ML19332C034: Difference between revisions
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: Pool Dynamic Loads Item A-7/D-01. | : Pool Dynamic Loads Item A-7/D-01. | ||
and Pressure Transients A-40 Seismic Design Criteria NC Action incorporated into j A-46. ij C- - Complete NC.- No Changes Necessary | and Pressure Transients A-40 Seismic Design Criteria NC Action incorporated into j A-46. ij C- - Complete NC.- No Changes Necessary | ||
'NA.- Not_ Applicable I - Incompiete- | 'NA.- Not_ Applicable I - Incompiete- | ||
' E - Evaluating A:tions Required ; | ' E - Evaluating A:tions Required ; | ||
Line 130: | Line 128: | ||
'U31/MPA' ! | 'U31/MPA' ! | ||
"- NUMBER TITLE . STATUS /DATE ., REMARKS l E A-42/ Pipe Cracks in Bolling 1/95 I' Required for restart. l B-05 Water Reactors Inspections / evaluations and 1 hardware required. . | "- NUMBER TITLE . STATUS /DATE ., REMARKS l E A-42/ Pipe Cracks in Bolling 1/95 I' Required for restart. l B-05 Water Reactors Inspections / evaluations and 1 hardware required. . | ||
k- Reference TVA. letter from s M. J. Ray to NRC.- dated 6/30/89 and NRC 4/24/89 meeting notes. | k- Reference TVA. letter from s M. J. Ray to NRC.- dated 6/30/89 and NRC 4/24/89 meeting notes. | ||
!' A-43 Containment Emergency NC' The resolution of this USI: a Sump Performance 'did not involve changes to ; | !' A-43 Containment Emergency NC' The resolution of this USI: a Sump Performance 'did not involve changes to ; | ||
Line 153: | Line 150: | ||
-A-49 Pressurized Thermal NA Applicable to PWR's only. | -A-49 Pressurized Thermal NA Applicable to PWR's only. | ||
, Shock ; | , Shock ; | ||
't | 't CD- Complete | ||
CD- Complete | |||
'NC ..No Changes Necessary < | 'NC ..No Changes Necessary < | ||
4 lNA'- 'Not Applicattle li . Incomplete E - . Evaluating. Actluns Requirt d | 4 lNA'- 'Not Applicattle li . Incomplete E - . Evaluating. Actluns Requirt d | ||
Line 185: | Line 179: | ||
, A-6 . Mark I.Short-Term' 12/8/78 C Closed by License Amendment; | , A-6 . Mark I.Short-Term' 12/8/78 C Closed by License Amendment; | ||
' Program- .42 which incorporated . | ' Program- .42 which incorporated . | ||
.drywell-suppression chamber ' | .drywell-suppression chamber ' | ||
differential pressure and q chamber water. level " | differential pressure and q chamber water. level " | ||
requirements. | requirements. | ||
A-7/. Mark I Long-Term 5/90 I Required for resta'rt. . | A-7/. Mark I Long-Term 5/90 I Required for resta'rt. . | ||
Line 205: | Line 197: | ||
.NA ~Not Applicable I - Incomplete E' Evaluating Actions Required * | .NA ~Not Applicable I - Incomplete E' Evaluating Actions Required * | ||
- e y Q;g | - e y Q;g 1a.- - ENCLOSURE 2-(Continued) ll~' | ||
1a.- - ENCLOSURE 2-(Continued) ll~' | |||
BROWNS FERRY' NUCLEAR POWER PLANT - UNIT 2 | BROWNS FERRY' NUCLEAR POWER PLANT - UNIT 2 | ||
. STATUS Of UNRESOLVED SAFETY ISSUES FOR WHICH A A BEEN ACHIEVED FINAL TECHNICAL RESOLUTION _HAS k " | . STATUS Of UNRESOLVED SAFETY ISSUES FOR WHICH A A BEEN ACHIEVED FINAL TECHNICAL RESOLUTION _HAS k " | ||
Line 236: | Line 226: | ||
C-15' l! | C-15' l! | ||
A-39 -Determination-of SRV NA Resolved under Pool-Dynamic Loads -Item A-7/0-01. | A-39 -Determination-of SRV NA Resolved under Pool-Dynamic Loads -Item A-7/0-01. | ||
'and Pressure Transients A . Seismic Design Criteria- NC Action incorporated into l A-46. ! | 'and Pressure Transients A . Seismic Design Criteria- NC Action incorporated into l A-46. ! | ||
