ML20107K519
| ML20107K519 | |
| Person / Time | |
|---|---|
| Site: | Limerick  |
| Issue date: | 10/04/1984 |
| From: | PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC |
| To: | |
| Shared Package | |
| ML20107K496 | List: |
| References | |
| PROC-841004-01, NUDOCS 8411130173 | |
| Download: ML20107K519 (18) | |
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3843067870 Page 1 of 4
' Revision 12 10/04/84 EMERGENCY PLAN PROCEDURE INDEX PROCEDURE REV.
DATE SIGNED DATE OF LAST NUMBER
-NO.
TITLE BY SUPER.
PERIODIC REVIEW EP-101 2
Classification of Eme rg enc ie s 09/27/84 EP-102 4
Unusual Event Response 07/20/84 I
EP-103 4
Alert Response 07/20/84 EP-104 4
Site Emergency Response 07/20/84 EP-105 4
General Emergency Resconse 07/20/84 EP-106 1
Written Summary Notification 06/08/84 EP-110 2
Personnel Assembly and Accountability 06/08/84 EP-120 1
Site Emergency Coord inator 06/08/84 EP-201 1
Technical Support Center (TSC) Activation 06/08/84 EP-202 2
Operations Support Center (OSC) Activa tion 09/25/84 EP-203 2
Emergency Operations Facility (EOF) Activation 09/27/84 EP-208 2
Security Team Activation 06/08/84 EP-210 1
Dose Assessment Team 06/08/84 EP-220 CANCELLED EP-221 1
Personnel Dosimetry, Bioassay, and Respiratory Protection Group 06/08/84 EP-222 2
Field Survey Group 07/17/84 EP-230 3
Chemistry Sampling and Analysis Team Activation 07/20/84 i
EP-231 4
Operation of Post-p A c d nt Sampling Systems Sjf(f.2Y Wine b/i'.a== m W EP-232 CANCELLED EP-233 3
Retrieving and Changing fe{- jg j
Sample Filters and
[n tj Cartridges from the
%7 Containment Leak Detector During Emergencies UlU IO 7 k d)dd ki h h nW u nt.sv
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B411130173 841025 PDR ADOCK 05000352 F
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Page 2 of 4
' Revision 12 y
10/04/84 EMERGENCY PLAN PROCEDURE INDEX
-i PROCEDURE REV.
DATE SIGNED DATE OF LAST NUMBER NO.
TITLE BY SUPER.
PERIODIC REVIEW EP-234 3
Obtaining Containment Gas Samples from the Containment Leak Detector During Eme rgenc ie s 07/20/84 7
^
EP-235 3
Obtaining Reactor Water Samples from Sample Sinks Following Accident Conditions 07/20/84 EP-236 3
Obtaining Cooling rower Blowdown Line Water Samples Following
-Radioactive Liquid Release after Accident Cond itions 08/07/84 EP-237 3
Obtaining the Iodine /
Particulate and/or Gas Samples from the North Vent Wide Range Gas Monitor (WRGM) 07/20/84 EP-238 3-Obtaining Liquid Radwaste Samples from Radwaste Sample Sink Following Accident Conditions 07/20/84 EP-240 2
Obtaining Off-Gas Samples from the Air Ejector / Holdup Pipe Discharge Sample Station 06/08/84 EP-241 4
Sample Preparation and Handling of Highly Radioactive Liquid F
Samples 10/04/84 EP-242 3
Sample Preparation and Handling of Highly Radioactive Particulate
- Filters and Iodine Cartridges 07/20/84 EP-243 4
Sample Preparation and Handling of Highly Radioactive Gas Samples 08/06/84 EP-244 O
Of fsite Analysis of High Activity Samples 06/08/84
'EP-250 1
Personnel Safety Team Activation 06/08/84 I
EP-251 1
Plant Survey Group 06/08/84 n-..
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Page 3 of 4
' Revision 12 10/04/84 EMERGENCY PLAN PROCEDURE INDEX PROCEDURE REV.
DATE SIGNED DATE OF LAST NUMBER NO.
-TITLE BY SUPER.
PERIODIC REVIEW EP-252 2
Search and Rescue /First Aid 07/20/84 EP-254 1
Vehicle and Evacuee Control Group 06/08/84 i i EP-255 1
Vehicle Decon tamina tion 06/08/84
~
EP-260 1
Fire and Damage.
