ML19347D486
| ML19347D486 | |
| Person / Time | |
|---|---|
| Site: | Midland |
| Issue date: | 03/18/1981 |
| From: | Tedesco R Office of Nuclear Reactor Regulation |
| To: | Jackie Cook CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.) |
| References | |
| NUDOCS 8103260120 | |
| Download: ML19347D486 (27) | |
Text
s
>R [to E('
[o, UNITED STATES
'n NUCLEAR REGULATORY COMMISSION l
WASHINGTON, D. C. 20555
$j a
.. [..
MAR 1 8 193; 7
Docket Nos.:
50-329/330
/ gl% k2
/S t-L,,k
% e, Mr. J. W. Cook
/
cSf pOg Vice President Consumers Power Company 1945 West Parnall Road Jackson, Michigan 49201
Dear Mr. Cook:
SUBJECT:
CHECKLIST OF GENERIC LETTERS AND BULLETINS FOR 1980 Attached for your infonnation is a listing of generic letters and bulletins issued to Powr Reactor Licensees and Applicants in 1980.
The listing is in two parts: (a) those items sent to Power Reactor Licensees and applicants, and (b) those items sent to applicants only.
The listing identifies the addressee generically, by PWR type and licensing status. Should you have questions regarding this list with respect to Midland Plant, Units 1 and 2, contact our licensing project manager.
Si ncerely, F 0 'C 4 ~
Rober t L. Teaesco, Assistant Director for Licensing Division of Licensing
Enclosure:
As stated I
cc: See next page.
C10826 0 %
fN-
s Mr. J. W. Cook Vice President Consumers Power Company 1945 West Parnall Road Jackson, Michigan 49201 I
cc: Michael I. Miller, Esq.
Ronald G. Zamarin, Esq.
Mr. Don van Farowe, Chief Alan S. Farnell, Esq.
Division of Radiolooical Health Isham, Lincoln & Beale Department of Public Health
,r.
Suite 4200 P.O. 00x 33035 1 First National Plaza Lansing, Michigan a8909 Chicago, Illinois 60603 James E. Brunner, Esq.-
Consumers Power Company William J. Scanlon, Esq.
212 West Michigan Avenue 2034 Pauline Boulevard Jackson, Michigan 49201 Ann Arbor, Michigan 48103 Myron M. Cherry, Esq.
U. S. Nuclear Regulatory Commission i
1 IBM Plaza Resident Inspectors Office Route 7 Chicago, Illinois 60611 Midland, Michigan 48640 Ms. Mary Sinclair 5711 Summerset Drive Ms. Barbara Stamiris 5795 N. River Midland, Michigan 48640 Freeland, tiichigan 48623 Frank J. Kelley, Esq.
Attorney General State of Michigan Environmental Protection Division 720 Law Building Lansing, Michigan 48913 Mr. Wendell Marshall Route 10 Midland,' Michigan 48640 Mr. Steve Gadler 2120 Carter Avenue St. Paul, Minnesota 55108 g
.4.y3
1
- -- S
..O s,u,,,:
..is., Pc,. R --.
.R,.--..e---
- .i:x..
.. i t.
.v
.a:
.u u. v
..:..::2
-e r,. t c#.. ru n u r:xo...,.
i..a,. u.c :.-..:~...,
i2
..s nCL.-,
4 C r. -.4 5. t.... c.'4 r--.d....
sv.
.n e.a z.
ina
.e W
n E
d o
S g
y est s
d s
s t
st) y s
y y
s 0E PT 0
iepn y
ad a it eul ee SA a
bnD I
ED 4
nqnck D
oeuxa 0
a 9
R 1
's 0
lf r( et 9
7 4
9 l
e
- a c
rc n
S oi eg D
f r i ir A
nt ri c
i el f
d rl e
pl o
o oe ll xa i
f u ef n
nae re i f o
o1 n
t s P
ar id i
i1 s
t t
ro eot a
is E
t gt crr u
ds S
n oa e
e l
O e
rr rl s a
al da P
a R
m Pe on vy C
s n
gri U
o Ae et g
P C
Qg is t ni t i
ny sl i
s i
on t ol el t
e d
wl scl rt snm e
n ee e
u ia eop e
is utif ur uii t
vel qt qe qt u x
eii ei o ep eaq E
I do Rwt Ro R
t nie i
l g
se i
f nA t n iC nf l
S at lO ie D
un lL nr A
Qe e
eo wr rt m
s f
So ia e
o ai p
l f
ur e
y t u qe u
yl nq gs en l
t p t
nl Re uf i
ip n
ie G
a l u nf T
dd e
f C
do cl i S oi l
E aM ne d
lac i s r
l.
