ML20034C787
ML20034C787 | |
Person / Time | |
---|---|
Site: | Fort Saint Vrain ![]() |
Issue date: | 04/19/1990 |
From: | PUBLIC SERVICE CO. OF COLORADO |
To: | |
Shared Package | |
ML20034C092 | List: |
References | |
EOP-1, NUDOCS 9005100056 | |
Download: ML20034C787 (14) | |
Text
~
Db E0P.-
Issue 3-Public FORT ST, VRAIN NUCLEAR GENERATING STATION Page 1 of 14
$9tVlCO' Pustic saavecs COMPANY OF COLORADO O
TITLE: RESTORATION OF REACTIVITY CRITICAL SAFETY FUNCTION
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4 AUTHolqZED y
8Y va lJ,C PORC 8 7 7 APR 111990 gFFE,CTIVE
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,T DCCF NUMBER (S) kO-O\\ %L,.l 1
Q l
J FT. ST. VRAIN NON-CONTROLLED COPY VERIFY ISSUE STATUS WITH SITE DOCUMENT CONTROL CENTER PRIOR.
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1;-
Issue'3-Page 2 of 14-OPublic.
FORT ST. VRAIN NUCLEAR GENERATING STATION.
Service
- PUBUC SERWCE CORAPANY OF COLORADO TABLE OF CONTENTS 1.0 0BJECTIVE....................................................
3 2.0 SC0PE............
............................................. 3 3.0 ENTRY CONDITIONS............................................
3-4.0 PRECAUTIONS AND LIMITATIONS..................................
3 5.0 OPERATOR ACTIONS............................................ 5 j
i 6.0 ATTACHMENTS..................................................
13
' l 1
1
^
7.0 COMMITMENTS..................................................
13 i
1 4
i
' I 1
1 l
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.FORMto)372 22 3643 l.
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WEBSTER NE YORK 14580 (716) 265-1600
I E0P-1 l
Issue 3
?
Page 3 of 14 A Public FORT ST. VRAIN NUCLEAR GENERATING STATION
%F Service
- rusiuc senwes couramy or cotonAno l
1.0 OBJECTIVE L',
- 7.1*#*
To. provide detailed instructions to the plant l
operating personnel.for restoring and maintaining the Reactivity i
Critical Safety Function.
2.0 SCOPE This procedure gives instructions for ensuring and maintaining the reactor suberitical.
3.0 ENTRY CONDITIONS Scram of the reactor is required and Control Room equipment I
indicates that inadequate reactivity insertion has occurred such l
that the health and safety of the public may be threatened.
3.1 The following conditions exist:
~
l Control rods not inserting.
AND/OR The following instruments on I-03 do'not indicate negative rate:
t
.NI-1133-2 CH III RATE OF CHANGE NI-1134-2 CH IV RATE OF CHANGE i
NI-1135-2 CH V RATE OF CHANGE AND/0R The following instruments, located on 1-03, indicate that reactor power is not decreasing:
NI-1133-1 CH III LOG POWER NI-1134-1-CH IV LOG POWER ~
j=
NI-1135-1 CH V LOG POWER' NI-1133-3 LINEAR PWR CH III NI-1134-3 LINEAR PWR CH-IV NI-1135-3 LINEAR PWR CH V NI-1136 LINEAR PWR CH VI NI-1137 LINEAR PWR CH VII NI-1138 LINEAR PWR CH VIII AND/OR Linear Power Chennel Average, SPDS screen 3201,-indicates power is not decreasing AND/0R g
i Linear Power Channel Averaga Rate of Change (ROC), SPDS screen 3201, not decreasing.
4 FORM (Di372 22 3643 f
+
---e
~
m-
E0P-1 Issue 3 OPublic FORT ST. VRAIN NUCLEAR GENERATING STATION Service *-
PUBUC SERVICE COMPANY OF cot.ORADO
{s.
N -.