C L- Complete NC - No Chrnges Necessary NA'- Not Applicable 1 | C L- Complete NC - No Chrnges Necessary NA'- Not Applicable 1 | ||
Line 266: | Line 255: | ||
p V | p V | ||
: g. - | : g. - | ||
. ENCLOSURE 3 g BROWNS FERRY NUCLEAR POWER PLANT - UNIT 3 | . ENCLOSURE 3 g BROWNS FERRY NUCLEAR POWER PLANT - UNIT 3 | ||
Line 275: | Line 263: | ||
; changes not identified. No isolation condensers at BFN. | ; changes not identified. No isolation condensers at BFN. | ||
A -/ Asymmetric Blowdown NA Applicable to PWR's only. | A -/ Asymmetric Blowdown NA Applicable to PWR's only. | ||
D Loads on Reactor Primary Coolant Systems A-3 Westinghouse Steam NA Applicable to Westinghouse | D Loads on Reactor Primary Coolant Systems A-3 Westinghouse Steam NA Applicable to Westinghouse Generator Tube Integrit.v PWR's only. < | ||
Generator Tube Integrit.v PWR's only. < | |||
.A-4 CE Steam Generator Tube NA Applicable to CE PWR's only. | .A-4 CE Steam Generator Tube NA Applicable to CE PWR's only. | ||
Integrity A-5 B&W Steam Generator Tube NA Applicable to B&W PWR's Integrity only. | Integrity A-5 B&W Steam Generator Tube NA Applicable to B&W PWR's Integrity only. |
Latest revision as of 12:56, 18 February 2020
ML19332C034 | |
Person / Time | |
---|---|
Site: | Browns Ferry |
Issue date: | 11/15/1989 |
From: | TENNESSEE VALLEY AUTHORITY |
To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
References | |
TASK-***, TASK-OR GL-89-21, NUDOCS 8911220229 | |
Download: ML19332C034 (11) | |
Text
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TENNESSEE VALLEY. AUTHORITY CHATTANOOGA. TENNESSEE 37401 SN 157B Lookout Place NOV 151989 l c
l U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D.C. 20555 Gentlemen:
In the Matter of ) Docket Nos. 50-259 Tennessee Valley Authority ) 50-260 50-296 i
BROWNS FERRY NUCLEAR PLANT (BFN) - STAIUS OF IMPLEMENTATION Of UNRESOLVED SAFETY ISSUE (USI) REQUIREMENTS (GENERIC LETTER B9-21)
This letter provides TVA's response to Generic Letter B9-21, Request for
-Information Concerning Status of Implementation of Unresolved Safety Issue-(USI) Requirements, for BFN. Enclesure 1 provides the status of USIs for BFN Unit 1. Enclosure 2 provides the status of USIs for BFN Unit 2. Enclosure 3 '
provides the status of USIs for BFN Unit 3.
This letter does not include new commitments. Forecast implementation dates
-provided for USIs reflect previous correspondence and currently anticipated restart dates. If you have any questtons, please telephone Patrick P. Carter '
at (205) 729-3570.
Very truly yours, !
TENNESSEE VALLEY AUTHORITY ,
D '6icensing Manager, Nuclear and Regulatory Affairs Enclosures cc: See page 2
()h 1
41 8911220229 891115 An Equal Opportunity Employer 4
PD8t ADOCK 05000259 P PNV
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\ '
. U.S. Nuclear Regulatory Commission NOV 15 389 cc (Enclo'sures):
!. Ms. S. C,' Black, Assistant Director l ~
for-Projects TVA Projects Division i- U.S. Nuclear Regulatory Commission One White Flint, North 11555 Rockville Pike p
Rockville, Maryland 20852 l Mr. B. A.. Wilson, Assistant Director
- for Inspection Programs TVA Projects Division-U.S. Nuclear Regulatory Commission Region II P 101 Marletta Street,'NW, Suite 2900
, Atlanta, Georgia 30323 NRC Resident Inspector Browns Ferry Nuclear Plant Route 12, Box 637-Athens, Alabama 35609-2000 l
I l
4 i
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i 4 . e g ,-2 1, i; ; ENCLOSURE 1 h BROWNS FERRY NUCLEAR POWER PLANT - UNIT 1 j
' STATUS OF UNRESOLVED SAFETY ISSUES FOR WHICH A >
Iz FINAL TECHNICAL _RESQLUTION HAS BEEN ACHIEVED !
