|
---|
Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARB17848, Startup Test Rept Cycle 7. with1999-09-30030 September 1999 Startup Test Rept Cycle 7. with ML20211Q3361999-09-0707 September 1999 Proposed Tech Specs Removing Current Special Exception Which Precludes Applying Eighteen Month Functional Testing Surveillance to SG Hydraulic Snubbers ML20211H6471999-08-25025 August 1999 Proposed Defueled Tech Specs,Revising Sections 5.6.1,5.7.2 & 5.7.3 & Adding Proposed Section 5.6.4 to Reflect ACs Contained in NUREG-1433 ML20210Q5211999-08-0505 August 1999 Proposed Tech Specs Sections 3.8.3.2,4.6.2.1,4.6.2.2, 4.8.1.1,4.9.12 & Bases Section B 3/4.3.2,B 3/4.6.1.2 & B 3/4.8.4,incorporating Editorial Revs ML20210C6091999-07-16016 July 1999 Proposed Tech Specs Relocating Selected TS Related to Refueling Operations & Associated Bases to Plant TRM ML20206U1041999-05-17017 May 1999 Proposed Tech Specs Section 4.4.6.2.2.e,deleting Reference to ASME Code Paragraph IWV-3472(b) Re Frequency of Leakage Rate Testing for Valves Six Inches Nominal Pipe Size & Larger ML20206M8221999-05-10010 May 1999 Restart Assessment Plan Millstone Station ML20206D1761999-04-27027 April 1999 Rev 1 to Millstone Unit 3 ISI Program Manual,Second Ten-Yr Interval ML20205R2411999-04-19019 April 1999 Rev 3 to CP2804L, Unit 2 Rx Coolant & Liquid Waste Pass ML20205R2501999-04-19019 April 1999 Rev 0 to CP2804M, Unit 2 Vent & Containment Air Pass ML20205R2751999-04-19019 April 1999 Proposed Tech Specs,Reflecting Permanently Defueled Condition of Unit ML20205S5611999-04-16016 April 1999 Rev 5 to Epop 4426, On-Site Emergency Radiological Surveys ML20205M0891999-04-0707 April 1999 Proposed Tech Specs Modifying Value for Monthly Surveillance Testing of Tdafwp ML20205E4411999-03-29029 March 1999 Rev 2 to CP 2804L, Unit 2 Rx Coolant & Liquid Waste Pass ML20196K5771999-03-24024 March 1999 Rev 1 to Chemistry Procedure CP2804L, Unit 2 Rx Coolant & Liquid Waste Pass ML20205D5321999-03-22022 March 1999 Rev 3 to RPM 2.3.5, Insp & Inventory of Respiratory Protection Equipment ML20204J1581999-03-19019 March 1999 Proposed Tech Specs Section 6, Administrative Controls, Reflecting Certified Fuel Handler License Amend Changes, Approved on 990305 ML20204J4101999-03-19019 March 1999 Proposed Tech Specs Relocating Instrumentation TSs 3.3.3.2, 3.3.3.3 & 3.3.3.4 to Mnps,Unit 2 TRM ML20204K0971999-03-19019 March 1999 Proposed Tech Specs Supporting Spent Fuel Pool Rerack to Maintain Full Core Reserve Capability Approaching End of OL ML20204F9031999-03-17017 March 1999 Proposed Tech Specs,Revising 3.5.2,3.7.1.7 & 3.7.6.1 Re ECCS Valves,Atmospheric Steam Dump Valves & CR Ventilation Sys. Associated Bases Will Be Modified as Necessary to Address Proposed Changes ML20207H9551999-03-0505 March 1999 Proposed Tech Specs Section 6.0 Re Administrative Controls ML20206K1121999-03-0505 March 1999 Proposed Tech Specs Bases Sections 3/4.7.7, CR Emergency Ventilation Sys & 3/4.7.8 CR Envelope Pressurization Sys. Changes Are Editorial in Nature ML20207F6211999-03-0303 March 1999 Rev 2,change 1 to Communications - Radiopaging & Callback Monthly Operability Test ML20207E0321999-03-0202 March 1999 Proposed Tech Specs 3/4.7.4, SW Sys, Proposing Change by Adding AOT for One SW Pump Using Duration More Line with Significance Associated with Function of Pump ML20207D4821999-02-26026 February 1999 Proposed Tech Specs Re Addl Mods