ML20133G140
| ML20133G140 | |
| Person / Time | |
|---|---|
| Site: | Peach Bottom, Limerick  |
| Issue date: | 01/10/1997 |
| From: | James Shea NRC (Affiliation Not Assigned) |
| To: | NRC (Affiliation Not Assigned) |
| References | |
| NUDOCS 9701150177 | |
| Download: ML20133G140 (32) | |
Text
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't NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001
\ n s ,/ January 10, 1997 LICENSEE: PECO Energy Company (PECO)
FACILITY: Limerick Generating Station, Units 1 and 2 Peach Bottom Atomic Power Station, Units 2 and 3
SUBJECT:
SUMMARY
OF OCTOBER 25, 1996 MEETING BETWEEN NRC AND PECO REGARDING LICENSING ACTIONS FOR LIMERICK GENERATING STATION, UNITS 1 AND 2 (LGS), AND PEACH BOTTOM ATOMIC POWER STATION, UNITS 2 AND 3 (PBAPS)
On October 25, 1996 the NRC staff met with PEC0 representatives at the Peach Bottom Atomic Power Station in Delta, Pennsylvania, to discuss the status of licensing actions associated with LGS and PBAPS. Enclosure 1 is a list of those who attended the meeting. Enclosure 2 is a copy of the presentation material used by PECO at the meeting.
PEC0 representatives opened the meeting with a discussion of recent changes within the PECO nuclear organization. Recent versions of organizational charts for the Peach Bottom site and the PEC0 Nuclear Licensing organization are included as part of Enclosure 2. PEC0 also discussed planned visits by Senior PEC0 managers with NRC officials and NRC Commissioners schedule,1 for November 6, 1996 and November 22, 1996. Licensee representatives described that PEC0 was reviewing a study of a possible combined operating organization between PEC0 and Public Service Electric and Gas Company and that this topic ,
was one of several that might be discussed at the November 6 and November 22, '
1996 meetings.
The licensee next reviewed the status of licensing actions related to Limerick ;
Generating Station. The licensee provided a copy of its internal licensing i action priority list which is included as a part of Enclosure 2. PFC0 stated I that the priority for a number of the items is driven by the schedule for the next Limerick Unit 2 refueling outage, currently set to begin January 24, 1997. PECO indicated that certain license amendment requests, including one related to the residual heat removal system loop and subsystem operability requirements and another related to revisions to the pressure-temperature operating limit curves impacted the schedule for conducting the outage. The NRC staff indicated that it was reviewing all license amendment requests that had been submitted and would process them after appropriate technical review.
The staff informed the licensee that due to staff resource constraints, only licensing actions with impact on safety were being reviewed with any priority (
and that cost beneficial licensing actions would be assigned a low staff priority for the foreseeable future.
The staff and licensee discussed the status of various Peach Bottom licensing i I
actions currently under review by the NRC. Among the actions discussed were requested TS changes regarding installation of a wide range neutron monitoring .
system and changes to emergency core cooling system (ECCS) pump start relay time delay requirements. The licensee indicated that plans for installation .]Y[)
of an adjustable speed drive for the reactor recirculation pumps was still under review.
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! The license discusseditsrecent' effort.to: review'theaccuracyofthePeach i Bottom and . Limerick Final l Safety Analysis! Reports (FSARs) in light of recent
- NRC concerns about the. accuracy.of FSARs'overall. PECO indicated that it had identified some' discrepancies'which had been placed into its corrective action
{- system and that it was identifying additional measures to ensure the' accuracy
{ of the FSAR in the futuret i ;;
l 1
PECO also discussed its plansito design and build an. independent spent fuel j storage installation (ISFSI) at: the Peach Bottom site. PECO indicated that
- certain near term activities were~ underway and that.it hoped to have a
- facility ready.to accept spent fuel in the 1999 time frame. The staff stated
- i. that recent industry experience had shown that it was important to interact i with the NRC earlier in the ISFSI development process than is absolutely i j required by regulations. i
. 1 i
original signed by J.Shea.
Joseph W. Shea, Project Manager i Project Directorate I-2 Division of Reactor Projects - I/II .
Office of Nuclear Reactor Regulation t l Docket Nos.'50-277/278 !
j and 50-352/353 l
Enclosures:
- 1. Meeting Attendees
- 2. Meeting Handout 1
cc w/encls: See next page !