Team Activation 06/08/84 EP-261 1
Damage Recair Group 06/08/84 EP-272 1
Philadelphia Electric
-Company Officials 06/08/84 EP-273-2 Limerick Station Supervision Call List 10/04/84 EP-275 CANCELLED EP-276 1
Fire and Damage Team Phone List 06/08/84 EP-277 1
Personnel Safety Team Phone List 06/08/84 I
EP-278 0
Security Team Phone
) '
EP-279 1
Emergency Operations List 12/27/83 Facility (EOF) Group Phone List 06/08/84
[
EP-280 2
Technical Support l
Center Phone List 09/27/84 l
EP-282 1
Government and Emergency Management Agencie s 06/08/84 p
EP-284 2
Company Consultants and Contractors L
Phone List 09/27/84 EP-287 1
Nearby Public and Industrial Users of Downstream Water 06/08/84 EP-291 2
Staffing Augmenta tion 09/27/84 i
EP-292 3
Chemistry Sampling and Analysis Team Phone List 09/27/84 EP-294 1
Dose Assessment Team Phone List 06/08/84 EP-301 0
Operating the Evacuation Alarm and River Warning System 11/11/83 i
f,,,
Page 4 of 4
, Revision 12 10/04/84.
EMERGENCY PLAN PROCEDURE INDEX PROCEDU RE REV.
DATE SIGNED DATE OF LAST NUMBER NO.
TITLE BY SUPER.
PERIODIC REVIEW EP-303 2
Local Evacuation 04/02/84
-EP-304 2
Partial Plant Evacuation 07/09/84
-EP-305 2
Site Evacuation 09/25/84 EP-306 0.
Evacuation of the
-Information Cente r 12/27/83 EP-307_
1 Reception and Orientation of Support Personnel 06/08/84 EP-312 0
Radioactive Liquid Release 11/30/83 EP-313 1
Distribution of Thyroid.
Block ing Tablets 06/08/84 EP-315 0
Calculation of of fsite.
Doses During a Radiological Emergency Using RMMS in the funual Mode 07/17/84 EP-316 1
Cumulative Population and Near Real-Time Emergency Dose Calculations for Airborne Releases Manual Method 07/24/84
[
EP-317 0
Determination of Protective Action l
Recomme nd ation s 12/27/83 EP-318 0
Liquid Release Dose Calculations Method for Drinking Water 11/30/83 EP-319 0
Fish Ingestion Pathway Dose Calculation 11/30/83 EP-325 0
Use of Containment Radiation Monitors to l
Esti' mate Release Source l
Term 12/29/83 EP-330 2
Emergency Response Facility Habitability 07/20/84 EP-401 1
Entry for Emergency Repair and Operations 06/08/84 EP-410 1
Recovery Phase Imple menta tion 06/08/84 EP-500 1-Review and Revision g
of Emergency Plan 06/08/84 O'
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,1 3843067880 EP-241 Rev. 4 Page 1 of 9 T
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PHILADELPHIA ELECTRIC COMPANY LIMERICK GENERATING STATION EMERGENCY PLAN IMPLEMENTING PROCEDURE EP-241 SAMPLE PREPARATION AND HANDLING OF HIGHLY RADIOACTIVE LIQUID SAMPLES.
1.0 PURPOSE 2
The purpose of this procedure is to provide guidelines for-sample preparation and handling of highly radioactive liquid:-. -
' samples following accident conditions.
2'.0 RESPONSIBILITIES 2.1 The Chemistry Sampling and Analysis Group Leader is responsible for:
a.
Determining the processing procedure.
b.
Determining the method and location of e
saniple storage and/or disposal as required.
c.
Having group member (s) exposure monitored in conjunction with Health Physics guidance to ensure that the Administrative Exposure
-Guidelines are not exceeded.
d.
Directing group member (s) and the assigned Health Physics technician to perform the
~"
necessary steps of this procedure and to report-back the results of the sample
~
analysis as spon as they become available.
2.2' The Health Physics technician is responsible for:
a.
Providing constant coverage for the necessary steps of this procedure.
b.
Monitoring the extremity dose to the hands during sample handling.
Monitoring labora c.
Li.
d.
Conducting a pre-jo efg ning :
f ag 1.
RWP requirements.
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- - l' EP-241 Rev. 4 Page 2 of 9 TJY/RGH/mla 2.
