05000316/LER-1978-095-03, /03L-0 on 781206:while Decreasing Turbine Load, Reactor Coolant Average Temp Exceeded 576.2 F.Caused by Faulty Drain Valves on 5-A Heater,Creating Unstable Feedwater Control & Turbine Load

From kanterella
Revision as of 17:03, 7 January 2025 by StriderTol (talk | contribs) (StriderTol Bot insert)
(diff) ← Older revision | Latest revision (diff) | Newer revision → (diff)
Jump to navigation Jump to search
/03L-0 on 781206:while Decreasing Turbine Load, Reactor Coolant Average Temp Exceeded 576.2 F.Caused by Faulty Drain Valves on 5-A Heater,Creating Unstable Feedwater Control & Turbine Load
ML17317A828
Person / Time
Site: Cook 
Issue date: 12/20/1978
From: Murphy C
INDIANA MICHIGAN POWER CO.
To:
Shared Package
ML17317A823 List:
References
LER-78-095-03L, LER-78-95-3L, NUDOCS 7812270272
Download: ML17317A828 (2)


LER-1978-095, /03L-0 on 781206:while Decreasing Turbine Load, Reactor Coolant Average Temp Exceeded 576.2 F.Caused by Faulty Drain Valves on 5-A Heater,Creating Unstable Feedwater Control & Turbine Load
Event date:
Report date:
3161978095R03 - NRC Website

text

NRC FORM 366

{7.77)

U. S. NUCLEAR REGULATORY COMMISSION

~p 7

8 CON'T

~o 7

8 COMTROL BLOCK I

M I

D C

C 2

Oz 9

LICENSEE CODE 14

'15 LlCENSEE EVENT REPORT QI (PLEASE PRINT OR TYPE ALLREQUIRED (NFORMATION) 0 0

0 0

0 0

0 0

s A

1 1

1 1 s~Qs 0

0 25 26 LICENSE TYPE 30 57 CAT 58 LICENSE NUMBER

,oso,ULIQs 0

5 0

0 0

3 1

6 Qv1 2

0 6

7 8

Qs 1

2 2

0,.1 78 Qs 60 61 DOCKET NUMBER 68 69 EVENT DATE 74 75 REPORT DATE 80 EVENT DESCRIPTION AND PROBABLE CONSEOUENCES Q10 D

1 AT 1.00 POWER.

DEVELOPED TROUBLE WITH 5-A HIGH PRESSURE

~o 3

HEATER LEVEL CONTROL.

THE FEEDWATER CONTROL TO THE STEAM GENERATORS BECAME

~o 4

UNSTABLE.

PERFORMED AN EMERGENCY LOAD" REDUCTION OF 105 POWER.

WHILE DECREASING

~o 6

TURBINE LOAD THE REACTOR COOLANT AVERAGE TEMPERATURE EXCEEDED 576.2 DEGREES FOR

~OB 20 MINUTES IN VIOLATION OF TECHNICAL SPECIFICATION 3.2.5a.

~OB 7

8 9

80 7

8 SYSTEM

CAUSE

CAUSE COMP.

VALVE CODE CODE SUBCODE COMPONENT CODE SUBCODE SUBCODE

~Z.Z Q>>

UX Qvs UZ Qvs 2

Z 2

Z Z

2 Qvs UZ Qvs UZ'.

Qvs 9

10 11 12 13 18 19 20 SEQUENTIAL OCCURRENCE REPORT REVISION LERIRO EVENT YEAR REPORT NO.

CODE TYPE NO.

Qvv Rsvosv ~78 U

U00U5 Uw, ~03 UL Uo 21 22 23 24 26 27 28 29 30 31 32 ACTION FUTURE EFFECT SHUTDOWN ATTACHMENT NPRDC PRIME COMP.

COMPONENT TAKEN ACTION ON PLANT METHOD HOURS Q22 SUBMITTED FORM SUB.

SUPPLIER MANUFACTURER UXQvs UZQvg UZQvo UZQsi 0

0 0

0 UNQss UNQv4 UQvs 2

9 9

9 Qvs 33 34 35 36 37 40 41 42 43

~

44 47 CAUSE DESCRIPTION ANDCORRECTIVE ACTIONS 027 o

THE CAUSE OF THIS EVENT WAS.>FAULTY DRAIN VALVES ON 5-A HEATER, CREATING UNSTABLE FEEDWATER CONTROL AND TURBINE LOAD.

TURBINE LOAD WAS LOWERED RAPIDLY CAUSING THE TEMPERATURE TRANSIENT OF THE REACTOR COOL'ANT.

THE TRANSIENT WAS NOTED AND DEALT 3

WITH BY THE REACTOR OPERATOR.

BRINGING IT BACK INTO NORMAL RANGE WITHIN THE TIME 4

LIMIT OF THE ACTION STATEMENT.

THE DRAIN VALVES HAVE BEEN REPAIRED.

ACTIVITY CONTENT RELEASED OF RELEASE AMOUNTOF ACTIVITY UZ Qss 2

Qss NA 7

8 9

10 44 PERSONNEL EXPOSURES NUMBER TYPE DESCRIPTION Q3B

~lv ~00 0

Qsv UZQss NA 7

8 9

11 12 13 PERSONNEL INJURIES

~ ~o"'o'" o Q'"'"'"""

LOSS OF OR DAMAGETO FACILITY~43 TYPE

DESCRIPTION

~vo Lz{Q4v 7

8 9

10 PUBLICITY ISSUED DESCRIPTION~

p ~44 8

9 10 45 7

8 9

FACILITY

~3p METHOD OF STATUS YI POWER OTHER STATUS ~

DISCOVERY 1

5 6

Qvs ~l0 0

Qvs NA UAQsv 8

9 10 12 13 44 45 46 LOCATIONOF RELEASE 36 NA NRC USE ONLY 80 80 80 80 80 80 NAME OF PREPARER Mur 80' PHDNEI 61 465-5901 X-231 0.

)

l J>