4.0 PRECAUTIONS AND LIMITATIONS 4.1 More than one Critical Safety Function challenge may' be addressed at the'same time if adequate operations resources are available to ensure that the higher priority challenge is being addressed without introducing i
additional challenges..
i 1
U FORM 10)372 22 3643
E0P,
Issue 3
&Public FORT ST. VRAIN NUCLEAR GENERATING STATION
%)F Service
- Pusuc senvice courAmy or cotonApo 5.0 OPERATOR ACTIONS s
1 INSTRUCTIONS CONTINGENCY ACTIONS l
I i
l NOTE: Step 5.1 may activate MANUALI l
[
SCRAM alarms on I-03B, I
l l
windows 4-5, 5-5 and 6-5..
l l
l
-l-I l 5.1 Manually scram the reactor.
l l
l
- a. Place HS-9330, SCRAM l
l l
I switch on I-03 to SCRAM l
l position.
l.
l l
- b. Place HS-1216 REACTOR MODE l l
l switch on I-03 to 0FF l
l l
position.
l l
l
- c. Remove the key from
'l l
I HS-1216 REACTOR MODE l
.l l
switch on I-03.
l l
l l
l
~
l 5.2 Verify reactor is sub-l l
l critical.
l l
l
- a. The following instruments l l
l on I-03 indicate reactor l
'l i
power rate of change is l
.I
[]m
[
negative.
l l
l
- NI-1133-2 WIDE RANGE CH l l
l III RATE OF CHANGE I
l l
- NI-1134-2 WIDE RANGE CH l
-l l
IV RATE OF CHANGE l
l l
- NI-1135-2 WIDE RANGE CH l l
I V RATE OF CHANGE l
l l
l O_R l
l l
- b. The following instruments l l
l on I-03 indicate reactor. l l
l power decreasing.
l l
l
- NI-1133-3 LINEAR PWR l
l l
CH III l
l l
- NI-1134-3 LINEAR PWR l
l-l CH IV l
l l
- NI-1135-3 LINEAR PWR l
l l
CH V l
l l
- NI-1136 LINEAR PWR l
l l
CH VI l
l l
- NI-1137 LINEAR PWR l
l l
CH VII I
I l
- NI-1138 LINEAR PWR l
l l
CH VIII l
.]
I I
l L
l FORM (Os 372 22-3643
E0P-1 l
Issue '
OService*
Public FORT ST. VRAIN NUCLEAR GENERATING STATION Pusuc senvece courAmy or cotonAoo C) -
Q l
INSTRUCTIONS CONTINGENCY ACTIONS l
l l-l 5.3 IF reactor is suberitical, l 5.3 IF reactor is not l-
~
l THEN proceed to Step 5.20 l
subcritical, l-l (page 12).
l THEN proceed to-next step l
l l
l~
(5.4).
~
l l NOTE: Step 5.4 will activate l
[
l ACKNOWLEDGE RESERVE SHUTDOWN l l
-l or CONT R00 PURGE SYSTEM l
l l
LOCAL ALARM on I-01A, 1-9.
I l-I I
I l
l 5.4. Insert the 7-R00 GROUP l
'l l
reserve shutdown material.
l l
l
- a. Simultaneously hold
.l l
HS-1102-1'AND HS-1104-1, l
l l
RESERVE SHUTOOWN 7-R00 l
l l
. GROUP switches on I-03 to l l
l.
OPEN for approximately 10 l l
l seconds.
l l
l I
l-l 5.5 Verify reactor is sub-l l.
I critical..
l l
l l
- a. The following instruments l l
l O l
on I-03 indicate reactor l l
l O l
power rate of change-is l
l l
negative.
l l
l
- NI-1133-2 WIDE RANGE CH l j
l l
III RATE OF CHANGE l
j.
l
'
- NI-1134-2 WIDE RANGE CH I l
i l
l IV RATE OF CHANGE l
l l
l
- NI-1135-2 WIDE RANGE CH l l
l V RATE OF CHANGE l
l l
OR l
l l
- b. The following instruments l l
1 on I-03 indicate reactor l l
l power decreasing.
[
[
l
- NI-1133-3 LINEAR PWR l
l l
CH III l
l l
- NI-1134-3 LINEAR PWR l
l l
CH IV l
l l
- NI-1135-3 LINEAR PWR l
l l
CH V l
l l
- NI-1136 LINEAR PWR l
[
l CH VI l
l l
- NI-1137 LINEAR PWR l
l l
CH VII l
l l
- NI-1138 LINEAR PWR l
l l
CH VIII l
l l
1 i
FORM 10)372 22 3643
E0P'-1 Issue'3 Page 7 of 14 0 Service
- Public FORT ST. VRAIN NUCLEAR GENERATING STATION; Pusuc sanvice couramy or cotonaoo r~'
l.
1 L
l INSTRUCTIONS CONTINGENCY ACTIONS l.
I l
l l 5.6 IF reactor is subtritical, l 5.6
~-I F -- reactor is not l
l l-THEN proceed to Step 5.20 l
subcritical, l
l (page 12).
l THEN proceed to next step.
l l
l-(5.7).
