ML20002B575
| ML20002B575 | |
| Person / Time | |
|---|---|
| Site: | La Crosse File:Dairyland Power Cooperative icon.png |
| Issue date: | 12/05/1980 |
| From: | Linder F DAIRYLAND POWER COOPERATIVE |
| To: | Harold Denton Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML20002B576 | List: |
| References | |
| RTR-NUREG-0578, RTR-NUREG-578 LAC-7266, NUDOCS 8012120225 | |
| Download: ML20002B575 (9) | |
Text
,
D DA/RYLAND COOPERAT/VE
- LA CROSSE WISCONSIN 51601 (608) 788 4 000 December 5, 1980 In reply, please refer to LAC-7266 DOCKET NO. 50-409 Director of Nuclear Reactor Regulation ATTN:
Mr. Harold Denton, Director Office of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission Washington, D. C.
20555
SUBJECT:
DAIRYLAND POWER COOPERATIVE LA CROSSE BOILING WATER REACTOR (LACBWR)
PROVISIONAL OPERATING LICENSE NO. DPR-45 ADDITIONAL INFORMATION - THREE MILE ISLAND LESSONS LEARNED (NUREG-0578 )
REFERENCE:
(1)
NUREG-0578, "'IMI-2 Lessons Learned Task Force Status Report and Short-Term Recor.mendations," dated July 1979.
Gentlemen:
Enclosed in this submittal are the reports on the reviews of plant transient and accident analyses required by NUREG-0578, Section 2.1.9.
If you have any questions regarding this submittal, please contact us.
Very truly yours, DAIRYLAND POWER COOPERATIVE A44' M
U Frank Linder, General Manager FL:LSG: abs CC:
J. Keppler, Reg. Dir., NRC-DRO III FGL.
S33'AUJ; Nc u
' p' '-c:
Enclosures 9 3 11 !?] !l03361 j m q,,, -
htins/J!i -
8012120 JJ f
s b
SUMMARY
OF ACCIDENT ANALYSES This report contains analyses of all plant accidents considered in the LACBWR Safeguards Report, other than those recently submitted (LAC-6905, 6705, 6769.)
i This report provides the accident portion of the analysis required by NUREG-0578, Section 2.1.9.
The accidents considered in this report are:
1)
Fuel Loading Accident 2)
Power railure 3)
Control Rod Drive Mechanism railure 4)
Puel Element railure 5)
Inadvertant Liquid Release 6)
Inadvertant Airborne Stack Effluent i
The event tree format is utilized in this presentation of accident analyses.
The event trees are self-explanatory.
This report will not address the probability of occurrence of the above accidents.
The actions which would occur following.the above accidents are presented, as are possible consecutive failures.
Operator actions necessary or incorrect are also included.
e r
. - _. =... -
I 1
REFERENCES j
i 1.
Lacrosse Boiling Water Reactor Safeguards Report, August 1967.
2.
[ACBWR Environmental Report DPC-ED-3, Section 6, September 1972 4
(LAC-1360).
i l
3 IACBWR Operating Manual.
3 i
1, l
1 t
f I
l l
1 l
l I
1
~
1 t
1 i
\\
I I.
FUEL LOADING ACCIDENT Reactor Goes "
Rcpid Increase In Operators One Control Rod Half-Locked l
Critical During Count Rates On Stoo Fuel Half-Cocked During Scrams In C l
Fuel Loadina Source Ranne Channels Insertion Fuel Loading On Short PQ l
On Channels Criticality Monitors Does Not 4 Auto Scro Alarm All Rods Fully Inserted During Fuel Loading (Rod Position Specified In Special Fuel llandlina Drocedures) i i
l-I ofE D J
@ o Wy n
i %
W1 Rh w.,-
t
) '
72-
..n
- ~..,. - - -. - -
-,,,n.,
l Rod uto.
rind 1 or 2
~
' Evacuate No Fuel Goerator Scrams Rod Works 701' Level Damage In Manually Due To
,rk Hi Counts A Radiation Monitors Alarms Manual Scram Does Not Work Operators Withdraw Assembly Beinq Loaded D**D "gTYg' oJu 15 L i
os l
4 i
_ -... ~. ~... _...-
4
)
I 1.
POWER FAILURE Reserve Feeds Pick Up 1
l Load (Offsite Power)
Loss of Onsite t
l Generated Power j
Reserve Feeds Do Not Emergency Diesel Reserve Feed Operator i
Pick Up Auto.
Generators Start Operator Picks Up Load Secures EDG's Switches Loads t
a to Reserve Feed Offsite Power EDG's Supply i
Not Available Essential Buses s
j.
4 l'
1 1
I i
i.j i
1 I
l i
i 1
]'.
i i
2 I
f
j i
d III. CONTROL ROD DRIVE MECHANISM FAILURE I
4 Failure that Prevents a Completely
(
3 Withdrawn Control Rod From Entering Core Subcritical By at least 0.5% AK/K Core Under Scram Condition L
i CRDM Fails Low Gas or Oil Pressure In Any Partial Scram i
Rod's Accumulator o
I Hydraulic Pressure Lost While Electirc Motor Drives Rod In a
Reactor is In Scram Condition k
t 1
I 4
i J
l l
l i
I i
I l
s
?
4 I
i
- j. -
i i
l I
.1 l
l IV.
FUEL ELEMENT FAILURE
'Several Rods With I Well Within MPC Small Defects l
Limits at All Locations Small Defects Fuel Many Rods With Element Small Defects failure l
High Activity Offgas Tanks HP Takes Shutdown Failed Gross Detected By Outlet Valves Primary as Per Elements Failure Offgas Monitors Close Sample i
TS Limits
, Removed If Offgas is Purification Routed to Cond. Increase Stack,' Jill Auto Shift to Tanks Reactor Steam Flow Decrease Possible High Area Radiation Alarm
V.
LIQUID WASTE DISCHARGE s
Operator Starts Pumping Contents of Waste or Retention Tank Nornal Activity to River Which is Not Sampled or For Which Sample Was Incorrectly Contents of Waste Water Operator Terminates
~ ~ ~ '
Analyzed High Activity Monitor Alarms Discharge to River Condenser Discharge Monitor Possibly Alarms
l t l
sa
\\
l l
VI.
INADVERTANT AIRBORNE STACK RELEASE Offgas Routed to Air Ejector Of fgas Tanks (Normal Mode)
Radiation Hi Alarm Received 1
Air Ejector Offgas Routed Offgas Routed Directly to Offgas Radiation Stack (Alternate Hi Alarm
""~
Operation Mode)
Received Of fgas FaHs to ally O m a m l
Shift to Tanks Valves to Shift to Tanks t
E 7 0 i
foe y
- -( t e
o p
4 s
f I
1 Offgas Bleed Gas in Tanks to Stack Storage After Allowing to Decay & Sample Tank i
Discharge Inadvertant Opening of Valves in Valve Line From a Full 12,000-Gallon i Insignificant Closes Storage Tank at 300 PSIG to Stack l Dose Offsite Of fgas Storage Tank Operator Manu-Discharge Valve ally Terminates Fails to Close Discharge mmg mg'g" "g f o o A\\ e A\\.1 }Alhka h
T i'
I i
..,..._,._.,,.,..., _ _ _ _.. _.. -.. _.. - _... _..