TXX-4824, Interim Deficiency Rept CP-86-19 Re Installation of Steam Svc Pressure Transmitters Above Root Valves W/O Steam Traps or Wet Legs.Initially Reported on 860321.Evaluation of Corrective Action & Next Rept Expected by 860730

Interim Deficiency Rept CP-86-19 Re Installation of Steam Svc Pressure Transmitters Above Root Valves W/O Steam Traps or Wet Legs.Initially Reported on 860321.Evaluation of Corrective Action & Next Rept Expected by 860730

ML20210T683
Person / Time
Site:	Comanche Peak
Issue date:	05/23/1986
From:	Counsil W TEXAS UTILITIES ELECTRIC CO. (TU ELECTRIC)
To:	Johnson E NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
References
CP-86-19, TXX-4824, NUDOCS 8606020018
Download: ML20210T683 (2)

Text

Log # TXX-4824

, . File 0 10110

- 910.3 TEXAS UTILITIES GENERATING COMPANY MKYWAY TOWER . 400 NORTH OIJVE STREET. L.B. 88 e DALLAS. TEKAS 78301 May 23, 1986 -

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Mr. Eric H. Johnson, Director Division of Reactor Safoty and Projects U. S. Nuclear Regulatory Commission 611 Ryan Plaza Dive, Suite 1000 Arlington, TX 76012

SUBJECT:

COMANCHE PEAK STEAM ELECTRIC STATION (CPSES)

DOCKET NOS. 50-445 AND 50 446 PRESSURE INSTRUMENT INSTALLATIONS SDAR: CP-86-19 (INTERIM REPORT)

Dear Mr. Johnson:

On March 21, 1986, we verbally notified your Mr. R. Hall of a deficiency involving the installation of steam service pressure transmitters which were located above the root valves without steam traps or wet legs. We have submitted an interim report logged TXX-4770, dated April 21, 1986. We have concluded that this deficiency is reportable under the provisions of 10CFR50.55(e). We anticipate evaluation of all corrective action and submittal of our next report by July 30, 1986.

Very truly yours, M

W. G. Counsil JCH/arh Attachment c - NRC Region IV (0 + 1 Copy)

Director, Inspection & Enforcement (15 copies)

U. S. Nuclear Regulatory Commission Washington, D.C. 20555 lf>0 Do$ f S

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PRESSURE INSTRUMENT INSTALLATIONS DESCRIPTION This aboveissue the rootinvolves the installation valves without steam traps orofwetsteam legs. service pressure The following press transmi instrument installations have been identified as having the transmitter mounted at a higher elevation than the root valve connected to the steam f ~

process fluid:

Unit 1: 1-PT-514, 1-PT-516, 1-PT-524, 1-PT-524F, 1-PT-526, 1-PT-534, 1-PT-536, 1-PT-545, 1-PT-546, 1-PT-2325, 1-PT-2326, 1-PT-2327, 1-PT-2328; Unit 2: 2-PT-516, 2-PT-526, 2-PT-534, 2-PT-546, 2-PT-2327.

l The impulse tubing between the root valve and transmitter is routed without a wet leg (a wet leg ensures the tubing at the transmitter stays filled with condensate). Installations of this type could result in erratic, high, or low analog outputs from the transmitters to the Engineered Safeguards Features Actuation System (ESFAS) or Power Operated Relief Valve (PORV) logics.

The concern is applicable to Units 1 and 2.

SUMMARY

OF EVENTS Date Discovered: March 19, 1986; identified due to site engineering review of a Unit 2 Safeteam concern.

Date NRC Notified as Potentially Reportable: March 21, 1986.

Interim Report to NRC: April 21, 1986.

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Date Determined Reportable: May 23, 1986.

SAFETY IMPLICATION Unreliable monitoring of the main steam pressure in this manner could result in failure of the Engineered Safeguards Features Actuation System to perform I its intended nuclear safety function. l CORRECTIVE ACTION Site engineering shall evaluate all unit 1 and 2 steam service installations to accurately identify additional instruments which may be mounted above their root valves without wet legs. Upon completion of the evaluation, Design Change Authorizations (DCA's) will be issued for implementation to ensure proper instrument installation.

The estimated completion date for finalization of engineering evaluations and l design change package issuance is July 15, 1986.

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