View source for TXX-6511, Interim Deficiency Rept CP-86-41 Re small-break LOCA Evaluations of Effects of Operational Status of Equipment During Mode 4.Initially Reported on 860528.Westinghouse Owners Group Evaluating Issue.Next Rept Expected by 880229

{{Adams
| number = ML20215B620
| issue date = 06/12/1987
| title = Interim Deficiency Rept CP-86-41 Re small-break LOCA Evaluations of Effects of Operational Status of Equipment During Mode 4.Initially Reported on 860528.Westinghouse Owners Group Evaluating Issue.Next Rept Expected by 880229
| author name = Counsil W
| author affiliation = TEXAS UTILITIES ELECTRIC CO. (TU ELECTRIC)
| addressee name = 
| addressee affiliation = NRC OFFICE OF ADMINISTRATION &amp; RESOURCES MANAGEMENT (ARM)
| docket = 05000445, 05000446
| license number = 
| contact person = 
| document report number = CP-86-41, TXX-6511, NUDOCS 8706170385
| document type = DEFICIENCY REPORTS (PER 10CFR50.55E &amp; PART 21), TEXT-SAFETY REPORT
| page count = 1
}}

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Log # TXX-6511 File # 10110 Ref #      FR50.55(e)      !
                                                      ~
TUELECTRIC                        June 12,1987               I William G. Counsli Executive Vice President U. S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555 J

==SUBJECT:==
COMANCHE PEAK STEAM ELECTRIC STATION (CPSES)
DOCKETS NOS. 50-445 AND 50-446 SMALL BREAK LOCA MODE 4 OPERATION SDAR: CP-86-41 (INTERIM REPORT)
Gentlemen:
On May 28, 1986, we verbally notified your Mr. Ian Barnes of a deficiency involving small break LOCA evaluations regarding the effects of the                                       j operational status of plant equipment during Mode 4 operation. This is an                                  !
interim report of a potentially reportable item under the provisions of                                   j 10CFR50.55(e).           Our most recent interim report was logged TXX-6062, dated                        ;
October 29, 1986.
J!
At this time, the issue of Small Break LOCA in Mode 4 has not been resolved by                             i the Westinghouse Owners Group (WOG).                    The WOG met with the NRC staff on                 l November 6,1986, in Bethesda to discuss the W0G's plans for resolving the                                  !
issue. As a result of questions arising from that meeting, the WOG sent a                                 i letter to the NRC dated January 8, 1987, (0G-209) which discussed the                                      !
feasibility of applying Leak-Before-Break Technology in the resolution of this                            !
issue.                                                                                                    1 All WOG activities have been on hold pending word from the NRC, with the                                   !
exception of the Operations Subcommittee's effort to prepare procedural                                    I guidance which will help operators deal with a LOCA in the shutdown modes.                                 !
This interim guidance was sent to WOG representatives in W0G-87-102 dated                                  J May 12, 1987, and it is being evaluated by TV Electric.
We anticipate submitting our next report on this issue by February 29, 1988, i
Very truly yours,          ,
M W. G. Counsil              1 JCH/gj                                                                                                     I l
c - R. D. Martin, Region IV                                                                                ;
Resident Inspectors, CPSES (3)                                                                     l 8706170385 070612 PDR        ADOCK 05000445                                                                         Th O S                             PDR                                                                  h        t 0
400 North Olive Street LB 81 Dallas, Texas 75201
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