ML19262A413
| ML19262A413 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 03/04/1977 |
| From: | Arnold R METROPOLITAN EDISON CO. |
| To: | Reid R Office of Nuclear Reactor Regulation |
| References | |
| GQL-0295, GQL-295, NUDOCS 7910290500 | |
| Download: ML19262A413 (3) | |
Text
NRCPoRM 195 U.s. NUCLE AR REGULATORY COMMISSaoN OoCKET NUMBER 50 289
- r. 7si f
NRC DISTRIBUTICb roR PART 50 DOCKET MATERI AL
/O:
FROM:
DATE oF DOCUMENT R.W. REID METRCPOLITAN EDISON CO.
3/4/77 DATE RECEIVED R.C. Arnold
/0/I,'
MLETTER O NOTo RIZ E D PROP INPUT FORM NUMBER OF COPIES RECEIVED oRiclNAL U NC LASSIFI E D COPY DE SC RIP Tlo N ENCLOSURE 3
g ggg g g g, phone conversation between Mr W.F.. Potts of
~
Met-ED.ind Mr. G. Zwetzig of NRC relating o Met-Ed's analysis of the NRC fission gas y
release medel.
)
l
\\
\\ '. m *,C T' 9 D, j PLANT NAME-
, g,T E I f
1AoA 170 SAFETY FOR ACTION /INFORMATION pyfT un I
'T U 7 rLv ASSIGNED AD:
AcqTmen An.
/ HMllCH CHIEF!
K e. t d-( 5) npAven evTer.
7 PROJECT E\\ NAGER:
'2 u.; e. -h 2.,t t PROJECT MANAGER:
- 4 LIC. ASST. ?
,T-n 3 r-im LIC. ASST. :
~
~
~
l INTERN AL DISTRIBUTION
/ RFfr 7">
SYSTEMS SAFETY PLANT SYSTEMS SITE SAFETY &
~
4 NRC PDR HEINEMAN TEDESCO ENVIRO ANALYSIS f-I-& E (2.)
- SCHROEDER-BENAROYA *' -
DENTON & M" T ro -
/
OELD TATNA9
/ GOSSICK & STAFF ENGINEERING l
IPPOLITO ENVIRO hCE.
I MIPC MACARRY I-KTRKWOOD ERNST CASE BOSNAK BALLARD HANAUER SIHWEIL I
OPERATING REACTORS YOCiG3LOOD HARLESS PAWLICKI STELLO
+
SITE TECH.
PROJECT MANAGEMENT I
REACTOR SAFETY
{
OPERATING TECH.
CAMMILL BOYD
/
ROSS
/l EISENHUT STEPP P. COLLINS NOVAK
./l SEA 0 HULMAN i
HOUSTON ROSZTOCZY
/ BAF3
[7)
PETERSON
/
CEECK
'/
B'AER SITE ANALYSIS MELTZ
/
/( yyl.s V, s
/
CBP.I.E S VOLIJtER HELTEMES AT & I
/
F Ce f J. e o BUNCH SKOVHOLT SALTZMAN
/
.7.
G u t. hwr
/
J._ _C_0LLINS I
RUTBERC KRECER EXTERNAL DISTRIBUTION CON TROL NUMBER g LPDR:#cp w b<n /t NAL_L\\3 :
BRO.QKHAVEN MAT. TA9-
/ TIC:
REG V.IE ULRIKSON (PRNL) 7 NSIC:
LA 55E
[/
ASLB:
CO'IS_ULTANTS :
"J")c')80203
)
/ ACRS Jb CYS ttCtDINO/5ENT d b CPfF NRC soRu tos e.:ci N91ooo.6*O
~
= Mjj G/. a a
,'c reen ran manss METROPOLIIAN EDISON COMPANY POST 0FFicE BOX 542 READING PENNSYLVANI A 19603 TELEPHONE 215 - 929-3601 March h, 1977
.,.,..-.,y.-,4 ry - a. m e,,,l 029;-
I uw A..,.. 2 -
.a3a..-iw. s s
Directcr cf Nuclear Reactor Regulations
/g' _
Attn:
R. W. Reid, Chief v4,,$.@'7.?agk Cperating Res.ctors Eranch No. L
~ ' <l r'N! M ^
/
U. S. :inclear Regulatory Ocnrissicn M
' 5.W
'4ashington, D. C.
20555 c D/%
i>
A
//'Al1
Dear Sir:
e Docket !o. 50-259 Operating License No. DFR-50 As stated in the telephone conversation between Mr. '4. E. Potts of Met-Ed and Mr. G ' Zwetzig cf the IEC, we are sending this letter to inform you of the latest develeprents cencerning cur analysis cf the :GC fissien gas release ecdel.
GPUSC has been conducting an independent analysis of the proposed IEC fission gas release ecdel in crder to evaluate the results reported by E&'4's TAFY code. This analysis has been performed using an in-house version of the GAFCON-TEERMAl-2 fuel performance code which was medified to incorporate bcth the E&~4 and the IEC fission gas release =cdel.
The results indica.te that fer the E&'4 release scdel there is good agreement thrcugh end of life (apprcxint.tely 3h,CCO MWD /MIU) between the TAFY and SAPCCII pin pressure. EcVever, tsing the IEC burnup - dependent release redel, GAFCCII generates consistently higher pressu~e than TA?Y; the difference also increases with increasing burnup. The GAPCCN values indicate that the pressure in the peak rod will exceed TMI '.'s syster preszure (2135 psi) at approximately 32,000 MWD /:CU. This vculd cccur at the earliest in !!cvember, assuming 100,5 capacity factor. TAFY predicts pressures which are belev syster pressure at end cf Jycle 3.
1484 129
% Q s?. 4 U 7 O7 [D h
4 R. '.;. Reid.
The results of the GPUSC study to evaluate the E&W analysis are provided for informatien only. Because of uncertainties concerning the accuracy and medeling of GAFCON - THERMAL - 2, these results can only be considered interim and the GPUSC analysis is centinuing. The differences between the GAFCCH and TAFY calculated pin pressure therefere provide no basis for believing that the E&W results are in error.
~t may be noted that the TAFY code is NRC appreved while GAFCCH is not.
Althcue. the results to date cf the GPUSC analysis do not allev a conrident ec=parison with the E&W response to the NRC, they do de=cnstrate that any pctential difficulties due to the imposition cf the propcsed NRC fission gas release model en TMI-l fuel vill net cecur before the end of the year. Therefore, we request approxinately three =cnths to forward GFUSC's evaluation of E&W's analysis.
Sincerely, t
/i I
L
. o
&cj R. C. )
..cid Vice rresident ECA:DGM:kl 1484 130