ML19332C034
| 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) | |
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s TENNESSEE VALLEY. AUTHORITY CHATTANOOGA. TENNESSEE 37401 SN 157B Lookout Place NOV 151989 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. provides the status of USIs for BFN Unit 2.
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 '6 Manager, Nuclear icensing and Regulatory Affairs Enclosures cc: See page 2
()h 141 8911220229 891115 PD8t ADOCK 05000259 An Equal Opportunity Employer 4
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NOV 15 389 U.S. Nuclear Regulatory Commission cc (Enclo'sures):
Ms. S. C,' Black, Assistant Director l
for-Projects TVA Projects Division
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i-U.S. Nuclear Regulatory Commission One White Flint, North 11555 Rockville Pike Rockville, Maryland 20852 p
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
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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
\\"
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f USI/MPA.
P
- 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
NA Applicable-to Westinghouse L
A-3
- Westinghouse Steam-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 Program 46 which incorporated n
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
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' 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.'
l A-12 Fracture' Toughness of NA Applicable to PNR's oi y.
Steam Generator and Reactor Coolant Pump ~
l i
Supports
-~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
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ENCLOSURE 1-(Continued)
BROWNS FERRY NUCLEAR POWER PLANT - UNIT 1 STATUS OF UNRESOLVED SAFETY ISSUES FOR WHICH A-
)
y 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 M. J. Ray to NRC.- dated s
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.
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. 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 lNA'- 'Not Applicattle 4
li
. Incomplete
- %. >.O E -. Evaluating. Actluns Requirt d y
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3 ec m
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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
USI/MPA o
F NUMBER' TITLE STATUS /DATE.
REMARKS V
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I c:
A-1.
-Water Hammer NC The resolution of.this'USI
.I f
did not involve hardware or
~
, design changes to operati.ng-c plants.
Plant specific' procedure or training.
changes not Identified.
No!
isolation condensers at BFN.
(
A-2/
Asymmetric Blowdown NA Applicable to PHP's only.
o 1
i P
D-10 Loads on Reactor Primary L
- Coolant Systems p.
.A-3 Westinghouse Steam NA Applicable to bestinghouse 1
Generator Tube Integrity' PWR's only, j
L r
A CE Steam Generator Tube NA Applicable to CE PWR's only.
4
- Integrity r
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
'A-8 Mark II Containment NA Applicable to Mark 11 BWR's 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
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ENCLOSURE 2-(Continued) ll~'
BROWNS FERRY' NUCLEAR POWER PLANT - UNIT 2 STATUS Of UNRESOLVED SAFETY ISSUES FOR WHICH A FINAL TECHNICAL RESOLUTION _HAS BEEN ACHIEVED A
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
. Supports i
'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.
l
' C-10,-
Near Spent Fuel Submittal required.
C-15' 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 - Incomplete 1
- E - Evaluating Actions Reautred
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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 A-42/
Pipe Cracks in Bolling 6/30/89 C Reference TVA letter from
'o 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 of Equipment '1 Cycle 8) required.
Reference TVA' m
Operating Plaus lettee from M. J. Ray to-
.NRC, cated July 31, 1989.
t 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 BROWNS FERRY NUCLEAR POWER PLANT - UNIT 3 g
- ~
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 ENCLOSURE 3 (Continued) i
-;=
~q #n BROWNS FERRY NUCLEAR POWER ?LANT - UNIT'3 i
STA1US Of UNRESOLVE0 SAFETY ISSUES FOR WHICH A 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 f'. '..
' g,:
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/
Pipe Cracks in Bolling 1/93 I.
Required for restart.
L B-05 Hater Reactors Inspections / evaluations and i
L hardware required.
Reference TVA letter from..
n M. J. Ray to NRC, cated 6/30/89 and NRC 4/24/89..
meeting notes.
n 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