l as o
ri vs I
l C -
re H
I i
ui et na S
e sD pa i
I l i
l O
r 0r s
o u
1 C 3
u "s Ag r
1 e
6t 1 f 1
n t
0n 0o 0 pi yi n
P
- us td o
0 9i GRy ir C
8e 7 os E
l l a v
Rda a gl R
l l
l nn uei W
l a t a l
l i l iNaA QR O' V
I c
I e
s si s
e eO e
e s
sr n
na e
ee c
cl
)
rL i
i c y
oO 0
1 L,
L u a
t it B
cn s
r r
i s
aa ra O
o os et e i o
J t
t a ed Rs t i c
cs) sl t
ct t
a an2 no ri ai e
ea eh ew eu R
ikd cn w
H t
rn iu os s
r rAa Ll P e re e
e l
w wtI Rt Rt wt i
ei o
op p
l
'e P
Pes 8 e Bl Pl l
i oi t
i ct c
i i
l l xi l x l c l c l
lE n A
A(U A (e l
l a l a Af A'.
0 0
0 0
0 8
8 8
b
/
/
/
l E
/
/
0 T
3 7
4 1
1 A
/
/
/
/
/
1 1
D 1
1 1
1 1
h s'
RESP 0 rise DATE TO SUBJECT PURPOSE DATE 1/21/80 All BWR Licensees with a lLU B0-02 Inadequate quality Requesting Information on 90 Days CP or OL Assugnce for Nuclear Supplied feedwater spargers and Ei;6ilg1rnent thermal sleeves from Harvin Engineering I
I 1/29/80 All Power Reactor Licensees Low Level Radioactive klaste informing of revised require-Be fore fg'-
flisposal ments on waste forms; submit Opera t ion
(
revised Process Control no specif j
Program (lf required) date i
2/6/80 All lloiders of Power IEB 80-03 Loss of Charcoal from Requiring inspection and 45 Days
- ~
)
Reactor OLs and cps Standard Type II, 2 Inch, Tray evaluation of charcoal adsor-Adsorber Cellt ber cells 2/8/80 All PilR Reactor IEB 80-04 Analysis of a PWR Main Review accident analysis fo.r 90 Days facilities llolding OLs Steam Line Break with Continued containment overpressure and and to those nearing feedaater Addition the reactivity increase from Licensing cooldown
' 'I. i
/ 2/23/80 All LilR Licensees LilR Primary Coolant System Pressure Requires 1) description of valve 14 Days isolation Valves configuration 2) description of testing and 3) description of modi fications if necessary 0
t
E d
S e
d d
i E
r s
s e
e t0T i
r s
r y
y PA eu i
y a
a i
SD nq eu a
eu DdD E
oe nq D
nq R
ir n
oe oe t
0a1 l
r 0
l r
f 6
1 f
9 n
i f
r s
oy e
m r
d d
t m
erna n
n n
s e
t o o'ss a
a I
n l
s i
o b
yet e nasor l
f s
i u r o
srpc oct o
ne nt r
ui e 4ii ntf l
ocf P
l srn 5t gar (
aow ao tf s l sc 6 aol o n
e aesf 0 rl Pps n
n oes h
rei ao pt eea n
i ve t
f pd G pi e u n mh tii etd d
o n
E: ran l) e d sS a.
at v t e wd o l
l n
n ce av woni uPRonPt E
pna ner S
pi hl el at l
pi n
or t o i
c rf s re f
O u
s f rd P
snn s
vnsa gooeseu R
oo noe ne eit nf Rswn s
icd or rane U
sii i
n eoo P
ttt n7 i
t av t aoynPC s
,a2 t n snti tii cd ias esp-ae eo t
irt nerd mn e snu rC x9 ne rcpc u eaeran i I e7 nb t
noq ue st u ga e a i
af u/
o u t d, r nil rpl rnf ql dB f s R t MW'.
