ML20011E796

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Special Rept 90-01:on 900126,Limiting Condition for Operation 3.7.11.1 Entered When Two Fire Suppression Water Strainers Removed from Svc During Planned Outage.Strainers Cleaned & Repaired & Pressure Control Valve Returned to Svc
ML20011E796
Person / Time
Site: Sequoyah  Tennessee Valley Authority icon.png
Issue date: 02/09/1990
From: Michael Ray
TENNESSEE VALLEY AUTHORITY
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
90-01, 90-1, NUDOCS 9002220500
Download: ML20011E796 (2)


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' TENNESSEE VALLEY. AUTHORITYL:

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CHA7fANOOGA, VENNESSEE 37401 '

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FEB 091990 S'

lif.S.NuclearRegulatoryCommission

-ATTN:? Document Control-Desk:

. Washi.ng ton,, 0;C. 20555

-; Gentlemen:

~CIn the Matter of

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Docket Nos. 50-327.

JTennessee Valley Authority

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50-328 s

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-.SEQUOYAH NUCLEAR PLANT-(SQN) TECHNICAL SPECIFICATION (TS) 3.7.11.1 - SPECIAL L

~ REPORT 90, The enclosed-special report: pro'vides details concerning-the fire suppression-Lwater system being declared inoperable because of an extended fire header outage.l This report-istbeing made:In-accordance with TS Action Statement 3.7.11.1.b.2.c, If<you havelany questions concerning this submittal, please telephone 1

iM. A. Cooper at=(615)'843-6651'.

Very truly yours,

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TENNESSEE VALLEY AUTHORITY d

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and Regulatory Affairs d

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Enclosure:

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cc-(Enclosure):

lMs. S.:C. Black, Assistant Director for Projects ~ _

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'TVA Projects Division

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._U.S.~ Nuclear' %gulatory Commisslon

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y Mr.EB. A. H11 son, Assistant Olrector

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.TVA Projects ~01 vision J

1 U.S. Nuclear Regulatory Commission

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1101-Marletta Street, NW, Suite 2900 0

l Atlanta, Georgia. 30323 1

_NRC Resident Inspector q, _

!Sequoyah Nuclear Plant g

L2600:;Igou ; Ferry Road i

Soddy Dalsy,.Tennesseei 37379 a

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SQN Special. Report 90 j l;; ~

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.On' January 26; 1990, at 0550 Eastern standard time (EST), with Unit 3 1 and 2 J 7 in Mode ~l (100-percent power, 2,235 pounds per square inch gauge, &nd 578 degrees Fahrenheit), Limiting Condition for Operation (LCO)'3.7.ll.1 was entered when two fire suppression water strainers and the normal system pressure control valve were removed from service for maintenance and repairs.

The: system was'always functional 1n that fire protection was supplied from the a"

same fire protettlon pumps through an alternate path using the high pressure fire protection (HPfP) piping to all areas normally designated to have water H

suppresston= fire protectlon.

LCO 3.7.11.1 w.is entered as a conservative measure because-of the complexity and: method being utilized to maintain the ' operability of the HPFP system.

.This~ method utilized the.HPfP piping flow path that-supplies fire protection-first to the auxiliary building: areas.

This. path is+ longer and water must flow through1the auxiliary and-control buildings to reach the fire protected areas 1-the yard and' turbine. building.

The significance of utilizing this alternve flow path.is that 'a backup or tertiary flow path is not available.

In the: event of an auxiliary or control building demand for fire protection, the pressure and.five could be reduced in the turbine building and yard areas.

i The outage was a planned outage to repair and maintain components in the HPfP system.

The.two water strainers were cleaned and repaired along with the pressure differential backflow switch associated with-the strainers..The

. pressure control: valve for the system was also removej from service, repaired,

-and' returned lto service during this outage.

The LCO was ex!ted on January 27,.1990, at 2130 EST.

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