05000324/LER-1983-019, Updated LER 83-019/01T-2:on 830210,instrument Air Tubing to Safety Relief Valve/Automatic Depressurization Sys Valve Accumulator Inadequately Supported.Caused by Rerouted Tubing.Supports Installed

Updated LER 83-019/01T-2:on 830210,instrument Air Tubing to Safety Relief Valve/Automatic Depressurization Sys Valve Accumulator Inadequately Supported.Caused by Rerouted Tubing.Supports Installed

ML20090E269
Person / Time
Site:	Brunswick
Issue date:	07/12/1984
From:	Dietz C, Pastva M CAROLINA POWER & LIGHT CO.
To:	NRC OFFICE OF ADMINISTRATION (ADM)
References
BSEP-84-1626, LER-83-019-01T, LER-83-19-1T, NUDOCS 8407190377
Download: ML20090E269 (4)

LER-2083-019, Updated LER 83-019/01T-2:on 830210,instrument Air Tubing to Safety Relief Valve/Automatic Depressurization Sys Valve Accumulator Inadequately Supported.Caused by Rerouted Tubing.Supports Installed

Event date:
Report date:
3242083019R00 - NRC Website

text

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LICENSEE EVENT REPORT UPDATE REPORT:

• PREVIOUS REPORT DATE: 1-30-84

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l L Q l During a short-term unit maintenance outage, while performing a routine drywell l

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_o4 l SRV/ ADS valves' accumulators appeared to be inadequately supported. An inspection and l

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,g o gl with plant design requirements. This event did not affect the health and safety l g l of the public. g

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_Ii19ll During the installation of an SRV modification, the subiect tub *v had been rerouted I Suonorts I sii li l l without adequate procedural controls to ensure sunoort desien comoliance.

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LER ATTACH"nT - RO #2-83-19 Facility: BSEP Unit 2 Event Date: February 10, 1983 While performing a routine inspection in the Unit 2 drywell, a resident NRC inspector observed that the instrument air tubing supplying the accumulators of the unit's SRV/ ADS valves appeared to lack adequate support. An engineering inspection and evaluation of the subject tubing determined the tubine support was not~in accordance with the plant design requirements.

The most probable cause of this deficiency is attributed to_ rerouting of the -

tubing during the installation of a plant todification which installed two-stage SRVs to replace the former three-stage design SRVs. Rerouting of the subject tubing occurred without adequate procedural controls in the modification installation package. This resulted from an oversight on the part of the responsible engineer, who did not realize the design requirement that the tubing be supported in accordance with the spacing table requirements of ANSI B31.1.1.

Additional supports were installed on the subject tubing in accordance with Plant Modification 83-25 to ensure structural integrity of the tubing during a seismic event. Additional supports will be added during a future unit outage in order to bring the tubing system into full compliance with design requirements.

The respective Unit 1 SRV/ ADS valve accumulator air tubing was inspected and .

modified as necessary during the 1983 Unit i refueling outage in order to allow full support design compliance prior to the subsequent startup of the

unit. In addition, prior to startup of Unit 1, a comprehensive inspection p'ogram culminating in seismic simulation / tubing integrity testing was patformed on Unit 1 to ensure compliance with structural integrity requirements.

As a result of this event, a plant memorandum was distributed on February 22, 1983, to all Engineering personnel, describing this event and outlining the 4

requirements for plant instrument air tubing support. In lieu of the training program addressed in our original response, our modification procedure will be revised to add additional controls to ensure design bases are completely defined. This revision will be completed by September 30, 1984.

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Brunswick Steam Electric Plant P. O. Box 10429 Southport, NC 28461-0429 July 12, 1984 FILE: B09-13510C .

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SERIAL: BSEP/84-1551 Mr. James P. O'Reilly, Director U.S. Nuclear Regulatory Commission Suite 2900 101 Marietta Street, NW Atlanta, GA 30323 BRUNSWICK STEAM ELECTRIC PLANT, UNIT 2 DOCKET NO. 50-324 LICENSE NO. DPR-62 SUPPLEMENT TO LICENSEE EVENT REPORT 2-83-19

Dear Mr. O'Reilly:

In accordance with Section 6.'9.1.81 of the Technical Specifications for Brunswick Steam Electric Plant, Unit 2, the enclosed supplemental Licensee Event Report is submitted. The original report fulfilled the requirement for a written report within 14 days of a reportable occurrence and both are in accordance with the format set forth in NUREG-0161, July 1977.

~Very truly yours, I

C. R. Dietz, General Manager Brunswick Steam Electric Plant MJP/sd1/ LETCH 1 Enclosure cc: Mr._R. C. DeYoung

.NRC A .us_e.ntiControl] Desk) l 1

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