ML18017B288: Difference between revisions

From kanterella
Jump to navigation Jump to search
(Created page by program invented by StriderTol)
(Created page by program invented by StriderTol)
 
Line 16: Line 16:


=Text=
=Text=
{{#Wiki_filter:SEOUL'ATOR+>>VFORNATION DISTRIBUTION
{{#Wiki_filter:SEOUL'ATOR+>>VFORNATION DISTRIBUTION                           +TEN     (RIBS)
+TEN (RIBS)ACCESS IOiV iVBR: 8012010339 DOC,~DATE: 80/11/24>>VO>>TARIZKD'!
ACCESS IOiV iVBR: 8012010339               DOC, ~ DATE: 80/11/24               >>VO>>TARIZKD'! NO                       DOC KEIT FACIL:50-400 Sbearon Harris Nuc1 ear Power Pl anti Unit 1 i Carolina                                                 05000400 50 401 Shear on Harri s Nucl ear Power Pl anti Uni t 2i Car ol ina                                         05000401 50 402 Shearon         Harris Nuc.leai Power Planti Unit 3i Carolina                                       05000402.
NO FACIL:50-400 Sbearon Harris Nuc1 ear Power Pl anti Unit 1 i Carolina 50 401 Shear on Harri s Nucl ear Power Pl anti Uni t 2i Car ol ina 50 402 Shearon Harris Nuc.leai Power Planti Unit 3i Carolina 50 403 Shearon Hartis Nuclear Power Planti U'nit 4i Carolina AUTH BYNAME.AUTHOR AFF>>IL>>I'ATION CHIANGiiN.J..
BYNAME.
Car ol>>ina, Power>>L Light Co>>,, RECIP-,NAME RECIPIE>>VT!
50 403 Shearon         Hartis Nuclear Power Planti U'nit 4i Carolina                                       05000403 AUTH                       AUTHOR AFF>>IL>>I'ATION CHIANGiiN.J..               Car ol>>ina, Power>> L Light Co>>,,
AFFILIATIO>>V
RECIP-,NAME                 RECIPIE>>VT! AFFILIATIO>>V .
.0'R E I LL>>Y i J~P"N Region 2'i Atlantai Office of the Director  
0 'R E I LL>>Y i J P
                  ~   "N         Region 2'i Atlantai Office of the Director


