ML20205P628

Forwards List in Response to 880922 Request for Addl Info Re Development of risk-based Insp Guide.Sys Descriptions, Abnormal Operating Procedures,Emergency Operating Procedures,Operating Procedures & Drawings Listed

ML20205P628
Person / Time
Site:	Brunswick
Issue date:	11/02/1988
From:	Loflin L CAROLINA POWER & LIGHT CO.
To:	NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
References
NLS-88-262, NUDOCS 8811080242
Download: ML20205P628 (7)

Text

-

COAL Carolina Power & Light Company NOV 0 21988 SERIAL: NLS-88 262 United States Nuclear Regulatory Commission ATTENTION: Document Control Desk Washington, DC 20555 BRUNSWICK STEAM ELECTRIC PIANT, UNIT NOS.1 AND 2 DOCKET NOS. 50-325 6 50 324/ LICENSE NOS. DPR-71 & DPR 62 REQUEST FOR ADDITIONAL INFORMATION DEVELOPMENT OF RISK-BASF.D INSPECTION CUIDE Centlemen:

By letter dated September 22, 1988, the NRC requested that Carolina Power & Light Company provide additional information concerning the Brunswick Plant Probabilistic Rick Assessment (PRA). This information was requested by the Staff to use in the preparation of a risk-base <*

inspection guide for the plant.

In response to your request, (he Company has compiled a list (Enclosure

1) and copies (Enclosure 2) of the requested information. As discussed with the Staff, due to the voluminous nature of Enclosure 2, it is being mailed directly to the NRC contractor, Brookhaven National Laboratory; and no other distribution of Enclosure 2 is being made.

Please refer a.y questions regarding this submittal to Mr. Stephen D Floyd at (919) 836-6901.

Yours very truly,

/D Leo ard I Loflin Man ger Nuclear Licensing Section WRMfwrm (\cor\prainfo)

Enclosures cc: Mr. M. L. Ernst*

Mr. W.11. Ruland*

Hr. B. C. .ackley*

Drookhaven National Laboratory

• Enclosure 1 only.

(CD\\

m 5.,.n. vin. su..i . r o eu issi . a. .e N C U602 8811080242 881102 -~~- ' - " " ~ ~ ^ ~ T" I i

l PDR ADOCK 05000324 (

( PNV

d ENCLDSURE 1 NRC RE( 2ST FOR ADDITIONAL INFORMATION  !

DEVELOPMENT OF RISK-BASED INSPECTION GUIDE PROCEDURES: ,

Plant Operating Manual Index i System Descrintions:

4 SD 03 Abnormal Doerating Procedures: [

A0P 01.0 l AOP 01.1 ,

AOP 02.0 '

A0P 2.1 AOP 02.2 AOP-03.0 ,

AOP 04.0 AOP 04.1 '

AOP 04.2 ,

. A0P 04.3 ,

I AOP-04.4 A0P-5.0 I AOP 05.1 <

A0P 05.2 '

I AOP 05.3 ,

A0P 06.0 AOP 06.1 AOP 06.2 i

'. A0P 07.0  ;

j A0P 09.0 AOP 12.0 6 i AGP 13.0

A0P 14.0 1 AOP 15.0 [

AOP 16.0  ;

AOP-17.0 AOP 18.0 A0P 19.0 l AOP 20.0  !

AOP 22.0 l AOP-23.0 [

A0P-26.0 l AOP-28.0 t AOP 29.0  !

AOP-30.0 l AOP 31.0

{

i El-3 v

e NRC REQUEST FOR ADDITIONAL INFORMATION DEVEI4PMENT OF RISK-BASED INSPECTION CUIDE-Abnormal Operating Procedures: (Continued)

A0P-32.0 AOP-33.0 AOP-34.0 AOP 34.1 AOP 01 APP AOP 01 CCP.

Emerrency Ooerating Procedures:

E0P-01-EDP E0P-01.EPP 1L E0P 01 EPP 1M E0P-01 EPP-1N E0P 01 EPP-1F E0P 01-EPP 2A E0P-01 EPP 23 E0P 01 FP (Includes flowcharts)

E0P 01 LEP 01 E0P 01 LEP 02 E0P 01 IIP-03 (Includes one flowchart)

E0P 01 LRP E0P 01 SPCP E0P 01-SRP AEP E0P 01 SRP CSW E0P-01 SRP ISA E0P 01 SRP NSW E0P 01 SRP RBCCW E0P-01-SRP TBCCW E0P-01 STCP E0P 01 UG Operating Procedores:

OP 03 OP 05 OP 08 OP 16 OP 17 OP 18 OP 19 i OP 20 OP 21 OP 32 OP 37 OP 37.1 OP 37.2 OP 37.3 OP 37.4 OP 37.5 ,

OP 37.7 OP 37.8 El 4 t

i y,- , , -. _

y.- , ., -- ----

NRC REQUEST FOR ADDITIONAL INFORMATION s

DEVELOPMENT OF RISK-BASED INSPECTION GUIDE

~

Ooeratine Procedures: (Continued)

