ML20064G787
| ML20064G787 | |
| Person / Time | |
|---|---|
| Site: | Prairie Island  |
| Issue date: | 12/10/1982 |
| From: | Schuelke D NORTHERN STATES POWER CO. |
| To: | |
| Shared Package | |
| ML20064G778 | List: |
| References | |
| PROC-821210-01, NUDOCS 8301120022 | |
| Download: ML20064G787 (21) | |
Text
'
PAGE 1 OF 2 l
l EMERGENCY PLAN IMPLEtiENTING l
r-~x l
PRAIRIE ISLAND NUCLEAR PROCEDURES l
i l
-GENERATING PLANT l
l NORTHERN STATES POWER COMPANY Number: TABLE OF CONTENTS Rev: 17 l
l History Copy l l
Retention Time:
Li fe time l
n I
l TITLE:
-l
$'upt. Rad Protec t. ion l
l fp.
g' l
IMPLEMENTING PROCEDURES l
l l
TABLE OF CONTi'NTS l
I l
l l
l l
l l
l I
I l
NUMBER TITLE REV #
l l
l l
1 Onsite Emergency Organization 2
l l
l l
2 Classifications of Emergencies 2
l l
l l
3 Responsibilities T uring a Notification of l
l Unusual Event 2
l l
l l
4 Responsibilities Juring an Alert, Site Area, l
l or General Emerg(ncy 6
l l
l r
p/
l 5
Emergency Notifications 6
l
(
I I
l 6
Activation and Operation of Technical l
l Support Center 2
l l
l l
7 Activation and Operation of Operational l
l Support Center 3
l l
I l
l 8
Recommendations for Offsite Protective l
l Actions 1
l l
l l
9 Emergency Evacuation 1
l l
l l
10 Personnel Accountability 3
l I
I i
l 11 Search and Rescue 1
l l
l l
12 Emergency Exposure Control 2
l l
l t
l 13 offsite Dose Calculations 3
l l
l l
14.1 Onsite Radiological Monitoring 2
l l
l l
14.2 Operations Emergency Surveys 0
l l
l Ol 15 Responsibilities of the Radiation Survey l
l Teams During a Radioactive Airborne Release 5
l l
l l
1 83o1120o22 83o10s I
~
PDR ADOCK 05000282 F
Table of Contents Page 2 Rev. 17 NUMBER TITLE REV #
16 Responsibilities of the Radiation Survey Teams During a Radioactive Liquid Release 3
17 Core Damage Assessment 1
18 Thyroid Iodine Blocking Agent (Potassium Iodide) 1 19 Personnel and Equipment flonitoring and Decontamination 0
20 ffanual Determination of Radioactive Release Concentrations 2
21 Establishment of a Secondary Access Control Point 2
22 Prairie Island Radiation Protection Group Response to a Monticello Emergency 2
23 Emergency Sampiing 4
24 Record Keeping During an Emergency 1
25 Re-Entry 2
26 DELETED 27 DELETED 28 Review and Revision of Emergency Plans 0
29 Emergency Security Procedures 1
O IBfl
}
l PAGE 1 OF 12 s
l l EMERGENCY PLAN IMPLEMENTING l
(7 l
PRAIRIE ISLAND NUCLEAR PROCEDURES l
)
l GENERATING PLANT l
sV l NORTHERN STATES POWER COMPANY Number:
F3-17 Rev: 1 l
l liistory Copy l l
o
/)
Retention Time:
Lifetime l
l
/
/
l TITLE:
l R'ad P tection l
l Sup)t. g') }JLO/.Jr j l
CORE DAMAGE ASSESSMENT l
l Approved By: ys l
t-L'-
l l
l Plant Ma ggbr l
l l'
OC Date:j/-/8-ML l
l l
l l
l 1
l 1.0 PURPOSE
-l l
l l
The purpose of this procedure is to provide a means to best l
l estimate the degree of reactor core damage from the measured l
l fission product concentrations in water and gas samples taken l
l from the primary system and containment under accident conditions.
l l
l l
l l
2.0 APPLICABILITY l
l l
l This procedure shall apply to the Nuclear Engineering Staff.
l l
l l
l l
3.0 PRECAUTIONS l
l l
l 3.1 The numbers obtained using this procedure are at best, l
l estimates only.
l l
l l
3.2 Whem making core damage calculations as per this procedure, l
l considerations should be given to other plant indicators, l
l for example:
l 1
l l
(1)
Incore Thermocouples l
l (2) Containment Radiation Monitors l
l (3) Hydrogen Concentration in the RCS And/0r Containment l
l Atmosphere l
l (4) Radioisotopic Analysis l
l l
l 3.3 All formulas in this procedure are based upon equilibrium l
l full power core isotopes.
