05000260/LER-1981-028-01, /01T-0:on 810611,while Performing Routine Surveillance Test SI 4.2.B.8 During Maint Outage,Reactor High Pressure Switches Ps 68-93 Switch 2 & Ps 68-94 Switch 2 Were Above Tech Spec Limits.Caused by Setpoint Drift

From kanterella
(Redirected from ML20005A574)
Jump to navigation Jump to search
/01T-0:on 810611,while Performing Routine Surveillance Test SI 4.2.B.8 During Maint Outage,Reactor High Pressure Switches Ps 68-93 Switch 2 & Ps 68-94 Switch 2 Were Above Tech Spec Limits.Caused by Setpoint Drift
ML20005A574
Person / Time
Site: Browns Ferry Tennessee Valley Authority icon.png
Issue date: 06/25/1981
From:
TENNESSEE VALLEY AUTHORITY
To:
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
Shared Package
ML20005A558 List:
References
LER-81-028-01T, LER-81-28-1T, NUDOCS 8106300465
Download: ML20005A574 (2)


LER-1981-028, /01T-0:on 810611,while Performing Routine Surveillance Test SI 4.2.B.8 During Maint Outage,Reactor High Pressure Switches Ps 68-93 Switch 2 & Ps 68-94 Switch 2 Were Above Tech Spec Limits.Caused by Setpoint Drift
Event date:
Report date:
2601981028R01 - NRC Website

text

une > uliu x.

  • am LICENSEE EVENT REPORT

('.LJN ! 8108 0 8 OC K.

l l

l 1

l l

(PLE ASE PRINT OR TYPE ALL RFOUIRED INFORMATIONI f

[u.f_C lMLJ B I R l F 12 l@l 0l 0l -l 01 0l 01 0101 - l 0l O l@l 4 l 11 11 1 l 1 ]@l l

l@

d-It ' 's LifJ N. e t s'out 14 1%

L* CENSE NUMutn 16 7te LICCNSE f vPE J0 SF C A T sd C ON't l '_E]

",'"'/l" LLj@l 0 l 5 l010 10 l2 l6 10 )@l 016 l 111181 1 l@l o l 612 l s I s I 1 l@

GU Eel Out'.aL E I NUMtlE H fue f/J EvFNT DAIE to 7%

REPOR T DAIE 88 0 Eve nr oe.u'iPuoN ANo Pnon Ante constooEucts @

liTD L0uring a maintenance outage, while performing routine surveillance test, SI 4.2.B.8, I

in;in l reactor high-pressure switches PS 68-93 switch #2 and PS 68-94 switch #2 controlling l

[n,w ! shutdown cooling valves of the RHR system were found above limits of T.S. Table 3.2. A. ]

Q j g lThe greatest out of tolerance was 6.5 percent. There was no danger to the health or l

[ jim i safety _ of the public. Previous similar events: BFR0-50-259/7816, 7908, 8058, 8129, 1

t,022, 8057, 8123; 296/7907, 7912, 7928, 8022, 8030, 8045, I QT) 1.8132; 260f7802, 7317 7924 8

t 1

L Q ] (8052, 8107.

  • iG 1

11 8%

Su=E 5 nae c

Va" S20 s

M',.

COMPom~r coot

[,Tl l Cl Fl@ @@ l El@ lI lN lS lT lR lU l@ l Sj@ @ @

.e n.

i.

n

%f t1tst Nil AL OtCURRENC(

REPORT 84f Vl580N t */Efe f VL Att HfPOstf NC CODE fvPE Ntj

@,'lf I at f ee s I811l

[_j l0l2l8I [gj

!011 l lTI L-.-l 10I

.'.fl,:;',',

_l'

.' J 7J 79

. r, Ja j'J g,1 ju 3t 32 TA tf Af. f t ta a

PLA T U IMO MOUH5 5 fl 17 0 fos [Lu SUPPLt E R MANUF ACTtJREM lE_j@lEJ@

L7J@

LLj@

l0101010i LY.J@

LNJ@

[Lj@ - lB 10 16 19 [( '

If I4

.I' m JG 31 40 44 42 43 44 47 h

causr ncerHIPflON AND CONNECTIVE ACUOi [ijoj ISetpoint drift. Setpoints on the model B2T-M12SS pressure switches were reset to l

l MD L e proper value, and the surveillance instruction was completed satisfactorily.

th 1

y,,

j l Additionally, a design change request (DOR 1398) has been initiated to replace these i

g l switches with an analog transmitter with a trip switch.

[

I E,

I 40 1

%POWEn OTHEF4 5f Af ts5 O SCO R OsSCOVERY QESCRIPTION Is I [G_j @ l 0 l 0 l 0 l @ l NA l

lBl@l Surveillance test l

i '

'a s0 aC% v., y Co'"ic ni d

AMovNr OF Acmily h l LOC Af TON OF RELE ASE @

nEtr eEo ur Hetc Ase NA l

NA l

L'J.s_1 LZ.J (,3j) LZ._J@l Aq s

as

't I f) gg 44 as _

8't it'.e tNNf 4 4 4t(r.tdal %

  • si tMill t f l YP6 t ef '.LillP f TON -

l l TTl 101010J,,@lz l@l NA no r,, c.o~,.,,,,,..... s PilJP 9ttf Il l)f %Citif f1GN 101010 l@l NA l

i 60 i

14

't i1 12 r

f

  • 1 C PT O NA l

L,W)L.,IJ81 0

,o it* P T ir )N eqqt ig t @f st LN_j l

NA l

l l 1 I I l i t l 1 1 I l ',-

l

.* a 68 69 80 ;

et

'l f ft C

NAP

  • p,40N E:

l l u v u o o.

F PltEPAlt(H

... e

, Tin'nessee Valley Authority Form BF 17 Itrowns Ferry Nuclear Plant DF 15.2 6/04/81 1.F.Il SUPPLIG1 ENTAL INFORMATION flFitO-50, 260 f 81028 Te chnical Specification involved Table 3.2.A Itcported Under Technical Specification __fi.1.2.A(5)

  • Date duc NRC:_6f.25/81 0920 Date r..' Occurrence _6/Uf31_, Time of Occurrence _1115 Unit 2

hjentification_ and Description of Occurrence:

During SI 4.2.B.8, reactor high pressure switches were found at:ove T.S. limits.

At 0920 PS 68-93 switch #2 was found at 124 psi; at 1115,PS 68-94 switch #2 was found at 131 psi. Test limit is 123 psi, which is the limit of 115 psi plus 8 psi water leg.

Conditions Prior to Occurrence:

Unit I refueling outage.

C Unit 2 maintenance outage Unit 3 at 100%

Action specified in the Technical Specificatii;n SurveiUance Requirements met

@tdo inopgrable equipnyent. Describe.

None Apparent Cause of Occurrence:

Setpoint drift

@@ sis of Occurrence:

There was no danger to the health or safety of the public, no release of activity, no damage to the plant or equipment, and no resulting significant chain of events.

Corrective Action

s'etpoints'were reset to the proper value, and the surveillance instruction completed satisfactorily. Additionally, a design change request (DCR 1398) has been initiated to replace these switches with an analog transmitter with a trip switch.

Failure Data: BFRO-50-259/7816, 7908, 8058, 8129, 8132; 260/7802, 7917, 7924, l

8022,~~ BUS 7T8123; 296/7907, 7912, 7928, 8022, 8030, 8045, 8052, 8107.

l Hetention :

Per )d - I.ifetime; llesponsibility - Document Control Supervisor

  • llevision:.

[_

P00R CR E