ML20058F535
| ML20058F535 | |
| Person / Time | |
|---|---|
| Issue date: | 07/21/1982 |
| From: | Bevan R Office of Nuclear Reactor Regulation |
| To: | Vassallo D Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML20058F540 | List: |
| References | |
| NUDOCS 8207300556 | |
| Download: ML20058F535 (13) | |
Text
s Q
3 c,
g n
Jut 2 f 193 MEMORANDUM FOR:
Domenic B. Vassallo, Chief Operating Reactors Branch #2 FROM:
Roby Bevan, Project Manager Operating Reactors Branch #2
SUBJECT:
SUMMARY
OF JULY 14, 1982 MEETING WITH EXXON NUCLEAR COMPANY A meeting was held between NRC staff and Exxon Nuclear Company (ENC) on July 14, 1982. The meeting had been requested by ENC for the purpose of discussing the status of the NRC staff review of generic and plant / cycle specific topical reports on ENC fuel reloads, and to present the detailed ENC licensing procedure as applied to upcoming BWR reloads. Attendees to the meeting are identified in Enclosure 1.
A copy of a non-proprietary version of the viewgraphs used are contained in Enclosure 2.
The status of the generic reload analyses was reviewed. The hope was ex-pressed by ENC that the staff's SERs on those topical could be completed by September 1982. The staff indicated that this is a realistic schedule.
A holdup in obtaining some data tapes seemed to be critical in completion of the staff reviews of ENC topical 80-19 and this was promised to get expedited attention.
Regarding upcoming plant / cycle specific reloads of jet pump BWRs for which ENC has contracts, plant specific reload analyses were discussed, including analyses of nomal operation (mechanical,themal, hydraulic, and nuclear design analyses), anticipated operational occurrences, and postulated accidents (e.g. LOCA, control rod loop accident).
Technical specification changes necessary for reloads with ENC fuel were discussed, and were compared to the Standard Technical Specification l
for the BWR-6.
The need for certain types of infomation not readily apparent in the ENC proposal was identified by the staff.
Parts of staff policy regarding licensing of new fuel types (e.g. need to prenotice or not) were discussed.
Finally, a proposed fomat for the plant specific reload analysis was d'j]
presented and discussed With the staff in some detail.
i 8207300556 820721 PDR TOPRP EMVEXXN C
PDR orrice) suanue >
oave >
unc ronu aia 00-80> Nacu oao OFFIClAL RECORD COPY usam mi-m. a
t,b Q
C"~.s
.a,
_ l-?
2_
l Since much or most of the content of the presentation was ENC proprietary, details of the content cannot be given in this meeting summary.
A non -
proprietary presentation was also given, using the attached viewgraphs as an outline. A more detailed description of the material presented by ENC is available for official staff use.
[/'
Roby Bevan, Project Manager Operating Reactors Branch #2 Division of Licensing
. r
- 5. ["#2M, 'M
orrice t em sua m e)
. 7
...y.g..
oan >
NRC FORM 318 (10-80) NnCMONO OFFICIAL RECORD C.OPY usam i i-m..
l
=
ENCLOSURE 1
~
Attendance list - Meeting with ENC - 7/14/82 NRC Roby Bevan C. H. Berlinger NRC/DSI/CPB G. A. Schwenk NRC/DSI/CPB G. F. Owsley Exxon Nuclear J. N. Morgan Exxon Nuclear J. C. Chandler Exxon Nuclear J. R. Wojnarowski Celo - NFS C. L. Tyrone MP & L - Nuclear Fuels J. G. Cesare MP & L - Supc. of Licensing H. E. Williamson Exxon Nuclear C. E. Dodge PP & L - Nuclear Fuels G. F. Dick NRC/NRR' E. H. Davidson NRC/DSI/RSB C. Graves NRC/DSI/RSB S. L. Wu NRC/DSI/CPB Larry Phillips NRC/DSI/CPB Ralph Meyer NRC/DSI/CPB George Sofer Exxon Nuclear Ernest Moore Cincinnati Gas & Electric James Cunningham*
- present only at the non-proprietary presentatinn.
$7M**w;wa; -** 7-*, +wf w..=.,m e
%.,e g.,,,
t
\\
I
~
~
l..
~ ~
ENCLOSURE 2 JET PUMP BWR FOLLOW-0N LICENSING JULY 114, 1982 BETHESDA, MARYLAND AGENDA INTRODUCTION J. N. MORGAN STATUS OF GENERIC REVIEW G. F. 0WSLEY APPLICATION OF,THE ENC LICENSING PROCEDURE TO BWR RELOADS J. C. CHANDLER GENERIC RELOAD ANALYSES PLANT SPECIFIC RELOAD ANALYSES TECHNICAL SPECIFICATIONS INDIVIDUAL PLANT RELOAD DOCUMENTATION
SUMMARY
AND SCHEDULES OPEN DISCUSSION
__ _._ ___ 2*?_y **-~_y_*_w g e y q._% gr.m._qf
- w.
..e.
w - =.w -, esuppee
.**w-#,c.
w w e~..
7,- w e 9_,
7.._ o....m y ep., e.