==SUBJECT:==
==SUBJECT:==
Forwards interim deficiency rept re 801017 confirmation of nonsafety hea'tingiventilation L a',ir con'ditioning for C-lass IE.mo.tor control ctrs.Due to extensive nature o,f problemi al 1 co,r r ective action expected to>>be comp>>lated by 810215~.DISTRISUTION CODE: BO>>9S COPIES RECEIVED:LiTR J>>ENCLI 3 SIZEl: 0'ITLE;Construction Deficienc'y Report (10CFRSO~55EO NOTES: DOC KEIT 05000400 05000401 05000402.05000403 RECK P IEV'T ID CODE'/>>VAME ACTION: A/D LIICENSNG'4 RUSHBROOK'EM' 06 INTERNALS:
Forwards interim deficiency rept re 801017 confirmation of nonsafety hea'tingiventilation L a',ir con'ditioning for C-lass IE. mo.tor control ctrs.Due to extensive nature o,f problemi al co,r r ective action expected to>> be comp>>lated by 810215 ~ .
AD'/RCI'/IEi 17 ASLBP/J,HARD EDO Ii'TAFFI 19 KYD/GKOi BR'2 LZC QUALI BR 12.NRC PDR 02, P'=4-RE>>Y'3 REG F>IL r 01~PROS DEiV'l COPIES LITTR ENCL." 1.1 1 1 1, 1 1 1 1.1 1, 1>>REC'IP IENT~ID-CODE/NA>>>>>>IE'OUNGBLOODEB>>
1 DISTRISUTION CODE: BO>>9S COPIES RECEIVED:LiTR J>> ENCLI 3                                         SIZEl:
05>>'HILSONEJERRY 07 AEOD 18'/D I R HUM F AC:1 5 EQUIP QUALI BR11.I tl Kr 09 MPA 20 OELD 21 QA BR'4 RUTHERFORD'i
Construction Deficienc'y Report (10CFRSO ~ 55EO                                             0'ITLE; NOTES:
'rf B IE>>COPIES LTTR ENCL>>1 1 1.1 1 1 1 1 1 1 1 1.1 1 1 1 1 1.1 EXTERNAL):
RECK P IEV'T           COPIES              REC'IP IENT            ~          COPIES ID CODE'/>>VAME           LITTR ENCL."      ID-                                  LTTR ENCL>>
ACRS NSIC>>16 08 16 16 1 1 LPDR 03>>DEC 2 1980 TOTAL>>NUMBER OF>>COPIES RKQUIRED: LTTR 39 ENCL>>39 C.g, r I a If E a%l FOAM 21-SOM File!SH N>>2/18 Xtem 52 Carolina Power&Light Company Aalelgh, N, C.27602 November 24, 1980 Mr.James P.O'Reilly United States Nuclear Regulatory'Commission, Region XX 101 Marietta Street, Northwest Atlanta, Georgia 30303 SHEARON HARRXS NUCLEAR POWER PLANT UNXTS 3.~2, 3 A1TD 4 DOCKET NOS.50-'400, 50-401, 50-402 AND 50-403 NONSAPETY HVAC POR CLASS lE MOTOR CONTROL CENTERS-INTERIM REPORT
CODE/NA>>>>>>IE'OUNGBLOODEB>>
ACTION:         A/D LIICENSNG'4               1. 1                                      05>>    1            1 RUSHBROOK'EM'         06       1      1    'HILSONEJERRY 07                          1.            1 INTERNALS: AD'/RCI'/IEi             17       1,          AEOD                                                    1 IR 18'/D ASLBP/J,HARD                 1                          HUM F AC:1 5                1            1 EDO     Ii'TAFFI   19                     EQUIP QUALI BR11.                                      1 KYD/GKOi       BR'2           1 1            I tl Kr                          09 1
1            1 LZC QUALI BR         12.       1.          MPA                              20      1.
BR'4 1
NRC     PDR         02,       1            OELD                              21      1            1 P       '= 4-   RE>>Y'3         1,          QA                                        1          1 REG     F>IL r     01 ~     1>>           RUTHERFORD'i 'rf B IE>>                   1.         1 PROS    DEiV'l EXTERNAL): ACRS                     16     16     16     LPDR                             03>>
NSIC>>                08        1      1 DEC   2 1980 TOTAL>> NUMBER         OF>> COPIES   RKQUIRED: LTTR       39     ENCL>>               39 C.g,


==Dear Mr.O'Reilly:==
r I
As required by 10CPR50.55(e), attached is an interim report on the subject deficiency.
a If E
Due to the extensive nature of the problem, all corrective action has not yet been completed and it is now anticipated that all, corrective action will be completed by Pebruary 15, 1981, at which'ime the final 10CPR50.55(e) report will be submi.tted.
 
Thank you for your consideration in'his matter.NJC/mt (425,627)Attachment cc: Mr.G.Maxwell W/A Mr.V.Stello (2)W/A Yours very truly, Original Signad By<.J.Chiangi N.J.Chiangi-Manager Engineering
a%
&Construction Quality Assurance  
l FOAM 21-SOM Carolina Power & Light Company Aalelgh, N, C. 27602 File!  SH  N>>2/18 Xtem 52 November 24, 1980 Mr. James P. O'Reilly United States Nuclear Regulatory'Commission, Region XX 101 Marietta    Street, Northwest Atlanta, Georgia 30303 SHEARON HARRXS NUCLEAR POWER PLANT UNXTS 3.~ 2, 3 A1TD 4 DOCKET NOS. 50-'400, 50-401, 50-402 AND 50-403 NONSAPETY HVAC POR CLASS lE MOTOR CONTROL CENTERS  INTERIM REPORT
~4y J~(~f rP<v (I 4 J l~)fg Pff." f~S f'.off'fd fife g fVt,ff 0f I~v'ff/~ff AA g j c l s'f f, far'".1 b'P f.f~I f'a ffl.g ff~1 4~r~f f ff g f{f f~1 f t~v'lf f a(s":u L4~~l*~6 f v~~~'4, ff C.V I~f gf[f v\f Oftf SHEARON HARRIS NUCLEAR POWER PLANT UNIT NO.1 NONSAFETY HVAC FOR CLASS 1E MOTOR CONTROL CENTERS Interim Report November 10, 1980 Reportable Under 10CFR50.55(e)
 
