Text

Responds to FOIA Request for Summary of NRC 820301 Meeting W/Rochester Gas & Electric Corp.Summary Encl
	ML20054C873
Person / Time
Site:	Ginna
Issue date:	03/22/1982
From:	Felton J; NRC OFFICE OF ADMINISTRATION (ADM)
To:	Wert M; GANNETT ROCHESTER NEWSPAPER, ROCHESTER, NY
References
	FOIA-82-123 NUDOCS 8204220050
	Download: ML20054C873 (1)
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Democrat and Chronicle Gannett Rochester Newspapers 55 Exchange Street IN RESPONSE REFER Rochester, NY 14614 TO F0IA-82-123

Dear Mr. Wert:

This is in response to your letter dated March 1,1982, in which you requested, pursuant to the Freedora of Information Act, a copy of the summary of the March 1,1982 meeting between NRC and Rochester Gas &

Electric Corporation.

Enclosed is the requested document.

Sinc rely, J.

. Felton, Director Division of Rules and Records Office of Administration

Enclosure:

As stated 8204220050 820322 PDR FOIA WERT82-123 PDR i-

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UNITED STATES g

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NUCLEAR REGULATORY COMMISSION g

j WASHINGTON, D. C. 20555 March 8, 1982 LS05-82-03-051

' OCHESTER GAS AND ELECTRIC COMPANY LICENSEE:

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FACILITY:

R. E. GINNA

SUBJECT:

SUMMARY

OF MARCH 1, 1982 MEETING WITH RG&E TO DISCUSS THE REC 0VERY ACTIVITIES AT THE R. E. GINNA PLANT On Monday, March 1,1982, members of the NRC staff met with representatives of Rochester Gas and Electric Corp. (RG&E) and Westinghouse to discuss the recovery program at R. E. Ginna. RG&E has decided to extend the current outage in order to refuel and perform other scheduled maintenance through-out the plant concurrent with the steam generator repairs. As required by a letter from D. Eisenhut, NRC, to J. Maier, RG&E, the licensee will obtain the NRC's prior approval, based on written submittals, before significant and irreversible programs are ondertaken. The purpose of this meeting was to obtain the NRC's approval for the removel of a small number of tube :

samples for metallurgical examination. A copy of the slides used by RG&E during the presentation and the attendence list are enclosed.

Video inspections of both steam generators have been completed. Several foreign objects have been located in the periphery of the "B" steam generator hot leg and of the "A" cold leg.

In addition, a number of damaged tubes have been seen on the periphery of the "B" hot leg.

In general, the damage in the "B" hot leg periphery is restricted to previously plugged tubes although some minor scrape marks are visible on currently in-service tubes. The scrape marks are below the minimum sensitivity of theveddy current inspection technique. No damaged tubes have been seen in the "B" cold leg or in either of the hot leg or the cold leg of the "A" steam generator.

Investigations as to the failure mechanism are continuing. Originally, the cause investigation centered around possible mechanical loading j

mechanisms on tubes between the first support plate and the tube sheet l

with flow induced vibration as a contributing factor. The current l

cause investigation, since discovery of foreign objects in the "B" steam generator, is focussing on mechanical failure of plugged tubes as the result of impact by foreign objects and the progression of damage on l

structurally degraded plugged tubes with possible resultant damage to other tubes including the burst tube.

However, the investigation program is designed to provide information regarding other possible failure mechanisms and is not restricted to a single postulated cause.

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( March 8, 1982 The next step in RG&E's plans is to remove a small number of steam generator tube sections for metallurgical examination in order to obtain additional information necessary to finalize repair plans and to assist in determination of the failure mechanism.

RG&E proposed that sections of at least 4 tubes be removed for metallurgical analy-sis; this would include R42C55, R43C55, R44C55 and 45C47. The first tube is the burst tube, the second and third tubes must be removed to obtain access to the burst tube, and the fourth tube is one with an eddy current indication approximately 24 inches above the tube.' sheet.

The sections removed for analysis will be between the tube sheet and first support plate.

The removal process will involve putting a 3 inch access port in the steam generator shell, EDM and mechanical cutting (of tubes, and possible removal of one periphery U-bend section R45C47). RG&E has not identified any other tube sections to be removed, although a small number may be identified should it appear important information could be obtained from an additional,small, number of tubes.