Concerning Compliance Issues Number 4 ML20207J0001999-02-22022 February 1999 Rev 7 to Millstone Unit 2,IST Program for Pumps & Valves ML20206D1991999-02-11011 February 1999 Change 7 to Rev 5 to ISI-3.0, Inservice Testing Program. Pages 2 of 3 & 3 of 3 in Valve Relief Request Section 6.1 of Incoming Submittal Not Included ML20203E4051999-02-11011 February 1999 Proposed Tech Specs Re DG Surveillance Requirements ML20210D2121999-01-21021 January 1999 Proposed Tech Specs Sections 3/4.5.2 & 3/4.5.3, ECCS Subsystems for Info Only ML20199L2841999-01-20020 January 1999 Proposed Tech Specs & Final SAR Proposed Rev to Ms Line Break Analysis & Revised Radiological Consequences of Various Design Basis Accidents ML20199L0801999-01-18018 January 1999 Proposed Tech Specs Change to TS 3/4.2.2 Modifies TS to Be IAW NRC Approved W Methodologies for Heat Flux Hot Channel factor-FQ(Z).Changes to TS Section 6.9.1.6 Are Adminstrative in Nature ML20199L4561999-01-18018 January 1999 Proposed Tech Specs Revising TS Table 3.7-6, Air Temp Monitoring. Proposed FSAR Pages Describing Full Core off- Load Condition as Normal Evolution Under Unit 3 Licensing Basis,Included ML20199L3271999-01-18018 January 1999 Proposed Tech Specs 3.6.1.2, Containment Sys - Containment Leakage ML20199L0431999-01-18018 January 1999 Proposed Tech Specs Removing TS 3/4.6.4.3, Containment Systems,Hydrogen Purge Sys ML20199E0931999-01-13013 January 1999 Rev 2 to Health Physics Support Procedure RPM 2.3.4, Insp & Maint Process for Respiratory Protection Equipment ML20206P5121999-01-0404 January 1999 Proposed Tech Specs 3.5.2,3.6.2.1,3.7.1.2,3.7.3.1 & 3.7.4.1, Incorporating Changes to ESF Pump Testing B17501, 1998 - 2000 Performance Plan - Work Environ Focus Area Update1998-12-31031 December 1998 1998 - 2000 Performance Plan - Work Environ Focus Area Update ML20198K6361998-12-31031 December 1998 Proposed Tech Specs Section 6.0, Administrative Controls ML20199A7531998-12-31031 December 1998 Restart Backlog Mgt Plan Commitments ML20198P9751998-12-28028 December 1998 Proposed Tech Specs Pages Revising Loss of Normal Feedwater (Lonf) Analyses to TS 2.2.1,TS Bases Change to Floor Value for Thermal Margin Low Pressure Reactor Trip & Proposed FSAR Changes ML20196H6301998-12-0404 December 1998 Proposed Tech Specs Re Section 6.0, Administrative Controls ML20197G9831998-12-0404 December 1998 Proposed Tech Specs 4.7.10.e,eliminating Need to Cycle Plant & Components Through SD-startup Cycle by Allowing Next Snubber Surveillance Interval to Be Deferred Until End of RFO6 of 990910,whichever Date Is Earlier ML20196A2181998-11-20020 November 1998 Restart Assessment Plan Millstone Station ML20195D4041998-11-10010 November 1998 Proposed Tech Specs,Modifying Sections 3.3.1.1 & 3.3.2.1 by Restricting Time That Reactor Protection or ESF Actuation Channel Can Be in Bypass Position to 48 H,From Indefinite Period of Time ML20195D8101998-11-10010 November 1998 Revised marked-up Page of Current TS 3.8.1.1 & Revised Retyped Page Re 980717 Request to Change TS ML20195H8681998-11-0404 November 1998 Rev 4 to Millstone Unit 2 Operational Readiness Plan ML20196H5921998-10-29029 October 1998 Rev 0 to TPD-7.088, Millstone 1 Certified Fuel Handler/ Equipment Operator Continuing Training Program ML20196H5861998-10-29029 October 1998 Rev 0 to TPD-7.087, Millstone 1 Certified Fuel Handler Training Program B17548, Rev 0 to TPD-7.089, Millstone 1 Equipment Operator Training Program1998-10-29029 October 1998 Rev 0 to TPD-7.089, Millstone 1 Equipment Operator Training Program ML20155B0331998-10-22022 October 1998 Proposed Tech Specs Changing TS 3.3.2.1, Instrumentation - ESFAS Instrumentation, 3.4.9.3, RCS - Overpressure Protection Sys & ECCS - ECCS Subsystems - Tavg 300 F 1999-09-07
