ML19332D290

Responds to Generic Ltr 89-21 Re Status of Applicable Usi. Updates Reflecting Current Status of USIs Encl

ML19332D290
Person / Time
Site:	Summer
Issue date:	11/22/1989
From:	Bradham O SOUTH CAROLINA ELECTRIC & GAS CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
REF-GTECI-MI, REF-GTECI-SC, TASK-***, TASK-OR GL-89-21, NUDOCS 8911300284
Download: ML19332D290 (5)

Text

+.

T Q ; yl < ,

'

' '

{ ' '

f

U

(*' S;uth Car:hna Electric & Gas Csmp:ny P.O. Bor 88 .

.

Ollie S,' Bradham Vice Presi%nt -  ;

I i . Jinknsville, SC 2006f Nuclear Opeiations

1. ~ . ' (803) 345-4040 '

'SCE&G-e acaam _ November 22, 1989 i

,

o a

f ^ ':i -1 w

1 i

,,

9 l

.

. - .

' Records'and Reports Management Branch'

Division of-Information Support Services

(

Office of Information Resources Management

,

U.S. Nuclear Regulatory Commission Washington, D.C. 20555

,

Subject:

Virgil'C. Summer Nuclear Station '

Operating License No. NPF-12 Docket No. 50/395 Response to Generic Letter 89-21 i

Gent 1'emen:-

\

South Carolina Electric & Gas Company (SCE&G) has reviewed the status of applicable' unresolved Safety Issues (USI) per the requirements of Generic

• Letter 89-21. Updates reflecting the current status of the USIs are attached-

'

to this letter.

-

L

l. Should you have any questions concerning the' status, please call Mr. Charles. .

l' McKinney of my staff at (803) 345-4723.

l. Ver.v truly yours,

0. S. Bradham-k CJM/fSB:1bs' Attachment c:- D. A. Nauman/0. W. Dixon, Jr./T. C. Nichols, Jr.

K. E.,Perkins S. D. Ebneter

'

W..A. Williams, Jr.

General Managers

)

K. W. Woodwaro R. L. Prevatte J. B. Knotts, Jr.

NPCF RTS (LTR 890021)

File (815.14) folkI 8911300284 891122 JDR ADOCK 0500o39g Ijl PDC I

- . ._- <

. c .m

-

-

.

_

,1

_ _

~

.)

'

"

~

• 1: ' j l'

_ _

-

. -

'

ENCLOSURE 1 ~j

'

e _

. UNRESOLVED SAFETY ISSUES FOR WHICH A FIMAL TECHNICAL RESOLUTION HAS BEEN ACH

-USI/MPA ..# .

NUMBER ' TITLE .REF. DOCUMENT APPLICABILITY STATUS /DATE* 1 REMARKS

. A-1 Water Hansner ~SECY-84-119.

.

All i

NUREG-09?7, Rev. 1 .C - 2/82 NRC. Inspection Report _82-06

'

NUREG-0993.-Rev. 1 >

~NUREG-0737 Item I.A.2.3 SRP revisions

• i A-2/ Asyneetric Blowdown NUREG-0609 PWR

.

MPA D-10 Loads on Reactor Primary GL 84-04, GDC-4 ~ NC'

. NUREG-0717 - Va C. - Summer Coolant Systems SER Section~3.9.3 A-3 Westinghouse Steam NUREG-0844 i

W-PWR C - 6/85 Generator Tube Integrity SECY 86-97 SCE&G-NRC. letter dated SECY 88-772 6/14/85~

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 88-272 GL 85 (No Requirements)

E X-6 Mark I Containment NUREG-0408 Park I-BWR NA Short-Term Program

'

-

• C - COMPLETE NC - NO CHANGES NECESSARY

.

NA - NOT APPLICABLE

'

.

I - INCOMPLETE

'E - FVALUATING ACTIONS REQUIRED

, -

'- -

. . .

,

. _ _ _ _ - _ - _ _ _ _ _ _ _ _ _ . _ _ __ . _ _ _ _ - _ . _ _ __ _

.

. , . . , _ _ _ _

.

-

~ :A L.

. -i V- ,

_

,

L-USI/MPA- .

-

_ _ .

-

NUMBER TTTLE- ' REF. DOC!?'ENT -- -APPLICA8ILITY STATUS /DATE*

'

REMARKS'-

' "'

'

A-7/ Mark I long-Tem NUREG-0661 Mark:I-BWR NA. [ ,

4 D-01 Program NUREG-0661 Suppl.- 1 GL.79 A-8 Mark'II Containment MUREG-0808 Mark II-BWRi :NA Pool Dynamic Loads NUREG-0487, Suppl. 1/2 NUREG-0802 SPP 6.2.1.1C -

GDC 16-A-9 Anticipated Transfents NUREG-0460, Vol. 4 All .C - 6/89 . NRC Inspection' Report

{ Without Scram 10 CFR 50.62 50-395/89-09

!

A-10/ BWR Feedwater Nozzle NUREG-0619 BWR NA MPA B-25 Cracking Letter from DG Eisenhut

,

!

dated 11/13/80 GL 81-11 A-11 Reactor Vessel Material NUREG-0744. Rev. 1 All NC NUREG-0717JSupp. 1 tos Toughness 10 CFR 50.60/ V. C. Sumer SER

'82-26 A-12 Fracture Toughness of NUREG-0577, Rev. . 1 PWP NA Steam Generator and. SRP Revision-Reactor Coolant Pump 5.3.4 ,

Supports

'

A-17 Systems Interactions 'Ltr: DeYoung to All NC licensees - 9/72 NUREG-1174 NUREG-

.1229, MUREG/CR-3922,

NUREG/CR-4261, NUPEG/

CR-4470, GL 89 (No: requirements)

.

