ML20024G757
| ML20024G757 | |
| Person / Time | |
|---|---|
| Site: | Monticello  |
| Issue date: | 07/24/1972 |
| From: | Mayer L NORTHERN STATES POWER CO. |
| To: | Anthony Giambusso US ATOMIC ENERGY COMMISSION (AEC) |
| References | |
| NUDOCS 9104290334 | |
| Download: ML20024G757 (2) | |
Text
-
D G
[*
bgulatorY d
(,,/
i v.
f NORTHERN STATES POWER COMPANY kf MIN N E A PO U S. MIN N E SOT A 95401 l
h[*+i
'e
'N Q'JN
.^
July 24, 1972
/ck y >
..~
8*
.,3 Q\\
h$
/s',
\\ v ',c/
p:
. x. b s
jf;.),y wN gt...
Mr. A Giambucco
'~
43,1
.f
- E-Deputy Director for Reactor Projectc 1
' i Ni
+-
MM.
Directorate of Licensing
$6-United States Atomic Diergy Commission Wachington, DC 205k5 y"y
Dear Mr. Giamburso:
1
[.
f MONTICELLO NUCLEAR GENERATING PLAtir t7 DOCIG'r No. 50-263 LICENSE NO. DPR-22 i
i g
CHANGE REQUEST NO. 4 Q"n Attached are three signed originals and nineteen conformed copies of by%^
a request for a change of Technical Specifications of Appendix A of F
the Monticello Naclear Generating Plant.
This change request han been
.Yi reviewed and approved by the Monticello Operations Con =ittee and Safety j
S Audit Cor=ittee.
Yours ver/ truly, y.
6'.,
l y
L 0 Mayer, P.E.
l 3
Director of Nuclear Support Services a
3 LOM/WJ/br y
l V LJ.
cc: B H Grier l
cW.
, \\ F ' a\\
Attachmente
-.b
<N
?H<
d I W ETED
d\\
@~
UuVC
-\\
.,:k
>\\
s J+
tH u UL 2 31972 > ji m
I
'\\
FTCULMcqy
['I
~~
' AM Q
MAIL SECDCN /'sf /1 /
, CCCKET CLEM ' '
. c.
N( /A
\\(O / 7
.*/
r W u-4156 bl-p.
n:.
N104290334 720724 l
PDR ADOCK 05000263 v.
P PDR l
o
e
/JC DISTRIEUTION FOR FART 50 DOCKET MATPRIAL
~'
(TEMPORARY FORM)
CONTROL NO: h156 h
ii ME FROM:
DATE OF DOC:
- ~
l North 2rn States Power Co.".'.pany Minneapolis, Minnesota 55401 L, O. Mayer 7-24-72 7-28-72 I
j TO:
/
SENT LOCAL PDR
/
1 Mr. Gi m busso 3
j INFtTI NO CYS REC'D DOCKET NO:
vs.: 1 GIE0PINFO
" 4.71%. < g..j CLASS:
",p.r;-
' ' NM"D? Wit 4Mb r NY I
22
~#'
ENCLOSURES:,,9 g;,g n h,Techf 9pic,s.Egggk
4.4 DESCRIPIION
Bequest'for. Change Ltr trans the following:
of the Montiosilo' maw" "eeneratingiFlamt/f?
j@!M;%
~
notarized V-24-72.'
- ,a ya py
., ~?)pyyjgt PLANT NAMES: Monticello Naclear Generating
( 22'cys c'd) '
~ACKH0 0.DGED M S
,J T
- ' ' ~
Mt FOR ACTION /I.NFORMATION 7-26-72 AB
~o+
BlJfLER(L)
K.NIEL(L )
VAdSALLO(L)
- 7.IEMANN(L)
KNIGHTON(ENVIRO)
W/' Copies,s W/ Copies W/ Copies W/ Copies Wf Copies me CLARK (L)
SCHWENCER(L)
H. DENTON CIIFIV0OD(FM) 6 W/ Copies W/ Copies W/ Copies W/ Copies W/ Copies GOLLER(L)
STOLZ(L)
SCHEMEL(L)
DICIER (ENVIRO) g W/ Copies W/ Copies W/ Copies W/ Copies W/ Copies INTERNAL DISI'RIBUTION
[
MGFIL]E TECH REVIEW VOLIlER HARLESS WADE dAt,c nm HENDRIE DEITION SHAFER A GC, ROOM F-506A SCHROEDER GRIIGS F&M BROWN VMUICZING/ST5FF MACCARY G/dS!ILL SMILET CASE IANGE KASTHER HUSSBAUMER A/T IND GIAMBUSSO PAWLICKI BALLARD ERAITMAN BOYD.L(BWR)
SHAO FINE LIC ASST.