The NRC staff concurred with RG&E's proposal to remove the steam generator tube sections and instructed RG&E to inform the NRC if additional tubes that might provide valuable information are to be removed. Upon comp', icn of removal of the steam generator tube samples, RG&E will perform previot2y planned maintenance to the upper portions of the steam generator while formulating their final course of action. The licensee expects to be able to return for a meeting with the NRC staff to present their finalized recovery program in the next two or three weeks.

. E. W ames E. Lyon Project Manager 0 eca ing Reactors Branch #5 Division of Licensing

Enclosures:

As stated cc w/ enclosures:

See next page l

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, Mr. Qohn E. Maier March 8, 1982 i

cc Harry H. Voigt, Esquire U. S. Environmental Protection Agency LeBoeuf, Lamb, Leiby and MacRae Region II Office 1333 New Hampshire Avenue, N. W.

ATTN:

Regional Radiation Representative Suite 1100 26 Federal Plaza Washington, D. C.

20036 New York, New York 10007, Mr. Michael Slade Herbert Grossman, Esq., Chairman 12 Trailwood Circle Atomic Safety and Licensing Board Rochester, New York 14618 U. S. N'uclear Regulatory Commission Washington, D. C.

20555 Ezra Bialik Assistant Attorney General Ronald C. Haynes, Regional Administrator Environmental Protection Bureau Nuclear Regulatory Commission, Region I New York State Department of Law Office of Inspection and Enforcement 2 World Trade Center 631 Park Avenue New York, New York 10047 King of Prussia, Pennsylvania 19406 Resident Inspector Mr. Eric Smith R. E. Ginna Plant NUS Corporation c/o U. S. NRC 2536 Countryside Blvd.

1503 Lake Road Clearwater, Florida 33515 Ontario, New York 14519 Mr. Bob Pollard Director, Bureau of Nuclear UCS Operations 1346 Connecticut Avenue N. W.

State of. New York Energy Office Suite 1101 Agency Building 2 Washington, D. C.

20036 Empire State Plaza Albany, New York 12223 Mr. Fred Levine Counsels Office Rochester Public Library New York State Consumer 115 South Avenue Protection Board Rochester, New York 14604 99 Washington Avenue Albany, New York 12210 Supervisor of the Town of Ontario 107 Ridge Road West Ontario, New York 14519 Dr. Emmeth A. Luebke Atomic Safety and Licensing Board U. S. Nuclear Regulatory Commission Washington, D. C.

20555 Dr. Richard F. Cole Atomic Safety and Licensing Board U. S. Nuclear Regulatory Com, mission Washington, D. C.

20555

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LIST OF ATTENDEES J. Lyons NRC H. Kister NRC G. Lainas NRC B. Johnston NRC W. Hazelton NRC S. Hanauer NRC

0. Woodruff Westinghouse T. Ippolito NRC C. McCracken NRC A. Curtis RGE J. Hutton RGE R. Smith RGE D. Eisenhut NRC A. Taboada NRC E. Igne ACRS J. Noon RGE B. Mecredy RGE J. Maier RGE J. Mazetis NRC J. Roe NRC B. Liaw NRC P. VanTeslaor W

D. Meoli il D. Rawlins II C. Hirst li M. Patel W

L. Ermold II D. White II P. Matthews NRC D. Crutchfihld NRC C. Cheng NRC E. Murphy NRC E. Brown NRC 0

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Ginna Station a

B - Steam Generator Proposed Recovery Program March 1, 1982 Agenda Introduction Schedule Steam Generator Configuration 4

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Steam Generator Inspection Results Potential Failure Mechanism (s) t Recovery Program

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Introduction Objectives of RG&E Program 1.

Restore steam generator to a condit. ion which is safe to operate 2.

Determine failure mechanism (s) 3.

Maintain radiation exposures as low as reasonably achievable i

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Obtain NRC concurrence for return to power t

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Purpose of Meeting 1.

To review results of inspections to date 2.

To obtain concurrence with steam generator program concepts 3.

To obtain approval for removal of metallurgical specimens O

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NSARB/NRC Review 1.

Concurrence with Program Concepts NSARB - 2/26 3/1 NRC s

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Approval of Removal of Metallurgical Samples NSARB - 2/26 3/1 NRC 3.

Approval of Complete Repair Program NSARB - mid March mid March NRC 4.

