05000289/LER-1981-007-99, /99X-0:on 810702,pipe Supports Found Located or Oriented Improperly When Installed Per IE Bulletin 79-02 & 79-14 Insp Results.Caused by Inadequate Insp Prior to Operation.Supports Are Being Modified

/99X-0:on 810702,pipe Supports Found Located or Oriented Improperly When Installed Per IE Bulletin 79-02 & 79-14 Insp Results.Caused by Inadequate Insp Prior to Operation.Supports Are Being Modified

ML20009E677
Person / Time
Site:	Crane
Issue date:	07/08/1981
From:	Stephenson C METROPOLITAN EDISON CO.
To:	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
Shared Package
ML20009E666	List: 05000289/LER-1981-007, Forwards LER 81-007/99X-0 05000289/LER-1981-007-99, /99X-0:on 810702,pipe Supports Found Located or Oriented Improperly When Installed Per IE Bulletin 79-02 & 79-14 Insp Results.Caused by Inadequate Insp Prior to Operation.Supports Are Being Modified
References
IEB-79-02, IEB-79-14, IEB-79-2, LER-81-007-99X, LER-81-7-99X, NUDOCS 8107280354
Download: ML20009E677 (4)

LER-1981-007, /99X-0:on 810702,pipe Supports Found Located or Oriented Improperly When Installed Per IE Bulletin 79-02 & 79-14 Insp Results.Caused by Inadequate Insp Prior to Operation.Supports Are Being Modified

Event date:
Report date:
2891981007R99 - NRC Website

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U. S. NUCLEAR C EIULATIC.Y COMMIS$lON 8tRC FOAM JS4 E 77)

LICENSEE EVENT REPORT CONTROL BLOCK: I-l l

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7 8 9 LICENSEE CODE 14 15 uCENSE NUMSER JS 26 LICENSE TYPE JQ

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6 60 61 DOCKET NuMgER 68 69 EVENT DATE 74 75 REPORT DATE 80 EVENT DESCRIPTION AND PROBA8LE CONSEQUENCES h 10121 l nurine lone rorm shutdown. insnocrinn rnanlee from I.

E. En11orins 74-02 /14 I

m l indicated that numerous pipe supports had been located or oriented improperly I

l O 14 l lwhen installed. Mejority of nonconformances were minor "out of enlornnca" l

iOi3j gsupports. Reanalysis indicates that public health and safety Oere and are not

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CODE TYPE NO.

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IN l h W h l Gl1 IS l0 lh 34 JS 36 37 40 el 42 43 44 47 33 CAUSE DESCRIPTicN AND CORRECTIVE ACTIONS h I i i O I l Durinn construction nine sunnorts were 'insenlina out of tolerance in violation I

I g i of construction specification. Asa result, existing supports (i.e. hanners.

i gl springs, snubbers} are being modified to meet desi m criteria as established I

W l by recent reanalysis' of affected systems.

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'o 6s 6e mD m-we Carl Stephenson

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l LICENSEE EVENT REPORT

NARRATIVE

'.EPORT TMI-l LER 81-007 I.

CdRRENT ACTIVITIES AT THE TIME OF THE OCCURRENCE TMI-Unit 1 was in long term cold shutdown condition.

At the conclusion of the inspection stage of our efforts to comply with II.

4 the inspection, analysis and reporting requirements of I.E.Bulletin 79-92 i

and 79-14, a variety of nonconformances were discovered.

An e.xtremely j

conservative approach was enbarked upon (since the plant was shut down),

t vuercin the systems which had these nonconformances were completely r4 analyzed using the "as built" support location and piping routings just verified. When reanalyzca, some of the nonconformances precipitated a number of piping system support changes.

i It is our judgment from simplified calculations and by inspection that although there were nonconformances identified, the system would and will perform their intended furntions. However, we are continuing our efforts in modifying the systems' supports in accordance with the piping analysis and support calculations now in progress.

j This Licensee Event Report is generic in its applicability to the non-complying supports at TMI-1.

Attached is a list of these supports with i

safety factors less than two.

These supports are being modified to satisfy the design criteria as determined by the recent re-analyses.

i i

III. DESCRIPTION

After inspections and analyses of pipe supports were completed, the supports identified in the attachment were determined to have safety factors less than two (2)'and that thereby they could fail prior to the application of the full calculated design load. This is being reported as a special report.

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IV.

RESULTANT EVENTS i

Since there have been no safety related piping system failures due to inadequate or non-conforming pipe supports since TMI-l has been in operation, j

there are no significant resultant events to report.

l V.

PREVIOUS EVENTS OF A SIMILAR NATURE There have not been any events of a similar nature.