If fuel damage is suspected to l
l have occurred during times of reduced power or near the time l
l of a significant power change, the core nuclide inventory l
l must be compensated accordingly.
l l
l
'l 3.4 Iodine spiking may occur after a shutdown or significant l
l power change, usually during the 2 to 6 hour6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> period l
l following the power change. Do not misinterpret this change l
l for fuel damage if there are no other fuel damage l
indications.
I I
IBM
. =
F3 Rev. 1 Page 2 3.5 Chemistry samples should be taken as soon as fuel damage is l
suspected. All samples should be decay corrected back to the estimated time of fuel damage, or to a specified time, e.g. sample time.
4.0 GENERAL DISCUSSION This procedure address two levels of core damage. The first level is a rupture of the fuel rod cladding (gap release) and the second is a failure of all or part of the fuel rod due to oxidation of the zirconium clad. Fisison products and actinides, contained in the reactor core, can be divided into typical release groups, based on the case with which they are volatilized.
One such grouping, in order of decreasing volatility is:
I Noble gases (Kr, Xe)
II Halogens (I, Br)
III Alkali metals (Cs, Rb)
IV Tellurium (Te)
V Alkaline earths (Sr, Ba)
VI Noble metals (Ru, Rh, Pd, Mo, Tc)
Vll Hare earths and actinides VIII Refractory oxides of Zr and Nb The most volatile, the noble gases and to a lesser extent, the l
halogens are gaseous at room temperatures and can readily diffuse through the fuel pellet to collect in the gap. any clad perforation or rupture can release these fission products to the coolant.
The release of Cesium (Group IEI) is variable and not as well predictable.
However, in order to have large releases of cesiinc.s, it is believed overheating of the fuel would have to
- occur, i.e.,
temperatures greater than 2370 F.
At even higher temperatures (5200 F), liquefaction or melting of the fuel would occur, thus releasing other fission products, such as tellurium and ruthenium. Under oxidizing conditions, however, some tellurium and ruthenium may be released even before melt occurs. Therefore, the presence of tellurium and ruthenium does not prove that melt has occurred, but the absence of them is a good indicator that melt has not occurred.
5.0 PROCEDURE 5.1 As soon as core damage is suspected, request the Radiation Protection Group to obtain and analyze an RCS sample.
IBM i
F3-17 A
Rev. 1 Page 3 I
l l NOTE: A complete. isotopic analysis shouldl l
be performed. The sample analysis l l
should be decay corrected back to l
l the estimated time of core damage l l
or to a specific time, e.g. sample l l
time.
l l
l 5.2 Obtain the power history for the affected unit for the last 30 days.
5.3 All calculations as per this procedure are based upon equilibrium full power core radiosotopes.
If fuel damaged is suspected to have occurred during times of reduced power or near the time of a significant power change, the core radioisotope inventory must be compensated according to Figure 1.
This is the core nuclide correction factor, CNCF.
l l
l NOTE: The core nuclide correction factor l l
need only be completed for I-131 l
l and Xe-133.
Changes to the l
l equilibrium full power core Cs-137 l l
value will be negligible due to thel l
long half life.
l l
l 5.4 Calculate the best estimate of the number of failed fuel pins as follows:
NO* FAILED PINS = NUCLIDE INVENTORY (uCi)xCNCFxESCAPE FA PINS CORE Where: Coolant Activity in uCi/ml may be either of the following isotopes:
I-131 Xe-133 Cs-137 Coolant Volume is in ml. RCS Volume = 45,000 Gallons or 45,000 Gal.x 3.785E3 ml/ gal =1.703E8 ml.
Nuclide Inventory in uCi. This is equilibrium full power core nuclide inventory, obtained from Figure 2.
CNCF = Core Nuclide correction factor as determined by Figure 1.
O.
Escape fraction = Total gap release value from Figure 3.
