ML20205C822
| ML20205C822 | |
| Person / Time | |
|---|---|
| Site: | Millstone, Haddam Neck, 05000000 |
| Issue date: | 06/15/1988 |
| From: | CONNECTICUT YANKEE ATOMIC POWER CO. |
| To: | |
| Shared Package | |
| ML20204H467 | List:
|
| References | |
| EOP-35-FR-S.1, NUDOCS 8810260579 | |
| Download: ML20205C822 (8) | |
Text
STATIhN PROCEDURE COVER SH IDENTIFICATION i
Number: E0P 35 FR-S.1 Rev.
2
-s IC)
Title:
RESPONSE TO NUCLEAR POWER GENERATION /ATWS Prepared By: H. K. Covin 8.
REVIEW I have reviewed the above procedure and have found it to be satisfactory.
e TITLE SIGNATURE DATE DEPARTMEt4T HEAD L fik l
n n s C.
SPECIFIC UNREVIEWED SAFETY QUESTION EVALUATION REQUIRED:
Modifies intent of procedure and changes operati of systems as described in design documents.
YES [ ]
NO,[. -T (If yes, perform written USQ determination and Safety
- Evaluation, and contact Manager, Safety Analysis Branch to determine need for Integrated Safety Evaluation.)
ENVIRONMENTAL REVIEW REQUIRED (Adverse environmental impact)
YES [ ]
NO []'
D.
SPECIFIC SAFETY EVALUATION REQUIRED Affects response of safety systems, performance of systems which may have been credited in the safety analysis or non-credited systems which may indirectly affect safety system response.
YES [ ]
NC [ t (If yes, perform written Safety Evaluation and contact Manager, Safety Analysis Branch to determine need for Integrated Safety Evaluation.)
E.
INTEGRATED SAFETY EVALUATION REQUIRED YES [ ]
N0 [
F.
PROCEDURE REQUIRES
/SORC REVIEW (In addition to revTew, ite ith a YES response
/
must be documented in the 50RC meeting minutes.)
YES [4 NO [ ]
D'SORC APPROVAL h/SORC Moeting Number 3 - 3 7-N T G.
H.
APPROVAL AND IMPLEMENTATION The attached procedure is hereby approved, and effectivs on the date below:
W 6 - /S~- bY 2m StatioE/ Service / Unit Superintendent Effective Date SF301/9/s/SES/87-12/lof1 8810260579 081007 "i DR ADOCK 050
a
(*
E0P 35 FR-S.1 Page 1 Rev. 2 O
~
RESPONSE TO NUCLEAR POWER GENERATIONS /ATWS Page No.
Eff. Rev.
1-7 2
i i
4
.I O
F I
I O
RESPONSE TO NUCLEAR E0P 35 FR-S.1 Page 2 POWER GENERATION /ATWS REV. 2 A.
PURPOSE This procedure provides actions to add negative reactivity to a core which is observed to be critical when expected to be shutdown.
B.
ENTRY CONDITIONS This procedure was written for Modes 1, 2, 3 and 4.
(AFW is not required if on RHR System). Using this procedure when not in these modes requires a step by step evaluation to determine if the required action is still applicable to current plant conditions.
This procedure is entered from 1)
E0P 35 E-0, REACTOR TRIP OR SAFETY INJECTION, Step 1, when reactor trip is not verified and manual crip is not effective.
2)
E0P 35 F-0.1, SUBCRITICALITY Critical Safety Function Status Tree on' either a RED or ORANGE condition.
O O
OP5084-2 344
RESPONSE TO NUCLEAR E0P 35 FR-S.1 Page 3 I POWER GENERATION /ATWS REV. 2
,~
~
'A STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OSTAINED NOTE If RHR is in service, i; ferences to AFW are not applicable.
1*
Verify Reactor Trip Manually trip reactor.
IF reactor will NOT trip, THEN TRIP Bus 32B and 32N load center supply breakers.
IF reactor trip is verified, THEN go to E0P 35 E-0, REACTOR TRIP OR SAFETY INJECTION, Step 2 and dispatch operator to locally trip the reactor tatp breakers.
a.
Reactor trip and bypass breakers - OPEN b.
Digital rod position indicators - AT ZERO c.
Neutron flux - DECREASING 24 Verify Turbine Trip a.
All turbine stop valves -
a.
Manually trip turbine.
CLOSED IF turbine will NOT trip, THEN manually turbine can NOT be ~~IF run back turbine.
runback, THEN~close Main Steam Isolation Valves and Main Steam Isolation Bypass Values.
3*
Check AFW Pumps Running a.
MD pumps - RUNNING a.