..y 7
CLa'z-'__2_..*
- ~ ~ ~ -
* ~ ~ ~ ~~~'"*' ~ ~ ~ ~ ~ ' ~ ~ ' ' ~ ^
a MEETING OBJECTIVES FOR JET PUMP BWRs:
IDENTIFY LICENSING TOPICS A)
GENERIC B)
PLANT / CYCLE SPECIFIC, IDENTIFY SCHEDULE FOR APPROVALS OF GENERIC TOPICAL REPORTS ESTABLISH CONTENT OF PLANT / CYCLE SPECIFIC SARs ESTABLISH CHANGES IN TECHNICAL SPECIFICATIONS FOR UTILIZING ENC FUEL ESTABLISH DOCUMENTATION SCHEDULE
..<**.-.wese* w.page., e+ + ceae..
- e'**t_*"*
_T"~**__**"?7'"**'*V'_*7**f_
7,*'.***~*'*'"**'""'"""'**'***
- '#~
~W
- 1.. -.,.. x. a :.a..,= :. x. w a..u...
- .- - --... a ~.. c...-.
-.a a-. -
t..
- - -. ~.
GENERIC BWR ANALYSES FUEL MECHANICAL DESIGN ANALYSES REPORTED IN XN-NF-81-21(A) i i
i i
CONTROL R0D DROP ACCIDENT
~
REPORTED IN XN-NF-80-19(A), VOLUME 1 i
170 CAL /GM FUEL FAILURE CRITERION (SRP) 280 CAL /GM LIMIT FOR VIOLENT EXPULSION OF FUEL (SRP) hMNr 'm-Me i recrw21.cm.F%ful.e&*EP:*.*L' PMT.E
_E m_P.h a ML A* T L* _* T*.a*Tet hi.N.M P.P N.WPB4 MMS *J.A...-,.
... MWP.
l, s
.s
~ ~ ~ *
- c
~~
PLANT SPECIFIC RELOAD ANALYSES r
ANALYSIS OF NORMAL OPERATION MECHANICAL DESIGN ANALYSIS THERMAL HYDRAULIC DESIGN ANALYSIS NUCLEAR DESIGN ANALYSIS ANALYSIS OF ANTICIPATED OPERATIONAL OCCURRENCES ANALYSIS OF POSTULATED ACCIDENTS TECHNICAL SPECIFICATIONS
+_.o.
.-w-sc-ns,,,.m_q,_.-.9...yw,y,..
s
_.,,p
%..m-,.am..
--m
l....... =........:
s.
t.
MECHANICAL DESIGN ANALYSIS l
O P
h 0
t 4
I I
I I
i i
I i
i t
i i
.o 0
ipyyew*= c e e e*w --
- =-e=*-.=we==ee eg e,
seg e weay ame
-p.
mey v=_--
9 gymmeewsne,
.w e ew wmy *= e,emmes pegpe ypg mme w ee.egave-e
_ pgg w.e-.mg%
a...
.a..
x.a.:. w..
....w..a a. ~ -
. u.
x..
t m
l I
l I
NUCLEAR DESIGN ANALYSIS FUE'l BUNDLE NUCLEAR DESIGN e
BUNDLE CONFIGURATION ENRICHMENT DISTRIBUTION BURNABLE POISON DISTRIBUTION TYPE AND LOCATION OF INERT RODS N
REACTOR CORE NUCLEAR DESIGN CORE CONFIGURATION SHUTDOWN MARGINS CONTROL ROD PATTERNS STABILITY ANALYSIS 6
5
-?w NwMa%*"MtN9 MtS9._ -
- w.c MP.UN*V MM"WF'"" N CN '* M*",'
""*M3T'8"'"'MMW"*"'"#"*"**"""
- .=,..
1.2-.,a
- .u..a.,.. ~
.. =.... -.
t..
..=.....a.-.
ANTICIPATED OPERATIONAL OCCURRENCES P'LANT TRANSIENTS AT RATED CONDITIONS
\\,
t l
ASME OVERPRESSURIZATION ANALYSIS i
REACTOR CORE EVENTS CONTROL R0D WITHDRAWAL ERROR FUEL LOADING EiROR DETERMINATION OF THERMAL MARGINS W
WS*MTLl '
--i'...
~
~ ?
TT*' *
- ?,"
^
' " !'[- "
u.
$T"?
- k.,...: a :u aw.=a a... n.
.z.-. x... =...
\\..
s s
/
...._...s
. _.g
.\\,
g I J i
POSTULATED ACCIDENTS
\\
r
(
LOSS OF COOLANT ACCIDENT (LOCA)
}
ACCEPTED EVALUATION MODEL DETERMINE MAPLHGR (NODAL P0WER) LIMITS Sn 8
- CONTROL R0D DROP ACCIDENT (RDA)
}
J
(
I l
s l
.ThO*?N4?M* M* ?ws'"*S9.TMge yw_*.wo.*,-eew t.
v.pp.ye;yy. 7.. y,., e,y.py.,.~
w.
mg,
D ' t@w72. -
_.n
- ~....
. :~
u..
a :.:x.
w...:, a w....
y, 4
TECHNICAL SPECIFICATIONS (NUREG-0123)
LIMITING. SAFETY SYSTEM SETTINGS MCPR FUEL CLADDING INTEGRITY SAFETY LIMIT STEAM DOME PRESSURE SAFETY LIMIT LIMITING CONDITIONS FOR OPERATION APRM SETPOINTS MAPLHGR LIMITS FOR ENC FUEL MCPR 0PERATING LIMITS LHGR LIMITS SURVEILLANCE REQUIREMENTS ADDRESSED IF APPLICABLE
,ep G
x-~=m==- =s us -,_,-_,,- --_ =-- 1_ =xu s a n vu-.m.mc--.--~~.=wv...---~~~~---