IBM
F3-17
- R;v. 1
'Page 4 l
l l
}
l NOTE:
(1)
If the coolant activity is l
l based on an RCS sample while the l
l RWST is injecting and prior to l
l recirc., dilution of the coolant l
l activity should be considered.
l l
l l
(2)
If long term recirculation hasl l
been established, assume a uniform l l
activity in the RCS and containment l l
sumps. The volume now must include l l
l l
l l
(3) For LOCA conditions, assume i
i the liquid contains the iodine and l l
cesium and the containment air l
l contains the Xenon.
l l
l l
(4) RWST = 3949 Gal /Ft or 2922 l
l Gal./%
l l
Free Containment Volume at 14.7 l
l PSIA = 3.91E10 CC.
l l
Corrected Containment Volwne =
l l
(14.7+ INITIAL PRESSURE) (3.91E10)ccl l
14.7 l
til b 5.5 Calculate the best estimate of the fraction of fuel melt that may have occurred as follows:
FRACTION FUEL MELT = COOLANT ACTIVITY (uCi/ml)xC00LANT VOLUME (ml)
NUCLIDE INVENTORY (uCi)xCNCFxESCAPE FRACTION Where:
Coolant Activity in uCi/ml may be either of the following isotopes:
I-131 Xe-133 Cs-137 Coolant Volume is in ml.
RCS Volume =
45,000 gallons or 45,000 Gal.x3.785E3 ml/ Gal =
1.703E8 ml.
Nuclide inventory in uCi.
This is Equilibrium full power core nuclide inventory, obtained from Figure 2.
CNCF = Core Nuclide correction factor as determined by Figure 1.
Escape fraction = listed in Figure 4.
1 l
IBM l
F3-17 T
Rev. 1 Page 5 l
l l NOTE:
(1) If the coolant acvitity is l
l based on an RCS sample while l
l the RWST is injecting and l
l prior to Recirc., dilution of l
l the coolant activity should be l
l considered.
l l
l l
(2)
If long term recirculation hasl l
been established, assume a_ uniform l l
activity in the RCS and containment l l
susps. The volume now must includel l
l 1
l l
(3) For LOCA conditions, assume l
l the liquid contains the iodine and l l
cesium and the containment air l
l contains the Xenon.
l I
l l
(4) RWST=3949 Gal /Ft or 2922 Gal./l l
l l
Free Containment Volume at 14.7 l
l PSIA = 3.91E10CC.
l l
Corrected Containment Volume =
l l
(14.7+ INITIAL PRESSURE) (3.91E10)CCl
<:::)
l l
5.6 Compare other plant indications along with professional judgement to now establish the beat estimate of core damage.
(1) The containment Ili range dome monitors (calibrated to Xe-133 equivalent) should be used to estimate the extent of core damage and/or the containment activity, using Figure 5.
(2) Using the incore thermocouples, determine if fuel overheating / melt may have occurred. Elevated fuel temperatures (>2370 F), may release reasonably large quantities of cesium. At even higher temperatures, (5200 F) liquefaction or melting of fuel may occur, with release of isotopes such as tellurium and ruthenium. The presence of tellurium and ruthenium does not prove that melt has occurred, since under some conditions, these isotopes can also be released before melt, however, the absence of them is a good indicator that melt has not occurred.
(3) Loss of subooling margin should be indicative of j
saturation conditions in the core and core uncovering.
I IBM l
l
F3-17 Rev. 1
'Page 6 (4) The RCS and the containment atmosphere hydrogen concentrations should be check, which would indicate zirconium degradation.
5.7 If any discrepencies occur between calculations and other plant indicators, recheck both the indications and calculations.
6.0 REFERENCES
6.1 WASil-1400, APPENDIX VII O
1 0
IBM
F3-17 Y
Rev. 1 Page 7 r"%
FIGURE 1 i
t
\\,
I CORE NUCLIDE CORRECTION FACTOR DETERMINATION (1) PLOT POWER HISTORY FOR PREVIOUS 30 DAYS TO TIME OF ESTIMATED CORE DAMAGE 100 80 60 1
x 20 0
-30
-20
-10 0
+10
+20
/'"'
TIME (DAYS)
(
l I
l NOTE: Power reductions and return to power l
l levels which occur in less than 24 l
l hours should be ignored. Assume an l
l average power level for these l
l calculations.