DISTRIBUTION w/ Enclosure 1 '
- w/ Enclosures 1 and 2 Hard Cooy
'* Docket File
- PUBLIC
- PDI-2. Reading *
- WPasciak, RGN-I E-Mail FMiraglia BGrimes RZimmerman 0GC-SVarga 7 WDean, EDO JZwolinski ' '
A6M JStolz '
M0'Brien *
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N OFFICE PDN2/L4( PDI 2/PN' PDI-2#/// PDI-2/D NAME MBNn JSNea[ FRiN JS N -
DATE O)hh6 hh/96 lb/%I/96 Ol/Q9[
OFFICIALRECORDCOP{ DOCUMENT NAME: G:\SHEA\PBLG1096.MTG
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The licensee discussed _its recent effort to review the accuracy of the Peach Bottom and Limerick Final Safety Analysis Reports (FSARs) in light of recent NRC concerns about the accuracy of FSARs overall. PECO indicated that it had identified some discrepancies which had been placed into its corrective action l system and that it was identifying additional mearures to ensure the accuracy '
, of the FSAR in the future.
PEC0 also discussed its plans to design and build an independent spent fuel i storage installation (ISFSI) at the Peach Bottom site. PECO indicated that l certain near term activities were underway and that it hoped to have a facility ready to accept spent fuel in the 1999 time frame. The staff stated 4 that recent industry experience had shown that it was important to interact with the NRC earlier in the ISFSI development process than is absolutely required by regulations. ,
4
/ r3 cr< , ll Js W. Shea, Project Manager o ct Directorate I-2 l Division of Reactor Projects - I/II '
Office of Nuclear Reactor Regulation J
Docket Nos. 50-277/278 and 50-352/353
Enclosures:
- 1. Meeting Attendees j
- 2. Meeting Handout cc w/encls: See next page 4
l PECO Energy Company Peach Bottom Atomic Power Station, Units 2-and 3 '
Limerick Generating Station, Units 1 and 2 cc:
J. W. Durham, Sr., Esquire Mr. Rich R. Janati, Chief Sr. V.P. & General Counsel LDivision of Nuclear Safety PECO Energy Company Pennsylvania Department of 2301 Market Street, S26-1 Environmental Resources Philadelphia, Pennsylvania 19101 P.O. Box 8469 ,
Harrisburg, Pennsylvania 17105-8469 l PECO Energy Company 4 ATTN: Mr. T. N. Mitchell, Vice President Board of Supervisors !
Peach Bottom Atomic Power Station Peach Bottom Township 1848 Lay Road R. D. #1 :
Delta, Pennsylvania 17314 Delta, Pennsylvania 17314 PECO Energy Company Public Service Commission of Maryland ATTN: Regulatory Engineer, A4-SS Engineering Division Peach Bottom Atomic Power Station Chief Engineer Route 1, Box 208 6 St. Paul Centre Delta, Pennsylvania 17314 Baltimore, MD 21202-6806 l Resident Inspector Mr. Richard McLean i U.S. Nuclear Regulatory Commission Power Plant and Environmental l Peach Bottom Atomic Power Station Review Division '
P.O. Box 399 Department of Natural Resources Delta, Pennsylvania 17314 B-3, Tawes State Office Building Annapolis, Maryland 21401 :
Regional Administrator, Region I l U.S. Nuclear Regulatory Commission Mr. David P. Helker, 62A-1 475 Allendale Road Manager - Limerick Licensing King of Prussia, Pennsylvania 19406 PECO Energy Company 965 Chesterbrook Boulevard Wayne, Pennsylvania 19087-5691 Mr. Roland Fletcher Department of Environment Mr. Walter G. MacFarland, Vice President 201 West Preston Street Limerick Generating Station Baltimore, Maryland 21201 P.O. Box A Sanatoga, Pennsylvania 19464 A. F. Kirby, III External Operations - Nuclear Mr. Robert Boyce Delmarva Power & Light Company Plant Manager P.O. Box 231 Limerick Generating Station Wilmington, DE 19899 P.O. Box A _
Sanatoga, Pennsylvania 19464 Chairman Board of Supervisors of Limerick Township 646 West Ridge Pike Linfield, PA 19468 s ;
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. t PECO Energy Company Peac BottomfAfomic Powbr Station, Units 2 a'nd 3 .