I l-NOTE: Step 5.7 will activate l-l-
l' ACKNOWLEDGE RESERVE SHUTDOWNI.
l l
or CONT R0D PURGE SYSTEM l-l l
l LOCAL ALARM on I-01A 1-9.
l
_ l I
]
l 5.7 Insert the 30-R00 GROUP l
l l
reserve-shutdown material.
I l
l
- a. Simultaneously hold l
l l.
HS-1102-2.AND HS-1104-2, l
l l
RESERVE SHUTDOWN 30-ROD l
l
]
GROUP switches on I-03 to l l
l OPEN for approximately 10 l l
l seconds.
l l
1 l
l 5.8 Verify reactor is sub-l l
critical.
l 1,
I
- a. The following instruments l l_
m I'v) l on I-03 indicate reactor l l
l power rate of change is l
l l
negative.
I l
e l
- NI-1133-2 WIDE RANGE CH I l
l III RATE OF CHANGE l
l l
- NI-1134-2 WIDE RANGE CH l
.l.
l IV RATE OF CHANGE l
l l
- NI-1135-2 WIDE RANGE CH l l
l V RATE OF CHANGE I
l 1
OR l
-l-l
- b. The following instruments l
~l l
on I-03 indicate reactor l-j j
power' decreasing.
l
.l 4
l
- NI-1133-3 LINEAR PWR l
l l
CH-III l
l
- NI-1134-3 LINEAR PWR l
l.
l l
CH IV l
_l_
l
- NI-1135-3 LINEAR PWR l
l l
CH V l
l l
- NI-1136 LINEAR PWR I
l l
CH VI l
l l
- NI-1137 LINEAR PWR I
l l
CH VII l
l 1
- NI-1138 LINEAR PWR l
l l
CH VIII l
l l
l l-
. A V
~ FORM (D)372 22 3643 1
kUY-1:
Issue'3 Page 8 of 14 A Public FORT ST. VRAIN NUCLEAR GENERATING STATION -
W Service
- PusuC SERVICE COMPANY OF COLOF. ADO l.
INSTRUCTIONS CONTINGENCY ACTIONS _
l l
l IF reactor is not l
l 5.9 IF reactor is suberitical, l 5.9 -
subcritical, l
l TilEN proceed to Step 5.20 l
l (page 12).
l THEN proceed to next step l
l I
(5.10).
l l 5.10 Dispatch an Equipment l
l l
Operator to level 10 of the l l_
l reactor building to locally l l
l insert all reserve shutdown l l
l material per Section 1.0 of l l'-
l of this l
l l
procedure.
l
[
l l
I l 5.11_ Verify reactor is sub-l l
l_
critical.
l l
l
- a. The following: instruments l l
[
on I-03 indicate reactor l'
l l
power rate of change is l
l l
negative.
l l
l
- NI-1133-2 WIDE RANGE-l l
l
.CH III RATE OF CHANGE l
l
[
- NI-1134-2 WIDE RANGE l
l 1
f^)
l CH IV RATE OF CHANGE l'
l
(/
l
- NI-1135-2. WIDE RANGE-l l
l CH V RATE OF CHANGE l
l l
[
l l
- b. The followIng instruments l l
~
l on 1-03 indicate reactor l l
l l
power decreasir.g.
l l
l l
- NI-1133-3 LINEAR'PWR l
l l
l CH'III l
l l
- NI-1134-3 LINEAR PWR l
l l
CH IV l
l l
l
- NI-1135-3 LINEAR PWR l
l l
l CH V l
l j
j
- NI-1136 LINEAR PWR l
l l
CH VI l
l
.s l
- NI-1137 LINEAR PWR l
l l
CH=VII l-l.
l
- NI-1138 LINEAR PWR l-l l
CH VIII
.l l
1 I
l 1
O FORM (D)372 22 3643
E0P-1 Issue 3 0 Service
- Public FORT ST. VRAIN NUCLEAR GENERATING STATION rusuc sanvice comeAmy or cotonApo A.O l
INSTRUCTIONS CONTINGENCY ACTIONS l
l I
reactor is suberitical, I 5.12 IF
(~
l TAEN proceed to Step 5.20 l
~~
reactor is not l
l 5.12 IF suberitical, l-l
.(page 12).
l THEN proceed to next step 1
l l'
(5.13).