A-24/ Qualification of Class MUREG-0588,-Rev. 1 All 'I - 4/90 NRC Inspection. Reports

. MPA B-60 1E Safety-Related SRP 3.11 50-395/88-01 & 88-23 Equipment 10 CFR 50.49 (One item remains open)

• GL 82-09. GL 84-24

- -

GL 85-15

- .

.

m

, , - ap u* er % .c - wm-- ya .A- --

a=% +m e+ws  %- n.e a - ,. g w-e i+-c.g~---

., ._ _ . _ _

y _ m. ,

m > , ,_ _ ,

y .w , ,

~

.- *

- :_:

-

' - 3'- ~ .

-

-

, __

USI/MPA

'

.

NUMBER TITLE REF. DOCUMENTE APPLIC48ILITY STATUS /DATE*- REMARKS A-26/ Reactor Vessel Pressure

~

DOR Letters to: PWR NC ' SCE&G-Document Control MPA B-04 Transient Protection Licensees 8/76-

~

' Desk 1/12/89

.NUREG-0224 - J. Hayes-SCE&G 2/7/89 NUREG-0371 SRP 5.2-GL 88-11 A-31 Residual Heat Removal NUREG-0606 All Ots After NC ^J

• NUREG-0717 - V. C. Sumer Shutdown Requirements RG 1.113, 01/79. 'SER .

'RG 1.139 SRP 5.4.7 A-36/ Control of Heavy Loads NUREG-0612 All C - 6/85 NUREG-0717 - V. C. Summer C-10 Near Spent Fuel SRP 9.1.5 SER Sections 9.1.4 &

C-15 GL 81-07, GL 83-42, App. C GL 85 - SCE&G-H.R.Denton 1/25/85m.

Letter from DG "'

Eisenhut dated

- 12/22/80

.i A-39 Determination'of SRV NUREG-0802 BWR NA Pool Dynamic loads NUREGs-0763,0783,0802

• and Pressure Transients. NUREG-0661 SRP 6.2.1.1.C-A-40 Seismic Design SRP Revisions,:NUREG/ All C - 4/811 NUREG-0717 - V. C. Sumer :

Criteria CR-4776 NUREG/CR-0054, SER Supplement 1  ;

NUREG/CR-3480, NUREG/

CR-1582, NUREG/CR-1161, MUREG-1233, NUREG-4776 NUREG/CR-3805 NUREG/CR-5347.

NUREG/CR-3509 A-42/ Pipe Cracks in Boiling -NUREG-0313. Rev. 1- BWR NA

, MPA B-05 Water Reactors NUREG-0313 Rev.:2

,

' GL 81-03, GL'88 ~, -

4

, , . . _ . . . - ~ - _ - - . s.. - . - - - ,

N.- '.n

.- -- - . - - ~- -s.s-. $- - _ - ,, n , r,-6...,._vs- e- - - L.e_w.__x:ua=.-_m_e._'_c -a d _= .= _ .~

u .- - _ .. . - - ,

g

^

'

r- -

_ , _ -

, a ~.-

2 USI/MPA '

=L NUMBER TITLE REF. DOCUMENT APPLICABILITY STATUS /DATE* ~ REMARKS l -

A-43

'

Containment Emergency NUREG-0510 - .

All NA i Sump Performance NUREG-0869, Rev. 1-NUREG-0897, R.G.I.87

,

'

(Rev. 0), SRP 6.2.2 GL 85-22 No Requirements A 44 Station Blackout RG 1.155- All I.- 11/91 Modifications'& Procedure-NUREG-1032 'to be imp 1dmented by-NUREG-1109 Fall 1991.

,

.10 CFR 50.63 .SCE&G-Document Control A-45 Shutdown Decay Heat SECY 88-260.

Desk 4/17/89 & 10/2/89-Removal Requirements All I - 8/92 SCE&G-Document Control NUREG-1289 Desk 10/31/89 NUREG/CR-5230 SECY 88-260 (No requirements)

A-46 Seismic Qualification NUREG-1030 All NA

'

of Equipment in NUREG-1211/

Operating Plants GL 87-02 GL 87-03 A-47 Safety Implication NUREG-1217, NUREG- All-of Control Systems 1218 E - 3/90. Generic Letter 89-19 response due by 3/90.

GL 89-19 l A-48 Hydrogen Control 10 CFR 50.44 All, except NA i Measures and Effects SECY 89-172 PWRs with of Hydrogen Burns large dry on Safety Equipment containments A-49 Pressurized Therwal- PGs-1.154, 1.99 PWR NC SCE&G-Document Control-Fhock SECY 0?-465 Desk 1/12/89.-

, SECY'R3-260 SECY 81-687

-

. 10 CFR 50.61/

,

. GL 88-11

-

.

,

,w

-g- --a-- w .-w . - < , - -,aw. - - - - -a.--~~,-- - - ~ ,ww-m--,-- . . - - -r--- -..-,msx

.

- - - - m.--.+-