ML19332D290
| 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) | |
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S;uth Car:hna Electric & Gas Csmp:ny Ollie S,' Bradham I
U P.O. Bor 88 Vice Presi%nt -
i Jinknsville, SC 2006f Nuclear Opeiations
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' (803) 345-4040
'SCE&G-acaam
_ November 22, 1989 e
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' Records'and Reports Management Branch'
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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:-
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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 Should you have any questions concerning the' status, please call Mr. Charles.
l.
l' McKinney of my staff at (803) 345-4723.
l.
Ver.v truly yours, k
- 0. S. Bradham-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
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R. L. Prevatte J. B. Knotts, Jr.
File (815.14) folk 8911300284 891122 I
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ENCLOSURE 1
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. 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
.C - 2/82 NRC. Inspection Report _82-06 i
NUREG-09?7, Rev. 1 NUREG-0993.-Rev. 1
~NUREG-0737 Item I.A.2.3 SRP revisions i
A-2/
Asyneetric Blowdown NUREG-0609 PWR
~ NC' MPA D-10 Loads on Reactor Primary GL 84-04, GDC-4
. NUREG-0717 - Va C. - Summer Coolant Systems SER Section~3.9.3 A-3 Westinghouse Steam NUREG-0844 W-PWR C - 6/85 SCE&G-NRC. letter dated i
Generator Tube Integrity SECY 86-97 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
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USI/MPA-NUMBER TTTLE-
' REF. DOC!?'ENT --
-APPLICA8ILITY STATUS /DATE*
REMARKS'-
A-7/
Mark I long-Tem NUREG-0661 Mark:I-BWR NA.
[
D-01 Program NUREG-0661 Suppl.- 1 4
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
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Without Scram 10 CFR 50.62
.C - 6/89
. NRC Inspection' Report 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)
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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
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- 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
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- NUREG-0717 - V. C. Sumer Shutdown Requirements RG 1.113, 01/79.
'SER
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,
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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.
.SCE&G-Document Control Desk 4/17/89 & 10/2/89-A-45 Shutdown Decay Heat SECY 88-260.
All I - 8/92 SCE&G-Document Control Removal Requirements 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-E - 3/90.
Generic Letter 89-19 of Control Systems 1218 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/
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