\" l i; .
fP USI/MPA. ;
NUMBER, TITLE STATUS /DATE REMARKS L
F A-1 - Water Hammer NC The resolution of this USI did not. involve hardware or
+
design changes to operating- ;
li . plants. Plant specific procedure or training !
^l changes not Identified. No ;
, ' isolation condensers at BFN. ,
! . A-2/ Asymmetric Blowdown NA Applicable to PWR's only.
0-10 Loads on Reactor Primary
[:- Coolant Systems L .
L A-3 - Westinghouse Steam- NA Applicable-to Westinghouse L Generator Tube Integrity PWR's only, i:
A-4 CE Steam Generator Tube. NA Applicable to:CE PWR's only.
Integrity-g' A-5 B&W Steam Generator Tube- NA -Applicable to B&W PWR's Integrity: only.
A-6= Mark I Short-Term 12/8/78 C . Closed by License Amendment n Program 46 which incorporated
- .. drywell-suppression chamber differential pressure >and chamber water level requirements, b A-7/ Mark I Long-Term 1/95 I Required for restart.
0-01 Program Hardware required.
Reference BFN Performance Plan, Section-III.3.1.
A-8 Mark II Containment NA Applicable to Mark II BWR's Pool Dynamic Loads: only.
-A-9 Anticipated Transients 1/95 I Required for restart.
Without Scram Hardware required.
Diversity issue also requires resolution.
Reference TVA letter from
. M. J. Ray to NRC, dated 6/16/89.
C : - Complete .
NC - No Changes Necessary
- NA Not App 11 cable' I: - Incomplete E - Evaluating Actions Required im y
ffu. .
, y
+
~ '
[ + .
' ENCL 0SURE 1.(Continued) -
BROWNS' FERRY NUCLEAR POWER PLANT - UNIT 1 ,
STATUS Of UNRESOLVED SAFETY ISSUES FOR WHICH A FINAL TECHNICAL RESOLUTION HAS BEEN ACHIEVED ,
~ USI/MPA NUMBER' TITLE STATUS /DATE REMARKS l i
s - A-10/ BHR Feedwater Nozzle 12/11/84 C Date_ installation of Itak '
. B Cracking. detection. system completed. ,
' A-ll Reactor Vessel Material NA TVA will' submit Technical--
Toughness Specification revisionscto ,
comply with Regulatory Guide 1.99, Revision 2, prior _tol3/1/91 or fuel load. Reference TVA. letter from M.-J. Ray to NRC, !
dated 11/30/88.'
A-12 Fracture' Toughness of NA Applicable to PNR's oi y.
l Steam Generator and Reactor Coolant Pump ~ i Supports l
-~A-17 , . System. Interaction. NC Resolved by Generic Letter [
89-18. No actions required. -
A-24/ Qualification of Class 1/95 I Required for restart, a B-60 IE Safety-Related Hardware and procedures Equipment required.
l A-26/- Reactor. Vessel Pressure NA Applicable to PHR's only.
B-04 Transient Protection q A-31 . Residual Heat Removal NA" Generally applicable to +
. Shutdown Requirements OL's after 01/79 only. No -- ;
BFN specific action 3 required.
'A-36/ Control of Heavy Loads 1/95 I Required for restart.
- C-10, Near Spent Fuel ' Hardware required.
C-15 <
A-39 Determination of SRV NA Resolved under
- Pool Dynamic Loads Item A-7/D-01.
and Pressure Transients A-40 Seismic Design Criteria NC Action incorporated into j A-46. ij C- - Complete NC.- No Changes Necessary
'NA.- Not_ Applicable I - Incompiete-
' E - Evaluating A:tions Required ;
4 c-, -
% ~
j{r j,j. .
ENCLOSURE 1-(Continued)
BROWNS FERRY NUCLEAR POWER PLANT - UNIT 1 y
STATUS OF UNRESOLVED SAFETY ISSUES FOR WHICH A- )
FINAL TECHNICAL RESOLUTION HAS BEEN ACHIEVED ;
i
'U31/MPA' !
"- NUMBER TITLE . STATUS /DATE ., REMARKS l E A-42/ Pipe Cracks in Bolling 1/95 I' Required for restart. l B-05 Water Reactors Inspections / evaluations and 1 hardware required. .
k- Reference TVA. letter from s M. J. Ray to NRC.- dated 6/30/89 and NRC 4/24/89 meeting notes.