qaI araeece ef nE na i
Tio eh rCvmri s R N,a I Ih h
I" EEPt u i
f mo i
r l
f l
a r
a ut c
Qn pe e
i) w s
mS i
e l m ro a
neC TP e
ohV ap ti l
rl iCC nu e
t
(
e q' ol R
t u io nE dt m i
cf s-n e
n
'oE a
a oet 3
rI e 7, G
Cgs g
R0 T
i~
ay n
C vs 0
n mms i
31 E
ns o
ua n
J Ea i
ry uDl n
n l
s c
o a
u C
el s
S B
ve anrs l
i Vitk P
1 f it f
0o Ra nn 5 goa y
m d
0nCT c
li 9n e
- i n
ax c
0t ep e
7 o t o n
8l n u g
i sr Bt a
uud r
Ea yp h
Bsl l e
rp n
E eoo n
I c CA E
I RVl E -
l se i
t r
i o
l t
se i
tt r c
c sP nao a
a f
e rLC art R
oO cec t
a ipa r
cg lOe W
o anh rp R
- O t
T c
B eit opo Rdi tat r) a w
c ed g
l e
R n
ro adeue ehe ensot i
L t
w s
RanPe r0 e
as oso e
L w n, re Peh rscrc s
it eeiao ee l
oa Rt weLeD i
P ps W
i io os l
l On h
L Plt PnacR l t e
e uA i
l c l
li l cd l
crNS li Aw AL A
'A f a ALf a(
l l an*
li o f
08 0
0
/
0 8
8 0
E 9
8
/
/
8 T
2
/
0 A
/
6 0
/
1 1
0 D
2
/
/
/
1 3
3 3
/3 iip 1
g, I.
I I
f
.i 3
/
~
i RESPONSI DATE 10, SUBJECT PURPOSE DATE
. 4/12/80 All Operating Nuclear Plants NRC Nuclear Data Link (NDL)
Transmits for infonnation None
" Nuclear Data Link Required Speci fica tions" 3/13/80 All Power Reactor facilities IE8 80-06 Engineered Safety Review system drawings and 90 Days with an OL feature (EST) Reset Controls provide a scliedule of, testing g
to assure tilat uposi reset all i
ESF equipment remains in the emergency snode 3/28/80 '
All Power Reactor Applicants Qualifications of Reactor Revised criteria for reactor Various -
.and Licensees Opera tors operator traittisig and licensing:
30 Days (1) experience, 2) training, 3) 240 Days facility certifications, 4) asid increased scope of exams 5)
I20 Days requali fication programs g /4/80 All GE 8tlR-3 and 8tlR-4 IE8 80-07 8tlR Jet Pump Assembly Requires visual inspections arid 30 Days 4
facilities with an OL failure ultrasonic examinations of jet pump s tructures, written report f
4/7/80 All Power Reactors with a IE8 80-08 Examination of Requires ' report of non-f.0 Days CP and/or 01 no later than Contalem.ent Liner Penetration destructive esa.uinations 4i April 7, 1980 lleids flued head design penetic: asig
e8 RESP 0tiSE DATE TO SullJECT PURPOSE DATE j/7/80 All DWR licensees Hodifications to Boiling Water Informat fori concerning tiie Hone Reactor Control Rod Drive Systems NRC staff's conclusions on Required CR0 system nodifications to eliminate cracking in the return line nozzle 4/10/50 All Power Reactor Licensees Operability of Systems Clarify nicaning of term 30 Days Operatile as it applies to single failure criterion for safety systems required tech spec.submittals 4/17/80 All Power Reactor Operating ifit 80-09 Ilydranotor Actuator Report verifications that 60f$ays facilities and liciders of Deficiencies ample nurgin exists for Power Reactor Construction actuation with luiproper Permits springs installed
. 4/25/80 All Power Reactor Licensees Clarification of flRC Requircuients Information on facilities lione for fmergency Response facilities Required at Each Site 4/25/80 Individual Licensees E f f ec t of a DC power Supply Confirm that the f.! re ference Jn Days f ailure on ICCS perforuunce s tuily regarding mininami I CC',
equipment availability with a DC power supply failure is appropriate for plant speciiIc application
,a RESPONIE DATE TO SUBJECT QM,
DATE _ _ _
5/6/80 All Power Reactor facilities IED 80-10 Contamination of tion-Report on the review of 45 Days with an OL or CP radioactive System and Resulting systems that could become Potential for Unmonitored. Uncon-contaminated due to leakage trolled Release to Environ!nent valving errors; establish routine monitoring program 5/7/80 All Operating Reactor five Additional IMI-2 Related Transmits requirements for:
Various(S Licensees Requirements to Operating Reactors
- 1) Shift Hanning. 2) Licensing enclosure Exams 3) Licensee Dissemination of letter of Operating Eiperiences. 4)
L0fil and SBLOCA Generic Revleu and 5) Control Room liabitability 5/8/80 All Power Reactor facilit-IEB 80-11 Hasonry llall Design Report on reevaluation of masonry 60 Days les with an OL except Trojan wall design with attachments and from safety related equipment IBu Days 5/8/80 Individual Licensees Transmitting fluREG-0645 " Report In formation ilone of the Bulletins and Orders Task force and appropriate flDREG-0626 Required
" Generic Evaluation of feedsater Transients and Small Break Loss-of-Coolant Accidents"
s8 -
DATE TO SUBJECT.