Radiological concerns and precautions
-(ALARA).
3.
The use of staytimes to ensure that exposures do not exceed limits.
2.3 The Chemistry Sampling and Analysig Group members are
_ responsible for:
.a.
Preparing the hot lab post accident sample preparation station to accept the sample.
[
b.
Performing sample dilution-and. analysis
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requirements as.specified.by-the Chemistry..
Sampling and Analysis Group Leadet.
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c.
Following RWP and Health Physics requirements as specified by the Health Physics technician.
~-
- 3. 0~
. APPENDICES 3.1
-EP-241-1 Data Sheet f
'4.0 PREREQUISITES 4 '.1 -
Ventilation in the sample preparation hood is operating.
15. 0 SPECIAL EQUIPMENT 5.1 Liquid sample vials.with septum.
- 5. 2 '
Appropriate liquid microsyringes.
5.3 Rubber gloves.
I 5.1 Plastic ' sample-bags.,
e-5.5 Sample handling tongs.
5.6
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0.OlN nitric acid solution (500 ml).
5.7 Eye protection 9
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EP-241 Rev. 4 Page 3 of 9 TJY/RGH/mla 6.0 SYMPTOMS m
' None
~7.0 ACTION LEVEL 7.1 This pr'ocedure shall be implemented when preparing or handling highly radioactive liquid samples during an emergency situation.
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8.' O
-PRECAUTIONS In all steps of this procedure, keep exposures ALARA.
8.1 9.0'
' PROCEDURE 9.1 ACTIO'S
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9.1.1 Determination of processing procedure.
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9.1.1.1 The Chemistry Sampling and Analysis Group s_
-4 Leader shall obtain the appropriate EP-M Sample Data Sheet and select one of the
'r fc11owing processing procedures based on the t
radiation levels of the sample.
.a.
Send the sample off-site for analysis per EP-244 Offsite Analysis of High Activity Samples.
b.
Place the sample in temporary storage for future analysis.
c.
Analyze the sample on-site.
COMPLETE SECTION I OF APPUNDIX EP-241-1 5
9.1.1.2 The Chemistry:, Sampling and Analysis Group-Leader shall determine the following sample parameters based on sample dose rates and analysis requirements.
a.
Analysis to be performed.
b.
Order of analysis e
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EP-241 Rev. 4 Page 4 of 9 TJY/RGH/mla s,
c.
Number and magnitude of dilutions d.
Analysis sample volume desired PH DETERMINATION CANNOT BE PERFORMED ON DILUTED SAMPLES.
COMPLETE SECTION II OF APPENDIX EP-241-1.
9.1.2 Pre-Job Briefing 9.1.2.i The Chemistry Sampling and Analysis Group p'
Leader, Health Physics Technician and the Chemistry Sampling and Analysis Group-Members shall assemble and review this procedure.
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9.1.2.2-The Chemistry Sampling and Analysis Group Leader shall direct group members to perform the necessary steps of this procedure.
SECTION 9.1.3 AND 9.1.4 SHOULD BE PERFORMED AS EARLY AS POSSIBLE.
THE SAMPLE MAY NOT BE PLACED IN THE SAMPLE PREPARATION STATION UNTIL THESE SECTIONS HAVE
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BEEN COMPLETED..
9'.1.2.3 The Health Physics Technician shall brief J.
group members on:
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a.
RWP requirements b.
Radiological concerns and precautions (ALARA) c.
Staytimes and exposure limits i
9.1.3 Preparation of sample preparation station for liquid samples o
9.1.3.1 The Chemistry Sampling and Analysis Group I
Member (s) shall. prepare the dilution vials b
(with appropriate labe'ls) per appendix EP-L 241-1 and place the vials in the appropriate l
'y dilution vial positions-in-the sample, - ----
(
preparation station.
Place lead caps over the vials (liquid position).
THE LEAD CAPS MAY BE POSITIONED FOR GAS OR LIQUID
~~
SAMPLES.
FOR THE PURPOSE OF THIS PROCEDURE THEY SHALL BE IN THE LIQUID POSITION w
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-l EP-241 Rsv. 4 Page 5 of 9 TJY/RGH/mla S
9.1.3.2 The Chemistry Sampling and Analysis Group Member (s) shall ensure that the necessary liquid micro syringes (with needles), sample handling tongs and sample analysis containers are in place and available to fulfill dilution and analysis requirements per appendix EP-241-1.
