ML20054K009
| ML20054K009 | |
| Person / Time | |
|---|---|
| Site: | Grand Gulf  |
| Issue date: | 06/12/1982 |
| From: | MISSISSIPPI POWER & LIGHT CO. |
| To: | |
| Shared Package | |
| ML20054J949 | List:
|
| References | |
| 05-1-02-V-4, 5-1-2-V-4, NUDOCS 8206300295 | |
| Download: ML20054K009 (3) | |
Text
^"
.-m
-~
2 k
PLANT OPERATIONS MANUAL f.
I 4
.l l
Volume 5 05-1-02-V-4 Section 02 Revision:
11 Date: 6-12-82 2
ej i
0FF-NORMAL EVENT PROCEDURE 3
PRESSURE CONTROL FAILURE - REACTOR PRESSURE INCREASING t
SAFETY RELATED 1
,i
/
i i'
g _ _- _.
~, -
~. g~
.. Prepared:
3 0
/
?///
Reviewed:
L.
/
/
M /,8,p Nuclear Plant Quality 'Superint6ndent
@ nnical Review Approved:
Operat(fon Superintend t
Concurrence:
M m
{
s ant Pl 'nt Manager f
db,lgy
~ ~ ~
PSRC:
~
... ]..,.
..T...... '
~~....I. /
.l..
=L.
r:.
t List of Effective Pages:
Page:
1-2 List of TCN's Incorported:
Revision TCN No.
10 None 11 None 8206300295 820625 DR ADOCK 05000 c
-m-r
RAND CULF NUCLEAR STATION OFF-NORMAL EVENT PROCEDURE l
Title:
Pressure Control Feilure No.:
05-1-02-V-4 Revision:
11 Page:
1
-Reactor Pressure Increasing i
i 1.0 PURPOSE / DISCUSSION 1.1 This procedure provides instructions to the operator in the event of a pressure control failure which causes increasing reactor pressure due to control / bypass valves closing.
1.2 This procedure may interface with the Emergency Plan and/or Emergency Procedures.
1.3 This pressure control system has been designed to be resistant to j
failures.
The sys tem consists of the three IPC channels, two EHC valve lift controllers, and four bypass valve control channels. The mode of pressure control failure dictates the rate of valve movement and the resulting transient severity.
Reactor pressure increasing, as a result of control / bypass valves going closed, will occur on failure of either of the EHC valve lif t controllpr output signals, the loss of the actual pressure signal to more than one of the IPC channels, or the loss of EHC fluid pressure.
Note that the loss of EHC fluid pressure will result in a direct scram.
~
If the bypass valves are failed or failing closed, they can be controlled manually with the BPV opening jack.
2.0 SYMPTOMS 2.1 Main turbine control / bypass valves closing 2.2 Reactor power and pressure increasing 2.3 Decreasing main generator output i
2.4 Pressure controller fault light on panel H13-P680 3.0 AUTOMATIC ACTIONS 3.1 Reactor scram on high flux or high pressure, or low EHC fluid pressure'.
3.2 Safety / relief valves may operate.
3.3 If reactor water level drops to -41.6":
3.3.1 HPCS Initiation P
e e
/
GI'p:D GULF !."'CI.EA!: STATIO!!
CFF-!!0PX*.L EVE!!! PROCEDURE
Title:
Pressure Control Failure No.:
05-1-02-V-4 Revision:
11 Page:
2
- Reactor Pressure Increasing l
3.3.2 RCIC Initiation 3.4 Recirc pump shift to LFMG at-+ 10" indicated reactor water level.
3.5 Recirculation pumps trip ~if reactor water level drops to -51".
4.0 IMMEDIATE OPERATOR ACTIONS-4.1 Verify automatic actions occur.
I 4.2 Verify reactor pressure decreasing or stabilized.
4.3 Refer to Reactor Scram CNEP 05-1-02.I-1 and Turbine Generator Trip ONEP 05-1-02-I-2, if applicable.
4.4 Notify the Shif t Supervisor. -
~/
5.0 SUBSEQUENT ACTIONS 5.1 Initiate the Emergency Procedure and Emergency Plan as directed by the
~
= = -.
~ '~ ~
-Shif t7 Supervisor /Superin~tehdent. -
' + ~ t
~~
5.2 Establish normsl reactor pressure using manual bypass valve control, if possible. Use the safety / relief valves if necessary.
5.3 Establish normal reactor water ievel using the feedwater system, if possible.
5.4 If RCIC and/or HPCS are operating and reactor water level has stabilized, shut them down and return them to standby per th'e applicable section of their respective SOI's.
~
5.5 If necessary, initiate Suppression Pool Cooling in accordance with SOI
_ 04-1-01-E12-1 to maintain suppression pool temperature less than 95 *F.
5.5 Attempt to fe-establish normal Bypass Control Valve operation.
~
5.7 Refer to IOI 03-1-01-3, Plant Shutdown.
-a--a______