RESP 0flSE PURPOSE DATE 5/9/80 Each PWR with an OL IEB 80-12 Decay lleat Removal Report on adequacy of 30 Days System Operability decay licat renoval capability during all nodes of operation 5/12/80 All BWR's with an OL IEB 80-13 Cracking in Core
'nspect and report on core 30 Days Spray Spargers spray spragers and related piping 5/19/80 All Licensees witti Reactor Fire Protection Rule Enclosing proposed rule flone Operating Licenses issued
" fire Protection Prograni Required Prior to January 1,1979 for fluclear Power Plants Operating Prior to Jan.1, 1979 5/19/80 All Power Reactor Licensees Genert'c Technical Activity A-12 Requesting connents on Potential 60 Days Fracture Toughness for Low Fracture Tonghness and Lamellar Tearing on PWR Steani Generator and Reactor Coolant Pump Supports flVREG-0577 5/22/80 All Licensees with Reactor fire Protection Rule Enclosuing revised pages to ihne Operating Licenses issued S/19/80 letter on fire Required Prior to January 1,1979 frotection
st
RESPONSE
DATE TO SUBJECT PURPOSE DATE 6/3/80 Individual Licensees Nuclear Safeguards Problems Participation in a study of None people-related problems in Required nuclear safeguards 6/5/80 All BWR Licensees Generic Activity A BWR 1ransmitting fluREG-0619 30 Days '
' Cracks "BilR Feedwater Nozzle and Control Rod Drive Return Line Nozzle Cracking, requesting cournen ts.
6/9/80 All Operating Reactor Five additional THI-2 related Transmitting errata sheets to tione Licensees requirements May 7 letter on five Required additional 1HI-2 related requirenents 6/11/80 All Operating Pressurized Decay lleat Removal Capability Requesting anendment to 15 re 120 Days Water Reactors reactor decay heat removal
capability 6/12/80 All BilR's with an OL IEB 80-14 Degradation of Scram Report on review of SDV level 45 Days Discharge Volume Capatoility switches and associated piping l
. E d
p 5
d e
s l
0 f
y e
f r
i r
_ D a
S1 eu D
i nq eu EA 0
ne 0
nq P, D 6
iR 3
oe f
iR l
s e
l eh vt o
a n
rt i t i
c t u e
ti d ei l
co w
i rr a
en sg a
i t s l
r l
a tl c re il in c
i 0cai rs gi car i 8et r oo et r
i ane ru9l nt cR f ow d1 eec Rc t
io n
me dr el c St p a,rnl ne l
ae l
l it a r7 ooe ap rl ne a
tl E re o2f r n
o eae et i
if wr d nmf l pi eynvo E
l os Haon ep eono S
a f
i n
fio Mien vi O
nf g
t o
e s
geiogrn P
ti o ndcdi rrr R
aa ieent s oe riRvi U
hmf tt t aat nft nt i
f t eo t ao cn o
t t eeat r
idr,i e si t r cn t
s m
psf n t nm mesf m i
sie rds sr eio ros scuip ol o neell p oin i i pul ad rb a m pt a at sau cli r
eo rriauo ecr roiuq Rwa TOf cqc rat 1 l dqe f
nod
- r i n t a t e r
a h
low e
c1t s o
d I
5ie P
r i
wd f
l 1 O
oe p1 o
p sC t
d asr si n
sl et sS a
et u o-i Lf i
Hdt p a
f oit u
Mmu eO d
la sO l
n
,n T
bf a
i C
io r
t
.a n c r "D E
s o
9 J
ss m
enT" m
os e
Q t Io er E
Po M
t S
L Pt ro i
nu n
r us 5h o
o s "A o
1 t 6
i me s
- i 1 er" s
0w s
g 8
0 sP r n
in 8o e
e i
s)
R2h t
Bn nQ B
5t c
Ei oE Ef1 l e
Il C(
o1E H
I s
tn r
a e
c wo l
s P ' d i
e p
n L
i p
a O
t A
s i
t s
l r
n ri r
ra omse O
i o
T c
o f ree t
t h eens a
c ct f
as sPsir ai t
ngo ee rs Re ew r
aL R
i nend s
aocE n s
eO rn cii/e l
re tLtV ee l
ei cg wc wtP purer i c c
un oi oiC prot o Ni PL d
Pl Attit ia ll l d schc Oar c
l o naca l n l
AH Aa Afo ACRAR oere l
0 0
0 0
8 8
8 8
/
/
E 8
5
/
/
7 T
1 2
0 A
/
/
2 3
D 6
6
/
/6 6
d.
