ML20098B902
| ML20098B902 | |
| Person / Time | |
|---|---|
| Site: | Limerick  |
| Issue date: | 09/21/1984 |
| From: | Kemper J PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC |
| To: | Schwencer A Office of Nuclear Reactor Regulation |
| References | |
| OL, NUDOCS 8409260333 | |
| Download: ML20098B902 (4) | |
Text
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PHILADELPHIA ELECTRIC COMPANY 2301 M ARKET STREET P.O. BOX 8699 PHILADELPHIA, PA.19101 (2151841 4502
... "?tif l 11 SEP 21 1984 Mr. A. Schwencer, Chief Docket No. 50-352 Licensing Branch No. 2 50-353 Division of Licensing U. S. Nuclear Regulatory Camtission Washington, D.C.
20555
Subject:
Limerick Generating Station, Units 1 and 2 Information for Reactor Systems Branch (RSB)
Regarding 'Ibchnical Specification Figure 3.2.3-1
References:
Telecon between RSB and PECO on 9/20/84 File:
GOVT l-1 (NRC)
Dear Mr. Schwencer:
Attached is a draft change to our response to FSAR Question 440.5 which is being made as a result of the referenced telecon.
The information contained in this draft FSAR change will be incorporated into the FSAR, exactly as it appears on the attachment, in the revision scheduled for October 1984.
Sincerely, DEC/gra/09148402 Attachment Copy to:
(See Attached Service List) 8409260333 840921 I
PDR ADOCK 05000352 A
cc: Judge Lawrence Brenner (w/ enclosure)
Judge Peter A. Morris (w/ enclosure)
Judge Richard F. Cole (w/ enclosure)
Judge Christine N. Kohl
- (w/ enclosure)
Judge Gary J. Edles (w/ enclosure) dudge Reginald L'. Gotchy (w/ enclosure)
Troy B. Conner, Jr., Esq.
(w/ enclosure)
Ann P. Hodgdon, Esq.
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Mr. Frank R. Romano.
(w/ enclosure)
Mr. Robert L. Anthony (w/ enclosure)
Ms. Maureen Mulligan (w/ enclosure)
Charles W. Elliot, Esq.
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Zori G. Ferkin, Esq.
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Mr.' Thomas Gerusky (w/ enclosure)
Director, Penna. Emergency (w/ enclosure)
Management Agency Angus R.' Love, Esq.
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David Wersan, Esq.
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' Robert J. Sugarman, Esq.
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Martha W. Bush, Esq.
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Spence W. Perry, Esq.
(w/ enclosure) day M. Gutterre2., Esq.
(w/ enclosure) 4 Atomic Safety S Licensing (w/ enclosure)
Appeal. Board Atomic Safety & Licensing (w/ enclosure)
Board Panel Docket'S Service Section (w/ enclosure)
.Mr. James'Wiggins (w/ enclosure)
Mr. Timothy R. S. Campbell (w/ enclosure) r a-
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LGS FSAR DRAIFT OUESTION 440.5 (Section 15.0)
GE' calculations performed for rapid pressurization and for decrease in core coolant temperature (Feedwater Controller Failure, Maximum Demand) events using the ODYN model have shown that in some cases a more severe CPR is predicted than that by the REDY model (NEDO-10802).
Show that the loss of feedwater heating event would still remain the most limiting by assuming the following transient events to be analyzed with the ODYN model:_
(1) generator load rejection without bypass; (2) turbine trip,without bypass; and (3) feedwater controller failure, maximum demand.
RESPONSE
Results of the reanalysis of the three requested transients are shown in Table 440.5-1 and Fig (ures 440.5-1, 0*E' *s 2 and 3.
LastetO The required operating limit CPRJvalues are summarized in Table 440.5-2 for these three pressurization transients and for two non-pressurization events:
The Loss of Feedwater Heater and the Rod Withdrawal Error Transients.
The reqsicer operating limit
'(
CPR is determined by b:t' t' = ~ m grrrrrrirrtic.. eventW, and is
^
the:same for both Op A and Option B ODYN adjustment factors, regardless of the frequency category of the turbine bypass failure transients.
g
$n Albkihlon'[o Qt a %o w e.
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})pe g N eg.[ o f St hilfkris*C byJJ lpeiny I*soye-s ble. was gagn+c[tej for ihC.
l Feea waa-c..Ja.Ite t -;Iu, Muin
- l)e,. a eveJ e,,) p.;. s; Jon
- l-Feedwaku Ace 4~ e v<.d.
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ba+k o f %p eJe h fous J 4 Le 1,,r in it e de.rtp w e.,
f'.rtcal><bllaQ OLc PR.
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loeye.,1 -He d wyn ba.r ts, he lo<d Rejec% eveni and
-be Feed w de-CoAntle-Gilwe, Mut-De n< J eucJ w"'
hAiet p<.u and esaludel a.ra.a,n t.,y % f hok y
rea:e<.aled;*1 pa a.,yr idy
( ECC-VPT) wo<e inope<<ble 3 N'N re1a;<eJ Ot-C.PR.! whia i.s boa,d<d by '
l re.rvlled. in a
j lim s t ran3 ins fe.,
I2s' b t-32. 7~h e ' resolf r are A l.ro included In l\\
oV'%en ad46to-sal autyse r
'Ti kl e.
'N O. f - 2 440.5-1 Rev. 20, 05/83
. ~
LGS FSAR DRA'FT TABLE 440.5-2 REQUIRED OPERATING LIMIT CPR VALUESC1)
Pressurization Events:
CPR CPR (Option A)(a)
(Option B)(a)
Load Rejection Without Bypass 1.19 1.11 Turbine Trip Without Bypass 1.17 1.10 Feedwater Controller Failure, 1.17 1.14 127% Flow DRAFT Non-Pressurization Events:
CPR Rod Withdrawal ErrorC3) 1.21(*)
Loss of Feedwater Heater 1.22 ( * )
Supplemental Non-Chapter 15 Events:
~
Feedwater Controller Failure, 1.22 1.19 127% Flow. Withqut Bypass Feedwater Controller Failure, 127% Flow. With ut Bypass, q, 4 l /26 9
whs E o c- ({ P T Load Rejection Without Bypass an,d, nd Without E0C-RPT 1,28 1.17 Loss of Feedwater Heater Withogt Bypa>>
1.21(*)
l=
(1) For minimum CPR of 1.06 l
(2) Includes adjustment factors as specified in the NRC safety evaluation report on ODYN, NEDO-24154 and NEDE-24154-P.
l OLCPR value is obtained for the 107% Rod Block setpoint, (3)
Control Cell Core analysis.
l
(*) Required OLCPR using either Option A or Option B adjustment factor regardless of frequency category of the turbine-generator trip events with bypass failure.
Rev. 20, 05/83 L'