ML19206A401
| ML19206A401 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 05/26/1978 |
| From: | Herbein J Metropolitan Edison Co |
| To: | |
| Shared Package | |
| ML19206A395 | List: |
| References | |
| NUDOCS 7904200006 | |
| Download: ML19206A401 (7) | |
Text
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Three :lile Island Nuclear Station Unit 2 (TMI-2)
Operating License No. DPR-73 Cocket No. 50-320
_ Technical Soecification Chance Recuest No. 015 The licensee requests that the attached changed pages replace pages 3 3/4 7-1, 3/4 7-2, and 3/4 7-3 of the existing TMI-2 Technical Specifications.
Reason for Chanze Recuest Due to operational proble=s, Met-Ed has found it necessary to replace the 12 originally installed dual discharge port main steam relief valves, with 20 somewhat smaller single discharge port main steam reliaf valves.
It is necessary to change the TMI-2 Technic al Specifications to reflect this design change.
Safety Analvsis Justifyinn Chance The proposed change ia.reases the relief capacity of the system frca 114% of the total secondarf steam flow to 120% of that flow.
Because the purpose of the main steaa relier valves is to provide pressure relief for the main steas system, this change represents a change in the conservative direction.
Therefore any pror,3ed accident which could occur would be bounded by safety analyses which have already been perfor:ed.
In addition, all system modifications aill be cade in accordance with the requirements c-the appropriate sections of the ASME Codes.
For the reasons discursed above, it hac been determined that as a result of this change:
1.
The probability of occurrence of any accident analyzed in the TMI-2 FSAR is not increased.
2.
The probable consequences of any accideat analyzed in the TMI-2 FSAR are not magnified.
3.
The potential for the occurrence of an accident not prr.viously analyzed in the TMI-2 FSAR is not introduced.
Amendrent Classification (10 CFR 170.22) 3ecause this change it.volves a single safety iss:., this change representa a Class III License Ace.'d=ent (as defined by 10 CFR 170.22).
Therefore, enclosec please find the crescribed remittance of $4,0CO.00.
790420 0006
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3/4.7 P_ ANT SYSTEMS BASES 3/4.7.1 TURBINE CYCLE 3/4.7.1.1 SAFETY VALVES The OPERABILITY of the main steam line code safety valm
.,eres that the secondary system pressure will be limited to within i ndL of its design pressure during thq most severe anticipated system operational transient.
The maximum relieving capacity is associated with a turbine trip from 100% RATED THERMAL POWER coincident with an assumed loss of condenser hea t sink (i.e., nu steam bypass to the condenser).
The specified valve lift settings. and relieving capacities are in act.s: dance with the requirements of Section III of the ASME Boiler and Pressure Vessel Code,1958 Edition.
The total gelieving capacity for all valves on all of the steam lines is >- 14.63 10 lbs/he which is 120 l
percent of the total secondary steam flow of 12.2 10 lbs/hr at 100%
RATED THERMAL POWER.
a STARTUP and/or POWER OPERATION is allowable with safety valves inoperable within the limitations of the ACTION requirements on the basis of the reduction in secor.. lory system steam flow and THERMAL POWER required by the reduced reactor trip settings of the Nuclear Overpower channels.
The reactor trip setpoint reductions are derived on the following bases:
x whern j' = reduced Nutlear Overpower Trip Setpoint in percent of l
RATED THERMAL POWER 8
V = maximum number of inoperable s&fety valves per steam genera to r SP = Nuclear Overpower Trip Setpoint specified in Table 2.2.1 l
X = Totai relieving capacity of all safety valves per steam generator in lbs/heur Y = Relieving capacity of any one safety valve in 1bs./ hour (based on 120% re'leving cacacity for 20 valves).
THREE MILE ISLA:C - UNIT 2 B 3/4 7-1 b 4
'.7 '. 7
6
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R r
E a
W ctO l nP ci E
uoL L
NpA t
B t 1 A
eeR R
lSE E
b H
P a pT l
wi 0
orD f
I lTE l
l T
ara iT eR mw I
W uof mpo T
ir 9
4 8
7 3
N xet I
avn 0
MOe 4
4 3
3 2
P c
9 8
7 6
5 T
r E
e S
S P
E
(
P V
I L
R A T
V 1
R Y
7 E
T W E 3
O F
P A
E R
S L
E B
VET A
OI T
I R
L AEi d
i ICT U1 i
S f
E L
B y
A t
W e
O f r L
ao L
St A
a er M
l e U
b n M
ae I
rG X
e A
pm M
oa ne It S
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b n mo lu se mv ulma ivxa fi t4
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gna o aE2r cF" GEE i
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TA0l.E 3,7-4 STEAM LIflE SAFETY VALVES "ER STEAM GEflERATOR val.VE fillMBER LIFTSETTIllG(t1%)*
ORIFICE SIZE h
{squareinches) lP Steam Generator A i
BE a.
MS-R21A 1050 psig 16 r5 b.
MS-R22A 1050 psig 16 E2 l
2; c.
MS-R26A 1050 psig 16 k h 0
6.
MS-R27A 1050 psig 16 Eir; e.
MS-R23A 1065 psig 16 m
f.
hs-R28A 1065 psig 16 g.
MS-R24A 1075 psig 16 h.
MS-R29A 1075 psig 16 to2
- i. MS-R25A 1102 psig 16 y
L>
- j. f15-R30A 1102 psig 16 Steam Ge_nera tor B a.
MS-R21B 1050 psig 16 b.
MS-R220 1050 psig 16 c.
MS-R26B 1p50 psi 9 16 C,'
d.
MS-R27B 1050 psig 16
-Ta i
e.
f15-R23B 1065 psig 16
, y,
.s bh
~
TABLE 3 7-4 (C0flTIflVED)
STEAM LIrlE SAFETY VALVES PER STEAM GEtlERATOR N
VALVE fluMBER LIFT SETTIflG (i 1%)*
ORIFICE SIZE lIl f.
f15-R28B 1065 psig 16 P
g.
f45-R24B 1075 psig 16 g
W G
(-
h.
MS-R29B 1075 psig 16 E5 i.
MS-R25B 1102 psig 16 j.
f tS-R30B 1102 psig 16 ro t'
u g,'
T O
C
-d 6
'O
- The lift setting pressure shall correspond to ambient conditions of the valve
!I at nominal operating temperature and pressure.
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