RESP 0f4SE DATE TO SUBJECT PURPOSE DATE 7/2/80 All Pressurized Water Reactor THI-2 Lessons Learned Enclosing Model Techical 60lyyg Licensees Specifications for NUREG-0578 THI-2 Lessons Learned Category A Items, requires submittal 7/2/80 All Bolling Water Reactor THI-2 Lessons Learned Enclosing flodel Technical 60 Days Licensees Specifications for NUREG-0578 Illi-2 Lessons Learned Category A Items. Requires submittal 7/3/00 All BilR Power Reactor 108 80 17 failure of Control Report on review of emergency 14 Days facilities llo) ding OLs Rods to Insert During a Scrara operating procedures, on one at a BilR manual and one automatic scram test 7/7/80 All Boiling Water Reactors Scram Discharge Volume Designs Requesting amenda.ent to technica190 Days specificationis with respect to control rod drive scram discharge volume capabillty 7/11/80 lo All Applicants for Licensing Schedule Requests Coninent 30 ' cays Operating Licenses and Construction Permit flolders
t 3 RESP 0flSE DATE 10 SUBJECT PURPOSE DATE 7/18/80 All BWR Power Reactor IEB 80-17 Supplement 1 Report on SDV systems, 4S Days facilities Holding Ots failure of' Control Rods to install water level Insert During a Scram at a nonitoring system BWR 7/22/80 All Boiling Water Reactors Scram Discharge Volume Referencing 7/7/80 letter None and stating that TS change Required request is a Class III Ifcense fee submittal 7/22/80 All BWR Power Reactors,
IED 80-17 Supplement 2 Report on review of SDV 7 Days failures Revealed by Testing vent system Subsequent to failure of Control Rods to insert During A Scram at a BUR 7/24/80 All PWR Pouer Reactor IEB 80-18 Maintenance of Report on calculations of 60 Days facilities lloiding OLs Adequate itinimum flow Thru minimum cooling flow for and to those PLlRs Centrifugal Charging Pumps centrifugal charging pumps nearing Licensing following Secondary Side liigh and corrective actions if Energy Line Rupture necessary 7/31/80 All fluclear Pouer.
IEB 80-19 failures of flercury-Report on use and surveillance 90 Days facilities llaving Either Wetted 11 atrix Relays in Reactor of mercury-wetted nutrix an OL or a CP Protective Systems of Operating relays fluclear Pouer Plants Designed by Combustion Engineering
RESP 0rl50 f4TE T_0 SUBJECf PURPOSE DATE 7/31/80 To Each Nuclear Power facility IE8 80-20 Failures of Westinghouse Report on use, testing 90 Days in your Region having an OL or Type W-2 Spring Return to tieutral and corrective actions a CP Control Switches for 11-2 spring return switches 7/ 31/80 All Licensees of Operating Interim Criteria for Shift Staffing Requires the development and lione Plants and Applicants for Operating Licenses and Holders implementation of adininis-Required of Construction Pennits trative procedures by 10/31/80 8/1/80 All Applicants for Con-
" functional Criteria for Emergency for infonaation and coament 30 Days struction Pennits, Licensees Response facilities" flVREG-0696 of Plants Under Constru-ction and All Operating Nuclear Power Plants 8/7/80 All Operating Power Lessons Learned Tech Specs Referencing letters of flone Reactor Licensees 7/2/80 and requesting Required Anaud.nent fee Classi fication 8/15/80 All Westinghouse Pressur-Refueling flater Level Transmittincj Standard 30 Days ized llater R.: actor Licensees Technical Specifications to require at least 23 feed of water over the top of the reactor pressure vessel flange
e' RESP 0flSE DATE TO SilBJECT PURPOSE DATE 8/20/80 All BWRs with Mark I Hark I Containnent Long-Term Enclosing Cy of NUREG-Nune Containnen t Program 0661 " Hark I Containment Required Long-Term Program Safety Evaluation Report, Re-solution of Generic Technical Activity A-7" 8/22/80 All 811R Power Reactor IEB 80-17 Suppleinent 3 Report on procedures requiring 14 Days facilities Holding OLs failures Revealed by Testing iminediate nunual scram cn Subsequent to failure of various conditions Control Rods to Insert During a Scram at a B!!R 9/5/80 All Licensees of Preliminary Clarification of Reques ts coiunents, discusses fio speci fi.