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VI.

ROOT CAUSE The supports listed in the attachmtat were determined to have safety factors less than two (2) due to the improper location of one or more of the supports in the system during the construction phase. The nonconforming supports identified in our various reports to the NRC on this subject were apparently not inspected adequately prior to operation.

VII.

DMEDIATE CORRECTIVE ACTION _

Upon discovery of the nonconformances a program to re-analyze the effected systems was started.

Since the plant was shut down there was no need for an expeditious justification of system operability to maintain continued operation.

VIII.

LONG TERM CORRECTIVE ACTION Approximately 40% of the supports with safety factors less than two (2) have been modified.

Prior to restart all the remaining pipe supports currently or subsequently identified with safety factors less than two (2) will be modified.

At the conclusion of these modifications the Commission will be notified.

Pipe support units (excluding structural members designed to AISC) with safety factors greater than two (2) and less than five (5) will be modified either during operation or during our next refueling outage, as determined by the supports' accessibility. A concluding statement of completion will be submitted when these modifications are finished.

Supporm with safety factors greater than five (5) will not te modified in compliance with the bulletin criteria.

Procedures are being Amplements which will preclude the improper installation for pipe supports in the future.

IX.

COMPOSENT FAILURE DATA Since no components failed, no data is incluc'ed.

ATTACHMENT SYSTEM SUPPORT NO.

Intermediate Cooling ICE-25 Condensate COE-12 Building Spray SPSH-24 Building Spray SPWH-32 Make-up Cooling Water MCH-32 MCH-63 Pressurizer Relief PR-9 Reactor Building Spray RBE-42 RBE-150 RBE-39 RBE-40 RBE-157 RBE-163 Feedwater FW-89 FW-74 Main Strea=

MS-201 MS-59 MS-60 MS-244 River Water RWE-10 RWH-55 RRH-2 Emergency Feedwater EF-3 EF-6 EF-8 EF-72 Decay Heat DHH-213 DHH-184 DH-23 DH-34 DCH-13 DHH-33 DHH-ll7 DCH-18 DCH-60/61 DH-30 DH-31 DHH-135 DHH-199 DHH-218 DHH-198 Emergency Feedwater EF-125 Reactor Bldg. Spray RBE-147 Reactor Coolant RC-32 Makeup & Purification MUH-184 MUH-185 MUH-191 MUH-317 MUH-320 MUH-65 MUH-66 MUE-2 MUE-4 MUH-237 MUH-245 MUH-251 MUH-254 MUH-258 MUE-10 MUE-ll

ATTACHMENT Pagi. 2 of 2 SYSTEM SUPPORT NO.

Makeup & Purification (cont.)

MUE-12 Mull-287 Mull-284 Mull-288 Mull-282 Mull-292 Mull-122 MUH-123 MUH-126 Mull-341 MUH-343 MUH-166 MUH-171 Mull-172 Mull-173 Mull-356 MUH-128 Mull-199 MUH-344 Mull-346 MUH-354 MUH-138 Mull-78 Mull-198 MUE-47 MUE-36 MUH-353 Spant Fuel SFE-30 SFil-123 SFil-362 SFil-130 SFil-132 SFE-ll SFE-2 SFil-13 SFil-19/12 SFH-64 SFE-13 SFE-15 SFE-16 SFH-45 SFil-15 SFE-1 SFE-3 S Fil-77 SFil-170 SFil-l:1 SFE-19 S Fil-86 SFE-17 SFE-37 SFE-38 SFE-39 SFE-40 SFil-51 SFH-52 SFH-157 SFE-24 SFE-23 SFE-7 SFH-104

!!uclear Services NS11-3 NSE-276 NSil-52 NSil-54A NSH-37 NSH-62 NSil-99 NSil-132 NSil-71 NSH-90 NSil-86 NSH-156 NSE-54 NSE-134 NSE-136 NSil-301 NSil-343 NSil-345 NSil-107 NSil-75 NSE-94 NSil-204 NSE-70 NSE-273 NSil-349 NSE-69 NSil-235 NSH-274 NSE-264 NSH-260 NSil-262 NSil-264 NSE-59 NSE-265 NSil-267 NSE-268 NSH-252 NSil-253 NSil-253A NSE-66 NSH-242 NSil-243 NSH-244 NSE-272 NSil-295 NSil-312 NSH-318 NSH-320 NSil-325 NSil-327 NSH-328/330 NSE-147 NSE-263 NSH-279 NSil-290 NSH-313 NSil-128 NSE-56 NSH-335 NSil-339 NSil-342 NSil-17 NSil-395 NSH-75 NSE-113 NSE-57 NSE-58 NSH-357 NSH-27