l l
l (2) To correct for core radioisotope inventory if fuel damage is suspected to have occurred during times of any power level (except 0%) where the power level has not changed by greater than 110% within the last 30 days, use the following core nuclide correction factor (CNCF):
CNCF = % REACTOR POWER 100 %
(3) To correct for core radioisotope inventory when power changes have occurred (i.e. power history does not fit situation described in #2 above), perform the following:
O IBM
F3-17 '
,Rev. I f
Page 8 l
I I
I l
NOTE: t= The niedian time to make a power l
l change plus the time after the power l
l change, in days.
l 1
1 I
I l
NOTE: A= Decay Cgnstant For Particular Isotopel l
in Days l
A Y'
I-131 A
"Y" Xe-133 l
l A.
% POWER =
tiedian Time For Power Change =
HOURS Time At New Power Level =
HOURS TOTAL TIllE =
IIOURS+24:
DAYS
^^
(% POWER)e
+(NEW% POWER)(1-e
)=
% INVENTORY
{
)
B.
% INVENTORY FR0ff ABOVE =
t!edian Time For Power Change =
HOURS Time At New Power Level =
HOURS TOTAL TIME =
HOURS 24=
DAYS
(% INVENTORY)e -
(NEW1 POWER)(1-e -
)=
+
%1NVENTORY C.
% INVENTORY FR0tt ABOVE =
tiedian Time For Power Change =
HOURS l
Time At New Power Level
=
HOURS TOTAL TIME =
HOURS +24=
DAYS
^^
(% INVENTORY)e
+(NEW% POWER)(1-e "
)=
% INVENTORY D.
CONTINUE AS ABOVE UNTIL % INVENTORY IS CALCUATED AT ESTIMATED l
I TIME OF CORE DAMAGE.
E.
CORE NUCLlDE CORRECTION FACTOR (CNCF) = % INVENTORY AT TIME OF DAMAGE 100%
e L.
F3-17 Rev. 1
.Page 9
/
T
\\v/
FIGURE 2 TOTAL INVENTORY OF SELECTED RADIONUCLIDES IN THE NUCLEAR REACTOR EQUILIBRIU!! FULL POWER VALUES RADIOACTIVE INVENTORY RADIONUCLIDE SOURCE (curies)
HALF-LIFE (days) 5 Cobalt-58 4.04x10 71.0 5
Cobalt-60 1.48x10 1,920 Krypton-85 2.90x10 3,950 7
Krypton-85m 1.25x10 0.183 7
Krypton-87 2.45x10 0.0528 7
Krypton-88 3.53x10 0.117 4
Rubidium-86 1.37x10 18.7 7
Strontium-89 4.84x10 52.1 Strontium-90 1.93x10 11,030 7
Strontium-91 5.69x10 0.403 6
Yttrium-90 1.99x10 2.67 7
Yttrium-91 6.26x10 59.0 7
Zirconium-95 7.97x10 65.2 7
Nobium-95 7.97x10 35.0 b
Molybdenum-99 8.53x10 2.8 7
Technetium-99m 7.39x10 0.25 Ruthenium-103 5.69x10 39.5 7
Ruthenium-106 1.31x10 366 7
Tellurium-127 3.02x10, 0.391 5
Tellurium-127m 5.69x10 109 7
Tellurfum-129 1.59x10 0.048 7
Tellurium-129m 2.73x10, 0.340 6
Tellurium-131m 6.83x10 1.25 Tc11urium-132 6.26x10 3.25 7
Iodine-131 4.38x10 8.05 Iodine-132 6.26x10 0.0958 7
Iodine-133 8.53x10 0.875 Iodine-134 9.67x10 0.0366 7
Iodine-135 7.97x10 0.280 7
Xenon-133 8.53x10 5.28 1.76x10f Xenon-135 0.384 Cesium-134 3.87x10 750 6
Cesium-136 1.54x10 13,0 6
Cesium-137 2.45x10 11,000 7
Barium-140 8.53x10 12.8 7
Lanthanum-140 8.53x10 1.67 7
Cerium-141 7.97x10 32.3 Cerium-143 6.83x10 1.38 Ce ri um-144 4.38x10 284 7
Praseodymium-143 6.83x10 13.7 IBH
- s..