[Table view] Category:TEST/INSPECTION/OPERATING PROCEDURES
MONTHYEARML20206M8221999-05-10010 May 1999 Restart Assessment Plan Millstone Station ML20206D1761999-04-27027 April 1999 Rev 1 to Millstone Unit 3 ISI Program Manual,Second Ten-Yr Interval ML20205R2501999-04-19019 April 1999 Rev 0 to CP2804M, Unit 2 Vent & Containment Air Pass ML20205R2411999-04-19019 April 1999 Rev 3 to CP2804L, Unit 2 Rx Coolant & Liquid Waste Pass ML20205S5611999-04-16016 April 1999 Rev 5 to Epop 4426, On-Site Emergency Radiological Surveys ML20205E4411999-03-29029 March 1999 Rev 2 to CP 2804L, Unit 2 Rx Coolant & Liquid Waste Pass ML20196K5771999-03-24024 March 1999 Rev 1 to Chemistry Procedure CP2804L, Unit 2 Rx Coolant & Liquid Waste Pass ML20205D5321999-03-22022 March 1999 Rev 3 to RPM 2.3.5, Insp & Inventory of Respiratory Protection Equipment ML20207F6211999-03-0303 March 1999 Rev 2,change 1 to Communications - Radiopaging & Callback Monthly Operability Test ML20207J0001999-02-22022 February 1999 Rev 7 to Millstone Unit 2,IST Program for Pumps & Valves ML20206D1991999-02-11011 February 1999 Change 7 to Rev 5 to ISI-3.0, Inservice Testing Program. Pages 2 of 3 & 3 of 3 in Valve Relief Request Section 6.1 of Incoming Submittal Not Included ML20199E0931999-01-13013 January 1999 Rev 2 to Health Physics Support Procedure RPM 2.3.4, Insp & Maint Process for Respiratory Protection Equipment B17501, 1998 - 2000 Performance Plan - Work Environ Focus Area Update1998-12-31031 December 1998 1998 - 2000 Performance Plan - Work Environ Focus Area Update ML20199A7531998-12-31031 December 1998 Restart Backlog Mgt Plan Commitments ML20196A2181998-11-20020 November 1998 Restart Assessment Plan Millstone Station ML20195H8681998-11-0404 November 1998 Rev 4 to Millstone Unit 2 Operational Readiness Plan ML20196H5921998-10-29029 October 1998 Rev 0 to TPD-7.088, Millstone 1 Certified Fuel Handler/ Equipment Operator Continuing Training Program B17548, Rev 0 to TPD-7.089, Millstone 1 Equipment Operator Training Program1998-10-29029 October 1998 Rev 0 to TPD-7.089, Millstone 1 Equipment Operator Training Program ML20196H5861998-10-29029 October 1998 Rev 0 to TPD-7.087, Millstone 1 Certified Fuel Handler Training Program ML20154G5311998-10-0707 October 1998 Rev 4 to Project Procedure PP-02, Accident Mitigation Sys Review ML20154G5391998-10-0606 October 1998 Rev 6 to Project Procedure PP-07, Discrepancy Repts ML20154G5351998-10-0606 October 1998 Rev 3 to Project Procedure PP-04, Regulatory Review Procedure ML20154G5521998-10-0606 October 1998 Rev 5 to Project Instruction PI-01, Svsr Implementation Checklists & Workbook ML20154G5251998-10-0505 October 1998 Rev 4 to Independent C/A Verification Program for Millstone Unit 2 Audit Plan ML20236Q9341998-06-30030 June 1998 Rev 4 to PI-01, Sys Vertical Slice Review Implementation Checklists & Workbook ML20236Q9321998-06-25025 June 1998 Rev 4 to PP-01, Sys Vertical Slice Review ML20153C6171998-06-18018 June 1998 Rev 2 to CP 3804K, PASS Rcs/Rss Sample ML20153C6221998-06-18018 June 1998 Rev 1 to CP 3804L, PASS