ML20213E910: Difference between revisions

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#REDIRECT [[TXX-6065, Interim Deficiency Rept CP-86-71 Re Possibility of Electrical Cable Pulling Tension Exceeding Allowable Limits. Initially Reported on 861002.Investigation & Evaluation Planned.Next Rept Will Be Submitted by 861126]]
| number = ML20213E910
| issue date = 10/31/1986
| title = Interim Deficiency Rept CP-86-71 Re Possibility of Electrical Cable Pulling Tension Exceeding Allowable Limits. Initially Reported on 861002.Investigation & Evaluation Planned.Next Rept Will Be Submitted by 861126
| author name = Counsil W, Keeley G
| author affiliation = TEXAS UTILITIES ELECTRIC CO. (TU ELECTRIC)
| addressee name = Johnson E
| addressee affiliation = NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
| docket = 05000445, 05000446
| license number =
| contact person =
| document report number = CP-86-71, TXX-6065, NUDOCS 8611130363
| document type = DEFICIENCY REPORTS (PER 10CFR50.55E & PART 21), TEXT-SAFETY REPORT
| page count = 2
}}
 
=Text=
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Log # TXX-6065 File # 10110 TEXAS UTILITIES GENERATING COMPANY                                908.3 October 31, 1986 WILLIAM G. COUNSIL                                                              _ _ __
suscumr ecs PassicsNT                                                            '
Mr. Eric H. Johnson, Director Division of Reactor Safety and Projects U. S. Nuclear Regulatory Commission U~S 611 Ryan Plaza Drive, Suite 1000                                                          y Arlington, Texas 76012                                                -
1
 
==SUBJECT:==
COMANCHE PEAK STEAM ELFCTRIC STATION (CPSES)                                      l DOCKET NOS. 50-445 AND 50-446 CABLE PULLING TENSION SDAR:  CP-86-71 (INTERIM REPORT)
 
==Dear Mr. Johnson:==
 
On October 2,1986, we verbally notified your Mr. Ian Barnes of a deficiency regarding electrical cable pulling. This is an interim report of a potentially reportable item under the provisions of 10CFR50.55(e).
A concern exists over the possibility of allowable cable tension being exceeded for some cables because cable installation procedures did not address correction factors for vertical cable pulls and co-efficient of friction for cable pulls into conduits with previously pulled cables. Although no specific damage has been identified, an investigation and engineering evaluation will be conducted to determine if the actual cable pulling method used could have caused any damage.
Our investigation and subsequent evaluation will be based on the following plan of action.
: 1.      Review the installation specification, construction procedures and quality assurance procedures on cable pulling to determine the overall adequacy of the program.
: 2.      Interview personnel from Engineering, Construction, Quality Assurance, Start-up and Training to evaluate current installation practice.
: 3.      Review the calculations associated with the cable pulling charts to determine what margins are included.
: 4.      Review NCRs and Start-up deficiencies for problems associated with cable pulling to determine causes and resolutions of past cable pulling deficiencies.
: 5.      Perform an engineering evaluation of cable installations susceptible to increased pulling tension.
8611130363 861031      5 DR  ADOCK 0500
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TXX-6065 October 31, 1986                                                              (
Page 2 We will submit our next report on this issue no later than November 26, 1986.
Very truly yours,
                                            //Y      (Cu-HiLY W. G. Counsil By:'          '
G. S. Keeley  W'      -
Manager, Nuclear Lid 6nsing WJH/gj c - NRC Region IV (Original + 1 copy)
Director, Inspection and Enforcement (15 copies)
U. S. Nuclear Regulatory Commission Washington, D. C. 20555 l
1 i
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