!' A-43 Containment Emergency NC' The resolution of this USI: a Sump Performance 'did not involve changes to ;
operating plants.
I t A-44 Station Blackout 1/95-I Required for' restart. i
[? . Procedures required.
Reference TVA' letter from ;
e C..H. Fct to NRC, dated -;
L 4/18/89.- ;
i A-45 Shutdown Decay Heat NC Issue.to De addressed
- Removal Requirements. under Generic Letter 88 . -
(IPE). 1 1
L ~A-46; Seismic Qualification' I (Prior to Walkdowns/ evaluations..
of Equipment in Cycle 7)- ' required. Reference TVA-Operating Plants letter from R.'L. Gridley '
to NRC, dated October 5 ,
1988. l
< A-47 Safety Imnlication E. Response to' Generic Letter J
~of Contr,i Systems 89-19 due 3/13/90, i A-48 Hydrogen Control 1/95 I Required for restart.
Measures and Effects Hardware required, ~
t of Hydrogen Burns Reference License Amendment 142 which requires nitrogen >
supply'to Containment i' Atnospheric Dilution System.
-A-49 Pressurized Thermal NA Applicable to PWR's only.
, Shock ;
't CD- Complete
'NC ..No Changes Necessary <
4 lNA'- 'Not Applicattle li . Incomplete E - . Evaluating. Actluns Requirt d
- %. > .O -
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ENCLOSURE 2 !
"+
BROWNS FERRY NUCLEAR POWER FLANT - UNIT 2-STATUS OF UNRESOLVED-SAFETY ISSUES FOR-WHICH A.
FINAL TECHNICAL-RESOLUTION HAS BEEN ACHIEVED i
o USI/MPA F NUMBER' TITLE STATUS /DATE. REMARKS l
\
V I c: A-1 . -Water Hammer NC The resolution of.this'USI .I f did not involve hardware or ~
c , design changes to operati.ng- "
plants. Plant specific' procedure or training. !
changes not Identified. No!
(
isolation condensers at BFN. ;
o 1 A-2/ Asymmetric Blowdown NA Applicable to PHP's only. ;
P D-10 Loads on Reactor Primary i L : Coolant Systems ,
p.
.A-3 Westinghouse Steam NA Applicable to bestinghouse j
1 Generator Tube Integrity' PWR's only, L r A CE Steam Generator Tube NA Applicable to CE PWR's only. 4 r : Integrity ;
U A-5 B&W Steam Generator Tube NA Applicable to B&W PWR's' ,
Integrity only. ;
, A-6 . Mark I.Short-Term' 12/8/78 C Closed by License Amendment;
' Program- .42 which incorporated .
.drywell-suppression chamber '
differential pressure and q chamber water. level "
requirements.
A-7/. Mark I Long-Term 5/90 I Required for resta'rt. .
0-01 Program Hardware. required. -!
Reference BFN Performance
, Plan, Section 11.3.1. t so m
- Applicable to Mark 11 BWR's
'A-8 Mark II Containment NA Pool Dynamic Loads only.
A-9 Anticipated Transients 5/90 I Required for restart.
Without Scram Hardware required. :
Diversity issue also requires resolution.
Reference TVA letter from M. J. Ray to NRC, dated
' 6/16/89.
C - Complete
- NC - No Changes Necessary
.NA ~Not Applicable I - Incomplete E' Evaluating Actions Required *
- e y Q;g 1a.- - ENCLOSURE 2-(Continued) ll~'
BROWNS FERRY' NUCLEAR POWER PLANT - UNIT 2
. STATUS Of UNRESOLVED SAFETY ISSUES FOR WHICH A A BEEN ACHIEVED FINAL TECHNICAL RESOLUTION _HAS k "
LUSI/MPA-
! NL'MBER TITLE- STATUS /DATE REMAR_KS !
t A-10/~ BHR Feedwater Nozzle -S/90 I Required for restart.
'B-25 Cracklag, Hardware required.-
1 ,
A-Il Reactor Vessel Material NA TVA will. submit Technical; j Toughness Srecification, revisions to ,
,, comply with Regulatory Guide 1;99;-Revision.2,. prior to ;
3/1/91. Reference TVA l Lletter from M. J. Ray to- 1 I. NRC, dated 11/30/88. l L .