Containment Air Sample ML20153C6291998-05-31031 May 1998 Rev 0,Change 1 to CP 3804M, PASS Ventilation Samples ML20247R7851998-05-20020 May 1998 Rev 1 to Epop 4455C, Technical Assistant ML20247Q7011998-05-20020 May 1998 Rev 1 to Epop 4490, Implementation of Recovery Operations ML20247R8081998-05-20020 May 1998 Rev 1 to Epop 4455F, Rumor & Inquiry Control ML20247Q6671998-05-20020 May 1998 Rev 1 to Epop 4422A, Thermal Hydraulic Evaluation Methods ML20247Q6901998-05-20020 May 1998 Rev 1 to Epop 4475A, External Resources Coordinator ML20247R7921998-05-20020 May 1998 Rev 1 to Epop 4455D, News Releases ML20247Q6771998-05-20020 May 1998 Rev 1 to Epop 4428I, Direction of Posl Field Sampling ML20247R7541998-05-20020 May 1998 Rev 1 to Epop 4455A, Nuclear News Manager ML20247R7491998-05-20020 May 1998 Rev 1 to Epop 4455, Manager of Public Info ML20216B1791998-05-0808 May 1998 Independent Corrective Action Verification Program for Millstone Unit 3,Interim Rept,Executive Summary ML20247H4581998-04-0909 April 1998 Rev 19 to EOP 35 E-0, Reactor Trip or Safety Injection B17159, Backlog Mgt Plan for Unit 31998-03-31031 March 1998 Backlog Mgt Plan for Unit 3 ML20216K0641998-03-20020 March 1998 Rev 2 to Oversight Plan NNECO - Millstone Site Independent Third Party Oversight Program ML20216H7101998-03-13013 March 1998 Independent Corrective Action Verification Program Status Rept ML20216H7191998-03-0303 March 1998 Independent Corrective Action Verification Program Status Rept ML20203F6931998-02-20020 February 1998 Rev 6 to PI-MP3-11, Discrepancy Rept Submittal & Closure ML20203E2131998-02-19019 February 1998 Cancelled Rev 26 to 1-OPS-10.11, Locked Valve List ML20203D4111998-02-18018 February 1998 Revised 1-OM-index Unit 1 Operations Dept OM Index & Rev 2 to OM 3.8, Millstone Unit 1 Operations Manual ML20203F6751998-02-16016 February 1998 Rev 2 to PI-MP3-07, Review of Accident Mitigation Systems ML20203F6601998-02-16016 February 1998 Rev 5 to Audit Plan for Independent Corrective Action Verification Program ML20216H7351998-02-11011 February 1998 Independent Corrective Action Verification Program Status Rept 1999-05-10
[Table view] |
Text
'
l
.. 1
.4 I
e MILLSTONE NUCLEAR POWER STATION
{} f EMERGENCY PIAN OPERATING PROCEDURE h Q h II ix. Fb A M* W Jj @}k-,y
,,7 , ,,3' g.h, (TOP',y'kHi$ky ,:g's; Ace.
, . 2, , , a
, eview
- a j;;~e
- p%; ?K) , ' mqj lO Technical Assistant 1
EPOP 4455C l
Rev.1
'O Approval: M.b ' /r SORC Mtg. No: QF Al Date: 6 cDo-97 Effective Date: c5@9C)(
9805290216 900521 PDR ADOCK 05000245 F PDR
,O l SME: C. Manner Level of Use Information a
Millstone All Units
. Emergency Plan Operating Procedure
]
Technical Assistant TABLE OF CONTENTS
- 1. PURPOSE....................................................2
- 2. P RE R EQ UI S ITES . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2
- 3. P R ECAUTI O N S . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3
- 4. I N STR U CTI O N S . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3
- 5. REVIEW AND SIG NOFF . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 4
- 6. R E FE R EN C ES . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 4
- 7. S UM M ARY OF CH ANG ES . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 4 KITACliMENTS AND FORMS Attachment 1, " Supplemental Information" . . . . . . . . . . . . . . . . . . . . . . . . . 6
)
. (_)
Level of Use m f . , . .~[ ,' ,',,v.d ., ,REVIEWd,._ - ..
