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{{#Wiki_filter:+. | {{#Wiki_filter:+. | ||
T Q ; yl < , | T Q ; yl < , | ||
{ ' ' | { ' ' | ||
f''' | f''' | ||
U | U | ||
(*' S;uth Car:hna Electric & Gas Csmp:ny P.O. Bor 88 . | (*' S;uth Car:hna Electric & Gas Csmp:ny P.O. Bor 88 . | ||
Ollie S,' Bradham Vice Presi%nt - ; | Ollie S,' Bradham Vice Presi%nt - ; | ||
I i . Jinknsville, SC 2006f Nuclear Opeiations | I i . Jinknsville, SC 2006f Nuclear Opeiations | ||
: 1. ~ . ' (803) 345-4040 ' | : 1. ~ . ' (803) 345-4040 ' | ||
'SCE&G-e acaam _ November 22, 1989 i | 'SCE&G-e acaam _ November 22, 1989 i o | ||
a f ^ ':i -1 w | |||
f ^ ':i -1 w | |||
1 i | 1 i | ||
9 l | 9 l | ||
' Records'and Reports Management Branch' Division of-Information Support Services | |||
' Records'and Reports Management Branch' | |||
Division of-Information Support Services | |||
( | ( | ||
Office of Information Resources Management | Office of Information Resources Management U.S. Nuclear Regulatory Commission Washington, D.C. 20555 | ||
U.S. Nuclear Regulatory Commission Washington, D.C. 20555 | |||
==Subject:== | ==Subject:== | ||
Line 54: | Line 40: | ||
\ | \ | ||
South Carolina Electric & Gas Company (SCE&G) has reviewed the status of applicable' unresolved Safety Issues (USI) per the requirements of Generic | 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- | * Letter 89-21. Updates reflecting the current status of the USIs are attached-to this letter. | ||
to this letter. | |||
L | L | ||
: l. Should you have any questions concerning the' status, please call Mr. Charles. . | : l. Should you have any questions concerning the' status, please call Mr. Charles. . | ||
Line 63: | Line 46: | ||
: l. Ver.v truly yours, | : 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. | : 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 | K. E.,Perkins S. D. Ebneter W..A. Williams, Jr. | ||
W..A. Williams, Jr. | |||
General Managers | General Managers | ||
) | ) | ||
Line 71: | Line 52: | ||
NPCF RTS (LTR 890021) | NPCF RTS (LTR 890021) | ||
File (815.14) folkI 8911300284 891122 JDR ADOCK 0500o39g Ijl PDC I | File (815.14) folkI 8911300284 891122 JDR ADOCK 0500o39g Ijl PDC I | ||
. c .m | . c .m | ||
,1 | ,1 | ||
~ | ~ | ||
.) | .) | ||
~ | ~ | ||
* 1: ' j l' | * 1: ' j l' ENCLOSURE 1 ~j | ||
ENCLOSURE 1 ~j | |||
: e _ | : e _ | ||
. UNRESOLVED SAFETY ISSUES FOR WHICH A FIMAL TECHNICAL RESOLUTION HAS BEEN ACH | . UNRESOLVED SAFETY ISSUES FOR WHICH A FIMAL TECHNICAL RESOLUTION HAS BEEN ACH | ||
Line 97: | Line 64: | ||
NUMBER ' TITLE .REF. DOCUMENT APPLICABILITY STATUS /DATE* 1 REMARKS | NUMBER ' TITLE .REF. DOCUMENT APPLICABILITY STATUS /DATE* 1 REMARKS | ||
. A-1 Water Hansner ~SECY-84-119. | . A-1 Water Hansner ~SECY-84-119. | ||
All i | All i | ||
NUREG-09?7, Rev. 1 .C - 2/82 NRC. Inspection Report _82-06 | 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 | |||
NUREG-0993.-Rev. 1 > | A-2/ Asyneetric Blowdown NUREG-0609 PWR MPA D-10 Loads on Reactor Primary GL 84-04, GDC-4 ~ NC' | ||
~NUREG-0737 Item I.A.2.3 SRP revisions | |||
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 | . 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~ | W-PWR C - 6/85 Generator Tube Integrity SECY 86-97 SCE&G-NRC. letter dated SECY 88-772 6/14/85~ | ||
Line 113: | Line 75: | ||
A-5 R8W Steam Generator NUREG-0844, SECY 86-97 88W-PWR NA Tube Integrity SECY 88-272 GL 85 (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 | 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 | |||
* C - COMPLETE NC - NO CHANGES NECESSARY | |||
NA - NOT APPLICABLE | |||
I - INCOMPLETE | |||
