TXX-5014, Interim Deficiency Rept CP-86-16 Re Adverse Fire Effects on Instrument Tubing.Initially Reported on 860321.Evaluation Should Be Completed by 860930.Next Rept Will Be Submitted by 861022: Difference between revisions
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{{#Wiki_filter:m | {{#Wiki_filter:m Log # TXX-5014 | ||
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Filo # 10110 909.5 TEXAS UTILITIES GENERATING COMPANY NKYWAY TOWER. 400 NORTH OLIVE NTREET. L.B. at. DALLAS. TEKAs 7830$ | |||
September 17, 1986 3g@gggh wiw w.cou m Mr. Eric H. Johnson, Director SEP l 9i986 Division of Reactor Safety and Projects y | |||
September 17, 1986 wiw w .cou m | U.S. Nuclear Regulatory Commission 611 Ryan Plaza Drive, Suite 1000 Arlington, TX 76012 | ||
611 Ryan Plaza Drive, Suite 1000 Arlington, TX 76012 | |||
==SUBJECT:== | ==SUBJECT:== | ||
| Line 28: | Line 27: | ||
==Dear Mr. Johnson:== | ==Dear Mr. Johnson:== | ||
On March 21, 1986, we verbally notified your Mr. R. Hall of a deficiency involving the detrimental effects of low melting point metals on stainless steel instrument tubing during a fire. This is an interim report of a potentially reportable item under the provisions of 10CFR50.55(e). On September 5,1986, we verbally requested and received an extension for submitting this report from your Mr. I. Barnes until September 17, 1986. We have submitted interim reports logged TXX-4767 and TXX-4842, dated April 21, 1986, and June 6, 1986 respectively. | On March 21, 1986, we verbally notified your Mr. R. Hall of a deficiency involving the detrimental effects of low melting point metals on stainless steel instrument tubing during a fire. This is an interim report of a potentially reportable item under the provisions of 10CFR50.55(e). On September 5,1986, we verbally requested and received an extension for submitting this report from your Mr. I. Barnes until September 17, 1986. We have submitted interim reports logged TXX-4767 and TXX-4842, dated April 21, 1986, and June 6, 1986 respectively. | ||
The significance of stainless tubing in direct contact with galvanized material (zine) such as Unistrut supports and clamps during a fire is being evaluated by Engineering. The complexity of the interaction and the probability and duration of a simultaneous occurrence of high tensile forces in the presence of molten zinc at temperatures above 7500C are being considered. | The significance of stainless tubing in direct contact with galvanized material (zine) such as Unistrut supports and clamps during a fire is being evaluated by Engineering. The complexity of the interaction and the probability and duration of a simultaneous occurrence of high tensile forces in the presence of molten zinc at temperatures above 7500C are being considered. | ||
A field verification has been completed to identify all galvanized hardware utilized for supporting instruments required for fire safe shutdown. It is anticipated that the evaluation will be completed by September 30, 1986. The schedule for any resulting corrective measures and the reportability of that item will be established at that time. | A field verification has been completed to identify all galvanized hardware utilized for supporting instruments required for fire safe shutdown. | ||
It is anticipated that the evaluation will be completed by September 30, 1986. The schedule for any resulting corrective measures and the reportability of that item will be established at that time. | |||
We are continuing our evaluation of this issue and anticipate submitting our next report by October 22, 1986. | We are continuing our evaluation of this issue and anticipate submitting our next report by October 22, 1986. | ||
l | l Very truly yours, b | ||
8609230325 860917 | n 8609230325 860917 W G Co s1 DR ADOCK 0500 5 | ||
Manager,Licensingf JCH/amb | G. S. Keeley w | ||
/ | |||
Manager,Licensingf JCH/amb a 1>urssuou or rexas vrzurses esecruzc couraur ithi075 | |||
1 | 1 | ||
.1 c - NRC Region IV (0 + 1 copy) | |||
Director, Inspection & Enforcements (15 copies) | Director, Inspection & Enforcements (15 copies) | ||
U. S. Nuclear Regulatory Commission Washington, D.C. 20555 t | U. S. Nuclear Regulatory Commission Washington, D.C. | ||
20555 t | |||
1. | 1. | ||
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Latest revision as of 21:05, 7 December 2024
| ML20203N338 | |
| Person / Time | |
|---|---|
| Site: | Comanche Peak  |
| Issue date: | 09/17/1986 |
| From: | Counsil W, Keeley G TEXAS UTILITIES ELECTRIC CO. (TU ELECTRIC) |
| To: | Johnson E NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| References | |
| CP-86-16, TXX-5014, NUDOCS 8609230325 | |
| Download: ML20203N338 (2) | |
Text
m Log # TXX-5014
~
Filo # 10110 909.5 TEXAS UTILITIES GENERATING COMPANY NKYWAY TOWER. 400 NORTH OLIVE NTREET. L.B. at. DALLAS. TEKAs 7830$
September 17, 1986 3g@gggh wiw w.cou m Mr. Eric H. Johnson, Director SEP l 9i986 Division of Reactor Safety and Projects y
U.S. Nuclear Regulatory Commission 611 Ryan Plaza Drive, Suite 1000 Arlington, TX 76012
SUBJECT:
COMANCHE PEAK STEAM ELECTRIC STATION (CPSES)
DOCKET NOS. 50-445 AND 50-446 FIRE EFFECTS ON INSTRUMENT TUBING SDAR: CP-86-16 (INTERIM REPORT)
Dear Mr. Johnson:
On March 21, 1986, we verbally notified your Mr. R. Hall of a deficiency involving the detrimental effects of low melting point metals on stainless steel instrument tubing during a fire. This is an interim report of a potentially reportable item under the provisions of 10CFR50.55(e). On September 5,1986, we verbally requested and received an extension for submitting this report from your Mr. I. Barnes until September 17, 1986. We have submitted interim reports logged TXX-4767 and TXX-4842, dated April 21, 1986, and June 6, 1986 respectively.
The significance of stainless tubing in direct contact with galvanized material (zine) such as Unistrut supports and clamps during a fire is being evaluated by Engineering. The complexity of the interaction and the probability and duration of a simultaneous occurrence of high tensile forces in the presence of molten zinc at temperatures above 7500C are being considered.
A field verification has been completed to identify all galvanized hardware utilized for supporting instruments required for fire safe shutdown.
It is anticipated that the evaluation will be completed by September 30, 1986. The schedule for any resulting corrective measures and the reportability of that item will be established at that time.
We are continuing our evaluation of this issue and anticipate submitting our next report by October 22, 1986.
l Very truly yours, b
n 8609230325 860917 W G Co s1 DR ADOCK 0500 5
G. S. Keeley w
/
Manager,Licensingf JCH/amb a 1>urssuou or rexas vrzurses esecruzc couraur ithi075
1
.1 c - NRC Region IV (0 + 1 copy)
Director, Inspection & Enforcements (15 copies)
U. S. Nuclear Regulatory Commission Washington, D.C.
20555 t
1.
i
,e-
,y-.,.,..
...y,3r 3
3 m.,,
m
. -