Manually start pumps.
b.
Turbine - driven pump -
b.
Manually open steam r.. LING IF NECESSARY supply valves O
oPK681 344
O RESPONSE 10 NUCLEAR E0P 35 FR-S.1 Page 4 POWER GENERATION /ATWS REV. 2
-,x STEP ACMON4XPECTEO RESPONSE RESPONSE NOT OSTAINED 4*
Initiate Immediate Boration of RCS a.
Check Charging pump -
a.
Start a Charging Pump RUNNING b.
Align boration path b.
Open gravity feed valve (s) and close
- 1) START both Boric the VCT Outlet Acid Transfer Isolations Pumps
- 2) OPEN Direct Boric Acid to Charging valve c.
Check charging flow path c.
Open normal Charging aligned flow path or OPEN changing header SI
- 1) OPEN Charging Flow valves Control Valve d.
Check PZR pressure d.
Perform the following
< 2350 psia
- 1) Verify PZR PORVs l
and block valves O,
open.
IF NOT, THEN open PZR PORVs and block valves as necessary until PZR pressure
< 2150 psia.
5 Check If the Following Trips Have Occurred a.
Reactor trip breakers -
a.
Dispatch operator to OPEN locally trip reactor trip breakers, b.
Turbine trip b.
Dispatch operator to locally trip turbine at the front standard O
OPM401 344
RESPONSE TO NUCLEAR E0P 35 FR-S.)
Page 5 POWER GENERATION /ATWS REV. 2 STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED 6
Check SG 1evel a.
Narrow range level in a.
Perform the following:
at least one SG > 4%
(34% FOR ADVERSE CONTAINMENT)
- 1) Verify total feed flow > 1150 GPM.
IF NOT, THEN manually start pumps and align valves as necessary.
- 2) Maintain total feed flow > 1150 GPM until narrow range level > 4% (34%
F,0R ADVERSE CONTAINMENT) in at least one SG.
b.
Control feed flow to maintain narrow range level between 4% (34%
O FOR ADVERSE CONTAINMENT) and 50%.
O "PS0641 344
O RESPONSE TO NUCLEAR E0P 35 FR-S.1 Page 6 POWER GENERATION /ATWS REV. 2 ib STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OSTAINED 7
Verify All Dilution Paths -
Manually isolate dilution ISOLATED a.
Primary makeup water to blender - CLOSED b.
Chemical mix tank outlet isolation valve (3CHS-V317)
- CLOSED c.
Manual dilution valve (3CHS-V305) - CLOSED d.
BTRS - 0FF and bypassed 8
Check For Reactivity Insertion IF controlJed cooldown NOT l
From Uncontrolled RCS in progress, THEN go to Step 12.
Cooldown a.
RCS temperature -
DECREASING IN AN UNCONTROLLED MANNER
- OR -
b.
Any SG pressure -
DECREASING IN AN UNCONTROLLED MANNER 9
Check Main Steamline Manually close valves.
Isolation and Bypass Valves - CLOSED 10 Identify Faulted SG(s) a.
Check pressures in all a.
Go to Step 12.
SGs -
- 1) ANY SG PRESSURE DECREASING IN AN UNCONTROLTED MANNER
- OR -
- 2) ANY SG COMPLETELY DEPRESSURIZED O
1 OPSO441 3-44
e RESPONSE TO NUCLEAR E0P 35 FR-S.1 Page 7 POWER GENERATION /ATWS REV. 2 b
STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OSTAINEO CAUTION 1.
At least one SG must be maintained available for RCS cooldown.
2.
If all SGs are faulted, at least 75 gpm feed flow should be maintained to each SG.
l 11 Isolate Faulted SG(s)
Hanually close valves.
IF valves can NOT be closed, a.
Isolate main feedline THEN dispatch operator t's locally close valves or b.
Isolate AFW flow bicck valves.
c.
Close steam supply a
valve (s) to turbine-driven AFW pump d.
Verify atmospheric dumps - CLOSED 12 Verify Reactor Subcritici Continue to borate.
IF boration NOT available, THEN aTTow RCS to a.
Power range channels heat up.
Perform actions of
< 5%
other Function Restoration Procedures in effect which do b.
Intermediate range Not cool down or otherwise add r;1annels-NEGATIVE positiva reactivity to the core.
STARTUP RATE.
Return to Step 4.
13 Ver fy Security has checked Obtain status of SLCRS doors all SLCRS doors - CLOSED from Security.
~
CAUTION~
Beration should continue to obtain adequate snuwown margin during subsequent actions.
14 Return to Procedure and Step Ir Effect FINAL -
O OPS 0681 3-84