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'w . . . Limerick Generating Station,
' Units 1 and'2 i
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~ Mr. Darryl P. Lequia Mr. Neil S. Perry ,
Director - Site Support Services Senior Resident Inspector -
Limerick Generating Station U.S. Nuclear Regulatory Commission
'P. O. Box A P.O. Box 596 Sanatoga, Pennsylvania 19464 Pottstown, PA 19464 Mr. ' James L. Kantner, Library i
. Manager - Experience Assessment U.S. Nuclear Regulatory Commission :
= Limerick Generating Station Region I P. O. Box A . . 475 Allendale Road Sanatoga, Pennsylvania 19464 King of Prussia, PA 19406 Mr. Ludwig E..Thibault Dr. Judith Johnsrud )
Senior Manager - Operations National Energy Committee Limerick Generating Station Sierra Club i P. O. Box A 433 Orlando Avenue
'Sanatoga, Pennsylvania 19464 State College, PA -16803 Mr. Michael P. Gallagher PECO Energy Company .
Director - Site Engineering- G. D. Edwards, Plant Manager Limerick Generating Station Peach Bottom Atomic Power Station i P.O. Box A Route =1, Box'208 l Sanatoga, Pennsylvania 19464 Delta, Pennsylvania 17314 Bryan W. Gorman, Manager Joint Owners / External Affairs Interface Public Service Electric and Gas Company.
P.O. Box 236 Hancocks Bridge, NJ 08038-0236 i
Mr. George A. Hunger, Jr. 1 Director-Licensing, MC 62A-1 '
1 PECO Energy Company
~ Nuclear. Group Headquarters .
Correspondence Control Desk <
P.O. Box No. 195. --
Wayne, PA 19087-0195 .
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NRC/PECO Energy Company c , October 25;'1996 Meeting Attendance List a:
" fWiE ' '
s ORGANIZATION
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- 31. . J. Shea 4 NRC/PD I-2
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- 2. F. Rinaldi- ' - +
NRC/PD I-2
- 3. G. Hunger * '
, PECO
- 4. D. Helker -
PEC0
- 5. M. Christinziano e PEC0
- 6. D..Neff: PEC0
- 7. D. Foss PEC0 .,
- 8. A. Cross-Dial PEC0
- 9. G. Lengyel PECO
- 10. J. Katner PECO
- 11. B. Knierem Delmarva Power
- 12. H. Abendroth Atlantic Energy Enclosure 1
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t PBAPS Experience Assessment Group '
~
-NR'R Interface Meeting e Organization
. UFSAR Verifications
. Personal Library Software (PLS) ;
. Heavy Loads Committee ,
. i
. Tech Spec Proposals -
. Future issues
. Spent Fuel Storage ,
. Electronic ' Juke Box'
April 1,1996 OFFICE OF THE VICE PRESIDENT T. N. Mitchell SUCCESSION OF AUTHORITY Vice President vice nesiaent Plant Manager Director, Outage Management -l Director, Site Engineering Director, Maintenance -
Sr. Manager, Operations Shift Manager vacant . 1 L. Wiley
. q Senior Organizational . Secretary Development Specialist
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Direct r
- D rector Tr 'nina S numan
""a*aar maintenance S't*
3ManaMnts 3 - , ' tag,ggort Resources
, ,n,in , rino ; +.g c.. ;. _ 7g, m 3 TN Mitchell
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PLANT DIVISION ,
~
G. D. Edwards ,
Plant Manager .
W. A. Felts Secretary
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D. C. Dicello S. C. Baker G. J. Lengyel :
G. H. Gellrich Manager A. D.- Odell Manager Manager Sr. Manager Manager . ,
Operations Radiation Chemistry Radwaste Experience ,
Protection ,
Assessment a fQ G. D. Edwards "
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T. N. Mitchell~
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A' l EXPERIENCEASSESSMEl\lril1,1996 T '
l Lengyel G. J.
Manager -
B. A.~ Hedrick Secretary i
ANALYSTS R TORY PHYSICIST i
R' K' Smith A. F. Plante R. G. Andrews D. J. FOSS G. A. John .
r-J. H. Gallaher zate,x -
/ QI f Legik/@l G. D. Edwards
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Phase 1 A:ND Phase 2 -
I Phase 1 .
- One-day review of entire PBAPS UFSAR focusing on nonconservative design or operation. .
cx i a Phas~e 2 .