E A Fracture Toughness of NA Applicable to PWR's only, !
Steam Generator and- .
Reactor Coolant Pump -
i
. Supports !
'l
(" A-17 System Inter actton .NC Resolved by Generic Letter 89-18. No actions-required. ,
s ,
A-24/- Qualification of Class 5/90 I Required for restart.
B-60 IE Safety-Related- Hardware required.
-Equipment A-26/ Reactor Vessel Pressure NA . Applicable to'PWR's only. -
L B-04 Transient Protection ,
A : Residual Heat Removal NA' Generally applicable to Shutdown Requirements OL's. af ter 01/79: only. No ,;
BFN specific action ' q required. ,
A-36/. Control of Heavy Loads 5/90_I Required for restart. .
' C-10,- Near Spent Fuel Submittal required.
C-15' l!
A-39 -Determination-of SRV NA Resolved under Pool-Dynamic Loads -Item A-7/0-01.
'and Pressure Transients A . Seismic Design Criteria- NC Action incorporated into l A-46. !
C L- Complete NC - No Chrnges Necessary NA'- Not Applicable 1
1 - Incomplete
- E - Evaluating Actions Reautred
?>
(, ,
.~ ... .
+
,. ENCLOSURE 2 (Continued) m BROHNS FERRY NUCLEAR' POWER PLANT - UNIT 2 i STATUS OF UNRESOLVED SAFETY ISSUES FOR WHICH A-FINAL TECHNICAL RESOLUTION HAS BEEN ACHIEVED' USI/MPA~
NUMBER TITLE _
STATUS /DATE REMARKS
'o '
A-42/ Pipe Cracks in Bolling 6/30/89 C Reference TVA letter from B-05 Hater Reactors M. J. Ray to NRC, dated June 30, 1989.
A-43 Containment Emergency- -NC The-resolutton of this USI Sump Performance did not involve changes to operating plants.
A Station Blackout I Implementation pending receipt of Safety.
Evaluation. Procedures required. Reference TVA F
letter from C. H. Fox to NRC, dated 4/18/89.
L- A-45. Shutdown Decay Heal NC Issue to be-addressed-p Removal Requirements under Generic Letter 88-20 L (IPE).
L P A-Co Seismic Qualification I (Prior to Walkdowns/ evaluations m ,
of Equipment '1 Cycle 8) required. Reference TVA' Operating Plaus lettee from M. J. Ray to-t
.NRC, cated July 31, 1989.
A-47 Safety Implication E Response to Generic-Letter of Control Sy';tems 89-19 due 3/19/90.
A-48 Hydrogen Control 9/30/88 C Date modification to add Measures and Effects nitrogen supply to of. Hydrogen Burns Contai nment . Atmospheric Dilution System completed.
Reference-License Amendment 138.
A-49 -Pressurized Thermal NA Applicable to PWR's ohly.
J Shock C Complete NC --No Changes Necessary NA - Nc,t Applicable I . Incomplete E - Evaluating Actions Required h
p V
- g. -
. ENCLOSURE 3 g BROWNS FERRY NUCLEAR POWER PLANT - UNIT 3
- ~ STATUS OF UNRESOLVED SAFETY ISSUES FOR WHICH A FINAL TECHNICAL RESOLUTION HAS BEEN ACHIEVED ,
USI/MPA' i NUMBER TITLE STATUS /DATE REMARKS A-1 Water Hammer NC The resolution of this USI l did not involve hardware or design changes to operating- ,
plants. Plant specific "
procedure or training ;
- changes not identified. No isolation condensers at BFN.
A -/ Asymmetric Blowdown NA Applicable to PWR's only.
D Loads on Reactor Primary Coolant Systems A-3 Westinghouse Steam NA Applicable to Westinghouse Generator Tube Integrit.v PWR's only. <
.A-4 CE Steam Generator Tube NA Applicable to CE PWR's only.
Integrity A-5 B&W Steam Generator Tube NA Applicable to B&W PWR's Integrity only.
, A-6 Mark I Short-Term 12/8/76 C Closed by License Amendment Program 19 which incorporated drywell-suppression chamber .
differential pressure and L chambt= water level requirements, ,
'A-7/ Mark I Long-Term 1/93 I Required for restart. 5 D-01 Program Hardware required.
Reference BFN Performance, '
Plan, Section 111.3.1.