Approval of Return to Power NSARB - mid April late April NRC "o

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Rev.2 2/26 AEC I

DATA REVIEW "B" 'S/G HOT LEG 2-16-82 RlC92 OK R2C92 OK R3C92 OK R4C92 OK R5C92 OK RC692 OK R7C92 OK R8C92 COLLAPSED WITH HOLE - PLUGGED A

PLUGGED B

R9C91 OD DAMAGE (Ripples on surface)

R10C91 OD DAMAGE - WIPED AREA - SCRAPED (Ripples) C PLUGGED RllC91 COLLAPSED WITH HOLE (Ripped) 4-5" above T.S. - PLUGGED D

R12C91 COLLAPSED WITH HOLE 4" above T.S.

PLUGGED E -

R13C90 OD DAMAGE - PLUGGED F

R14C90 COLLAPSED WITH OD DAMAGE - DEPRESSION G

R15C90 OQ DAMAGE WITH HOLE (Collapsed & Ripples) n PLUGGED H

3 R16C89 MINOR OD DAMAGE - PLUGGED I

R17C89 OD DAMAGE - PLUGGED J

R18C88 OK

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R20C88 OK l

R21C87 OK l

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PAGE 2 OF 7 Rev. 2 2/26 AEC 2-16-82 DATA REVIEW "B"

S/G HOT LEG R22C86 OK R23C86 OK R24C85 OK, R25C85 OK

-R26C84 OK R27C83 OK R28C82 OK R29C82 OK K

R30C81 OK

. PIECE OF TUBING ON TUBE SHEET STAY ROD OK R33C78 OK R34C77 OK R34C76 OK R35C76 OK R35C75 OK - PLUGGED R35C74 OK

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R36C73 OK R37C73 OK R37C72 OK L

R38C72 OD DAMAGE - PLUGGED - OK M

R38C71 OD DAMAGE - PLUGGED - OK R38C70 OK O

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PAGE 3 OF 7 Rev. 2 2/26 AEC DATA REVIEW "B" S/G HOT LEG

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OD DAMAGE - PLUGGED - OK R39C70 O

OD DAMAGE - PLUGGED - OK l

.R39C69 P

R39C68 OD DAMAGE - PLUGGED - OK Q

R40C68 OK - PLUGGED R

R40C67 OK - PLUGGED E

R41C66 OK - PLUGGED T

R41C65 OD DAMAGE - DINGS U

R41C64 OD DAMAGE - DINGS

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R42C63 OD DAMAGE - DINGS X

R42C62 OD DAMAGE - DINGS Y

SEVERVED E T.S. - PLUGGED R43C61 Z

R43C60 SCRAPED ON OD - PLUGGED AA R43C59 OD DAMAGE - PLUGGED AB COLLAPSED, OD DAMAGE - PLUGGED R44C58 AC t

COLLAPSED - MISSING? - PLUGGED R44C57 Ad R44C56 COLLAPSED, OD DAMAGE - PLUGGED AE R44C55 COLLAPSED, OD DAMAGE - PLUGGED AF R45C54 COLLAPSED, OD DAMAGE.- PLUGGED AG R45C53 COLLAPSED,,OD DAMAGE, PLUGGED,

AM R45C52 PULLED TUBE L

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PAGE 4 OP 7 Rev. 2 2/26 AEC 2-16-82 DATA REVIEW "B" S/G HOT LEG AI PLUGGED R45C51 MOTTLED (RIPPLED OD)

R45C50 OK - PLUGGED R45C49 OK - PLUGGED R45C48 OK - PLUGGED

~ R45C47 OK - PLUGGED R45C46 OK - PLUGGED R45C45 OK R45C44 OK,

.R45C43 OK R45C42 OK R45C41 OK R45C40 OK R45C39 OK R44C38 OK R44C37 OK g

R44C36 OK 9

R44C35 OK AJ R43C34 OK - PIECE OF WIRE R43C33 OK' l

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PAGE 5 OP 7 Rev. 2 2/26 AEC 2-16-82 DATA REVIEW "B"

S/G HOT LEG

-R42C29 OK R41C28 OK R41C27 OK R40C26 OK R40C25 OK R39C24 OK R39C23 OK R38C21 OK i

l R37C20 OK R36C19 OK R3SC18 OK R35C17 OK l

R34C16 OK R33C16 OK AK R33C15 0

- PLUGGED FOREIG,N OBJECT (PIECE OF TUBING) BETWEEN R32C15

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R30Cl3 OK R30C12 OF R29Cll OK, R2RC11 OK R27C10 OK i

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PAGE 6 OF 7 Rev. 2 2/26 AEC 2-16-82 DATA REVIEW "B" S/G HOT LEG R26C9 OK R25C8 OK R24C8 OK.