Prepared by: Carolina Power&Light Company  
==Dear Mr. O'Reilly:==
'Y'o  
 
As required by 10CPR50.55(e), attached is an interim report on the subject deficiency. Due to the extensive nature of the problem, all corrective action has not yet been completed and       it   is now anticipated that all, corrective action will be completed by Pebruary 15, 1981, at which'ime the final 10CPR50.55(e) report will be submi.tted.
Thank you   for your consideration   in'his         matter.
NJC/mt (425,627)                                                 Yours very truly, Attachment Original Signad By cc:   Mr. G. Maxwell W/A Mr. V. Stello (2) W/A
                                                                            <. J. Chiangi N. J. Chiangi Manager Engineering & Construction Quality Assurance
 
                                                                                                                          ~4y     J
                                                                                                  ~ (   ~   f rP
<v (I
4 l~)
fg J
Pff ."                 fife   g fVt,ff 0f     I ~       v   'ff/
                            ~ ff     AA         g   j c   l   s'f f, f'.off'fd f ~S far '   ". 1 b '     P f. f   ~   I f'     a ff  l. g r ~f f                                                             a(s   ":       u ff g    f{f                                                                            ~ ~ l *     ~ 6     fv ~
f
                                              ~
1 L4                                ~ ~ '4, ff                               f
~1 4    ~                      t~ v' ff lf f C. V I       ~f   gf   [f v\f Oftf
 
SHEARON HARRIS NUCLEAR POWER PLANT UNIT NO. 1 NONSAFETY HVAC FOR CLASS 1E MOTOR CONTROL CENTERS Interim Report November 10, 1980 Reportable Under 10CFR50.55(e)
Prepared by:   Carolina Power & Light Company
 
'Y 'o


==SUBJECT:==
==SUBJECT:==
10CFR50.55(e)
 