EPOP 4455C STOP' THINK ACT' Rev.1 Information m y.ms y ,g yryq y%,uz 1 ot y
f
- 1. PURPOSE 1.1 Objective l
l Provide guidance to the Technical Assistant, located at the Hartford Armory, for events which activate the Station Emergency Response Organization. These actions include the following:
- Gathering technical information from the site
. Operating OFIS in the State EOC
= Interfacing with the State DEP, as necessary 1.2 Discussion The Technical Assistant provides the NU contingent at the State EOC with information technically current with the events in progress. The Technical Assistant's main points of contact are the Executive Spokesperson, the Technical Information Coordinator at the EOF, or the Control Room Data Coordinator in the control room.
Information regarding roles and responsibilities is contained in Attachment 1," Supplemental Information."
- 2. PBEREOUISITES 2.1 General l
\
2.1.1 N/A 2.2 Documents 2.2.1 EPUG 08B," Millstone Emergency Preparedness Resource Book" 2.3 Definitions 2.3.1 CRDC - Control Room Data Coordinator l 2.3.2 PIO - Public Information Officer 2.3.3 TIC - Technical Information Coordinator l C) Level of Use . . .. .
- i. EPOP 4455C
.STOP . . .THINK .ACT' ~ REVIEW Rev.1 Information , , 2 of 7
- 3. PRECAUTIONS
) 3.1 It is important to conduct required communications at regular intervals (e.g.,30-90 minutes) to prevent communication overload (especially with the TIC and CRDC) or missed communications ofimportant events.
- 4. INSTRUCTIONS 4.1 After arrival at the State EOC, VERIFY the availability of the following:
= OFIS
= Procedures and media materials
- Logbook 4.2 Refer 'Ib EPUG 01," Time Sharing Option Equipment," at:d OllTAIN information on plant parameters.
NOTE
) EPUG 08B," Millstone Emergency Preparedness Resource Book,"is available as a guide for telephone numbers.
4.3 Refer To EPUG 08B, as necessary, and OllTAIN additional information by phoning the TIC at the EOE 4.4 IE the TIC is unavailable, REQUEST the CRDC provide information.
4.5 PROVIDE assistance to the Executive Spokesperson, as directed.
1 i
h 4 & EPOP 4455C Level of Use .s _ 2 . (/'
,, m _ , Review . . -
Information FF y7 F
",. ~.x_ jAcy y sq p-Rev.1 3 cg y j
j
\
l
_ _ _- _- D
)
- 5. REVIEW AND SIGhlOFF g-5.1 N/A i
- 6. REFERENCES 1 6.1 EPUG 01," Time Sharing Option Equipment" 6.2 EPOP 4455B," Executive Spokesperson" 6.3 EPOP 4465, " Technical Information Coordinator" 6.4 EPOP 4470," Control Room Data Coordinator"
- 7.
SUMMARY
OF CIIANGES 7.1 Changed the level of use from General to information.
7.2 Changed procedure from an NU common procedure (NUC EPOP) to a Millstone Nuclear Power Station Emergency Plan Operating Procedure (EPOP).
7.3 Deleted references to CY in all applicable locations.
7.4 Changed referenced procedure numbers from NUC EPOP to EPOP.
1 7.5 Added EPUG 0813," Millstone Emergency Preparedness Resource Book," i to the documents section.
7.6 Deleted step 2.1.2 that stated PAR procedures and charts are available.
7.7 Deleted step 2.1.3 that stated a phone list is available.
7.8 Deleted step 2.1.4 that stated basic media training has been provided as a prerequisite.
7.9 Added CRDC and TIC to the definitions section.
J 7.10 Deleted step 4.1 to notify the on-call Nuclear News Manager to see if the State EOC will be opening.
7.11 Deleted step 4.2 to report to the State EOC within 90 minutes if the State EOC will be opening.
7.12 Added note to step 4.3 that EPUG 0813 is available as a guide for g) telephone numbers.
l' A [ d EPOP 4455C Level of Use lnformation .
fg l
4
i
! 7.13 Corrected title of EPUG 01 in step 6.1.
