORTS JANUARY DECEMSER 199P (UC97A0001) n ISSUE 19....., UC9780318

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TYPt.........: PR Problem Report 108.fYPt.... MW

  • Notificat f ort ORICINAflNG FUNC. ORG.s 12
  • Operations ORICINAflNG CROUP.....: 793
  • UF6 Mandling Shifts PRIORl17.....

0 IN111AffD B7..........: 24539 40 CAT 100....t 015COVCRT DATE....... 1 01/19/1997 2200 SUILDING.....: C 310,

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UPQRA0f 0 70 (VENT REPORT PAO ER 199Te001 A smelt wisp of smoke was released from the cylinder vetve on eylinder PP.2549 PGLD TE.75 over the er, withdre et positten pletb L was actweted.

The operators were in the process of evacuating /purgirHI the pistelt on a futt prmoet cylinder.

The wisp was observed after the pigtelt was pressured above atmosphere. A noticeable crack circuwwe-ts the packing twt.

The operators exited the area and donned additionet PPI. The pistett was purged using s;betmosphe it doubting purges and the cylinder volve cenfirmed s bsed.

defective vatwo tog and caut{on tog was ptoced e the cylinder.Cy4 tnder was disconnected with no further incident ord results. The ARP was followed end the Pss notified MF and urenjun senples were pulled with nesetive

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eittsitJius H@,E B.{,COMM(40tQ ACT t0N_S

~' Replace cylinder valve on PP4549. Anatyre failure of vetve cap.

P35 JU$ffFICAft0N/COMMEN11 Urine samples were obtelned. UT6 detection safety system was actuated and opereted as designed. 24 howr event rescrt PA01997 002 issued. Criteria met Appendix ( l(e) unuquel and Apperdix F. J (2) 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. SheL L wisp released from cracked pecking nyt when pigtall pressured up. MP smeers were negative. Thle PR should be eyetveted for 10CFR2' a

reportebility.

MMARKS t181A, ELD.f)($PQNt(

4 Is:ve Reyfeed 02/05/1997 et 13:12:29 Printed 02/19/1 p r at 11:41:31 i

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03/13 '97 10:55 ID:fRA FAX 5024416798 PAGE 2

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Premien iiepers ne.po e sh.es 133Vs TITI.E., e C.340 stL3 Asp reon CYLINDBR VALV8 PE.598 l 8 W peepense puet 04/04/1997 W j ASSESSM Nf...: Peost,gM R3POR73 JANUAR7

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LOCATION.,...e Disc 0V3RY Daft......: 02/07/1997 0931 su!LDING...

-t C.sie MAIL ST3p...i C 331 PROC 5DUR5/5FEC./peAM.. CP4-CO creene Rey, o RQM' QWRp)TERMllsATlQN fopeoot Codatelt l

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mau-A emell whop of emoke wee roleseed f rom the eyllader valve en eyttnder PK.191 during purging operations. 7hte setivoted POLD TB 78 in the R $ withdrawen posit ten vent A3etion duct. The wasp wee observed after the pigtett was pressured above atmosphere. A not teeable creek ca rgumvents the packseg nut.

ACTI0na _TAKE.N 1

Operations imediately volted the area. Alarm wee roepended to per procedure, ur semples and wipes were noget1*e.

The pigtett was purged using subetmospherie doubling puryee. Cyltador wee disconnected with no further incident.

RBCQ9RisDED ACTIONS Repleve tylinder velve packteg nut on PR.591.

Investigate failure of packtrig nut.

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- PSS JUaTIFICATION/CeegettfrS 24 Nour Event poport por UE3 masto 30. Appredia 5 ortterae 1. J. unvevel (e), and Appendts F oratoria J.S.

Appet,priate roeponse wee nede. MP and HP evrveys were nogetive, Precautionary urine semples wege obtained from the two workers who pero present, hESBEE 03/06/97: Per PREC, sosign to Operet. tone for dieposition. This PR w!!! be closed to PR CO 97 0640 whteh to a DCpg.

03/05/97: por reportable events doe to DCS on/ef ter 03/03/91 (date NRC assumed regulatory oversight) have been downgreded to problem reporte. PR CO.91 fr640 has been placed back in PART etetus and till be taken back to the Screening Committee for SCAQ determination, action plan doe date, etc. Svent Report PAD BR.1997 004D (UCT78081tt nues been concelled.

MhtiMRfifMT pggpgggg soeve Revised 03/o4/t,,, at 25,4p:37 Printed 03/12/1997 at teiee.f1 i

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03<12 '97 16:01 ID:tRA FAX:5024416798 PAGE UC9711002 Susiness Pritritiretion system

    • 9e 1 Prot)Lem Report Rispense SheJt a))u PRosttM RCPotts

'll1Ut TITLE..: PACE!NG Nui C4 CYt.lNQtR PP 2520 tW t VARO CRACrt0 fMResponSoue-33/20/199' [

ASSESTMf.NT...t PRoeLEM REPORTS JANUART OECEM0fR 1997 (VC97A0001]

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l 9,(SCRfPt_th the packing nut on cylinder PP 2520 in the t yard was found cracked around the circumference (at approalmetely tre top threod) through approximately 807,of the section, ihls is a "Nunt" valve elloy "6 36" nut.

(Let #190795 6).

This pecu ng nyt f at ture was f ound white inspecting Paducah Plant cylinders with an eddy current probe f or indications of cracked nuts, but was ctently visible with erack opening of epprosimately 1/89 The cylinder appeered to ce ervtr.

actIONt tartN 40Ntr

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REQUED Acil0Nt N0ht E} M fy fjrAt(CN/ COMMENT,}

found during a random sampling of Munt valves with the a6 36" pecking nut. No sign of any leakage. 10 ton cyLfreer.

Per NMCSA records, is an enpty cylinder with notetlen requiring a vatve change. This should be evatuoted for 10 'E 21 and 71.93 opplienettity.

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02/20/m Part A is auf gned to Operations and Management response provided at PRsc. No further action resaired.

Part 8 is assigned to Engineering to evetuate for 10 CFR opplicabl(Ity,

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~ n Name of person providing response: Issue Revtsed 02/20/1997 et 09:59:34 rrInted 02/20/1997 at 13:23:43}}