Reportable Item Shearon Harris Nuclear Power Plant" (SHNPP)Nonsafety HVAC for Class lE Motor Control Centers IT&fS: MCC's 1A-35SA, MCC 1B-35SB, 2A-35SA&2B-35SB SUPPLIED BY: Design-Ebasco Services, Inc.NATURE OF DEFICIENCY:
10CFR50.55(e) Reportable Item Shearon Harris Nuclear Power Plant" (SHNPP)
Class 1E Motor Control Centers are not cooled by safety-related HVAC, as stated in the SHNPP FSAR.DATE PROBLEM HAS CONFIRMED TO EXIST: 'ctober 17, 1980 PROBLEM REPORTED: October 17, 1980,-CP&L (L.I.Loflin, K.V.'ate&R.K.Cothren)informed the NRC Region II office (Mr.J.-K.Rausch)by telephone that the problem was"potentially reportable" under 10CFR50.55(e).
Nonsafety   HVAC for Class lE Motor Control Centers IT&fS:
October 27, 1980-CP&L (N.J.Chiangi)informed the NRC Region II office (Mr.J.K.Rausch)by telephone that the problem was reportable under 10CFR50.55(e).
MCC's 1A-35SA, MCC 1B-35SB, 2A-35SA       & 2B-35SB SUPPLIED BY:   Design Ebasco Services,     Inc.
SCOPE OF PROBLEM: Equipment located in the common area of the Reactor Auxiliary Building (RAB)between Units 1&2 at Elevations 261 and 236 are not supplied with safety-related HVAC and may not be qualified for the room temperatures which will be reached in the event that electrical power and hence, ventilation, is lost.REASONS(S)
NATURE OF DEFICIENCY:
PROBLEM WAS REPORTABLE:
Class 1E Motor Control Centers are not cooled by safety-related HVAC, as stated in the SHNPP FSAR.
Class lE equipment in the Unit One&Common Reactor Auxiliary Building is cooled by safety-related HVAC equipment in order to reduce the temperature extremes to which this equipment would be subjected in the event of a LOCA.The Motor Control Centers at the 261 elevation of the Units 1&2 Common RAB are 0 Class lE and are qualified to a room temperature of 104 F (40 C).The normal HVAC for this elevation, as well as the 236'ommon RAB elevation, has a Non-1E power supply.In the event of a loss of HVAC, the temperature in the area of the 0 Motor Control Centers could exceed 104 F (piping containing 0 120 F fluid passes through this area).Since the Motor Control Centers are not qualified for temperatures above 0 104 F, the continued functioning of the MCCs cannot be certified.
DATE PROBLEM HAS CONFIRMED TO EXIST:       'ctober   17, 1980 PROBLEM REPORTED:
This condition deviates from the SHNPP FSAR Section 3.11.4.1 which states that"Plant areas containing ESF and RPS equipment and their~su ort~s stems are temperature controlled to provide a controlled environment even during the most severe DBA condition." Since the design of the Unit 1: and Common RAB has been approved and released for construction, this condition constitutes a significant deficiency which does not conform to the criteria and bases stated in the Safety Analysis Report.CORRECTIVE ACTION: A design change has been developed and issued for incorporation which adds safety-related HVAC units at the 286 elevation of the Unit 1 and Common Reactor Auxiliary Building.These HVAC units will provide safety-related ventilation to MCCs 1A-35SA, 1B-35SB, 2A-35SA and 2B-35SB.In addition, the architect-engineer (Ebasco)is preparing detailed temperature maps of the plant in order to verify that no such condition exists elsewhere in the plant.A detailed review of each equipment item against the temperature expected to exist in the area of the plant where the item is located will then be conducted.
October 17, 1980, CP&L (L. I. Loflin, K. V.'ate & R. K.
This review is expected to be complete, design changes initiated, if required, and final report issued by February 15, 1981.
Cothren) informed the NRC Region       II office (Mr. J.- K. Rausch) by telephone   that the problem was "potentially reportable" under 10CFR50.55(e).
h\}}
October 27, 1980 CP&L (N. J. Chiangi) informed the NRC Region   II office (Mr. J. K. Rausch) by telephone that the problem was reportable under 10CFR50.55(e).
SCOPE OF PROBLEM:
Equipment located in the common area of the Reactor Auxiliary Building (RAB) between Units 1 & 2 at Elevations 261 and 236 are not supplied with safety-related HVAC and may not be qualified for the room temperatures which will be reached in the event that electrical power and hence, ventilation, is lost.
REASONS(S)   PROBLEM WAS REPORTABLE:
Class lE equipment in the Unit One & Common Reactor Auxiliary Building is cooled by safety-related HVAC equipment in order to reduce the temperature extremes to which this equipment would be subjected in the event of a LOCA. The Motor Control Centers at the 261 elevation of the Units 1 & 2 Common RAB     0 are Class lE and are qualified to a room temperature of 104 F (40 C). The normal HVAC for this elevation, as well as the 236'ommon RAB elevation, has a Non-1E power supply. In the event of a loss of HVAC, the temperature     0 in the area of the Motor 0
Control Centers   could exceed 104 F (piping containing 120 F fluid passes through this area).         Since the Motor Control 0
Centers are   not qualified for temperatures above 104 F, the continued functioning of the MCCs cannot be certified.
 
This condition deviates from the SHNPP FSAR Section 3.11.4.1 which states that "Plant areas containing ESF and RPS equipment and their ~su ort ~s stems are temperature controlled to provide a controlled environment even during the most severe DBA condition."
Since the design of the Unit   1: and Common RAB has been approved and released for construction, this condition constitutes a significant deficiency which does not conform to the criteria and bases stated in the Safety Analysis Report.
CORRECTIVE ACTION:
A design change has been developed and issued for incorporation which adds safety-related HVAC units at the 286 elevation of the Unit 1 and Common Reactor Auxiliary Building. These HVAC units will provide safety-related ventilation to   MCCs 1A-35SA, 1B-35SB, 2A-35SA and 2B-35SB.
In addition, the architect-engineer (Ebasco) is preparing detailed temperature maps of the plant in order to verify that no such condition exists elsewhere in the plant. A detailed review of each equipment item against the temperature expected to exist in the area of the plant where the item is located will then be conducted. This review is expected to be complete, design changes initiated, February 15, 1981.
if required, and final report issued by
 
h
\}}

Latest revision as of 04:06, 22 October 2019

Forwards Interim Deficiency Rept Re 801017 Confirmation of Nonsafety Heating,Ventilation & Air Conditioning for Class IE Motor Control Ctrs.Due to Extensive Nature of Problem, All Corrective Action Expected to Be Completed by 810215
ML18017B288
Person / Time
Site: Harris  Duke Energy icon.png
Issue date: 11/24/1980
From: Chiangi N
CAROLINA POWER & LIGHT CO.
To: James O'Reilly
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
References
10CFR-050.55E, 10CFR-50.55E, 52, NUDOCS 8012010339
Download: ML18017B288 (8)
v • d • e