' C)
C 7.14 Deleted Public Information Resource Coordinator, External Notification Coordinator, and Employee Communications Coordinator from Attachment 1.
7.15 Added public information responsibilities to Attachment 1 for the Station Duty Officer, the EOF DSEO, the ADEOF, and the Nuclear News Manager.
7.16 Deleted reference to the on-call 90 minute response time in Attachment 1 for the ES, NNM, TA, and MPI positions.
7.17 Deleted Attachment 2,"Public Information Emergency Organization On-Call and Call-In," flowchart.
j Ur' 1
1 l
i 1
l )
i l
lR l
. (')
d l' EPOP 4455C Level of Use _I.STOP
.., , WINK1._ l
.-pCJ" ' REVIEW Rev.I 1 Information
.? % F7 p '% f"'N s 5 of 7 i
I l
Attachment 1
- Supplemental Information (Sheet 1 of 2) l (v
The following is a description of the individuals that have public information responsibilities:
- 1. Ih2 Station Duty Officer is the public information point of contact in the affected unit control room.
- 2. The EOF DSEO is responsible for approving all news releases.
- 3. The ADEOF is responsible for the technical review of all news releases.
- 4. ' Die NU Executive SpokespIIsn is an NU management representative. This individual carries a Level 2 radiopager and receives notification of Unusual Event or higher classification events.
The Executive Spokesperson represents NU at Governor's briefings and official news conferences at the State EOC. The Executive Spokesperson and the nuclear information staff are the only individuals authorized to male official statements on behalf of NU.
- 5. The Nuclear News Manager is a nuclear information representative. This individual carries a Level 1 radiopager and receives notification of all nuclear events.
O y1 The Nuclear News Manager approves news releases for all events until the EOF is activated.
The Nuclear News Manager reports to the Executive Spokesperson and directs the overall public information response for NU. At the Armory, the Nuclear News Manager will serve as the official spokesperson until relieved by the NU Executive Spokesperson.
The Nuclear News Manager coordinates with the Governor's Press Secretary to determine if the Joint Media Center in Hartford should be activated, or if a company media center should be established at the site Information and Science Center.
- 6. The Technical Assistant is a nuclear organization representative. This individual carries a Level 2 radiopager and receives notification of Unusual Events or higher classification events.
The Technical Assistant reports to the Executive Spokesperson and provides technical and plant-specific information to keep him appraised of the event.
c !
~
Level of Use _ - - [ .~~ .. j ,' - [ _. EPOP 4455C W
~~
TACT ~ ' REVIEW Rev.I Information y- IHINK ~
c3 , y / % 6of7 :
Attachmcnt 1 Supplemental Information
,_ (Sheet 2 of 2)
! > 1
\ '/
- 7. The Manager of Public Information is a nuclear information representative. This individual carries a Level 2 radiopager and receives notification of Unusual Event or I higher classification events.
The Manager of Public Information reports to the Nuclear News Manager and is the primay contact point for information concerning the event, however, information is coordinated through the Assistant Director Emergency Operations Facility.
The following NCS and NU staff will be called in as needed to cary out public information I emergency functions:
- The Media Center Liaison reports to the Nuclear News Manager at the Hartford Armory. This individual coordinates with a State Public Information Officer to oversee the operations of the Joint Media Center and responds to media inquiries.
The Media Center Liaison supervises the Technical and Radiological Briefers in the JMC.
. Ibc Rumor and_ Inquiry Control Liaison reports to the NNM at the Hartford Armory.
This individual coordinates with a State Public Information Coordinator to oversee the operations of the Joint Rumor and Inquiry Control Center, j j q = The Tednical Briefer reports to the Media Center Liaison at the Hartford Armory. 1 Q This individual provides technical plant-specific information to the media between official news conferences.
. The Radiological Briefer reports to the Media Center Liaison at the Hartford Armory. This individual provides radiologicalinformation to the media between official news conferences.
x~ / _
EPOP 4455C Level of Use . .
STOP THINK' ACT REVIEW Rev.1 lnformation
. 7 of 7