__Q F3-17
~
Rev. I Page 10 l
I FIGURE 3 CAP RELEASE COMPONENT VALUES FISSION GAP GAP TOTAL CAP PRODUCT RELEASE RELEASE RELEASE SPECIES FRACTION FRACTION VALUE Xe, Kr 0.03 (8) 1 0.03 I-Br 0.05(")
1/3 0.017 C)
C) 1/3(C)
Cs, Rb 0.15 0.05 C}
Sr, Ba 0.01 10 '(d) 0.000001
~
Te, Se, Sb 0.10 ")
-3(d) 10 0.0001 Negligible (^)
Others (a) Values can be higher or lower by a factor of 4
{
I (b) Value can be higher by a factor of 2 or lower by a factor of 4 (c) Values can be higher or lower by a factor of 3 (d) Values can be higher or lower by a factor of 100 (e) While no numerical value was developed for these various species, the number should not exceed that used for s t ron ti um-ba ri um.
O IBM
. ~ ~.
f t.
k o
y3 17
! 'y Rev. 1 l-Page.11 i
FIGURE 4 i
HELTDOWN RELEASE COMPONENT VALUES i.
i i
t j
j' RELEASE RANGE.
BEGT' ESTIMATE l
ELEMENTS (PERCENT)
(PERCENT) k 1
I j.
Xe, Kr 50-100 90
}
l I,~Br 50-100 90 l
t' j
Cs, Rb 40-90 80 r
t Te(")
5-25 15 I
f Ba, Sr 2-20 10
{
Noble Metals (b) 1-10 3
Rare Earths (C) -
.01-1 0.3 Zr, Nb
.01-1 0.3 i
t 1
[
a j
2 f
(a)
Includes Se, Sb g
(b) Includes Ru, Rh, Pd, Mo, Tc j
j (c)
Includes Y, La, Ce, Pr, Nd, Pm, Sm, Eu, Np, Pu I-I i
i I
i 1
l i
}
l l
l 5
r IBM i
t
?
I j
..__..__,._.--._,..,-m-,,.-...-_.
J
'F3-17
=
Rev.
- 1 FIGURE 5 Pag 3 12 CONTAINMENT DOSE RATE VS TIME
{ 10 9 8
10
.J
.. !.N...
..l....{...
i.... 4..- )..
- .i.;.>.;
....?.
.e "). 5
..i.:.i.e...
e.
s
.S i.:
...i - -. ' '
r 3......>...
..u.
. <.. a..
...... u... m.
- . n
..,...a.,
.,....,+..
.s
.s
..n.g NOTE: Reg. Guide 1.4 assumesi.
...h...... <....r e>
homogeneous atmosphe-:
.'.' : U.
ric mixture of:
7 100% Core equilibrium.k 10........<......:.
.....;...... m.:..
noble gas invent.:
E.
.........9....
..s
... 3
... 4... >. <.... v. :. s. -
........>.,.<..<.n
.,.3.<...,,.-.
....s...>..
.c...
..g.g.
., e:.:
ory s
3 50% Core e uilibrium
.....; 100.%. Regulatory G. uid. e 1.4
)
halogen invent-ory
- . e.
..:..u..m.
.:. a.
t.:.
1% All other fission products
,10 W 6
10...,.....>..>.,-
d b
.........,s.....
..~.....4..
3,.
t
.....e...>.
m.
.....e..<.
.. >................s....
r........,.<......
........ ~...... e.
- ....3 e.:.
4.. r >.:. n.i g
u
.........u...n.
. ~.........
,.c,
.........s....
...s..
u e
..:.. 4.... u.>..
.1.0..%...Regula to ry m
v m
u e h3 I
....... n.:,....
p
.g
.. <..:. i..:.:. ;
... >. e. <.. g
...:. n o
,a, g
g 105
.1 t
m r
~
..........>,r,
...;..,..s g
...... a.
..g
,.....3.....
.:.3 3
.,...>. c. ;. y u...
L e
1
...s..
a
[
] 1%. Regulatory n
+ ' < 7 pit,"
y M u+
i >:1 E
+'
H'
+
9 g
i 1.4 4 i.q i.
iHi:
- : + Mi
- + '-
E
., ' "i"t. ".;uide.
t:3 e,
..s...
.~.
34
_10 10 s
r.
. 5
,z, i
H 3
+ ;+
p
..~. t a. s p:,-.
...t***...
p.$.; c..;.! :.
- 5*
~
"..........,.t?,.P.
.. M. s..e..M t, ;-
g i
..s..