Text

SEOUL'ATOR+>>VFORNATION DISTRIBUTION +TEN (RIBS)

ACCESS IOiV iVBR: 8012010339 DOC, ~ DATE: 80/11/24 >>VO>>TARIZKD'! NO DOC KEIT FACIL:50-400 Sbearon Harris Nuc1 ear Power Pl anti Unit 1 i Carolina 05000400 50 401 Shear on Harri s Nucl ear Power Pl anti Uni t 2i Car ol ina 05000401 50 402 Shearon Harris Nuc.leai Power Planti Unit 3i Carolina 05000402.

BYNAME.

50 403 Shearon Hartis Nuclear Power Planti U'nit 4i Carolina 05000403 AUTH AUTHOR AFF>>IL>>I'ATION CHIANGiiN.J.. Car ol>>ina, Power>> L Light Co>>,,

RECIP-,NAME RECIPIE>>VT! AFFILIATIO>>V .

0 'R E I LL>>Y i J P

~ "N Region 2'i Atlantai Office of the Director

SUBJECT:

Forwards interim deficiency rept re 801017 confirmation of nonsafety hea'tingiventilation L a',ir con'ditioning for C-lass IE. mo.tor control ctrs.Due to extensive nature o,f problemi al co,r r ective action expected to>> be comp>>lated by 810215 ~ .

1 DISTRISUTION CODE: BO>>9S COPIES RECEIVED:LiTR J>> ENCLI 3 SIZEl:

Construction Deficienc'y Report (10CFRSO ~ 55EO 0'ITLE; NOTES:

RECK P IEV'T COPIES REC'IP IENT ~ COPIES ID CODE'/>>VAME LITTR ENCL." ID- LTTR ENCL>>

CODE/NA>>>>>>IE'OUNGBLOODEB>>

ACTION: A/D LIICENSNG'4 1. 1 05>> 1 1 RUSHBROOK'EM' 06 1 1 'HILSONEJERRY 07 1. 1 INTERNALS: AD'/RCI'/IEi 17 1, AEOD 1 IR 18'/D ASLBP/J,HARD 1 HUM F AC:1 5 1 1 EDO Ii'TAFFI 19 EQUIP QUALI BR11. 1 KYD/GKOi BR'2 1 1 I tl Kr 09 1

1 1 LZC QUALI BR 12. 1. MPA 20 1.

BR'4 1

NRC PDR 02, 1 OELD 21 1 1 P '= 4- RE>>Y'3 1, QA 1 1 REG F>IL r 01 ~ 1>> RUTHERFORD'i 'rf B IE>> 1. 1 PROS DEiV'l EXTERNAL): ACRS 16 16 16 LPDR 03>>

NSIC>> 08 1 1 DEC 2 1980 TOTAL>> NUMBER OF>> COPIES RKQUIRED: LTTR 39 ENCL>> 39 C.g,

r I

a If E

a%

l FOAM 21-SOM Carolina Power & Light Company Aalelgh, N, C. 27602 File! SH N>>2/18 Xtem 52 November 24, 1980 Mr. James P. O'Reilly United States Nuclear Regulatory'Commission, Region XX 101 Marietta Street, Northwest Atlanta, Georgia 30303 SHEARON HARRXS NUCLEAR POWER PLANT UNXTS 3.~ 2, 3 A1TD 4 DOCKET NOS. 50-'400, 50-401, 50-402 AND 50-403 NONSAPETY HVAC POR CLASS lE MOTOR CONTROL CENTERS INTERIM REPORT

Dear Mr. O'Reilly:

As required by 10CPR50.55(e), attached is an interim report on the subject deficiency. Due to the extensive nature of the problem, all corrective action has not yet been completed and it is now anticipated that all, corrective action will be completed by Pebruary 15, 1981, at which'ime the final 10CPR50.55(e) report will be submi.tted.

Thank you for your consideration in'his matter.