R23C7 OK

-R22C7 OK R21C6 OK R20C5 OK R19C5 OK

.R18C5 OK R17C4 OK R16C4 OK R15C3 OK R14C3 OK R13C3 OK AL R12C2 OK - PLUGGED RllC2 OK t

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PAGE 7 OF 7 Rev. 2 2/26 AEC 2-16-82 DATA REVIEW "B" S/G HOT LEG R4C1 OK R3C1 OK R2C1 OK RlCl OK e

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PAGE 1 OF 6 J

a Rev. 2 2/126 AEC -

DATA REVIEt4 "B" S/G COLD LEG j

2-18-82 RIC92 OK R2C92 OK R3C92 OK

. R4C92 OK RSC92 OK R6C92 OK R7C92 OK R8C42 OK R9C91 OK R10C91 OK R11C91 OK R12C91 OK R13C90 OK R14C90 OK R15C90 OK 4

R16C89 OK R17C89 OK R18C88 OK R19C88 OK R20,C88 OK R21CB7 OK R22C86 OK

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PAGE 2 OP 6 Rev. 2 2/26 AEC

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2-18-82 DATA REVIEW B" S/G COLD LEG R23C86 OK R24C85 OK R25C85 OK R26C94 OK R27C83 OK R28C82 OK R29C82 OK R30C81

'R33C78 OK PIECE OF TUBING ON TUBE SHEET BETWEEN TUBES A R34C77 OK R35C76 OK R36C74 OK R37C73 OK R38C72 OK g

.R38C71 0K R39C70 OK R39C69 OK R40C68 OK R40C67 OK R41566 OK R41C65 OK l

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R45C49 OK

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R45C47 OK R45C46 OK R45C45 OK e

R45C44 OK R45C43 OK e

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PAGE 4 OF 6 Rev. 2 2/26 AEC DATA REVIEW "B" S/G COLD LEG 2-18-82 R45C42 OK R45C41 OK R45C40 OK R45C39 OK R44C38 OK R44C37 OK R44C36 OK R44C35 OK R43C34 OK R43C33 OK R43C32 OK R42C31 OK R42C30 OK R42C29 OK R41C28 OK g

R41C27 OK R40C26 OK R40C25 OK SMALL SOUARE OBJECT LAYING ON TUBE SHEET APPROXIMATELY 3/4" X 3/4" SOUARE - COVERED WITH SLUDGE DUST B R39C24 OK I

R39C23 OK

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2-18-82 R38C22 OK R38C21 OK R37C20 OK R36C19 OK R35C18 OK R35C17 OK R34C16 OK

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R33C15 OK -

R32C15 OK R30Cl2 OK R29Cll OK R28Cll OK R27C10 OK R26C9 OK R25C8 OK' (g

R24C8 OK R23C7 OK R22C7 OK R21C6 OK R20C5 OK e

R19C5 OK R18C5 OK e

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PAGE 6 OP 6 Rev. 2 2/26 AEC 2-18-82 DATA REVIEW "B" S/G COLD LEG R17C4 OK R16C4 OK R15C3 OK R14C3 OK L

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R12C2 OK RllC2 OK R10C2 OK.

R9C2 OK R8Cl OK R7C1 K

R6C1 OK - SCRAPED SURFAC'E RSCl OK - SCRAPED SURFACE R4Cl OK R3Cl OK 4.

R2Cl OK.

