ML19332D647

Forwards Listing of USIs for Which Technical Resolution Has Been Achieved in Response to 891019 Generic Ltr 89-21 Re Status of Implementation of USI Requirements.Encl Status Based Upon Review of Correspondence Between NRC & Util

ML19332D647
Person / Time
Site:	Brunswick
Issue date:	11/27/1989
From:	Loflin L CAROLINA POWER & LIGHT CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
REF-GTECI-MI, REF-GTECI-SC, TASK-***, TASK-OR GL-89-21, NLS-89-308, NUDOCS 8912050076
Download: ML19332D647 (7)

Text

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SERIALt NLS-89-3L8 q l'

I' United States Nuclear Regulatory Commission-ATTENTION Document Control Desk l

Washington, DC. 20555 BRUNSWICK STEAM ELECTRIC PLANT, UNIT NOS. 1 AND 2

-DOCKET NOS. 50-325 & 50-324/ LICENSE NOS. DPR-71 & DPR-62 RESPONSE TO NRC CENERIC LETTER 89-213 REQUEST FOR INFORMATION CONCERNING STATUS'0F IMPLEMENTATION OF-UNRESOLVED SAFETY ISSUE (USI) REQUIREMENTS

.Centlement' ,

The infomation attached is provided in response to your Generic Letter 89-21 dated. October 19, 1989 regarding the status of implementation of Unresolved Safety Issue (USI) requirements. -Please note that the time provided to

-  : determine the status of implementation of all USIs as required by ycur request has been short. Therefore, the attached notations regarding the status of' i.

individual items are necessarily brief and cannot address all of the details .

of the more complex issues. The attached status has been compiled based upon a review of correspondence between CP&L and the NRC such as Safety Evaluation-i Reports (SER) and Inspection Reports, as well as other plant-specific i documents.

1; l 'If-you have any' questions concerning this information, please contact .

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'Mr. H.-R. Oates at (919)546-6063.

Yours very truly.

I. --

L. I. L f n l Manage Nuclear Licensi g Section

'LIL/LSR/lbf (539CRS)

! Attachment-

, ;~ cc Mr. S. D. Ebnet-s Mr. W. H. hulat. .

Mr. E. C. Tour!gny

/plb 411 Fayetteville Street e P. O. Box 1551

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UNRESOLVED SAFETY: ISSUES 10R WICH A FINAL TECHNICAL RESOLUTION MAS BEEN ACHIEVED _

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NUMBER TITLE :REF. 00CtMENT APPLICABILITY. ~

STATUS /DATE*: .. _ REMARKS' -

A-1 Water Hammer p

'SECY 84-119i .

All" NUREG-09?7, Rev.~1 .c 3/81-(Ul&2) <

. No te' ~ Al '

LNUREG-0993,'Rev. I NUREG-0737 Itan-4

i.A.2.3-SAP revisions ^

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A-2/ Asymmetric Riowdown NUREG-0609 PWR NAL MPA D-10 Loads:on Reactor Primary GL 84-04, G00-4 Coolant Systems

, A-3 Westinghouse Steam NUREG-0644 W-PWR'

' NA Cenerator Tube Integrity. SECY 86-97'

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SECY 88-772 GL 85-02 (No requirements)  ;

A-4 CE Steam Generator Tube NUREG-0844. SECY 86-97 CE-PWR NA  !

Integrity SECY 88-272-GL 85-02

'(No requirements)

A-5 R8W Steam Generator NUREG-0844. SECY 86-97 88W PWR NA Tube Integrity SECY 88-2/2 GL 85-02 (No Nequirements):

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X-6 Mark I Containment NUREG 0408- Park !-bWR ,

Short-Term Program c 5/83 (U1). Note A6-6/80 (U2) i

• C - COMPLETE NC - NO CHANGES NECESSARY N4 - NOT APPLICABLE a I - INCOMPLETE ,

F - EVALUATING ACTIONS-REQUIRED

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NUMBER TITLE - REF. DOCUMENT- APPLICABILITY-  ; STATUS /DATE* 1 REMRKS '

- ;;a Mark.I long-Tern NUREG-0661 - N rk.I-9NR "

L c 11/85j(U1) ENote' A7 --

.'D A-7/ - Program NUREG-0661; Suppl.:1; ;10/84L(U2) 1 i .GL 79-57:

. A-8 W rk II Containment NUREG-08108 Marl II-8tst: ~NA-' ~

Pool Dynamic loads ~ MUREG-0487 ' Suppl. 1/2-

NUREG-0802-SRP'6.2.1.10

[ GDC-16 -

Anticipated Transfents q A-9 'NUREG-0460. Vol. 4. 'All- :I 12/90 (U1) . Note AC

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i Without Scram '10 CFR 50.62 2/90 (U2).