9.1.3.3 The Chemistry Sampling and Analysis Group Member (s) shall ensure-that at least one pair of plastic gloves and two plastic sample bags are'available for each gamma.
analysis-to be performed.~.
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9.1.4 Preparation of ahalysis instrumentation.
9.1.4.1 The Chemistry Sampling and Analysis Group
^
Member (s) shall insure that the appropriate analysis procedures specified in appendix
,p EP-241-1 are available and have been L's performed to the point that each analysis instrument is ready to accept the sample for-l n analysis.
THE FOLLOWING STEPS ARE TO BE PERFORMED BY THE-CHEMISTRY SAMPLING AND ANALYSIS GROUP MEMBER (S)
(UNLESS OTHERWISE SPECIFIED) AND REQUIRE CONSTANT' HEALTH PHYSICS MONITORING.
LEAD BRICKS IN THE SAMPLE PREPARATION STATION HAVE BEEN MODIFIED TO ACCEPT THE SAMPLE.
THE LEAD BRICK LABLED " SAMPLE VIAL A" HAS BEEN MODIFIED TO ACCEPT A s
GAS OR LIQUID SAMPLE FROM THE PASS.
THE LEAD BRICK LABELED " SAMPLE VIAL B" HAS BEEN MODIFIED TO ACCEPT A LIQUID SAMPLE FROM THE REACTOR COOLANT SAMPLE STATION.
r.
9.1.5 Transport of sample from transport cask to sample preparation station..
9.1.5.1 Remove the lead cap from the lead brick to accept the sample.
9.1.5.2 Position the sample transport cask as'close to the Sample Preparation Station as possible.
9.1.5.3 As quickly and carefully as is possible, remove the sample from the transport cask and place it in the lead brick.
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.. m..y c-l EP-241 Rev. 4 Page 6 of 9 TJY/RGH/mla 9.1.5.4 Quickly place t'Te 1ead cap over the sample in the " liquid" position.
9.1.5.5 Retreat frcm the Sample Preparation Station and~ allow the. Health Physics Technician co take dose rate readings.
THE HEALTH PHYSICS TECHNICIAN SHALL INFORM THE CHEMISTRY SAMPLING AND ANALYSIS' GROUP MEMBER OF THE SAMPLE PREPARATION STATION' DOSE RATES AND STAY TIME.
9.1.6 Sample Dilution (if dilutions are not to be performed,_ proceed to step 9.-l.7)._
DILUTIONS TO BE MADE ARE DESCRIBED IN APPENDIX EP-241-1.
ALL ACCESSORIES USED IN THE DILUTION PROCESS SHALL BE MAINTAINED BEHIND THE LEAD SHIELD
~'
WALL ONCE THEY HAVE BEEN CONTAMINATED.
9.1.6.1 Insert the syringa thru the sample access hole in the lead cap then thru the sample vial septum and into the sample to be diluted.
Withdraw the predetermined (appendix EP-241-1)' aliquot from the sample vial.
?,-.
Withdraw-the syringe from the' sample and 9.1.6.2 I
insert it in the predescribed method into the next sequential dilution vial to accept the sample (Dilution Vial #1, #2 etc.).
Inject the aliquot into the dilution vial.
9.1.6.3 Withdraw the syringe from the sample.
Separate the needle and the syringe and discard them in the shielded waste container.
9.1.6.4 Remove.the lead cap over the diluted sample.
Grasp the' sample vial securely with the
~
sample handling tongs and raise the vial out-of the lead brick (but not above the. lead shield wall).
L 9.1.6.5
'Using-the tongs,' swirl the sample viale m enough to ensure adequate mixing, replace-the' vial.
Replace the lead cap'(liquid position).
9 1 6.6 If further dilutions are necessary (per 2
appendix EP-241-1) repeat steps 9.1.6.1 thru 9.1.6.5, always beginning with the last dilution vial to accept a sample aliquot.
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l EP-241 Rev. 4 Page 7 of 9 TJY/RGH/mla 9.1.6.7 When desired dilution is reached, the Health l
Physics Technician shall determine the dose rate of the diluted sample.
9.1.6.8' If the diluted sample dose rate is unacceptable, repeat steps 9.1.6.1 thru 9.1.6.5 until dose rate is acceptable.