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.CAUSE INVESTIGATION l
- Original cause investigation for plugged tubes in outer periphery of "B" Steam Generator since May 1975.
Consideration of possible mechanical loading mechanisms on tubes between the 1st support plate and the tube sheet with flow induced vibration as a contributing factor.
- Current cause investigation since discovery of foreign objects in the shell annulus of "B" steam generation on 2/10/82.
Mechanical failure of plugged tubes as the result of impact by foreign objects in a high cross velocity field.
Progression of damage on structurally degraded plugged tubes with possible resultant damage to other tubes ir.cluding burnt tube.
6 a
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Potential Failure Mechanism Postulated Failure Mechanism supported by:
Fact that first indications on B Steam Generator periphery occurred at first outage (1976) following removal of downcomer resistance plate (1975).
Postulated Failure Mechanism cannot be confirmed without additional inspections, an'alysis and testing.
Steam Generator Program designed to provide information regarding other possible failure mechanisms.
Investigations not restricted to a single postulated cause.
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E. GINNA S/G B - POSTULATED TUBE FAILURE MECHANISM STAGE.
PRE-REQUISITE MECHANISMS,. LOADS,, FACTORS (1)
COLLAPSE PLUGGING GIVEN:
EXT. AP, 0VALITY, INITIAL DEGRADATION AND CROSS-FLOW VELOCITY WITH POSSIBLE TURBULENCE.
ADDITIONAL:
LATERAL LOAD DUE TO DYNAMIC IMPACT OF-s FOREIGN OBJECT (PRIMARY)
AXI'AL LOAD DUE TO RESTRAINT (SECONDARY)
(2)
TUBE DESTRUCTION 0
COLLAPSE FATIGUE 0 AXIAL RESTRAINT WITH OPERATING 0
SHREDDING /
AN NTS 0
POSSIBLY, PRIOR FRAGMENTATION 0
FLUID-ELASTIC VIBRATIONS IMPACT / WEAR
.I 10 FLOW VORTEX /EDDYS DAMAGE 0
FULL SEVERANCE 0
DEEP LOCAL WEAR FATIGUE AND/0R CONCURRENT WITH COLLAPSE h
PENETRATION
^
(3)
DOMIN0 SEVERED TUBE HINGED'AT WEAR AND LATERAL LQADING FROM TUBE WHIP LEADING TSP IN CROSS-FLOW FIELD TO COLLAPSE OF PLUGGED TUBE (S) AND BURST OF ACTIVE TUBE I
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GINNA STATION B - STEAM GENERATOR INSPECTION PLANS i
o EDDY CURRENT EXAMINATIONS 100% hot legs random sample cold legs random profilometry adjacent to repairs o
SECONDARY SIDE VIDEO INSPECTIONS i
periphery
~
tube lane 1
no. 4 wedge area following repairs t
' UPPER INTERNALS VISUAL INSPECTION o
loose parts
~
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GINNA STATION B - STEAM GENERATOR REPAIR PROGRAM o
CATEGORIZATION OF DEFECTS structurally degraded OD damage plugging criteria preventatively plugged o
METALLURGICAL SAMPLES access port EDM cutting U-bend removal o
, REPAIR ALTERNATIVES t
tube removal primary stabilization secondary stabilization I
plug removal l
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s GDMA STATION B-SIEAM GE2ERATOR
' HOT LED PERIPHEFE PLUGGED 7UEES CATEGORY NO. 4 WEDGE AREA NO. 6 WEDGE AREA OIHER AREAS 1.
Structurally R-45 c-53 R-44 c-58 R-8 c-92 Degraded R-45 c-54 R-43 c-59 R-11 C-91 R-44 c-55M R-43 c-60 R-12 c-91 R-44 c-56 R-43 c-61 R-14 c-90 R-44 c-57 R-42 c-55M R-15 c-90 2.
Not Stucturally R-45 c-51 R-9 c-91 R-38 c R-10 c-91 R-38 c-72 Degraded; CD R-13 c-90 R-39 c-68 da.mge R-16 c-89 R-39 c-69 R-17 c-89 R-39 c-70 3
Standard R-43 c-53* R-44 c-54*
R-15 c-89*
R-12 c-2 Plugging R-43 c-54* R-45 c-46 R-28 c-12**'
criteria R-43 c-55*M R-45 c-47M R-30 c-15**-
R-43 c-56* R-45 c-48 R-31 c-15**
R-43 c-57* R-45 c-49 R-32 c-15**
R-43 c-58 R-45 c-50 R-33 c R-32 c-16**
R-44 c-52*
R-35 c-75 R-44 c-53' R-40 c-67 R-40 c-68 R-41 c-66 4.
Preventatively R-41 c-55 Plugged Good R-42 c-54 R-42 c-56 t
Tubes 28 11 16 Totmln IM Primary metallurgical samples.
Video inspecticn results not currently avniinhle o
i due to physical location.
Not accessible for video inspection due to stay bar Go Revision 0 l
R-45 c-52 Pulled April 1978 2/25/82 J. Hutton
.a
t Ginna Station.
B-Steam Generator
~
No. 4 Wedge ~ Area 62 61 60 59 58 57 56 55 54 53 1
50 49 48 47 46
~
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% % X X -*-
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O O
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O O
