GO2-79-111, Forwards Deficiency Rept Re Possible Failure of Portion of Pipe Whip Restraint Structure in Main Steam Tunnel
| ML17272A455 | |
| Person / Time | |
|---|---|
| Site: | Columbia  |
| Issue date: | 05/31/1979 |
| From: | Renberger D WASHINGTON PUBLIC POWER SUPPLY SYSTEM |
| To: | Engelken R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V) |
| Shared Package | |
| ML17272A456 | List: |
| References | |
| GO2-79-111, NUDOCS 7906080301 | |
| Download: ML17272A455 (4) | |
Text
REGULATORY IOORNATION DISTRIBUTION: SYS'I (RIBS)
ACCESSION NBRi7906080301>>
DOC",DATE'g 79/05/31 NOTARIZED; NO DOCKET' FACIL'!50 397 WPPSS Nuclear ProJect-i Unit 2i Washington-Public Powe-05000397 AUTH' NAME>>
AUTHOR'AFFILIATION RENBERGER,D',L,<
Washington Publ,ic Power. Supply System RECIP ~ NAMEl RECIPIENT AFFIL'IATION ENGELKENaR ~ HE Reg)on<< 5g san Francisco'ffice, of the'irecto I
SUBJECT:
For wards>> deficiency rept>> re possible failure of,portion of pipe whip restraint structure in>> main -steam tunnelB.
DISTRIBUTION CODE:
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CONSTRUCTXON DEFICIENCY REPORT
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g Washington Public Power Supply System A JOINT OPERATING AGENCY
- p. o. 8ox 968 3000 Gxo. w*s~iectoN war R<cv<Aeo, wAseivcro~ 99352 PHoNx (5095375 5000 May 31, 1979 G02-79-111 Nuclear Regulatory Commission Region V
Office of Inspection and Enforcement Suite 202, walnut Creek Plaza 1900 N. California Boulevard Walnut Creek, California 94596 Attention:
Subject:
I>>
Mr.
R.
H. Engelken, Director WPPSS NUCLEAR PROJECT NO, 2
DOCKET NUMBER 50-.397, CPPR-93 REPORTABLE DEFICIENCY - 10CFR50.55 e)
Dear Mr. Engelken:
In accordance with the provisions of. 10CFR50.55(e),
your staff was informed by telephone on April 27, 1979, of a reportable condition involving a possible failure of a portion of the Pipe Whip Restraint Structure in the Main Steam Tunnel.
Attached is our report of this deficiency.
Please contact us if you have additional questions.
Very truly yours, DLR/RPS/ln
Attachment:
As stated D. L.
RENBERGER Assistant Director Technology cc:
JJ Verderber - BSR, w/att JJ Byrnes - B8R, w/att C
Bryant - BPA, w/att JG Davis, Director, NRC, 'Washington, D.C., w/att MNP-2 Files, w/att
Washington Public Power Supply System A JOINT OPERATING AGENCY P. 0. ODX 966 3000 GED. WASHINGTON WAT AICHI.AND. WASHING'TDN 99352 PHONE (5091 375 5000 Hay 31, 1979 G02-79-111 Nuclear Regulatory Commission
'egion V
Office of Inspection and Enforcement Suite 202, Walnut Creek Plaza 1900 N. California Boulevard Malnut Creek, California 94596 Attention:
Hr.
R.
H. Engelken, Director 6
I. I: ; I'I TL JUN 8 1979 I
REGIOiV V
'Q IWEQION 8 PRMci7489'ubject:
MPPSS NUCLEAR PROJECT NO.
2 DOCKET NUHBER 50-397, CPPR-93 REPORTABLE DEFICIENCY -'10CFR50.55 e)
Dear Hr. Engelken:
In accordance with the provisions of 10CFR50.55(e), your staff was informed by telephone on April 27, 1979, of a reportable condition involving a possible failure of a portion of the Pipe tlhip Restraint Structure in the Hain Steam Tunnel.
Attached is our report of this deficiency.
Please contact us if you have additional questions.
Very truly yours, D. L.
RENBERGER Assistant Director Technology DLR/RPS/ln
Attachment:
As stated cc:
JJ Verderber - B8R, 'w/att JJ Byrnes - B8R, w/att C
Bryant - BPA, w/att JG Davis, Director, NRC, Washington, D.C., w/att LlNP-2 Files, w/att
~
pdPC g Gt P 6ET5 ++ O I
1'S NUCLEAR PROJECT NO.
2 REPORTABLE DEFICIENCY AND CORRECTIVE ACTION FOR DEFECTIVE STEEL PLATE USED IN SUPPORTING STRUCTURE FOR PIPE WHIP RESTRAINTS IN thAIN STEAN TUNNEL Attachment G02-79-111 WASHINGTON PUBLIC POl~ER SUPPLY SYSTEH DOCKET NO. 50-397 LICENSE NO.
CPPR-93 Nature of Deficienc AStlE SA-537 Class II steel from U, S. Steel Co. heat
!f74206 used in the main steam tunnel pipe whip restraint support structure was found to have extensive internal cracking as revealed by ultrasonic examination of
'n installed component.
Examination of the SA-537 Class II steel in the installed component was undertaken after cracking of material from the same heat w'as observed during fabrication, and subsequent examination of samples from material still in the fabrication shop indicated exten-sive cracking was present.
The cracking was attributed to overheating during the rolling or heat treatment
- process, and was concluded not to be laminations or lamellar. tearing.
The cracking is considered to be an injurious defect, and as such this deficiency was concluded to con-stitute a failure to meet ASt1E SA-20 performance specifications.
In addition, extensive cracking was observed on the edges of a second heat (T68042) of SA-537 Class II steel plate manufactured by U.
S. Steel Co,,
upon receipt at the fabricator's shop.
This material was rejected and was not used in fabrication.
Safet Im lications If the SA-537 material remained as installed in the main steam tunnel p'ipe whip restraint supporting structure, and was subjected to pipe whip impact loads, resulting from a pipe break in a reactor feedwater line, the com-ponent could fail and prevent the pipe whip restraint structure from re-straining the motion of the. ruptured pipe.
This could result in loss of containment integrity through damage to the reactor feedwater isolation valve or feedwater piping upstream of'he isolation. valve.
Corrective Action Taken All SA-537 material from the heat found to have internal cracking was rejected.
This includes the single component installed in the main steam tunnel, other components shipped to the site but not installed, components in fabrication, and raw material in the fabricator's shop.
Replacement SA-537 Class II steel plate has been ordered.