A-8 Mark II Containment NA Applicable- to Mark II BWR's Pool Dynamic Loads only.
A-9 Anticipated Transierts 1/93 I Required for restart.
Without Scrcm Hardware required.
Diversity issue also requires resolution.
Reference TVA 6/16/89 letter from M. J. Ray to 4RC, dated 6/16/89.
i C - Complete NC - No Changes Necessary NA - Not Applicable I - Incomplete ;
E - Evaluating Actions Required
4; o
- 3 ..
- 4 1
-;=
~q #n ENCLOSURE 3 (Continued) i BROWNS FERRY NUCLEAR POWER ?LANT - UNIT'3 i STA1US Of UNRESOLVE0 SAFETY ISSUES FOR WHICH A l FINAL TECHNICAL RESOLUTION HAS BEEN ACHIEVE 0 -l I
!i 'USI/MPA~~
NUMBER: TITLE STATUS /DATE REMARKS A-10/ BHR Feedwater Nozzle 10/15/84 C- Date install'ation of leak j E B-25 iCracking detection system completed. ;
5 A-11. Reactor Vessel Material NA TVA will submit Technical 4 '
Toughness Specification revisions to comply with Regulhtory ;
n- -
Guide 1.99, Revision 2,- 1 pricr to 3/1/91. Reference j TVA' letter from M. J. Ray- l to NRC, dated 11/30/88. -
)
A-12.. Fracture Toughness of NA~ Applicable to PWR's only.
Steam Generator and :
Reactor Coolant Pump '
. Supports , j A-17 ' System Interaction NC Resolved by Generic Letter - 89-18. No actions required.
A-24/ Qaalification of Class 1/93 I Required'for restart.
B IE Safety-Related Hardware and proe.edures.
Equipment required. j A-26/ ' Reactor Ve'ssel Pressure NA Anp11 cable to PWR's'only.- i B-04 Transient-Protection A Residual Heat Removal- NA Generi.11y applicable to ;
Shutdown Requirements- OL's after 01/79 only. No .i BFN specific action required. ;
A-36/- Control ~of Heavy Loads 1/93 I Required for restart.
C-10,. Near Spent Fuel Hardware required. >
C-15
'A-39 Determination of SRV NA Resolved under ,
Pool Dynamic Loads Item A-7/D-01. -
and Pressure Transients A-40.- Seismic Design Criteria NC Action incorporated into A-46.
C - Complete NC - No Changes Necessary NA - Not Applicable
'I . Incomplete E - Evaluating Actions Required .
i
g , -.-
' g ,:
f'. '. .
, ENCLOSURE 3 (Continued)
BROWNS FERRY NUCLEAR POWER PLANT - UNIT 3 STATUS Of UNRESOLVED SAFETY ISSUES FOR WHICH A ,
_ FINAL TECHNICAL RESOLUTION HAS BEEN ACHIEVED U$1/MPA NUMBER TITLE STATUS /DATE REMARKS
[ A-42/
B-05 Pipe Cracks in Bolling Hater Reactors 1/93 I. Required for restart.
Inspections / evaluations and i L
L hardware required.
n Reference TVA letter from..
M. J. Ray to NRC, cated 6/30/89 and NRC 4/24/89.. '
n meeting notes.
A-43 Containment Emergency NC The resolution of this USI Sump Performance did not involve changes to operating plants.
A-44 Station Blackout 1/93 I Required for restart.
Procedures required. ,
Reference TVA letter from C. H. Fox to NRC, dated ;
4/18/89. .
A-45 Shutdown Decay Heat NC Issue to be addressed -
Removal Requirements under Generic Letter 88-20 (IPE).
A Selsmic Qualification- I (Prior to Walkdowns/ evaluations of Equipment in Cycle Ti required. Reference TVA '
Operating Plants letter from R. L. Gridley to NRC, dated October 5, 1988.
A-47 Safety Implication E Response to Generic Letter of Control Systems 89-19 due 3/19/90. ;
A-48 Hydrogen Control 1/93 I Required for restart.
Measures and Effects Hardware required. '
of Hydrogen Burns Reference License Amendment 113 which requires nitrogen supply to Containment Atmospheric Dilution System.
A-49 Pressurized Thermal NA Applicable to PWR's only. *
- Shock C - Complete NC - No Changes Necessary NA - Not Applicable I. - Incomplete.
E . Evaluating Actions Required