Operating Plants and THI Action Plan Requirenents Regional tketings date '-
Applicants for Approx.
Operating Licenses and 30 Days lloiders of Construction Permits 9/19/80 All Licensees of Preliminary clarification of Addendum to 9/5 letter fione Operating Reactor Plants Ill! Action Plan Requirements Required and Applicants for Operating Licesises and llolders of Construction Pe mits
8'
_ 14
RESPONSE
DATE TO SUBJECT PURPOSE DATE 9/30/80 All Power Reactor Fact 11tles IEB 79-010 Supplenent 2 Information in the form None with an OL Environmental Qualification of of questions and answers Required Class IE Equipment 10/1/80 All Licensees of Operat.ing Environmental Qualification of Requests voluntary 30 Days Plants and Applicants for Safety-Related Equipnent assistance in an EQ testing Operating Licenses audit program and lloiders of Construction Permits 10/1/80
- All BUR Licensees BWR Scram System Submit. plans for partici-30 Days pation in long term program to upgrade scram systems 10/6/80 All Power Reactor Implementation of Guidance from Inforg.ation and suusnary of flone Licensees and Applicants Unresolved Safety Issue A-12 staf f's program required
" Potential for Lou Fracture Toughness and Lanellar Tearing on Component Supports" 10/21/80 All Operating Pressurized Seismic Qualification of romards preliminary lione llater Reactor Licensees Auxiliary feedaater Systems probabilistic assessment of ikquired seismically induced loss of decay heat renoval systems, discusses long term program
, s..
RESP 0llSE DATE TO SUBJECT PURPOSE DATE 10/24/80
- All Power React'or facilities IEB 79-010 Supplement 3 Clarification of subniittal None with an OL Environmental Quall*fication of requirements Required IE Equipment 10/31/80 All Licensees of Operating Post TH! Requirements
.fonearded requirements and 30 Days Plants and Applicants for NUREG-0737 implementation dates, Operating Licenses and requested corianitments lloiders of Construction Permits 11/04/80 All 1101ders of Construction ODYil Code Calculation information on staff's use tione Permits end Operating of ODYll Code in analyses of Required Licenses for BWRs pressurization transients 11/6/80 All Light Water Reactor IED 80-21 Valve yokes Report on inspection and,
30 Days facilities lloiding OLs or supplied by ltalcolm foundry corrective actions concerning cps Company, Inc.
flairom valve yotes 11/13/B0 All Licensees of Oper-Emergency Plan Describes submittal schedules ilone ating Reactor Plants, of new rule Required lloiders of Construction Pennits and Appilcants for Construction Pennits
8 - -
RESP 0tiSE DATE TO SUBJECT PURPOSE DATE 11/13/80 All BWR Licerisees Generic Activity A-10 Fonsards requireinents of 45 Days NUREG-0619 "8WR feedwater Nozzle and Control Rod Drive Return Line Nozzle Cracking" 11/14/80 All Power Reactors fire Protection forwards new Section 50.48 None and Appendix R. discusses Required schedules and SERs 11/14/80 All Nuclear Power IEB 80-23 failures of Report on use and replacement 45 Days OL or CP Solenoid Valves Engineering schedule for affected valves Corpora tion 11/20/80 All Power Reactors IED 00-24 Prevention of Report on actions to prevent 45 Days with OLs Damage due to Water Leakage flooding of containment Inside Containment 11/24/80 All Power 1icensas with Appendix R to 10 CFR 50 re.