SALTZMAN DEYOUDG-L(FWR)
KUUIH SERVICE VSKOVHDLT-L STELID ENVIRO MASON FudIS P-COLLIIB HDORE MULLER WIISON MCDONALD THOMPSON DICKER KARI N
REG OFR TEDESCO YdiIGHTON SMITH
/ FILE & REGION (2)
IDNG YOUNGBIDOD GEARIN C. MILES FORRIS LAINAS PROJECT LEADER DIGGS STmR HENAROYA TEETS EXI"OdU1 DISTRIsifflua vi.-IDCAL PDR Minneavolin. Minn.
vi-ICIE(IAUGIILIN)
(1)(5)(9)-IUCIONAL IAB'S 1-FDR-SAN /LA/NY 1-NSIC(EUCHAIUdi)
/diL/ORNL/FNL
- 1. GEP/4D LELLUCHE 1-ASL3-YORE SAYRE 1-R. CARROIL-00, GT-B327 EROCEJIAVEN IUS. IAB WOODWARD H. ST.
1-R. CATLIN, A-170-GT 1-EOUJ:D, IDAHO FALIS,
/16-CYS ACES EOLDING 1-COMSUUdTf 8 3 IDAE0(50-331 only)
NEWxAU./ELU'G/AGABIAN 1-ED.. !aLER.. F-309G2 l
l e
--*w p
w
A
.t.
a i
UNITED STATES ATOMIC ENERGY COIOiISSION
~'
NORTHERN STATES PO'4ER COMPANY Monticello Naclear Generating Plant Ibcket No. 50-263
,.M
- "~
REQUEST FOR AUTHORIZATION OF A CHANGE IN TECHNICAL SPECIFICATI0tG v
0F APPENDIX A
$+
PROVISIONAL OPERATING LICENSE NO. DPR-22 t..h bi (Change Pequeet No. 4 )
gW we Northern States Power Conpany, a Minnesota corporation, requests hg authorization for changes to the Technical Specifications as shown on g
the attachments labeled Exhibit A and Exhibit B.
Exhibit A descrites the proposed changes along with reacons for change.
Exhibit B is u copy of the Technical Specifications marked up to indicate the pmposed changes.
ot This request containc no restricted or other defence inf ormation.
E
~,,.
NORTHERN STATEE PO'4ER C[t!PANY By Arthur V.
Dientart f'
Vice President-Engineering
- i' '
- f
/
On thic w~
day of x // v /
,1972, before me a notary public g,
in and for cald County, peri Dienha rt, Vice President - Engineering, and%gnally appeared Arthur V.
v 'm s eing 'irst duly cuorn acknowledged that he N'
is authorized to execute this document in behalf of Northern Sthes Power h.
Company, that he has read it and knows the contents thereof, that to the best of his knowledge, infomation and belief, the statenents cade in it C
ar ltrue and that it is not interposed for delay.
h* ' '
j l/
h - hn J Ed.ith (h lh,
&J.
3.,
o
~
. ] Notary Fablic, Hennepin County, Minnesota 3%-
JCMN. on-*;
E Mo*wY Pubhc.Ihnn,:nT.hkg:nn...,
W b man tvr.,u,,s y n;,
bi fZ: O W
,n, 79 g v,./ v / J V v '
,2
- e.,
~"
I fy r-
..l 6011111I A o r MONTICELLO NUCLEAR GENERATING PLANT 1
DOCKET NO. 50-263
.w g r,.
PROPOSED CHANGES TO TECHNICAL SPECIFICATIONS f'
] y APPENDIX A 0F PROVISIONAL OPERATING
'e LICEUSL N0. DPR-22 p
M g:N t
$'X s
Pursuant to 10 CFR 50 59, the holders of the above mentioned licence hereby VI propoce changing Section 3 5.C, Residual Heat Removal (RHR) Service Water f
System of Appendix A, Technical Specifications of Provisional Operacing e
License LPR-22 as follows:
D g
On Page 102, Section 3 5. C.L, ".... against a head or 550 reet.",
should be changed to read, ".... against a cyctem head of at 1 cast 500 feet."
t Y
Rencon for chanre:
y,-
The wording of the present Technical Specification is more restrictive than N.r originally intended.
It has been establiched through periodic curveillance E
tests and additional tecting purcuant to the RER cervice water pump low head condition reported in our letter of July 3,1972 that the operatinr margin
- g available to meet the current RHR service water pump heaa requirement ic not Qf adequate. This condition arises basically from the pump performance charac-f' terictic which, as demonstrated on our system, doec not conform with the
.{
canufacturer's certified head-capacity characteristic, and the allovnna or inadequate operating margin in the original eclection of the Technien1 Cpec-nf ification limit.
y Basis for chance:
y.
e.