OP 39 OP 43 OP-46 OP 50 OP-51 OP-50.1 OP-52 DRAWINGS:

Drawing No. Title D-2523, Sheet 1 Reactor Building Piping Diagram High Pressure Coolant Injection System, Sheet 1 Unit No. 2 D 2523, Sheet 2 Same, Sheet 2 D-2521-1AA- Main Steam System D 2521-1C Feedwater System D 2040-1B Condensate Supply Crav. Unit 2 F 4073 Standby Cas Treatment D 2529, Sheet 1 Reactor Building Piping Diagram Reactor Core Isolation Cooling System, Sheet 1, Unit No. 2 D 2529, Sheet 2 Same, Sheet 2 D 2516, Sheet 1A Reactor Building Piping Diagram Control Rod Drive Hydraulic System Sh et 1A, Unit No. 2 D 2516, Sheet 1B Same, Sheet 2 D 2517-2B Instrument Air 70 75 psig D 7029 2A Instrument Air 30 psig F P-50015 7 Reactor Protection System D 2520, Sheet 3A Reactor Building Piping Diagram Nuclear Steam Supply System Sheet 3A, Unit No. 2 D 2516, Sheet 1A Reactor 3uilding Piping Diagram Control Rod Drive Hydraulic System Sheet 1A, Unit No. 2 D 2516, Sheet 1B Same, Sheet 1B F 3043 Unit Nos. 1 6 2 Key One Line Diagram 230 kV, 24 kV, and 4160 Volt Systems El 5

?.

f-NRC REQUEST FOR ADDITIONAL INFORMATION DEVELOPMENT OF RISK-BASED INSPECTION GUIDE Drawing No. Title F-3044 Unit Nos. 1 & 2 Key One Line Diagram 480 Volt System F-3006 Unit No. 2 Single Line Diagram 125/250 Volt DC System Distribution Switchboard 2A & 2B D 20041 1, Sheet 1 Piping Diagram Service Water System, Sheet 1. Unit No. 1 D 20041 Same, Sheet 2 D 20041-3 Same, Sheet 3 D 2034 1 Service Water to Discharge Canal 1 FP-05889, Shts 1 4~ Core Spray System, Unit No. 1 Sheets 1, 2, 3, 4 -

2-FP-05889, Shts 1-4 Core Spray System, Unit No. 2 Sheets 1, 2, 3, 4 1 FP-50039, Shts 1 8 HPCI System, Unit No. 1 Sheets 1 8 2-FP-50039, Shts 1 8 HPCI System, Unit No. 2 Sheets 1 - 8 1 FP 50098, Shts 1-7 RCIC System, Unit No. 1  !

Sheets 1 - 7 L 2-FP-50098, Shts 1-7 RCIC System, Unit No. 2 l Sheets 1 - 7 i i

2 FP 50015, ".eet 7 Reactor Protection System, Unit No. 2 0 FP 50017, Sheet 1 Residual Heat Removal System '

Unit Nos. 1&2 '

i 1 FP-50017, Shts 1A 12 Residual Heat Removal System, Unit No. 1 Sheets 1A 12 i

2 FP 50017, Shts 1A 12 Residual Heat Removal System, Unit No. 2 Shoots 1A - 12 i 0 FP 50017, Sheet 13 Residual Heat Removal System, Unit Nos. 1&2  !

Sheet 13 1 FP 50017 Sheet 14 Residual Heat Removal System, Unit No. 1 Sheet 14 i -

i El 6 J

4 i

F

., ? 2 NRC REQUEST FOR ADDITIONAL INFORMATION DEVELOPMENT OF RISK-BASED INSPECTION GUIDE -

' Drawing No. Title 2-FP-50017, Sheet 14 Residual Heat Removal System, Unit No. 2 Sheet 14 0-FP-50017, Sheet 15 Residual Heat Removal System Unit Nos. 1&2 Sheet 15 1 FP 50017, Sheet 16 Residual Heat Removal System, Unit No. 1 Sheet 16 2-FP 50017, Sheet 16 Residual Heat Removal System, Unit No. 2 Sheet 16 0 FP 50017, Shts17-18A Residual Heat Removal System, Unit Nos. 1&2 Shts 17 - 18A i

El 7

, , - _ ___ ,---,-.--,_m. .

• • . t b

-; c ENC 14SURE 2 NRC REQUEST FOR ADDITIONAL INFORNATION DEVELOFNENT OF RISK-BASED INSFECTION CUIDE Copies of the items listed in Enclosure 1.

Note: Some of the requested drawings are not legible in the specified 11" x 17" size; therefere, larger prints are

. provided.

4 4

e I

i l

i 4

1 l

_. . - - _ . _ - . . _ _ _ . . .-