TXX-6850, Interim Deficiency Rept CP-87-100 Re Three Containment Isolation Penetrations That May Lack Relief Protection. Initially Reported on 870910.Evaluation Continuing.Next Rept Will Be Submitted by 871211: Difference between revisions

From kanterella
Jump to navigation Jump to search
StriderTol Bot insert
 
StriderTol Bot change
 
Line 17: Line 17:
=Text=
=Text=
{{#Wiki_filter:_ ___
{{#Wiki_filter:_ ___
                                                              ,    E.--                  Log # TXX-6850 Fi1e:# 10110
E Log # TXX-6850 Fi1e:# 10110
                                                              =       =                             906.2 7t/ ELECTRIC                   Ref # 10CFR50.55(e)
.=
=
906.2 7t/ ELECTRIC Ref # 10CFR50.55(e)
-October 8,1987.
[
[
                                                                                          -October 8,1987 .
William G. Counsil Esecutive Vice President U. S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, D. C.
William G. Counsil Esecutive Vice President U. S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, D. C. 20555
20555


==SUBJECT:==
==SUBJECT:==
- COMANCHE PEAK STEAM ELECTRIC STATION (CPSES)
- COMANCHE PEAK STEAM ELECTRIC STATION (CPSES)
DOCKET NOS. 50-445~AND 50-446                                                         .
DOCKET NOS. 50-445~AND 50-446 CONTAINMENT PENETRATION OVERPRESSURE j
CONTAINMENT PENETRATION OVERPRESSURE                                               j PROTECTION
PROTECTION
                              .SDAR: CP-87-100(INTERIMREPORT)
.SDAR: CP-87-100(INTERIMREPORT)
Gentlemen:
Gentlemen:
On September 10, 1987, we verbally notified yc ~ Mr. I. Barnes of a deficiency involving three containment isolation penetrations that may lack relief protectiori . Specifically, the design validation process has revealed that one Safety Injection System containment penetration and two Primary Sampling System containment penetrations, which are water solid and isolable, may lack overpressure protection. This is an interim report of a potentially reportable item under the provisions of 10CFR50.55(e).
On September 10, 1987, we verbally notified yc ~ Mr. I. Barnes of a deficiency involving three containment isolation penetrations that may lack relief protectiori. Specifically, the design validation process has revealed that one Safety Injection System containment penetration and two Primary Sampling System containment penetrations, which are water solid and isolable, may lack overpressure protection. This is an interim report of a potentially reportable item under the provisions of 10CFR50.55(e).
We are continuing our evaluation and anticipated submitting our next report by December 11, 1987.
We are continuing our evaluation and anticipated submitting our next report by December 11, 1987.
Very truly yours, (d C. Couns A W. G. Counsil By /                 4 4 (J. S. Marshall               j Supervisor,                 J Generic, Licensing         )
Very truly yours, (d C. Couns A W. G. Counsil By /
CBC/grr c - Mr. R. D. Martin, Region IV Resident Inspectors, CPSES (3) 8710140189 871000                                                                                         (
4 4
PDR         ADOCK 05000445 S                           PDR v
(J. S. Marshall j
{D 400 North Olive Street LB 81 Dallas. Texas 73201}}
Supervisor, J
Generic, Licensing
)
CBC/grr c - Mr. R. D. Martin, Region IV Resident Inspectors, CPSES (3) 8710140189 871000
(
PDR ADOCK 05000445 S
PDR v
{D 400 North Olive Street LB 81 Dallas. Texas 73201}}

Latest revision as of 04:01, 3 December 2024

Interim Deficiency Rept CP-87-100 Re Three Containment Isolation Penetrations That May Lack Relief Protection. Initially Reported on 870910.Evaluation Continuing.Next Rept Will Be Submitted by 871211
ML20235U663
Person / Time
Site: Comanche Peak  
Issue date: 10/08/1987
From: Counsil W, John Marshall
TEXAS UTILITIES ELECTRIC CO. (TU ELECTRIC)
To:
NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
References
CP-87-100, TXX-6850, NUDOCS 8710140189
Download: ML20235U663 (1)


Text

_ ___

E Log # TXX-6850 Fi1e:# 10110

.=

=

906.2 7t/ ELECTRIC Ref # 10CFR50.55(e)

-October 8,1987.

[

William G. Counsil Esecutive Vice President U. S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, D. C.

20555

SUBJECT:

- COMANCHE PEAK STEAM ELECTRIC STATION (CPSES)

DOCKET NOS. 50-445~AND 50-446 CONTAINMENT PENETRATION OVERPRESSURE j

PROTECTION

.SDAR: CP-87-100(INTERIMREPORT)

Gentlemen:

On September 10, 1987, we verbally notified yc ~ Mr. I. Barnes of a deficiency involving three containment isolation penetrations that may lack relief protectiori. Specifically, the design validation process has revealed that one Safety Injection System containment penetration and two Primary Sampling System containment penetrations, which are water solid and isolable, may lack overpressure protection. This is an interim report of a potentially reportable item under the provisions of 10CFR50.55(e).

We are continuing our evaluation and anticipated submitting our next report by December 11, 1987.

Very truly yours, (d C. Couns A W. G. Counsil By /

4 4

(J. S. Marshall j

Supervisor, J

Generic, Licensing

)

CBC/grr c - Mr. R. D. Martin, Region IV Resident Inspectors, CPSES (3) 8710140189 871000

(

PDR ADOCK 05000445 S

PDR v

{D 400 North Olive Street LB 81 Dallas. Texas 73201