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8 O
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41 O
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O O
O O
O O
O O
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40 kpulledApril1978(1 tube) gstructurallydegraded(10 tubes) pODdamage(1 tube)
-g. plugging criteria (14 tubes) preventatively plugged (3. tubes) g e
(
.f Ginna Station B-Steam Generator Ib. 6 Wedge Area 92 91 90 89 88 87 O
O O
19 O
O O
is kO O
O 17 kO O
O 16 k, 4-O O
O 15 fO O
O O
14 kO O
O O
13
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O 12
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5
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8 O
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7
_ structurally degraded (5 tubes)
OD' Damage (5 tubes)
+
plugging criteria (1 tube *)
l Y
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Ginna Station B-Steam Generator
~
RC40C70 Area 77 76 75 74 73 72 71 70 69 68 67 66 65 42
+
O 41 -
A
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o O
40 hhkO O
O 39 hhO O
O O
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38 O
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O O
O O
37 O
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O O
O O
O 36 O
+
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O O
O O
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35 P
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O O
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O 34 structurally degraded ('no tubes)
OD damage (5 tubes) 4 plugging criteria (4 tubes) j
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Ginna Station B-Steam Generator No. 2 Wedge Area 17 16 15 14 13 12 11 34 O
O 33 O
O -+-
32 O
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O 31 O
O +
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OD damage (no tubes **)
+
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+
stay bar
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1 GINNA STATION B - STEAM GENERATOR TESTING AND MONITORING o
GENERAL INVESTIGATIONS harp test knocker probe test l
alignment check b'reakaway force o
HYDROSTATIC TESTING primary r
1 secondary o
INSTRUMENTATION loose parts monitors accelerometers o
PERIODIC INSPECTIONS eddy current video
~
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GINNA STATION B - STEAM GENERATOR FAILURE MECHANISM DETERMINATION o
FIELD inspections tests instrumentation o
ANALYTICAL PROGRAM
~ i fluid dynamics
~
structural failure rate repair procedures EPRI/EGOG l
'o LABORATORY PROGRAMS metallurgical examinations model testing structural testing O
e
(_
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O DIANOSTIC ANALYSIS PROVIDE ANALYTICAL / EXPERIMENTAL EVIDENCE TO SUPPORT ESTABLISHMENT OF A FAILURE MECHANISM (S) SUCH THAT I
APPROPRIATE ACTI NS CAN BE TAKEN TO PERMIT A SAFE AND TIMELY RETURN TO POWER.
e e
CONSIDERATION OF DEBRIS' w
9 CONSIDERATION OF OTHER CONDIT0HS 9
USE OF PREVIOUS ANALYSIS / TEST RESULTS 4
USE OF PHYSICAL DATA OBTAINED FROM THIS EVENT 9
ADDITIONAL' ANALYSIS AND TESTING 6
9 e
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MECHANISM EVALUATION PROGRAM 9
INVESTIGATION OF VARIOUS INFLUENCES MECHANICAL LATERAL LOADS GROSS FLUID LOADS
~
AXIAL LOADS LOCAL FLUID LOADS 8
HISTORICAL INFORMATION REVIEW 8
INITIAL PERIMETER TUBE DAMAGE INVESTIGATION 8
LABORATORY EXAMINATION OF REMOVED TUBE SECTIONS S
MODEL TESTING.
8 LABORATORY COLLAPSE AND FATIGUE TESTING 8
FIELD TESTING AND EXAMINATION
~
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REPAIR ANALYSIS PROVIDE TECHNICAL JUSTIFICATION FOR REQUIRED MODIFICATIONS /
1 REPAIRS:
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ACCESS H0LE(S) e CRITERIA FOR DAMAGED TUBE REMOVAL 0
STABILIZATION OF PARTIALLY REMOVED TUBES EVALUATE EFFECT OF ACTIONS TAKEN ON THE OVERALL THERMAL, HYDRAULIC, AND STRUCTURAL PERFORMANCE OF THE UNIT 9
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ML20054C873

Contents

Text

Dear Mr. Wert:

Enclosure:

SUBJECT:

SUMMARY

Enclosures:

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ML20054C873

Text

Dear Mr. Wert:

Enclosure:

SUBJECT:

SUMMARY

Enclosures:

Navigation menu

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