05000286/LER-1982-003

From kanterella
Revision as of 17:52, 15 March 2020 by StriderTol (talk | contribs) (StriderTol Bot insert)
(diff) ← Older revision | Latest revision (diff) | Newer revision → (diff)
Jump to navigation Jump to search
LER 82-003/01T-0:on 820415,during Cold Shutdown for Refueling Outage,Surveillance Test 3PC-R4 Indicated That Pressure Transmitters PT-456,PT-457 & PT-474 Were Out of Spec.Transmitters Calibr
ML20053E244
Person / Time
Site: Indian Point Entergy icon.png
Issue date: 05/26/1982
From: Gumble F
POWER AUTHORITY OF THE STATE OF NEW YORK (NEW YORK
To:
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
Shared Package
ML20053E221 List:
References
LER-82-003-01T-02, LER-82-3-1T-2, NUDOCS 8206070724
Download: ML20053E244 (2)


LER-2082-003,
Event date:
Report date:
2862082003R00 - NRC Website

text

wtuvaann v.uwsusnmtwsutwmaa (11H ..

LICENSEE EVENT REPORT a

CONTROL BLOCK: l i

l l l l l lh e

(PLE ASE PRINT OR TYPE ALL REOLHRED INFORMATIONI lo i sM l9 lN lY.lI 7

lP lS l3 l@l LICENSEE LODE 14 015 l 0 l -l 0 l 0LICENSE l0 l NUMBEH 0 l 0 l - l 0 l 0 l@l 2h 4 26 l 1LICENSE l 1 l 1TYPE l 1JOl@l57 CAT l 68 l@

CONT o9 i f i 1.

f 0 1 M

Ei lL h l0 l5 l0 l0 l 0 l 2 l 8 l 6 @l0 lL'il2lul2l@l01512l61812l@

60 61 DOCKET NUMBER 68 69 EVF,NT DATE 14 75 REPORT D ATE 80 EVENT DESCRIPTION AND PROBABLE CONSEQUENCES h o 2 l While at cold shutdown for a refueling outage, performance of sur- I g

veillance Test 3PC-R4 (Pressurizer pressure calibration) indicated that l g , l pressure transmitters PT-456, PT-457 and PT-474 were out of specifica- l g 3 g tion on the non-conservative side at a test pressure of 1800 PSIG. Worst l g 3 l case analysis determined that under these conditions, the low pressure l y o l,; ; reactor trip signal would occur at a system pressure of 1797 PSIG, which l

,gg; is below the 1800 PSIG limit set by Technical Specification 2.3.1.B.3. I DE CODE S BC E COMPONENT CODE SUBC dE S E

["OTIl

/ 8 l 11 Bl@ W@ l E l@ 11 IN is IT lR lu l@ W@ W @

9 10 11 12 13 18 19 20 SE QUENTI AL OCCURRENCE REPORT R EVISION EVENT YEAR REPORT NO CODE TYPE NO.

@ ,"gg j@tsRr90 l8 l2 l l0 l0 l3 l y l0 l 11 lTl l-l y, 32

_ 21 J2 23 24 26  ?? 28 M 30 31 AKE ACT ON ON PL NT ET HOURS SB IT FORA S. SUP L MAN F CTURER lEl@ J4W @ lZl@ Q_J@ l0l0l0l0l (_Y_j @

41

(_yj h (_N__j h lF l1 l8 l0 lh 47 33 J5 36 31 40 42 43 44 CAUSE DESCRIPTION AND CORRECTIVE ACTIONS i o l As the plant was in the cold shutdown condition. no immediate ac H nn wie I

, , l necessary under the Technical Specifications. Transmitters PT-456, i PT-457 and PT-474 (Foxboro E11CM-SAEI) were calibrated to within l g

acceptable limits. Similar events occurred on November 11, 1980(LER- l

, g 80-015/03L-0) and August 1, 1978(LER 78-021/03L-0). l 7 8 3 80 STA S  % POWER OTHER STATUS IS O RY DISCOVERY DESCRIPTION l1 15l W @ l0l0l0l@ L NA l (A_jh! ENGINEERING REVTFW l ACTivlTY Co TENT RFLE ASED OF RELE ASE AMOUNT OF ACTIVITY LOCATION OF RELEASE NA l l NA l li lo !8 Lz_J 7 9

@ tz_1@l to 11 44 45 80 PEHSONNEL E XPOSURES NUMB E R TYPE DESCRtPT'ON 1 7 l0l0l0l@lZl@l"

" " PERsONNEtiN;u' RIES '

NA l

NUMBE R DESCRIP TION 7

i R 8 9 l0l0l0l@l 11 12 NA 80 l

LOSS OF OR DAMAGE TO FACILITY TYPE DE SCRIP TION 1 9 [Zj@l NA l

' **_ 'o 8206070724 820526 80

' PDR ADOCK 05000286 NRC USE ONLY ,

0 PDR i

2 o H 9 issue @oESCniPTiON@

l in

, , , l 68 69 llllllllll lllj 80 &

FLOYD W. CDtBLE 914-739-8200,X217 E, NAME OF PREPAHER PHONE:

8 ATTACHMENT 1

.LER 82-003/01T-0 Power Authority of the Docket No. 50-286 State of New York The plant was in the cold shutdown condition during a refueling outage.

On April 15, 1982, performance of Surveillance Test 3PC-R4 (Pressurizer Pressure Calibration) indicated that Pressure Transmitters PT-456, PT-457 and PT-474 were out of specification in the non-conservative direction at a test pressure of 1800 psig.

As the plant was in the cold shutdown condition, no immediate action was required under the Technical Specifications. Transmitters PT-456, PT-457 and PT-474 (Foxboro Ell GM-SAE1) were calibrated to within acceptable limits and returned to service. Preliminary engineering analysis determined' that all three transmitters were set conservatively with respect to Safety Injection Initiation setpoints, but were non-conservative with respect to Low Pressurizer Pressure reactor trip setpoints by 12, 3 and 4.3 psi, respectively. This is a worst case condition, in that the derivative rate action circuitry associated with the pressurizer pressure logic would anticipate the trip and normally. respond sooner.

The Low Pressurizer Pressure setpoint is 1800 psig according to Technical Speci-fication 2.3.1.B.(3). Examination of plant operation records confirmed that at no time during the period since the last performance of this surveillance test did pressurizer pressure approach 1800 ps!g with the reactor critical.

The effect on the overtemperature delta-T trip setpoint, which also utilizes the pressurizer pressure signals, was as follows: pressure transmitters PT-455 and PT-456 were found to be set non-conservatively, thereby lowering the redundancy designated by Technical Specification Table 3.5.2., Item 3, from 2 to 0.

Two out of the four channels required for reactor trip remained _ operable at all times.

The cause of this incident was determined to be instrument drif t. Similar events, involving the failure of only a single transmitter occurred on November 1,1980 (LER 80-015/03L-0) and August 1,1978 (LER 78-021/03L-0).

J' i '*

i t

l l

i I

[ 1 of 1