Indicate additional' dilutions on appendix EP-241-1.
9.1.7 Sample Cup Preparation 9.1.7.1 For each analysis.to be performed (appendix.
EP-241-1) use -the syringe transfer method (step 9.1.6.1) to sequentially obtain the volume of sample required (Appendix EP-241-
- 1) from the appropriate diluted / undiluted sample source (appendix EP-241-1).
3 I
9.1.7.2 Inject the appropriate sample aliquot into its analysis cup.
DUE TO THE AMOUNT OF SAMPLE BEING REMOVED FROM THE BOTTLE IT MAY BE NECESSARY TO VENT THE BOTTLE BY PLACING A NEEDLE THRU THE SEPTUM.
DUE TO THE SMALL VOLUME OP SAMPLE USED TO PERFORM PH AND THE EFFECTS CO2 ABSORBTION WILL HAVE ON THE ANALYSIS, THE PH SHOULD BE DETERMINED IMMEDIATELY AFTER THE SAMPLE IS PLACED IN ITS SAMPLE CUP.
9.2 FOLLOW-UP 9.2.1 Perform the predetermined an& lysis (Appendix EP-241-1) in the predetermined sequence (Appendix EP-241-1).
9.2.2 Disposal of samples and contaminated materials THE STORAGE AND/OR DISPOSAL OF THE UNUSED PORTION OF THE ORIGINAL SAMPLE WILL BE AT THE DISCRETAON OF THE CHEMISTRY SAMPLING AND ANALYSIS GROUPS LEADER AND THE-HEALTH PHYSICS TECHNICIAN.--- - -
9.2.2.1 The remaining samples and contaminated sample cups shall be disposed of in the shielded waste container.
The sample handling tongs shall be used in the transfers.
The samples and sample cups should be kept behind the lead shield wall as much as is possible.
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9, I
EP-241 Rev. 4
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Page 8 of 9 TJY/RGH/mla-9.2.2.2 Transfer and disposal of the shielded waste contciner will be at the discretion of the Health Physics Technician and the Chemistry Sampling and Analysis-Group Leader.
10.0 REFERENCES
10.1 CH-901 Determination of Ions by Ion Chromatograph during Post Accident Conditions.
i Determination of--PH.in: Low Vo-lume Water 10.2 - CH-903-
. Samples.duringePost Accident Conditions.~a-10.3 Ch-904-Determination of Metals by DCP during Post Accident Conditions.
10.~4 CH-905 Determination of Gamma Isotopic activity during Post Accident Conditions.
Determination of chloride by Specific ton 10.5 Ch-906 during Post Accident Conditions.
10.6 CH-907 Determination of-Boron at ppm levels during VS Post Accident Conditions.
.4,
f n. _
10.7 EP-230 Chem'istry Sampling and' Analysis Team Activation l
10.8 LGS FSAR 11.5.5, Post-Accident Sampling System e
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TJY/RGH/mla Appendia EP-241 *
~ Data Sheet I.
p-Sample Source 8
Processing Procedures
( x)
Grab Sample Point A. Sent Offsite for Analysis (l)
('
)
Initial Sample Volume 8.
Placed in Temporary Storage (1),(2)
(.
)
Initial Contact Dose Rate C. Analyzed on Site
(
)
Sample Date/ Time
/
II.
l (4)
(5)
(3)
Total Analysis Acceptable Order of Proceduro Magnitude Number of Dilution Sample Analysis Analysts Analysis Number of Dilutions Dilutions Factor Volume Dose Rate 1
2 3
4 5
6 I
(1) If this method is used sign and date this data sheet and terminate this procedure.
~
(2) The Chemistry Sampling and Analysis Group Leader shall determine place of storage.
(3) Magnitude of Dilutions (4) If original sample is (5) Analysts Sample Volume 10:1
= 1 mi sample: 9 ml of 0.0IN a small volume diluted Nitric Acid sample, this dilution
.pH 0.5ml CI (IC) 4 ml 100.3 e I mi sample: 9.9 al of 0.0%
factor s.ust be Nitric Acid considered.
8 (DCP) 4 al (SIE)I ml 1000.1 = 0.01 al sample: 9.99 ml of 0.08 N Hitric Acid Due to the complemity of the dilution and analysis process, it is recommended that the same magnitude of dilution be used for all of the analysis.