A-10/

BNR Feec#ater f4czzle NUREG-0619 BW I 3/90 (Ul&2) . Note A10-

, MPA P-25 Cracking -Letter from DG Eisenhut- -

dated 11/13/80 GL Al-It a A-Il Reactor Vessel Material NUREG-0744. Rev. 1 All NA -Note All' Toughness 10 CFR 50.60/

82-26 A-12 Fracture loughness of NUREG-057) Rev. I PNP NA Steam Generator and SRP Revision Reactor Coolant Pump 5.3.4 Supports-A-17 Systems Interactions Ltr:' DeYoung to All I 8/92 (Ul&2) Note A17 Ifcensees - 9/77 NUREG-1174. Nt9EG-  :

1229. NURE.;/CR-3922 '

NUREG/CR-4761. NUPEG/  :

CR-4470.-GL 89-18.  ::

(No requirements)

A-24/ Oualification of Class NUREG-0588. Rev. I' A11

.c 11/85 (Ul&2) Note A24" MPA B-60 1E Safety-Related SRP 3.11 1

Equipment 10 CFR 50.49' GL.82-09, Gl 84-24 4

' GL 85-15~

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NtsmER -TITLE 'REF. DOCtNEENT' . APPLICABILITY- STATUS /DATE*' . rut 4RKS :

A-26/. Reactor Vessel Pressure DDR Letters to- PWR- :NA.

MPA 8 Transient-Protection Licensees'8/76 NUREG-0224 ~

NUREG-0371 1- -

SRP 5.2-GL 88-11~

A-31 Residual Heat Removal NUREG-0606 A11 0Ls After NA Shutdoun Nequirr.ments RG 1.113, 01/79.

RG 1.139 SRP 5.4.7 ,

y A-36/ Control of Heavy Loads NUREG-0612 All c 5/84 (Ul&2) . Note A36I - '

C-10 Near Spent Fuel SRP 9.1.5 6/85 (Ul&2)

C-15 GL 81-07, GL 83-42, GL 85-11 Letter frase DG Eisenhut dated 12/22/B0 A-39 Determination of SRV NUREG-0802~ BWR c 10/85 (U1) Note A39 ,

Pool Dynamfc Loads NUREGs-0763,0783,0002 9/84 (U2) end Pressure Transients NUREG-Oo61 SRP 6.2.1.1.C A-40 Seisafc Design SRP Revisions, NUREG/ All NC Note A46 I Criteria CR-4776. NUREG/CR-0054, l NUREG/0R-3480, NUREC/ ,

CR-1582, hi,i'EG/CR-1161, .

NUREG-1233, NUREG-4776 NUREG/CR-3805 NUREG/CR-5347 NUREG/CR-3509 A-42/ Pipe Cracks in Sciling NUREG-0313, dev. 1 MPA 8-05 Water Reactors NUREG-0313. Rev. 2

~BWR.

I 12/90 01) Note A42 ,

GL 81-03, GL~88-01 .2/90-(U2) 6 I

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'Q USI/MPA' TITLE REF. 00CimENT ~ APPLICABILITY- . STATUS /DATE* . REMARKS Nt#WER NC' r A-43 Containment Emergency -841 REG-0510, - . .All Sump - Perfor1mance 6 T6-u669JRev. 1 -

MS'EG-0897, R.G.I.87 (Sev. 0),1SRD 6.2.2 6 85-22~

Wo Requirements' RG 1.155 All I Note A44 A-44 Station Blackout NUREG-1032 NUREG-1109 1 10 CFR 50.63 A-45 Shutdown Decay Heat SECY 88-269 A!! E 8/92 (Ul&2) ' Note A45 Removal Requirements NUREG-1269 NUREG/CR-5230

-SECY 88-260 (No requirements)

A-46 Seismic Qualification. NUREG-1030 All I 5/92-(U1) Note A46 -

of Equipment in' :NUREG-1211/ 1/93 (32)

Operating Plants GL 87-02, GL 87-03 A-47 Safety Implication NUREG-1217, NUREG- -All E Note'A47-of Control Systems 1218 -

GL~89-19 All, except ,3 A-48 Hydrogen Control 10 CFP 50.44 Measures and Effects SECY 89-1?2 PWRs with .c 10/88-(U1) ' Note A48 I 4/90 (U2)-

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of Hydrogen Burns large dry on Safety Equipment contat ments Pressurized ~ Thermal PGs 1.154, 1.99 PWR NA A-49 (hock SECY 82-465-SECY P3-288

~SECY 81-687-

-10 CFR 50.61/_

GL 88-11:

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A-1 _ Operator awareness training was action for closing issue . .'.

keepfills were not- backfit or add-ons. -  !

