ML19332C034

Responds to Generic Ltr 89-21, Request for Info Concerning Status of Implementation of USI Requirements, for Plant. Forecast Inplementation Dates Provided for USIs Reflect Previous Correspondence & Anticipated Restart Dates

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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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

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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

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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  !

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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

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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

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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.'

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  ;

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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

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ENCLOSURE 2  !

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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

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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!

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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.-

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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  !

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(" A-17 System Inter actton .NC Resolved by Generic Letter 89-18. No actions-required. ,

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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

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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

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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

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. 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

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~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 .

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, 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