I I
I l
l 5.13 Dispatch an Equipment l
l l
Operator to level 10 of the l-l l
Reactor Building to insert l
l l
all reserve shutdown materia 1l l
l
l using ACM nitrogen bottles l
.l l
per Section 2.0 of Attachment l l
l 1 of this procedure.
l l
l l
l L
l critical.
j '
l l 5.14 Verify reactor is sub-l l
l
- a. The following instruments l l
i l
on I-03 indicate reactor l l
i I
power rate of cht..ge is l
l l
negative.
l l
l
- NI-1133-2 WIDE RANGE l
l l
CH III RATE OF CHANGE l
l e,,- g l
- NI-1134-2 WIDE RANGE l
l O
l CH IV RATE OF CHANGE l
l l
- NI-1135-2 WIDE RANGE I
l-l CH V RATE OF CHANGE l
l l
l OR
]
l l
- b. The follow ng instruments l l
l on I-03 indicate reactor l l
l power decreasing.
l l
l
- NI-1133-3 LINEAR PWR l
l l
CH III l
l 4
l
- NI-1134-3 LINEAR PWR l
l l
CH IV
]
l l
- NI-1135-3 LINEAR PWR l
l l
CH V l
l l
- NI-1136 LINEAR PWR l
-l l
CH VI l
l l
- NI-1137 LINEAR PWR l
l l
CH VII l
l l
- NI-1138 LINEAR PWR l
l l
CH VIII l
l l
l l
f I
v FORM (D) 372 22 + 3643
E0P-1 Issue 3 Public FORT ST. VRAIN NUCLEAR GENERATING STATION I
Service
- PusuC ssRWCE COMPANY OF COLORADO fM
\\
g..
I INSTRUCTIONS CONTINGENCY ACTIONS
-l:
I I
reactor is not l
l 5.15 IF reactor is subcritical, l 5.15 IF~~~
.subcritical, I
l TAEN proceed to Step 5.20 l
l (page 12).
l THEN proceed to next step l
l l
(5.16).
l l
I l-1 5.16 Initiate powered insertion ofl l
I all control rods.
.l I
l
- a. E rod 1 must be poweredl l
l l
in, I
l
)
l l
THEN place HS-1221, ROD l
l l
SELECT-TENS, on I-03 l l
l to position 0.
l l
l
- b. Place HS-1220, ROD SELECT-l l
l UNITS, on I-03 to position l l
l 1.
l l
l l
- c. Press and hold HS-93475, I
l l
A LOGIC, and HS-93476, l
l l
B LOGIC, pushbuttons on l
l l
l I-03.
l l~
I
- d. Place and hold HS-1245,.
l l
l INDIVIDUAL R0D ACTUATE,.on!
I
(
1 I-03 to "IN" until rod 1 l l
l is powered in.
l l
.j l
- e. E rods 2-37 must be l
l l
powered in, l
l l
THEN place HS-1224, ODD-l l
j l
EVEN GROUP SELECT, l
l l
on I-03 to 000 or l
l l
EVEN position as l
l l
appropriate.
I l
l
- f. Place HS-1226, EVEN GROUP l l
-i l
SELECT, or HS-1225, 000 l
l l
GROUP SELECT, on I-03 to I l
l l
appropriate group l
l l
position.
l l
I
- g. Determine, from the l
l 1
l operator aides mounted l
l l
above XI-93475, XI-93476, I l
I XI-93477 and XI-93478, on l l
l I-03, which-MCC powers thel l
1 l
rod (s) to be power l
l l
inserted.
l l
l
- h. E rods (s) is powered l
l l
l l
THEN press and hold l
l l
HS-93475, A LOGIC, I
l l
and HS-93476, B l
l O
l LOGIC, pushbuttons onl l
l
'd l
I-03.
l l
FORM (D)372 22 3643
1:
E0P-1 Issue 3 OPublic FORT ST. VRAIN NUCLEAR GENFRATING STATION Service
- rusuc senvece comeAmy or cotonAno
()v
-l INSTRUCTIONS CONTINGENCY ACTIONS l
l I
l
- 1. IF-rod (s) is powered I
l i
l from CR0 MCC 1, I
l l
THEN press and hold l
l l
HS-93477, A LOGIC, i
l l
and HS-93478, B l
l l
LOGIC, pushbuttons onl l
l I-03.
l l
l
- j. Place and hold HS-1219, I
l l
R0D A ACTUATE, HS-1222, I
l l
ROD B ACTUATE and HS-1223,l=
l l
ROG C ACTUATE, on I-03 to l l
l "IN" position until l
l l
appropriate rods are l
l l
powered in.
l l
l l
l l 5.17 Verify reactor is sub-l l-l critical.
l l
l
- a. The following instruments l l
l on I-03 indicate reactor i l
I power rate of change is l
l l
negative.