fonsards new regulations, lists 30 Days Plants Licensed prior to Fire Protection open items concerning fire if January 1, 1979 protection for each facility necessary
et ~
RESP 0tiSE DATE TO SUBJECT PURPOSE DATE 11/25/80 Operating Reactors with Inservice Inspection Programs Requests volusitary infor-None Prestressed Concrete Contain-mation on containment Required ment Structures tendon tests 11/25/80 To All Power Reactor fire Proetction forwards revised lione Licensees with Plants federal Register flotice Required Licensed Prior to Jarsry 1, 1979 11/26/80 All Licensees of Operating Orders on Environnental Provides clarification on ilone Plants and Appilcants for Qualification of Safety record requirements Required Operatirig Licerises asid Related Electrical Holders of Construction Equipnent Permits 12/9/80 To All BWR Licensees BIJR Scram Discharge Systen Trarismi ts staf t 's Generic *
- lione Safety Evaluation Report Required for Informat ion O
.s -
ItESP0tisf DATE 10 50tNECT PU,Rf050 fMTE 0
12/9/80 All Licensees of Operating Energency Planning forwards 1) NUREG-0654, idone Reactor Plants, lloiders of Revision 1" Criteria for Required Construction Permits and Preparation and Evaluation Applicants for Construction Permits of Radiological Energency Response Plans and Preparedness in Support of Nuclear Power Plants" and 2) sunninary rating sliects for evacuation tinie estimates 12/15/80 All Operating Reactor Periodic Updating of 15ARs losuards new rule and flone Licensees guidance in the form of Required questions and answers I?/18/fl0 All llWR ticensees
!!!! 80-17 Supplenent 4 Requires testinq of 45 Days failure of fontrol Rods to insert Cont inuous nmitoring During a Scram at a IlllH Sys t eal for Scram Discharge VoInitie l ? / 1 9 /110 All tillit Power iteac tos-IL(180-25 Opera t ting l'ioblepis it, view and test lesej r eqis i re.
90 Days Iacilitles nsith as 01.
with Iasyet ItocL Safetv IteIlef eini sits f or To get Roti S/RV and fermi ?, Shoseham Valves I?/22/lio All iicensees of Operating Control of fleavy loads luip leinen t interim action 90 Days Plants arid Applicasits for-Operat inir) I tcesises arid Reviesi arid Itepoi t 6 ::irilhs Permits Itesul t s 9 "inths
LETTERS TO OPERATING LICENSE AND CONSTRUCTION PERMIT APPLICANTS.*
W
,s DATE RESP 0fiSE TO SUBJECT PURp0SE DATE.
1/18/80 All BWR Applicants issuance of fiUREG-0313. Rev.1, for infonnation and C0 Days
" Technical Report on Material consnents Selection and Processing Guide-lines for BWR Coolant Pressure Boundary Piping" 2/S/80 All Constrcction Pennit Issuance of fluREG-0588, " Interim Transmitting tiUREG-0588 60 Days and Operating License Staff Position on Equipment for interim use and Applicants Qualifications of Safety-Related consnent (All PWR & BWR Electrical Equipment Applicants) 2/21/80 All Operating License Qualification of Safety-Related Requires review of all 45 days Applicants Electrical Equipment safety related electrical equipment quali fication documentation and description of descriptive aClion if necessary i
3/10/80 All Pending Operating Actions Required from Operating Requires infonnation related Info. to License Applicants of License Applicants of fluclear to Auxiliary feedaater Systems be provid.
iluclear Steam Supply Steam Supply Systems Designed by as amend-Systems Designed by Westinghouse and Combustion Eng.
ment on Westinghouse.ind resulting from the flRC Bulletins applicatic Coubustion Engineering and Orders Task force Review Regarding the Three Mile Island Unit 2 Accident i
e
el DATE RESP 0tlSE TO
' SUBJECT PURPOSE DATE-3/10/80 All. Power Reactor Licensees issuance of NUREG-06S4/ FEMA-REP-1, Transmitting NUREG-0654/ FEMA 1/1/81
& Applicants for a License
Criteria for Preparation and REP-1 for interini use in to Operate a Nuclear Power Evaluation of Radiological Emergency evaluation of emergency plans Reactor FSAR Docketed Response Plans and Preparedness in Call Power Reactor Licensees)
