ML19323F655

From kanterella
Revision as of 20:03, 31 December 2024 by StriderTol (talk | contribs) (StriderTol Bot insert)
(diff) ← Older revision | Latest revision (diff) | Newer revision → (diff)
Jump to navigation Jump to search
Reactor Trip
ML19323F655
Person / Time
Site: Oconee, Crane  Duke Energy icon.png
Issue date: 06/22/1977
From: Scott R
DUKE POWER CO.
To:
Shared Package
ML19323F652 List:
References
TASK-TF, TASK-TMR EP-O-A-1800-3, NUDOCS 8005290283
Download: ML19323F655 (4)


Text

P.

r

~

EP/0/A/1800/3 j

Checked Control copy

?

i l

DuxE Pcan Cc:e.urf P*

l OCONEE NUCLEAR STATION

[

r j

[

l REACTOR TRIP 5

l t

l e

l f

l l

1.0 Symptoms Channel. trip alarm on tuo or more reactor protective channels.

. 5 1.1

~

I 1.2 droups 1-7, control rod "in limit" light on.

1.-3 NI's indicating a rapid decrease in neutron power.

fl l'

1.4 ICS runb'ack in progress, l

1 2.0 Immediate Action I

l-;

I 2.1 Automatic-f Control rod groups 1-7 d:cp into the core, g

2.1. l '

i

-j

'2.1.2 Turbine generator trips.

t Unit auxiliary load transfers to startup transformer.

~ l 2.1.3 f

2.1.4 Turbine bypass valves open at setpoint +125 PSI.

i' j,

Feedwater runback to minimum level in OTSG's.

2.1.5 2.2 Manual iI I

Verify automatic actions occur, if not, perform manually.

2.2.1 2.2.2 Verify neutron level decreasing.

2.2.3 Close (2)(3) EP-5 (Letdown Isolation).

2.2.4 Maintain LDST level by adding water with boron concen-tration > RCS boron concentration.

2.2.5 If pressurizer level cannot be maintained due to severe shrinkage open (2X3) HP-26.

NOTE:

(2)(3) "C" HPI Pu=p can be used to maintain i

pressuri ct level if needed.

j f

8 0052 90-OXO g l

r, t

- ee s _ _

=

'T-2-

('

3.0 Subsequent Action

  • ?

3.1 Notify unit supervisor and arga dispatcher -

,j i

3.2

'w rify OTSG's controlling at' minimum level.

[

E 3.3 Determine cause of trip and correct-l t

3.4 If LDST level approaches zero, open (2)(3) HP-24 to supply i j

.i.t HPI pump suction from BWST.

t 5 I!

l8 3.5 Go to one hoewell pump, one condensate booster pump, and one

.I Ii

'feedwater pump, as required -

j 3.6

0. pen (2)(3) HP-5 when pressurizer level returns to normal.

i ;,

I'l i

.i 6

)

I g.

L, t

-t r

[,

d l

l l

l E

t o

e f

, _ ;.._ _ --,h 4_

- t r a.

h -._ -

7/

. Fro r.3 5-& W b

Tdp Sk\\ OWC fO bb*k W oTcG RPS L'dh a

'Tv 7 sqech4

=%

o"

-+

ton.

u c.naA i

W y,L OW' 'W % TW py r~ j k j

'{.

Y"f ad L J,;cf rw +- ~ p 4

g

cum, nr V <L vC-c cJ~ 7

~

com.

iLJ b:s

s

=.

t y

f fa 3PC-1002-0 l

. i:.

u.,. c e.

.w e -

p

' ~ ' ' ' ' ' ' "

'1

/ 746 j

. /

DUKE POWER C0' IPA';Y (1) ID Not.[A

2 '> ' C "' " PRCCEDURE 'PREPA2ATIC::

l}I

/

i g,,,}

6 /.'.s.,<j s. A PROCESS RECORD

_i ca

..i 9

OCOja= NUCLEAR STATION M

(2)

STATION:

Aeoo/e 7'~,d (3) PRoCccuaE TITLE:

/

r t

g (4) PREPARED BY: h.

Tea DATE:

M /?-77

$~/d 77 (5) REVIE!ED BY:

(1 DATE:

N/R:

Cross-Disciplinary Review By:

i

?

r (6) TDIPORARY APPRO\\*AL (IF NECESSARY):

(SRO)

Date:

By:

e Date:

By:

d e

1 4

e e

D D

F D W y{/il '

,M

'MJ 3

m

.