'E - FVALUATING ACTIONS REQUIRED | 'E - FVALUATING ACTIONS REQUIRED | ||
~ :A L. | ~ :A L. | ||
. -i V- , | . -i V- , | ||
L-USI/MPA- . | L-USI/MPA- . | ||
NUMBER TTTLE- ' REF. DOC!?'ENT -- -APPLICA8ILITY STATUS /DATE* | NUMBER TTTLE- ' REF. DOC!?'ENT -- -APPLICA8ILITY STATUS /DATE* | ||
REMARKS'- | REMARKS'- | ||
A-7/ Mark I long-Tem NUREG-0661 Mark:I-BWR NA. [ , | 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 - | 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 | 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 | { 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 | ||
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 , | '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 | Supports A-17 Systems Interactions 'Ltr: DeYoung to All NC licensees - 9/72 NUREG-1174 NUREG- | ||
A-17 Systems Interactions 'Ltr: DeYoung to All NC licensees - 9/72 NUREG-1174 NUREG- | |||
.1229, MUREG/CR-3922, | .1229, MUREG/CR-3922, | ||
:NUREG/CR-4261, NUPEG/ | :NUREG/CR-4261, NUPEG/ | ||
CR-4470, GL 89 (No: requirements) | CR-4470, GL 89 (No: requirements) | ||
A-24/ Qualification of Class MUREG-0588,-Rev. 1 All 'I - 4/90 NRC Inspection. Reports | 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) | . 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 | |||
GL 85-15 | |||
m | |||
, , - ap u* er % .c - wm-- ya .A- -- | , , - ap u* er % .c - wm-- ya .A- -- | ||
a=% +m e+ws %- n.e a - ,. g w-e i+-c.g~--- | a=% +m e+ws %- n.e a - ,. g w-e i+-c.g~--- | ||
y _ m. , | y _ m. , | ||
m > , ,_ _ , | m > , ,_ _ , | ||
y .w , , | y .w , , | ||
~ | ~ | ||
' - 3'- ~ . | ' - 3'- ~ . | ||
USI/MPA NUMBER TITLE REF. DOCUMENTE APPLIC48ILITY STATUS /DATE*- REMARKS A-26/ Reactor Vessel Pressure | |||
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- | DOR Letters to: PWR NC ' SCE&G-Document Control MPA B-04 Transient Protection Licensees 8/76- | ||
Line 208: | Line 122: | ||
NUREG/CR-3509 A-42/ Pipe Cracks in Boiling -NUREG-0313. Rev. 1- BWR NA | NUREG/CR-3509 A-42/ Pipe Cracks in Boiling -NUREG-0313. Rev. 1- BWR NA | ||
, MPA B-05 Water Reactors NUREG-0313 Rev.:2 | , MPA B-05 Water Reactors NUREG-0313 Rev.:2 | ||
' GL 81-03, GL'88 ~, - | ' GL 81-03, GL'88 ~, - | ||
4 | 4 | ||
Line 218: | Line 131: | ||
g | g | ||
^ | ^ | ||
r- - | r- - | ||
, a ~.- | , a ~.- | ||
2 USI/MPA ' | 2 USI/MPA ' | ||
=L NUMBER TITLE REF. DOCUMENT APPLICABILITY STATUS /DATE* ~ REMARKS l - | =L NUMBER TITLE REF. DOCUMENT APPLICABILITY STATUS /DATE* ~ REMARKS l - | ||
A-43 | 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. | |||
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. | .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) | 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 | A-46 Seismic Qualification NUREG-1030 All NA of Equipment in NUREG-1211/ | ||
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. | 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.- | 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 | , SECY'R3-260 SECY 81-687 | ||
. 10 CFR 50.61/ | . 10 CFR 50.61/ | ||
. GL 88-11 | . GL 88-11 | ||
,w | ,w | ||
-g- --a-- w .-w . - < , - -,aw. - - - - -a.--~~,-- - - ~ ,ww-m--,-- . . - - -r--- -..-,msx | -g- --a-- w .-w . - < , - -,aw. - - - - -a.--~~,-- - - ~ ,ww-m--,-- . . - - -r--- -..-,msx | ||
- - - - m.--.+-}} | - - - - m.--.+-}} |
Latest revision as of 11:36, 18 February 2020
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.
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)
, , - 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
^
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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.--.+-