9:
NO
'Ibe safety design basic of the RER cervice water pump head requirement vno reported to you in our July 3, 1972 letter.
Ac ve have reported, the nurrent I"
Technical Specification requirement is bacea in part upcn the manufacturer'c l;i rating ( 3500 gpm at 626 feet).
The maximum demand on the IdIR cervice water M,
pump would be approximately h80 feet.
The individual contributienc to thic value are cum.ariced as folloVS:
a,
- k.,
315 feet Shell side pressure; measured at heat exchanger inlet, 1 RHR pump e LOOO gpm y;
bl Y
62 feet Flow locces en RER service water cyctem; difference in measured values diccharge pressure and precsure 7"
at heat exchanger outlet (tube side) 8 7000 rpm W:
{
57 feet Primary containment preocure following a LOCA
>W
.g$
h6, feet Bequired differential pressure - tube to chell Ul-480 feet TOTAL w'[ '
tj+w a s~,.
t
f.
O o
7 p
.+
This situation occurs when only one of the two redunac.nt Rim paa.p.; is cperating (minimizing losses on the shell side), delivering 4000 gpm, ana both RER ter-vice water pumps are operatin6 (maximizing flow losses on the tube cide).
R When the RER service water is brought into service following a locs of coolant
- gy accident, a ten minute period is alloted in the design analysis to account for si" operator response time in limiting the containment transient by shifting to the RER containment cooling mode.
The containment pressure at this point ic approximately 22 psig. We have, in this case, conservatively taken the con-
[
tainment pressure at 25 poig, thereby coverin6 any situation where the opera-tor might respend in less than 10 minutes.
p 2he containment cooling mode of the RHR system serves to limit the long term
[
containment pressure and temperature transient.
Since torus water le being recirculated in this mode, the Eervice water pressure is kept higher than the b"
primary side pressure to preclude leakage to the open cycle service water sys-tem.
A minimum differential pressure of 20 psid is required.
The proposed f"
change to the Technical Specification vould provide a minimum m discharce
['
pressure of 500 feet (216 psi) measured in accordance with the definitions F
of the ASME Purep Test Code.
This vould result in a pressure on the RHR E.
service water side of the heat exchangers more than 20 psi greater than the
}t' RER primary side, thus forcing water into the torus in the unlikely event of a heat exchanger tube leak.
The 500 foot limit (i.e. k80 feet plus 20 feet margin) would be sufficient to assure adequate head to meet all cystem P
design bases and contingencies and, at the same time, leave sufficient mar-pT gin to assure the operating and testing flexibility important to plant safety.
b;,
This amendment to the Technical Specification is proposed on the basis of our Y
exyerience with the RER service water system and our complete saticfaction
(
that a reduction in the limit is both tolerable and desirable.
In our opin-ion, this proposed change lessens neithe:. the plant's safety nor reliability from a design or operational standpoint. Specifically, there is no increase T, -
in the probability of, no increases in the possible consequences of, or no A*,.
creation of a credible probability of an accident or equipment malfunction different from those previously evaluated in the FSAR.
The proposed change
[y: has been reviewed and approved by the Monticello Operations Ccm=1ttee and Safety Audit Co=mittee.
34 x'
Q, Y{
w h
$$(
yys A-
%4 TV c.
i.c h.T y
p
a 12HlBIT B 30 LIMITING CONDITIO!!S FOR OPERATIOli 4.0 SURVEILIARCE REQUIRH4DITS reactor operation is permissible only rernining subsystem shall be
(. y during the succeeding thirty days unless demonstrated to be operable imedi-such ptzp is sooner made operable, pro-ately and daily thereafter.
)
y vided that during such thirty days all other active components of the RHR service
'O water system are opernble.
} i 3
From and after the date that one of the 3
When one RHR service water system D
RiiR service water systems is made or founri becomes inoperable, the operable j
to be inoperable for any reason, reactor system shall be demonstrated to be operation is permissible only during the operable irrediately and daily V
succeeding seven days unless such system thereafter.
is sooner made operable, provided that durir,g such seven days all active compc>-
nents of the operable R!IR service water
,}_ b system shall be demonstruted to be opera-ble at least once each day.
4.
To be considered operable, a RJIR service
- I water pump shall be capable of delivering 3500 gpm against a -tcai.r m reet. a syst<m head of at leust 600 feet.
5 Ir the requirements or 3.5.c.1-3 cannot be met, either the requirements of 3 5.H shall be complied with or an orderly shutdown of the reactor will be initiated and the reactor water temperature shall be reduced ta less than 212 F within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
3 5/h.5-7 102
- ~
__ __ _ _ _ -