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- Detailed review of 30 selected UFSAR sections
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performed by teams.
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. Phase 1 Over 300 Disdrepancies j
- 6 NCR Issues-
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Reference A1024480 Phase 2 Over 500 Discrepanciss
- 50 Incorrects ( 66% Administrative Errors) ,
- 389 Ambiguous .
- 121 Typos 1 - n@ e.
-;0:NGR Isssues. .%;x@ym@ .u : .gg
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- f Where Do We Go :Froni Here.? -
f' L LFSAR Ownership -
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No Single Point Accountability ,
>>-Licensing Performs Administrative Functiorfs
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n Licensing Program Manager i LRO Single Point Accountability
>> Focus LRO's At The Sites .
->> Annual Assessments . e, .
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- Final Report m Common LGS /PBAPS.. PEP
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" Store Room Parts Catalog"
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"Cb Commitments" '
, " Code & Standard Abstracts" l
- "lNDUSTRY EVENTS 1985 - PRESENT" '
" INDUSTRY PHONE CALLS TO THE NRC"
! ."INPO "INPO Publication GOOD PRACTICES" Index" '
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,"lNPO SERS". ,
- "INPO SOERS"
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." LGS Design Basis DocumenE .
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" LGS ISEG Reports"
" LGS LER Abstracts"
" LGS LERs"
! . ;" LGS NCRs" j _ " LGS PEP DATA" 4g:';?r, 4 _." LGS QA Reports" j ~ LGS SERs" . _
" LGS Shift Update Notice A/Rs (AT-SUN)" ^
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" LGS Unit 1' Tech Specs" jy ,
. LGS Unit 2 Tech Specs" >
"NEl Information"
'"NRC DOCUMENTS" '
"NRC Reg. Guides" -
"NRC Region I Fines" "NUREG Abstracts"
"(SAR) PB 50.59 Annual Report"
"(SAR) PB Facility Operating Ucense" ;
"(SAR) PB Fire Protection Plan"
"(SAR) PB Offsite Dose Calculation Manual" .
"(SAR) PB Unit 2 Tech Specs" i
"(SAR) PB Unit 3 Tech Specs"
"PB 1994 Shift Logs" "PB Commitment Tracking Module Database" -
"PB Commitments 1974 - Present" "PB Correspondence 1974 - 1988" "PB Design Basis Documents" "PB Emergency Prepardness Plan" "PB Equipment Trouble Tags" "PB EVENTS 1988 - PRESENT"
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"PB ISEG Reports" 9
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Memorandum i
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Location: Peach Bottom Training Center Date: a
. October 4, 1996 -
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To: - . Rigging Program Committee l
From:
- Wayne Emberger ,
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. Meeting Agenda /
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I. Introductions and' Sign In l II. Committee Assignments
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Greg Magee- Team Leader c"$?.L c?,
! x Harry McFadden l.
Jim Armstrong
- Jack Nacrelli . f ,, -
i B. Procedure Committee - .r
. Mark Adams- Team Leader ,
I Phil Stinger ,
' Mike McGoldrick l Blaise Dubree j C. Qualification Committee i Jim Armstrong Team Leader
- Mark Adams
! Jack Nacrelli .
! Phil Stinger D. Regulatory / Licensing Committee l Fred Ungar- Team Leader Dan Shervini ,
. Dave Foss -
- III. QA . .
! Jules Guzejko -
Dale Wheeler 2
j IV. Committee Issues
! V. OMR Review i
VI. NRB Review
1 Heavy Loads
, Requirements Flowchart (Draft)
No l Is Rigging Operation Over ' Perform Rigging j
Spent Fuel, Rx Vessel, or Safe
, Shutdown Equipment ?
> IAW procedures I '
s . Yes .,
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Does Rigging Operation - -
i Comply w/Nureg-0612 3, Phase I Requirements ?
No Obtain Eng's Yes 8 Review /Appr
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2 Perform i No y i
Does Approved Analysis No pg,,
Rigging for Load Drop Exist that Ensures Safety Functions met ?
> Analysis 1
Operations Yes; c p .
No Does Analysis rely on Redundant IAW s Features to Ensure Safety .
Function ?
Safe Load Paths Yes y
Ensure Redun-dant Safety Features are 4 Operable During Lift
. _ _= .- =. . . . . . - .- .- . - -
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- Technical Specifications Amendment Proposals I I
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- LPRM GAIN CAllBRATIONS (TS) .