'l l
l
- NI-1133-2 WIDE RANGE l
l l
l CH III RATE OF CHANGE I
l l
- NI-1134-2 WIDE RANGE l
l l
CH IV RATE OF CHANGE l
l l
- NI-1135-2 WIDE RANGE l
l l
CH V RATE OF CHANGE l
l 1
E I
I l
- b. The following instruments l l
l on I-03 indicate reactor l l
l-power decreasing.
l l
l
- NI-1133-3 LINEAR PWR l
l l-CH III l
l l
1
- NI-1134-3 LINEAR PWR
.l l
l l
CH IV l
l l-
- NI-1135-3 LINEAR PWR I
l l
CH V l
l-l
- NI-1136 LINEAR PWR l
l l
CH VI l
l l
- NI-1137 LINEAR PWR l
l l
CH VII l
l l
- NI-1138 LINEAR PWR I
'l l
CH VIII l
l 1
I I
l 5.18 I_F reactor is suberitical, l 5.18 IF reactor is not l
l THEN proceed to Step 5.20 l
subcritical, 1-l (page 12).
l THEN proceed to next step l
l (5.19).
l FORM t01372 22 3643
--m--
E0P-1 Issue 3~
~'
Page 12 of 14 Public FORT ST. VRAIN NUCLEAR GENERATING STATION l
OService*
~ PUBUC SERVICE COMPANY OF COLORADO O
l-l INSTRUCTIONS CONTINGENCY ACTIONS l
I I
I 5.19 Declare Site Area Emergency l l
l per RERP-CR.
l l
1 I
l-l 5.20 Verify all Critical Safety l
l l
. Functions satisfied per l
l ll E0P-CSFM, then go to AOP-B l
l l
for followup actions.
l l
l l
l t
t l
l V
e FORM 10) 372 + 22 3643
E0P #
- Issue 3 OService*
Public; FORT ST. VRAIN NUCLEAR GENERATING STATION Pusuc senvecs comeAmy or cotonAno IO v-6.0 ATTACHMENTS 6.1 Attachment'1 " Local Insertion of Reserve Shutdown Material and Insertion of Reserve Shutdown Material-using ACM Bottles".
6.2 Attachment Last, " Reactivity E0P-1" Flow Chart.
7.0 COMMITMENTS i
The step (s)' and section(s) listed below may.not be deleted without issuance of comparable controls. The procedure itself, if initiated as a result of commitment corrective action, may not be deleted without issuance of comparable controls.
7.1 This procedure was prepared to meet commitments made in Nuclear Regulatory Commitment Log, Item CL-1126J.
O I
s t
l 1
l
't s
1 O
FORM (D)372 22 3643 i
,n.,.
--n
I E0P-1
- ?
~ :
Issue 3
&Public FORT ST. VRAIN NUCLEAR GENERATING STATION Page 14 of 14 My Service
- rusuc senwce comeAny or cotonaoo e
fTV
-1.0 LOCAL INSERTION OF RESERVE SHUTDOWN MATERIAL (Step 5.10) 1.1' Depress, and hold for approximately 10 seconds, the red button for each of the following relays. Relay actuation may be accomplished in any order:
CR.1112 and CR 1113 on I-21A' CR 1114-1 and CR 1115-1 on I-21A CR 1114-2A and CR.1115-2A on:1-21B CR 1114-2B and CR 1115-2B on I-21B CR 1114-3 and CR 1115-3 on I-21C.
CR 1114-4A and CR 1115-4A on I-21D-CR 1114-4B and CR 1115-4B on I-21D-1.2 Notify Reactor Operator that the relay actuation has been accomplished.
2.0 INSERTION OF RESERVE SHUTOOWN MATERIAL USING ACM BOTTLES (Step 5.13) 2.1 Connect the ACM quick-disconnect fitting from the' nitrogen '
bottle to the right side fitting at the following racks:
I-21A, I-21B, I-210, I-210. Rack actuation may be q
accomplished in any order.
2.2 Verify the connection is securely made up by observing that the snap-ring of the connector is extended, locking the two fittings together.
2.3 Verify the nitrogen bottle regulators are backed off completely.
2.4 Open the bottle valve completely.
2.5 Verify the vent valves for each rack are closed:
1 Rack No.
l I-21A V-821440 I-21B V-821441-I-21C V-821442 I-21D V-821443 2.6 Adjust the nitroger bottle regulators until the HV-1102 i
(-1 through -37) valves have opened.
2.7 Notify the Reactor Operator that the ACM actuation has been accomplished.
I FORM (D)372 22 3643
.