ML20069L873

First Interim Rept of Significant Const Deficiency 76 Re Damage to Pressurizer Heaters During Precore Hot Functional Testing.Initially Reported on 830311.Unacceptable Heaters Will Be Replaced/Reworked.Next Rept Expected by 830715

ML20069L873
Person / Time
Site:	Waterford
Issue date:	04/25/1983
From:	Maurin L LOUISIANA POWER & LIGHT CO.
To:	Jay Collins NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
References
W3I83-0119, W3I83-119, NUDOCS 8305020479
Download: ML20069L873 (2)

Text

i 142 DELARONDE STREET POWE R & LlGHT P O BOX 0008

• NEW ORLEANS louts 1ANA 70174 * (504) 366 2345

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April 25, 1983 voce Presnient Nuclear Ope a o W3183-0119 Q-3-A35.07.76 Mr. John T. Collins, Regional Administrator, Region IV e

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U. S. Nuclear Regulatory Commission l I('

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Arlington, Texas 76012 , .o ott_ _ _ _

SUBJECT:

Waterford SES Unit No. 3 ___

Docket No. 50-382 Significant Construction Deficiency Report No. 76

" Damage to Pressurizer lleaters During llot Functional Testing" First Interim Report

Reference:

Telecon f rom W. A. Cross to J. Boardman dated March 11, 1983

Dear Mr. Collins:

In accordance with the requirements of 10CFR50.55(e), we are hereby providing two copies of the Interim Report of Significant Construction Deficiency No. 76, " Damage to Pressurizer IIeaters During Ilot runctior.nl Testing". This condition was originally identified as PRD 108.

Verv truly yours, L. V. Maurin LVM/ MAL /grf cc: 1) Director 3) Mr. E. L. Blake Office of Inspection & Enforcement U. S. Nuclear Regulatory Commission Washington, D. C. 20555

2) Director 4) Mr. W. M. Stevenson Office of Management Information and Program Control U. S. Nuclear Regulatory Commission Washington, D. C. 20555 g 8305020479 840425 PDR ADOCK 05000382 S PDR

Interim Report of Significant Construction Deficiency No. 76

" Damage to Pressurizer Heaters During Hot Functional Testing" Introduction This report is submitted pursuant to 10CFR50.55(e). It describes damage which occurred to the pressurizer heaters during pre-core hot functional testing. At present, this problem is considered to be reportable under the requirements of 10CFR50.55 (e) (1) (iii) .

Description of Problem On March 10, 1983, Pre-core Hot Functional Testing was in progress with the plant conditions stable at a primary system test plateau of 460*F and 1100 psi for testing and equipment surveillance. Channel "X" was selected for pressurizer Level Control while leaking instrument tubing cotmeetions on the Channel "Y" system were being repaired by I6C technicians. Throughout the afternoon, unrecognized by control room personnel, the Channel "X" level control system erroneously indicated a pressurizer level of approximately 40% while Channel "Y" ranged from 31% down to 2.8%. Channel "Y" repairs had been completed by I&C Technicians but this information was unknown to Control Room personnel.

A low-low pressurizer level signal deenergizes all heaters to protect the heaters should they become uncovered. Channel "X" was selected for this function and due to the anomolous Channel "X" level indication, the pressurizer heaters were maintained energized while uncovered resulting in known damage to 21 heaters and suspected damage to the remaining 9 heaters.

Subsequent to the pressurizer heater damage, it was determined that the Channel "X" pressurizer level measurement and control system was inoperable due to leaks at instrument tubing connections and that Channel "Y" was providing valid level indication.

Safety Implicatie is At this time the full extent of the Pressurizer Heater damage has not been determined and the safety significance of this event is still under evaluation, l

i Corrective Action Hot Functional Test Coordinators, Test Directors, and Plant Staff Maintenance personnel were instructed in the use of Startup Administrative Procedure (SAP-08),

" Condition Identification and Corrective Action." Also emphasized was the need for proper approvals and communications with the Nuclear Operations Supervisor prior to

and at the completion of maintenance activities.

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Additionally, the full extent of the pressurizer heater damage will be determined and unacceptable heaters will be replaced or reworked.

l Further information on this matter will be submitted to the USNRC on or before July 15, 1983.

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