Support of Nuclear gower Plants 3/11/80 All Applicants for Constru-Change of Submittal Date for Postpones date for submittal 45 Days ction Permits and Licensees Evaluation Time Estimates of evacuation time estimates of Plants Under Construction pending GAO review completion 4/21/80 All Construction Permits Information Request on Category I Requests response to list of flone and Operating Licensee Masonry Walls Employed by Plants questions concerning Category I given Applicants Under CP and OL Review masonry walls 4/24/80 All Pending Operating Actions Required from Operating Requires evaluations and other Info. to License Applicants of License Applicants of fluclear Steam information cosicerning auxiliary be provide fluclear Steam Supply Supply Systems Designed by Babcock feedwater systems as an Systems Designed by and Wilcox Resulting from the flRC amend nent Babcock and Wilcox Bulletins and Orders lask force on applica Review regarding the Three Mile tion Island Unit 2 Accident (auxiliary feedwater systems) 11/25/80 All Appilcants for Operating Conmission Memorandum and Order of Requests date for completion of flone Licenses and lloiders of May 23,1980 (referencing If staf f review relating to equip-given Construction Permits Holletin 79-010-Supplement flo. 2 -
ment qualification of electrical Q.2 & 3 - Sept. 30, 1980) equipment
9 d
RESP 0rlS.E DATE TO SU3 JECT PURPOSE DATE lLU 110-02 Requesting Information on 90 Days 1/21/80 All BWR Licensees with a Assur,ance, Inadequate f]uality CP or OL for Nuclear Supplied feedwater sparger' and Equhtraent thermal sleeves from Harvin Engineering
'1/29/80 All Power Reactor Licensees Low Level Radioactive llaste informing of revised require-11e fore Disposal riients on waste forms; submit Operation-revised Process Control no speci fi t'rogram (lI required) date 2/6/80 All I! alders of Power IED 80-03 Loss of Charcoal from Requiring inspectf6n and a5 riavs Reactor OLs and cps Standard Type 11, 2 inch, Tray evaluation of charcoal adsor-Adsorber Cells ber cells 2/8/80 All PWR Reactor IED 80-04 Analysis of a PilR Hain Review accident analysis foy 90 Days facilities Holding 01s Steam Line Dreak with Continued contatriment overpressure and and to those nearing feedwater Addition the reactivity increase from Licensing cooldoun 2/23/80 All LWR Licensees LilR Primary Coolant System Pressure Requires 1) description of valve 11 Davs isolation Valves configuratinn 2) description of testing anil 3)' description of umil f ica t i.ons i( necessary
3 RESP 0t!SE DATE T0 5UBJECT PURPOSE DATE 0
2/29/80 All Power Reactor Fadilities
.IEB 79-018 Enviro'nmental Quali f f-Transmits supplemental tione with an OL cation of Class IE Equipment information in the form required of questions and answers
~
3/6/80 All Operating B&W Reactor Crystal River 3 Reactor Trip from Requires information on '
60 Days L.icensees Approximately 100% Full Power
'fitlI/ICS corsective actions and
'and expanded review of 11 Days IE8 79-27 3/10/80 All LWRs
- Enhanced Fission Gas Releas'e Information that the Problem flond has been resolved required 3/16/80
'All PUR Power Reactor IEB'80-05 Vacuum Condition Requires review of all systems 90 Days Facilities holding OLs Resulting in Damage to Chemical that contain low pressure or and to those wills a CP Volume Control System (CVCS) holdup tanks and description of Iloldup Tanks corrective action if necessary 3/10/80 All Power Reactor Emergency Planning Transmi tting flVREG,06S4 lione Licensees and Applicants
" Criteria for Preparation and required for a License to Operate Evaluation of Radiological a lluclear Power Reactor (FSAR Docketed)
Emergency Response Plants and Preparedness in Support of l
lluclear Power Plants (For Interim i
I Use and Coninent).
ei s.
RESP 0llSE DATE TO SUBJECT PURPOSE DATE 3/12/80 All Operating Nuclear Plants NRC Nuclear Data Link (NDL)
Transmits for information tione
" Nuclear Data Link Required Speci fica tions" 3/13/80 All Power Reactor, facilities IEB 80-06 Engineered Safety Review system drawings and 90 Days Nith an OL Feature (EST) Reset Controls provide a schedule of testing to assure that upon reset all ESF equipment remains in the energency node 3/28/80 All Power Reactor Applicants Qualifications of Reactor Revised criteria for reactor Various -
,and Licensees Operators operator training and licensing:
30 Days (1) experience, 2) training, 3) 240 Days facility certifications, 4) and increased scope of exams S) 120 Days requali fication programs 4/4/80 All GE BklR-3 and DilR-4 IEB 80-07 DilR Jet Pump Assembly Requires visual inspections and 30 Days facilities with an OL-failure ultrasonic examinations of jet pump structures, written report 4/7/80 All Power Reactors with a, IEB 80-08 Examination of Requires report of non.
- 64) Days CP and/or OL no later than Containtuent Liner Penetration destructive ceaminations of Aprl) 7, 1980 tields flued head design penetratin:.>
-