View source for TXX-6142, Interim Deficiency Rept CP-86-81 Re balance-of-plant (BOP) safety-related Instrument Setpoints.Initially Reported on 861107.Calculations for BOP Setpoints Indicate Omissions of Required Data,Per Rev 1 to Reg Guide 1.105

{{Adams
| number = ML20215D220
| issue date = 12/05/1986
| title = Interim Deficiency Rept CP-86-81 Re balance-of-plant (BOP) safety-related Instrument Setpoints.Initially Reported on 861107.Calculations for BOP Setpoints Indicate Omissions of Required Data,Per Rev 1 to Reg Guide 1.105
| author name = Counsil W
| 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 = 
| case reference number = RTR-REGGD-01.105, RTR-REGGD-1.105
| document report number = CP-86-81, TXX-6142, NUDOCS 8612160275
| document type = DEFICIENCY REPORTS (PER 10CFR50.55E &amp; PART 21), TEXT-SAFETY REPORT
| page count = 1
}}

=Text=
{{#Wiki_filter:Log # TXX-6142 File # 10110 907.6 TEXAS UTILITIES GENERATING COMPANY SKYWAY TOWER = 4e8 NORTH OLIVE STREET, LB. 88 . DALLAB. TEXAS 75301 December 5, 1986 hlY        f
= = = ,
Mr. Eric H. Johnson, Director Division of Reactor Safety and Frojects DEC ~ 91986 '
g                  jj U. S. Nuclear Regulatory Commission                                                                 /
611 Ryan Plaza Drive, Suite 1000                                                 L Arlington, Texas 76011                                                                                  '

==SUBJECT:==
COMANCHE PEAK STEAM ELECTRIC STATION (CPSES)
DOCKET NOS. 50-445 AND 50-446 B0P SAFETY RELATED INSTRUMENT SET POINTS SDAR:    CP-86-81 (INTERIM REPORT)

==Dear Mr. Johnson:==

On November 7,1986, we verbally notified your Mr. T. Westerman of a potentially reportable item involving the calculations for B0P Safety-related instrument setpoints indicating that omissions of required data or use of incorrect information occurred in performing the calculations required per Reg. Guide 1.105, Rev.1. This is an interim report of a potentially reportable item under the provisions of 10CFR50.55(e).
Evaluation of this issue, which is applicable to Units I and II, is being conducted by Stone & Webster Engineering Corporation. We anticipate submitting our next report by February 6, 1987.
Very truly yours,
                                                                                $f/8 mdst W. G. Counsil RDD/gj c - NRC Region IV (Original + 1 copy)
Director, Inspection and Enforcement (15 copies)
U. S. Nuclear Regulatory Commission Washington, D. C. 20555 8612160275 B y h 5 PDR    ADOCK O          PDR S
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