View source for TXX-4959, Interim Deficiency Rept CP-86-41 Re Effects of Operational Status of Plant Equipment During Mode 4 Operations.Initially Reported on 860626.Westinghouse Owners Group Developing Program to Address Concern.Next Rept by 861029

{{Adams
| number = ML20214K584
| issue date = 08/13/1986
| title = Interim Deficiency Rept CP-86-41 Re Effects of Operational Status of Plant Equipment During Mode 4 Operations.Initially Reported on 860626.Westinghouse Owners Group Developing Program to Address Concern.Next Rept by 861029
| author name = Counsil W, Woodlan D
| author affiliation = TEXAS UTILITIES ELECTRIC CO. (TU ELECTRIC)
| addressee name = Johnson E
| addressee affiliation = NRC OFFICE OF INSPECTION &amp; ENFORCEMENT (IE REGION IV)
| docket = 05000445, 05000446
| license number = 
| contact person = 
| document report number = CP-86-41, TXX-4959, NUDOCS 8608210293
| document type = DEFICIENCY REPORTS (PER 10CFR50.55E &amp; PART 21), TEXT-SAFETY REPORT
| page count = 1
}}

=Text=
{{#Wiki_filter:g Log # TXX-4959 File # 10110 915.6 TEXAS UTILITIES GENERATING COMPANY SKYWAY TOWER . 400 NORTH 01JVE NTREET. L.B. S 1 o DALLAS . TEXA8 7530 8 August 13, 1986
  .2M?d? .9lh                                                                   ,-
D $_ @ @ 0M3 h ll Mr. Eric H. Johnson, Director                                                    AL'G l 51986 Division of Reactor Safety and Projects                                    :
U. S. Nuclear Regulatory Commission                                       J                       j 611 Ryan Plaza Drive, Suite 1000 Arlington, TX 76012                                                                                  4

==SUBJECT:==
COMANCHE PEAK STEAM ELECTRIC STATION (CPSES)
DOCKET NOS. 50-445 AND 50-44C                                                 -
SMALL BREAK LOCA MODE 4 OPERATIONS SDAR:    CP-86-41 (INTERIM REPORT)

==Dear Mr. Johnson:==

On May 28, 1986, we verbally notified your Mr. I. Barnes of a deficiency involving small break LOCA evaluations regarding the effects of the operational status of plant equipment during Mode 4 operations. This is an interim report of a potentially reportable item under the provisions of 10CFR50.55(e). We have submitted an interim report logged TXX-4876, dated June 26, 1986.
Westinghouse has advised the NRC that information regarding this potential safety issue has been issued to all utilities with Westinghouse supplied PWRs. The WOG Analysis Subcommittee will be developing a program to address the concern for presentation to the WOG General Session in September, 1986.
We are continuing our evaluation and anticipate submitting our next report by October 29, 1986.
Very truly yours, e c.. W W. G. Counsil By:
g@e2 ggg ggggQ45                                                       D. R. Woodlan PDR          .
S                                                                      Licensing Supervisor JCH/arh c - NRC Region IV (0 + 1 copy)
Director, Inspection & Enforcement (15 copies)
U. S. Nuclear Regulatory Commission Washington, D.C. 20555 A DEVISION OF TEXAN UTTLETTER ELECTRIC COMPANY go
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