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UNIT 3 FUEL LIMIT (TS-U3) .
EDG SURVEILLANCE REQUIREMENTS (TS & TSB)
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Toins of Full Core C4floeil Capability Occdrsiuly 2000 .
. Loss of Refuel Capability Occurs July 2002 4000 -- - -
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3a19 Assemtmes 2R15 L54a
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5 Laos of fun Core Omood CapetmRy, z 2000 -- . - i 2720 July 2000
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1 Peach Bottom Atomic Power Station Licensing Report To the NRB For the Period 8/29/96 to 10/24/96 I. Significant Licensing Actions A. Technical Specifications , l
- 1. The following License Change Request (LCR) was approved by the NRC during this time period i l
LCR No. Date Subject LCR 96-01 9/27/96 Revision to MCPR Limits due to GE13 Fuel
- 2. The following LCR was submitted to the NRC LCR No. Date Subject ECR 96-03093 9/6/96 ECCS Instrumentation and AC Sources - Operating B. Relief Requests, Exemption Requests and 50.54(a) Requests
- 1. By letter dated August 30, 1996, the NRC approved the Quality Assurance Program Description changes for PBAPS and LGS Fire Protection Program Assessment Frequencies.
C. Significant Requests for Additional Information ( RAI' s ) , l By letter dated 9/27/96 PECO Energy provided additional information concerning LCR 96-01. D. Generic Letters (GL), Bulletins and Significant Information Notices (IN) GLs, Bulletins and Significant ins Issued by NRC No. Date Title l IN 96-50 9/4/96 Problems With Westinghouse 1 Circuit Breakers i IN 96-51 9/11/96 Residual Contamination I Remaining in Krypton-85 Handling System After Venting IN 95-52 9/26/96 Cracked Insertion Rods on Troxler Model 3400 Series Portable Moisture Density Gauges IN 96-53 10/15/96 Retrofit to Amersham 660 j Posilock Radiography Camera to l Correct Inconsistency in 10 CFR Part 34 Compatibility j l l l i
IN 96-54 10/17/96 Vulnerability to Stainless Steel to Corrosion When Sensitized There were no GL or Bulletin responses submitted to the NRC during this time period. II. Other Significant Operating Experience There were no INPO SERs issued during this time period. III. Significant Emerging NRC Issues
- 1. By letter dated August 28, 1996 the NRC notified the NEI that the NRC will begin its' review of NEI 96-07
- Guidelines for 10 CFR 50.59 Safety Evaluations."
- 2. By letter dated September 3, 1996, PECO Energy submitted the PBAPS, Unit 2 Core Spray In-Vessel Piping Repair Package to the NRC.
- 3. By letter dated September 12, 1996, PECO Energy submitted the PBAPS, Units 2 and 3 Reactor Vessel Internals Examination Plans for the Core Spray Piping.
- 4. By letter dated September 18, 1996, PECO Energy submitted the PBAPS, Units 2 and 3 1996 Annual Emergency Preparedness Exercise Scenario.
- 5. By letter dated September 20, 1996, PECO Energy submitted the PBAPS, Units 2 and 3, and the LGS, Units 1 and 2 Common Emergency Plan Revision No. 12 pursuant to 10 CFR 50.54 (q),
Appendix E and 50.4 (b) (5) .
- 6. By letter dated October 2, 1996 the NRC provided a final resolution of spent fuel storage pool safety issues. In this letter, the NRC requested that we confirm the accuracy of the staff's understanding of the plant design, the safety significance, the cost of potential modifications, or the protection provided by administrative controls by November 15, 1996.
- 7. By letter dated October 9, 1996, the NRC issued the maintenance rule team inspection report (Nos. 50-277/96-07 and 50-278/96-07). In this report, the NRC requested a predecisional enforcement conference.
- 8. By letter dated October 21, 1996, PECO Energy provided notification to the NRC of the conclusion of the PBAPS control room enhancement program.
- 9. By two letters dated September 26, 1996, and a letter submdtted September 27, 1996, PECO Energy submitted information concerning cracks discovered on the Loop B Core Spray header. NRC gave verbal permission to restart on September 27, 1996.