E i
j
.4...>.4....*,>
- 4. ;. H
..{.;
..).
s*.}..,;<<g.
,..,;{
, 39 Z'
l g
.l...:... g..:.. > 4..> ; l
..i..;. :. 4 /.g
....>.<.4..
.).....{.; y....
...t.:. ; ;
p y
.y 4
p g
U o
..:... u.>,
...;.; e..
O
~.
10' 3
10
...;...>.4
.i.
.. + ~.. ~.
. a. -.. ~.. -
.. m..
,. ~.. ~... ~...
, +
.C
- 4. s
. >...:. ; e 3
1
?**
. 4' ??:
? -; : : M t :
- l..-
...,........t'.*:
- t..
~- V.
t~' '.n.>
1% Fuel Defect
.s.
.'s.~
..s
... s
.,-- g
- ...... 9
.e; 4..
.., s.:
- 4..... :. n z:g{
1 2
,h v
r.
10 q
...r
(.
...;.... : 1.;
i.;.,.
i s;:
)
3
.]
{
. a
. ;. u.:p
. 1
...,1
.r 3
s 0
1 r10 10 1'
O.1
~~
1.0 10 100 1000
' id,000 TIME (HOURS AFTER SHUTDOWN)
PAGE 1 OF 6 l
l EMERGENCY PLAN IMPLEMENTING l
,em l
PRAIRTE ISLAND NUCLEAR l PROCEDURES l
(v')
l GENERATING PLANT l
l l NORTHERN STATES POWER COMPANY l Number:
F3-22 Rev: 2 l
l l
Ilistory Copy l l
n n
Retention Time:
Lifetime l
l M[
l TITLE:
l l
Supt,- Ra'd Protpction l
PRAIRIE ISLAND RADIATION l
l Approved By:
(c/,//)/
. u.
l PROTECTION GROUP RESPONSE l
l
/i, f l
TO A MONTICELLO EMERGENCY l
f l
Plant Manager l
1 l
OC Date:
l
~/,2- /tl1-ff*A l
l l
l l
l 1.0 PURPOSE l
l l
l When an emergency occurs at Monticello resulting in a significant l
l offsite release, the Prairie Island Radiction Protection Group SHALL l
l be requested to respond with personnel and equipment to support the l
l Monticello Radiation Protection Group. This support allows the l
l Monticello personnel to concentrate their efforts in performing onsite l
l sampling and monitoring and relieves them of the offsite monitoring l
l requirements.
l l
l l
The purpose of this instruction is to describe the personnel, equip-l l
ment, and procedures required to respond to a request for Radiation l
(T l
Protection assistance at Monticello.
l Q
l l
l l
l 2.0 APPLICABILITY l
l l
l This instruction SilALL apply to Shift Supervisors, Supt Radiation l
l Protection, and all Radiation Protection Group members.
l l
l l
l l
3.0 PRECAUTIONS l
I l
l 3.1 Extra survey team kits are available at the Monticello EOF in l
t l
case of equipment ' failure or if an additional field team is l
l required to be activated.
l l
l l
3.2 Check operability of all portable radios and source check all l
l meters prior to departing the Prairie Island plant site.
l l
l l
1 l
4.0 EQUIPMENT AND PERSONNEL REQUIRED l
l l
l 4.1 Two (2) offsite survey team sample kits.
l 1
l l
4.2 Two (2) vehicles (NSP or personnel) for transport to Monticello.
l 1
l l
l Imi l
l O
l l
l l
IBM i
"F3-22,
R;v.- 2
,Page 2 4.3 Five (5) members of the Radiation Protection Group (four Radiation Protection Specialists and one person qualified to serve as the l
Radiation Protection Support Supervisor) are required to respond to a Monticello Emergency, to perform offsite surveys, and staff the Radiation Protection Support Supervisor position at the EOF.
4.4 Personnel TLD's and dosimeters.
5.0 PROCEDURE 5.1 When an emergency occurs at Monticello, the call for Radiation Protection Group assistance will be received in the Control Room by the Shift Supervisor.
(1)
If the call for assistance occurs during normal working hours, the Shif t Supervisor SilALL notify the Superintendent, Radiation Protection or his designee.
The Superintendent, Radiation Protection or his designee SHALL direct the Radiation Protection Supervisor and/or Coordinators to mobilize a response team.