NJC/mt (425,627) Yours very truly, Attachment Original Signad By cc: Mr. G. Maxwell W/A Mr. V. Stello (2) W/A

<. J. Chiangi N. J. Chiangi Manager Engineering & Construction Quality Assurance

~4y J

~ ( ~ f rP

<v (I

4 l~)

fg J

Pff ." fife g fVt,ff 0f I ~ v 'ff/

~ ff AA g j c l s'f f, f'.off'fd f ~S far ' ". 1 b ' P f. f ~ I f' a ff l. g r ~f f a(s ": u ff g f{f ~ ~ l * ~ 6 fv ~

f

~

1 L4 ~ ~ '4, ff f

~1 4 ~ t~ v' ff lf f C. V I ~f gf [f v\f Oftf

SHEARON HARRIS NUCLEAR POWER PLANT UNIT NO. 1 NONSAFETY HVAC FOR CLASS 1E MOTOR CONTROL CENTERS Interim Report November 10, 1980 Reportable Under 10CFR50.55(e)

Prepared by: Carolina Power & Light Company

'Y 'o

SUBJECT:

10CFR50.55(e) Reportable Item Shearon Harris Nuclear Power Plant" (SHNPP)

Nonsafety HVAC for Class lE Motor Control Centers IT&fS:

MCC's 1A-35SA, MCC 1B-35SB, 2A-35SA & 2B-35SB SUPPLIED BY: Design Ebasco Services, Inc.

NATURE OF DEFICIENCY:

Class 1E Motor Control Centers are not cooled by safety-related HVAC, as stated in the SHNPP FSAR.

DATE PROBLEM HAS CONFIRMED TO EXIST: 'ctober 17, 1980 PROBLEM REPORTED:

October 17, 1980, CP&L (L. I. Loflin, K. V.'ate & R. K.

Cothren) informed the NRC Region II office (Mr. J.- K. Rausch) by telephone that the problem was "potentially reportable" under 10CFR50.55(e).

October 27, 1980 CP&L (N. J. Chiangi) informed the NRC Region II office (Mr. J. K. Rausch) by telephone that the problem was reportable under 10CFR50.55(e).

SCOPE OF PROBLEM:

Equipment located in the common area of the Reactor Auxiliary Building (RAB) between Units 1 & 2 at Elevations 261 and 236 are not supplied with safety-related HVAC and may not be qualified for the room temperatures which will be reached in the event that electrical power and hence, ventilation, is lost.

REASONS(S) PROBLEM WAS REPORTABLE:

Class lE equipment in the Unit One & Common Reactor Auxiliary Building is cooled by safety-related HVAC equipment in order to reduce the temperature extremes to which this equipment would be subjected in the event of a LOCA. The Motor Control Centers at the 261 elevation of the Units 1 & 2 Common RAB 0 are Class lE and are qualified to a room temperature of 104 F (40 C). The normal HVAC for this elevation, as well as the 236'ommon RAB elevation, has a Non-1E power supply. In the event of a loss of HVAC, the temperature 0 in the area of the Motor 0

Control Centers could exceed 104 F (piping containing 120 F fluid passes through this area). Since the Motor Control 0

Centers are not qualified for temperatures above 104 F, the continued functioning of the MCCs cannot be certified.

This condition deviates from the SHNPP FSAR Section 3.11.4.1 which states that "Plant areas containing ESF and RPS equipment and their ~su ort ~s stems are temperature controlled to provide a controlled environment even during the most severe DBA condition."

Since the design of the Unit 1: and Common RAB has been approved and released for construction, this condition constitutes a significant deficiency which does not conform to the criteria and bases stated in the Safety Analysis Report.

CORRECTIVE ACTION:

A design change has been developed and issued for incorporation which adds safety-related HVAC units at the 286 elevation of the Unit 1 and Common Reactor Auxiliary Building. These HVAC units will provide safety-related ventilation to MCCs 1A-35SA, 1B-35SB, 2A-35SA and 2B-35SB.

In addition, the architect-engineer (Ebasco) is preparing detailed temperature maps of the plant in order to verify that no such condition exists elsewhere in the plant. A detailed review of each equipment item against the temperature expected to exist in the area of the plant where the item is located will then be conducted. This review is expected to be complete, design changes initiated, February 15, 1981.

if required, and final report issued by

h

\

Retrieved from "https://kanterella.com/w/index.php?title=ML18017B288&oldid=1958543"