2
__ _ u. 1 . Limerick Tech Spec Priority List l Page 1 1
! 10/1/96
) ' PRIORITY TSCR#/ TAC # DESCRIPTION STATUS , i 1 95-14-0 Appendix J, Option B Pages: j FOL-7 (Unit 1 only)
- FOL-4 (Unit 2 only) l 3/4 6-1 3/4 6-2 4 3/4 6-3 3/4 6-4 3/4 6-5
- 3/4 6-6 j 3/4 6-8 3/4 6-14 B 3/4 6-1 l B 3/4 6-2
- M96117/18 6-14b 2 96-12-0 RHR SDC Loops vs. Subsystems
., Pages: . 3/4 4-25 3/4 4-26 3/4 9-17 3/4 9-18 B 3/4 4-6 M95809/10 B 3/4 9-2 3 95-18-2 New MCPR Values Pages: 2-1 M96391 B 2-1 4 96-01-0 ADS Valves Startup Testing Page: M95803/04 3/4 5-5 5 96-15-2 New PTOL Curves Pages: 3/4 4-20 M96390 B 3/4 4-5 I
Limerick Tech Spec Priority List Page 2 PRIORITY TSCR#/ TAC # DESCRIPTION STATUS 6 96-09-0 Deletion of Certain Response Time Tests Pages: 3/4 3-6 3/4 3-23 3/4 3-24 3/4 3-25 3/4 3-26 3/4 3-39 B 3/4 3-1 M96392/93- B 3/4 3-2 7 96-07-0 Increase Secondary Containment Inleakage Rate Pages: 3/4 6-46 3/4 6-53 3/4 6-54 B 3/4 6-5 B 3/4 6-6 8 95-01-0 LPRM Calibration Frequency Pages: 3/4 3-8 M93757/58 8 3/4 3-1 9 93-28-0 SBGT Functional Testing Frequency l Pages: 3/4 6-52 (V/1 only) 3/4 6-52a (U/2 only) M95807/08 3/4 6-55 o:\lic\ctw\wp51\priolg.dph k
~
J I 4 LGS LICENSING ACTIONS CURRENTLY WITH NRC (Non Tech Spec items) LGS RELIEF REQUESTS PRIORITIZATION j 1. REUEF REQUEST 41-VRR-2 (Rev. 3) - ADS VALVE TESTING (TAC M95805/06) i i l ! 2. REUEF REQUEST GVRR-1 (REV. 2) IN SUPPORT OF APPENDIX J, OPTION B: (TAC M96388/89) l } i i l { OTHER . I
- 1. '
REQUEST FOR APPROVAL OF NEW EALs (TAC M92363/64) 2. REQUEST FOR APPROVAL OF IPEEE (TAC M83636/37) 3. REQUEST FOR ECCS SUCTION STRAINER UPGRADE DEFERRAL (TAC M96153/54) 4. P.E-USE OF FUEL CHANNELS (TAC M96077/78) 5. OAPD CHANGE INVOLVING VENDOR EVALUATION (TAC M96545/46)
- 6. THERMOLAG ISSUES (TAC M85565/66) 7.
CORE SHROUD INSPECTION RESULTS (TAC M96071) STATUS DATE: 9/24/96 0;\UC\CLW\WP51\next12.fts
LICENSING DIRECTOR GEORGE HUNGER, JR. GAH X6761 Secretary NRB Secretary Mary Lou Skrocki Tammy Zemel MLS x6762 TLZ x5651 PEACH BOTTOM LIMERICK Manager EXPERIENCE Manager Martha Christinziano ASSESSMENT Dave Helker MAC x6789 DPH x6767 Engineer Engineer Mike McCabe Engineer Tom Loomis PEP X6737 Cristine lonescu TRL x6793 MCM X6778 CMI x6787 ' Engineer Engineer Andrea Cross-Dial Kevin Borton AEC x6768 KFB x6776 Engineer Engineer Jerry Phillabaum Chris Krajnik JLP x6785 CGK x6777 Engineer Analyst George Rombold LICENSING Rick Gropp GBR x6788 ORGANIZATIONAL STRUCTURE RWG x6774 PECO ENERGY COMPANY Secretary PECO NUCLEAR Secretary Barb Reuben STATION SUPPORT DEPARTMENT Cathy Wilson - BGR x6764 CLW x6964 OCTOBER 1996 P:OATALICENSING ORGANIZATION CHART. DOC
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