ML20204K041
| ML20204K041 | |
| Person / Time | |
|---|---|
| Site: | Comanche Peak  |
| Issue date: | 08/01/1986 |
| From: | Gad R ROPES & GRAY |
| To: | Bloch P, Jordan W, Mccollom K Atomic Safety and Licensing Board Panel |
| References | |
| CON-#386-247 OL, NUDOCS 8608110267 | |
| Download: ML20204K041 (5) | |
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h yi ROPES & GRAY 00CKETED 225 FRANKLIN STREET BOSTON, MASSACHUSETTS O2110 sttsa muusta s.osis noponaton esN (687) 423-610 0 f ttex nuusta ssiera norts onav esa 86 ALE -7 P,2.Js2, oro,
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s=rtenanomatisar) 4:3-seos MWir e:(202i *re-seas August 1, 1986 Peter B. Bloch, Chairman Atomic Safety and Licensing Board U.S. Nuclear Regulatory Commission Washington, D.C.
20555 Dr. Kenneth A. McCollom Administrative Judge Dean, Division of Engineering Architecture and Technology Oklahoma State University Stillwater, Oklahoma 74078 Mr. Walter H. Jordan Administrative Judge Atomic Safety and Licensing Board U.S. Nuclear Regulatory Commission Washington, D.C.
20555 Re:
Texas Utilities Generating Company et al.
Comanche Peak Steam Electric Station Docket Nos. 50-445 & 50-446 O L-
Dear Administrative Judges:
The " Applicants' a letter identified as TXX-4844 as " attached. "First Progress Report" r when the pleading was filed. attachment of the letter in question was In fact i
the pleading _had previously received lai copy of theIn p letter, with.the exception of the Board.
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Ropts & GRAY
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Peter B. Bloch, Chairman Dr. Kenneth A. McCollom Mr. Walter H. Jordan August 1, 1986 enclose a copy of the letter. and ask that the Board attach it to its copies of the " Progress Report."
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R. K. Gad III RKG/ajp Enclosure cc:
Mrs. Juanita Ellis 1
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TEXAS UTILITIES GENERATING COMPANY
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.....uiu June 9, 1986 E%". A.*M Mr. Eric H. Johnson, Director Division of Reactor Safety and Projects U. S. Nuclear Regulatory Commission 611 Ryan Plaza Drive, Suite 1000 Arlington, TX 76012
SUBJECT:
Co h HE PEAK STEAM ELECTRIC STATION (CPSES)
DOCKET N05. 50-445 AND 50-446 PIPE SUPPORTS SDAR: CP-86-36 (INTERIM REPORT)
Dear Mr. Johnson:
On May 9,1986, we verbally notified your Mr. I. Barnes that the scope of plant modifications resulting from the project's pipe support reverification program could be considered potentially reportable under the provisions of 10CFR50.55(e). The engineering evaluation to date has identified one instance which is reportable under the provisions of 10CFR50.55(e). The evaluation of this issue is continuing and we anticipate submitting our next report by August 13, 1986.
Very truly yours, W. G. Co sil By:
G.
S'. K4el Manager, Nuc icensing JCH/arh Attachment c - NRC Region IV (0 + 1 Copy)
Director, Inspection & Enforcement (15 copies)
U. S. Nuclear Regulatory Commission Washington, D.C.
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JUL 31 '86 13:39 LICENSING-TUGCO PAGE.83 i
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ATTACMENT PIPE SUPPORTS DESCRIPTION The issue involves the project's pipe support reverification program being conducted by stone and Webster Engineering Corporation (SWEC). This program employs an expanded set of design and installation criteria for the evaluation of the structural adequacy of existing installations.
While the primary scope of SWEC's work is to provide technical verifications, modification of certain pipe supports will provide expedient acceptance for the expanded requirements.
Initial results indicate support modifications are categorized'as follows:
1.
Prudent. Acceptance by physical modification versus analysis. Supports in this category may be technically acceptable; however, more time and expense would be involved than that required to physically modify the support and qualify the modification.
2.
Recent NRC and Industry recommended practice. Modifications implemented to eliminate snubbers to enhance plant maintainability, reduce in-service inspection, and minimize worker exposure (operating plant conditions).
3.
Adjustment. Minor modifications (such as re-torquing or shimming) implemented to meet more rigorous installation criteria contained in the resolution of the external source technical issues.
4.
Cumulative effects. Modifications that may be required due to the combined effect of multiple issues.
The scope of plant modifications resulting from this reverification program is of a magnitude such that it was considered potentially reportable under the provisions of 10CFR50.55(e).
The issue is applicable to Units 1 and 2 and involves all safety class piping systems.
The engineering evaluation to date has identified one instance which is reportable. On the seismic evaluation of stress problem 1-045T, for the chemical volume and control system (CVCS), the SWEC requalification has indicated an overstress condition. The cause for the condition was the use of inappropriate response spectra in the previous Gibbs and Hill piping analysis.
SUMARY OF EVENTS Date NRC Notified as Potentially Reportable: May 9, 1986.
June 9, 1986.
l Date Determined Reportable:
SAFETY IMPLICATION The overstress condition in the CVCS, stress problem 1045T, were it to have remained uncorrected, could have adversely affected the safety of operation l'
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'of the ' plant in the event of an earthquake.
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JUL 31 '86.13:40
' L I CE NS I N' -TUGCO PAGE.04 i
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ATTACitlENT
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PIPE SUPPORTS continued CORRECTIVE ACTION Corrective action is to add sufficient additional supports to relieve the overstress problem. Appropriate spectra will continue to be used for all stress problems in the requalification program, as was being used when the condition was identified.
In addition to the abovo, the support modifications initiated to date, by category as listed in the description section of this report, are as follows.
Uni 18 Catecorv NWr of Modifications I
Prudent 992 Recent Industry Practice 177 Adjustment 0
Cumulative Effects 15 II Prudent 699 Recent Industry Practice 35 Adjustment 11 Cumulative Effects 0
Subsequent status reports will continue to update the above list, and add i
additional support modifications which may be identified and initiated.
We anticipate submitting our next report no late than August 13, 1986.
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