(2)
If the call for assistance occurs during off-normal working hours, the Shift Supervisor S!!ALL contact the Superintendent, Radiation Protection or his designee at home. The Superin-tendent, Radiation Protection or his designee SliALL then request the Shift Supervisor to contact the members of the Radiation Protection Group, requesting four team members and one supervisory member (or as otherwise requested) to report to the plant site.
(See the Prairie Island Radiation Protection Group Call List, Attachment A).
l l
l NOTE:
The Shif t Supervisor may request the Shift l
l Emergency Communicator to assist in notifying l
l and activating the Radiation Protection Group l
l to form a response team to Monticello.
l l
l 5.2 All personnel requested to respond to the Monticello emergency SilALL assemble at the plant site to pick up to vehicles and equipment (as listed on Attachment B).
(1) Tuo (2) vehicles should be used to transport personnel to Monticello and to perform offsite surveys.
1 I
l NOTE.
Other transportation arrangements may be made l
l if necessary as long as all necessary equipment l l
and personnel arrive at Monticello l
l expeditiously.
l I
I IBM L
~
Y3-22 Rev. 2 P:g2 3 (2) Two (2) complete offsite survey team sample kits SHALL be l
/' 'N taken to Monticello.
(
i v
l l
l NOTE: Response check all meters prior to departing l l
the Prairie Island Plant site.
l l
l (3) Two (2) portable radios with mag-mount antennas.
l l
l NOTE: Verify operability of the portable radios l
l prior to departing the Prairie Island l
l plant site.
l l
l 5.3 The designated Radiation Protection Group members shall proceed to Monticello.
l l
l NOTE: For reference to routes to Monticello and the l
l location of the Monticello EOF, refer to the l
l Minnesota road map and Monticello survey map, l
l located in the field team survey kits.
l b(N l
l 5.4 When approaching the boundary of the Monticello 10 mile EPZ, attempt to contact the Monticello EOF using the portable radio.
Identify yourself as the Prairie Island Survey teams.
5.5 If determined from the initial radio contact with the Monticello EOF that the plume may be encountered while enroute, conduct a search for the plume, in accordance with EPIP 1.1.10 and proceed directly to the EOF.
5.6 Upon arrival at the Monticello EOF, contact the Emergency Manager or his designee at the Nearsite EOF for further instructions.
5.7 Perform the required offsite surveys and dose assessment as l
required by the Emergency Manager in accordance with EPIP 1.1.10 "Offsite Surveys" and EPIP 1.1.11 " Accident Assessment."
l l
l l
l NOTE: All field sample analysis SHALL be performed in l
l the EOF Count Room by Monticello Radiation l
l Protection Specialists.
If this facility becomes l l
unavailable, make arrangements to transport the l
l samples to the Monticello Plant Count Room (if l
l available) or to Prairie Island.
l tO l
l IBM a+ s m -
e---,4 m.e.
~
'F3-22, R;v. 2
,Page 4 5.8 Additional Prairie Island personnel should be augmented as soon as possible to supply short term 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> per day coverage (survey team positions and Radiation Protection Support Supervisor position).
l l
l NOTE:
Long term coverage for offsite survey teams shall l
l be provided by contract Health Physics personnel.
l l
Arrangements for contract services will be handled l
l by the Corporate Emergency Organization at the EOF.
l l
l 5.9 Continue with all assigned duties until relieved by the Monticello l
Emergency Manager.
O O
IBM
(a.
F3-22 Rtv. 2
~
Page 5 ATTACHMENT A PRAIRIE ISLAND RADIATION PROTECTION GROUP CALL LIST I
l l NOTE: All phone numbers for the Radiation Protection Group are l
l programmed on the auto-dialers in the TSC.
l l
l Radiation Protection Support Supervisor (1 Required)
NAME gY g
Radiation Survey Team Members (4 Required)
I i
_e
's
\\
mg> 2.
i acu" 6
IBM I
f
-FS-22 i
Rr,v. 2' Pcg2 6 ATTACIDIENT B O
MONTICELLO EMERGENCY SUPPORT EQUIPMENT LIST 1.
Personal TLD's and self-reading dosimeters (rezero) 2.
Vehicles to be used for offsite monitoring purposes 3.
Two (2) emergency survey team kits 4.
Two (2) portable radios with mag-mount antennas t
0 4
0 IBM
.