MDL's fors Boron Chloride Reactor Coolant Regions of Interest Activity DCP10 ppb ICl_ ppb Activity - 10 uCl/cc to IO Cl/cc Titr._J_ppe SIE_1_ppe Borod - 50 ppe to 1100 ppe Chloride greater than 10 ppe Chemistry Group Leader
/
C emistry Group Member
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l EP-273 Rev. 2 o
3843067890 Page 1 of 4 VA / MPG /mla
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j PHILADELPHIA ELECTRIC COMPANY
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LIMERICK GENERATING STATION EMERGENCY PLAN IMPLEMENTING PROCEDURE EP-273 LIMERICK STATION SUPERVISION CALL LIST 1.0 PURPOSE
{
The purpose of this procedure is to provide information for contacting Station Supervision.-
2.0 RESPONSIBILITIES 2.1 The communicatoE"shall contact Station Supervision.
3~ 0 APPENDICES -
None 4.0 PREREQUISITES None 5.0 SPECIAL EQUIPMENT None
- f. f
' f,f-E N
k 7.0 ACTION LEVEL 7.1 This procedure can be used when it is necessary to contact members of Station Supervision.
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Page 2 of 4 1
VAW/ MPG /mla 8.0 PRECAUTIONS None 9.0 PROCEDURE 9.1 ACTIONS 9.1.1 The communicator shall contact people from the following list as required:
9.1.1.1 STATION SUPERINTENDENT:
Home Work G.
M.
Leitch
~
9.1.1.2 ASSISTANT STATION SUPERINTENDENT!:
J.
F.
Franz
~
9.1.1.3 STARTUP DIRECTOR:
J. W.
Spencer (until Startup) 9.1.1.4 TECHNICAL ENGINEER:
P. J.
Duca 9.1.1.5 ENGINEER - MAINTENANCE:
J.
B.
Cotton 9.1.1.6 ENGINEER - OPERATIONS:
J.
Doering 9.1.1.7 SENIOR EEALTH' PHYSICIST:
R.
W.
Dubiel 9.1.1.8 SENIOR CHEMIST:
~
ppt D1 3-ADMI J T IV3 EERt 9.1.1.9 S
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l EP-273 Rev. 2 Page 3 of 4 VAW/ MPG /mla i
9.1.1.10 PERFORMANCE ENGINEER:
Home Work L.
A.
Hopkins V. J. Cwietniewicz 9.1.1.11 SECURITY ADMINISTRATIVE ASSISTANT-P.
Supplee 9.1.1.12 INSTRUMENTATION & CONTROL ENGI G.
R.
Rainey 9.i.l.13 REACTOR ENGINEER:
K.
W.
Hunt 9.1.1.14 APPLIED HEALTH PHYSICIST:
R. J. Titolo 9.1.1.15 HEALTH PHYSICIST - TECHNICAL SUPPORT:
~
G.
W. Murphy 9.1.1.16 ASSISTANT ENGINEER - MAINTENANCE G. Paptzun 9.1.1.17 SUPV - CHEMIST:
l J.
Sabados 9.1.2 SHIFT SUPERINTENDENT:
9.1.2.1 C.
Gillespie,
9.1.2.2 R.
Hampton or u.m;-w 9.1.2.3 J. Monaghan 9.1.2.4 W.
Tru 9.1.2.5 W.
Barn wg Q[
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Home Work 9.1.3 SHIFT SUPERVISORS:
l 9.1.3.1 G. Paton 9.1.3.2 R. Delaney l
F I
9.1.3.3 W. Russell 9.1.3.4 R. Kennedy 9.1.3.5 W. Stanley 9.1.3.6 M. Cory
10.0 REFERENCES
None e
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UNITED STATES NUCLEAR REGULATORY COMMISSION c.
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November 1, 1984 wAsHiwoToN. D. C. 20555
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50-352/353 Limerick MEMORANDUM FOR:
Chief Document Management Branch, TIDC FROM:
Director, Division of Rules and Records, ADM 1
~
SUBJECT:
REVIEW 0F UTILITY EMERGENCY PLAN DOCUMENTATION The Division-of Rules and Records has reviewed the attached document and has determined that it may now be made publicl available.
/
(d
. M. Felton, Director d[J ivision of Rules and Recor Office of Administration
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Attachment:
'As stated.
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