H -A-6 .' Vent header deflectors installed to reduce loads as interim measure '

pending A-7 resolution.

L -. A-7 J . Dates show modifications. completed, SER dated 3/19/84 accepts our i: 10/1/82 analys!s' report.

A-9 The remaining modifications for each unit consist of repacing the existing ARI ATTUs manufactured by Rosemount with ATTUs made by CE.

The modifications are scheduled for Brunswick-1 Reload 7 and Brunswick- t 2 Reload 8. .The completion dates provided are the currently scheduled

.'end dates for these outages. Design and schedule were approved by the NRC~in a letter dated-August 8, 1988.

• An' additional design questinn was raised by the NRC in a letter dated August 21, 1989. CP&L responded to this question in a letter dated October 23. 1989. It is the Company's position that the ARI system as designed fulfills the requirements of the ATWS Rule and, as such, no 4: further, modifications till be necessary. Resolution of thi s item is .

.pending.

'A Instrumentation to evaluate the need for feedwater low flow ccatroller installation and RWCU Re-coute installed. Data collection is in progress wit n evaluation of the need to install modifications currently scheduled to be completed by 3/31/90. If modifications are required, the-schedule will.be aetermined.

Spargers (7ec.dwater Nozzlec) are being inspected in accordance with the schedule established in NUREC-0619, Table 2. No sparger replacement made to date. If inspections indicate the need for replaceraent, it will be scheduled.

This plan and schedule is based on our letter dated March 22, 1985. No

, response from the NRC was received.

A-11 Charpy and drop weight tests applied to BSEP Units 1 and 2 design were considered adequate to assure sufficient fracture toughness for the design life of tg plant where the peak fast neutron iluence will be

.less than 2 x 10 . Confirmation will be provided by the use of full Chatpy curves at 8 EFPY for Unit 1 and 10 EFPY for Unit 2.

K A-17 Cuidance of Gcneric Letter 89-18 to be considered in completion of the

,, Brunswick IPEs. The status date le the currently scheduled completion date for the Brunswick IPEs as committed to in our letter (NLS-89-290) dated 10/31/89.

A-24 Coapliance required in November, 1935 or shutdown until compliance is I met. Unit i down for schr.duled outage . . . Unit 2 shutdown until compliance was achieved.

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COMMENTS (cont'd A-36 Thelcotpletion date for Phase 1 represents the NKC's SER for Brunswick )

Pha.se 1. The Phase 2 completion date is the date of Generic Letter 85-  ;

l 11',t6/28/85, which informed licensees that Phase 2 was not necessary. '

due to impicmentation'of Phase 1. i

, -A-39 7/85 SER for Amendment 85/111 issued; incorporates suppression pool I temp monitoring . ..

'M A-40c . Enveloped by-USI A-46.

A-42 ' Inlet Riser Pip *ng & Nozzle Safe End Replacement in process for U21 U1 replacemert scheduled for 1990 outage. HWC system in place to help

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mit* gate ICSCC . . . swaiting amen (ment for HWC from NRC.

A-44 Implementstion of modifications and procedure changes is required I

, within 2 years after notifict. tion provided by the Director, NRR of  !

acceptanu 'of' Brunswick proposal. This schedule is in accordance with j

'10CFR50.63(c)(31. The Brunswick response was submitted on 3/3/89 and revised on 10/10/89. )

.A-45 LThis issue will be addressed-through completion of plant specific IPEs. The-Brunswick IPEs are scheduled for completica by 8/92 as committed to-in our letter (NLS-89-290) dated October 31, 1989.

-A-46 The NRC and'SQUC'are working jointly in the development.'of Generic Implementation Procedures (GIP). The implementation schedule for-Brunswick is contingent on NRC approval of Revision 3 to the CIP.

Currently, Revision 2 is in review with the NRC. In a letter dated October 6,1988, CP&L committed to complete walkdowns for Brunswick-1 during Reload 8 (scheduled to begin 2/92 and end 5/92) and for tBrunswick-2 during Reload 10 (scheduled to begin 9/92 and end 1/93).

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This schedule may be delayed if NRC approval of the CIP is not completed on a timely schedule. Any work resulting from the walkdowns will be prioritizad and scheduled for action as appropriace.

.A-47; Response to CL89-19 will be submitted by March 19, 1990.

A-48 The NRC SER was issued on 8/18/89 with a supplement on 10/27/89. The installation schedule was approved in an NRC letter dated 12/17/87.

~The BSEP-1 completion date was the end of Reload 6 plus 2 months. The projected BSEP-2 completion date is the end of Reload 8 plus 2 months.

.DBB/rij (534CRS)

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