ML20081D442
| ML20081D442 | |
| Person / Time | |
|---|---|
| Site: | Nine Mile Point  |
| Issue date: | 10/26/1983 |
| From: | NIAGARA MOHAWK POWER CORP. |
| To: | |
| Shared Package | |
| ML17054A188 | List: |
| References | |
| NUDOCS 8311010189 | |
| Download: ML20081D442 (17) | |
Text
_.
s LIMITING CONDITION FOR OPERATION SURVEILLANCE RE0UIREMENT 3.2.2 MINIMUM REACTOR VESSEL TEMPERATURE FOR 4.2.2 MINIMUM REACTOR VESSEL TEMPERATURE FOR PRESSURIZATION PRESSURIZATION Applicability:
Applicability:
Applies to the minimum vessel temperature Applies to the required vessel temperature for required for vessel pressurization.
pressurization.
Objective:
Objective:
To assure that no substantial pressure is To assure that the vessel is not subjected to imposed on the reactor vessel unless its any substantial pressure unless its temperature is considerably above its Nil temperature is greater than its NDTT.
Ductility Transiti cn Temperature (NDTT).
Specification:
Specification:
a.
During reactor vessel heat-up and a.
Reactor vessel temperature and pressure cooldown when the reactor is not shall be monitored and controlled to critical the reactor vessel temperature assure that the pressure and temperature and pressure shall satisfy the limits are met.
requirements of Figure 3.2.2.a.
b.
During reactor vessel heat-up and b.
Vessel material surveillance samples l
cooldown when the reactor is critical located within the core region to permit the reactor vessel temperature and periodic mcnitoring of exposure and pressure shall satisfy the requirements material properties shall be inspected of Figure 3.2.2.b, except when on the fall cwing schedule:
dg g
performing low power physics testing o
with the vessel head removed at power First capsule - cne f curth service life c) levels not to exceed 5 mw(t).
Second capsule - three fourth service life a)g o-I., the event the surveillance specimens at 35 one quarter cf the vessels service life indicate a shift of reference temperature o<
greater than predicted the schedule shall Ca:
be revised as follows:
@h Second capsule - one half service life 77
LIMITING CONDITION FOR OPERATION SURVEILLANCE REOUIREMENT 9
c.
During hydrostatic testing the
/
reactor vessel temperature and f
pressure shall satisfy the require-ments of Figure 3.2.2.c if the core is not critical and Figure 3.2.2.d if the core is critical.
d.
The reactor vessel head bolting studs shall not be under tension unless the temperature of the vessel head flange and the head are are equal to or greater than 100F.
78
1600 1400 1200 LIMIT FOR NON-CRITICAL OPERATION INCLUDING HEATUP/ COOLDOWN AT f
UP TO 100 F/HR aa bO w n.
mO 800 u)
W 712 600 mm OS o <r 387 200 O
O 100 16 0 200 300 i
MINIMUM VESSEL TEMPERATURE (F) l FIGURE 3.2.2.a 1
a MINIMUM TEMPERATURE FOR PRESSURIZATION DURING HEATUP OR COOLDOWN (RE CTOR NOT CRITICAL)
(HEATING OR COOLING RATE $ IOOF/HR)
FOR UP TO TEN EFFECTIVE FULL POWER YEARS OF CORE OPERATION
LIMIT FOR NON-CRITICAL OPERATION INCLUDING HEAT-UP/C00LDOWN AT UP T0 100F/HR i
PRESSURE (psig)
TEMPERATURE (F) 387 100 387 100-160 712 160 762 166 812 172 862 177 912 182 962 187 1012 192 1062 196 1112 199 1162 203 1212 207 1312 213 1412 219 TABLE 3.2.2.a MINIMUM TEMPERATURE FOR PRESSURIZATION DURING HEAT-UP OR C00LDOWN (REACTOR NOT CRITICAL)
(HEATING OR COOLING RATE 100F/HR)
FOR UP TO TEN EFFECTIVE FULL POWER YEARS OF CORE OPERATION h
1600 1400 1200 LIMIT FOR POWER u) o OPERATION (CORE Q. O CRITICAL) INCLUDING HEATUP/COOLDOWN AT UP TO 100 F/ HR
~
g 8"
/
yZ 712 x
O 600 xx OD F u)
O <t 40 2
38 WATER LEVEL MUST BE IN NORMAL
//
302 OPERATING BAND FOR CORE TO BE 200
/
CRITICAL AT
/
TEMPERATURES M
O O
100 200 300 MINIMUM VESSEL TEMPERATURE (F) l FIGURE 3.2.2.b 5
l MINIMUM TEMPER ATURE FOR PRESSURIZATION DURING HEATUP OR COOLDOWN -(REACTOR CRITICAL) l (HEATING OR COOLING RATE 5 IOOF/HR)
FOR UP TO TEN EFFECTIVE FULL POWER YEARS OF CORE OPERATION 1
9 LIMIT FOR POWER OPERATION (CORE CRITICAL) INCLUDING HEAT-UP/
C00LD0WN AT UP TO 100F/HR PRESSURE (psig)
TEMPERATURE-(F) 302 100 312 106 362 127 387 136 387 137-200 712 200 762 206 812 212 862 217 912 222 962 227 1012 232 1062 236 1112 239 1162 243 1212 247 1312 253 1412 259 TABLE 3.2.2.b MINIMUM TEMPERATURE FOR PRESSURIZATION DURING HEAT-UP OR C00LD0WN (REACTOR CRITICAL)
(HEATING OR COOLING RATE 100F/HR)
FOR UP TO TEN EFFECTIVE FULL POWER YEARS OF CORE OPERATION l
1600 I4I2' 1400 1200 q
W M
O.
1000
%O Litv.lT FOR INSERVICE TEST O
930 (CORE NOT CRITICAL, m
FUEL IN VESSEL) ea
$f 800 a.
l--
$o F. uj 600 W
uo
-m$4 4
387 m
?
I 200 O
O 10 0 130 200 300 MINIMUM VESSEL TEMPERATURE (F)
FIGURE 3.2.2.c 1
MINIMUM TEMPERATURE FOR PRESSURIZATION DURING m
HYDROSTATIC TESTING (REACTOR NOT CRITICAL) 4, FOR UP TO TEN EFFECTIVE FULL POWER YEARS OF CORE OPERATION
LIMIT FOR IN-SERVICE TEST (CORE NOT CRITICAL, FUEL IN VESSEL)
PRESSURE (psig)
TEMPERATURE (F) 387 100-130 930 130 962 135 1012 142 1062 148 1112 153 1212 164 1312 173 1412 181 TABLE 3.2.2.c MINIMUM TEMPERATURE FOR PRESSURIZATION DURING HYDR 0 STATIC TESTING (REACTOR NOT CRITICAL)
FOR UP TO TEN EFFECTIVE FULL POWER YEARS OF CORE OPERATION h
4 1600 1400 1278 1200 m
G.
1000 EO LIMIT FOR INSERVICE TESTS (CORE CRITICAL) h 800 a.
F-600 x
0D
-m 4 4 400 387 -
x 200 O
10 0 170 200 300 MINIMUM VESSEL TEMPERATURE (F)
FIGURE 3.2.2.d g
MINIMUM TEMPERATURE FOR PRESSURIZATION DURING HYDROSTATIC TESTING (REACTOR CRITICAL)
FOR UP TO TEN EFFECTIVE FULL POWER YEARS OF CORE OPERATION
LIMIT FOR IN-SERVICE TESTS (CORE CRITICAL)
PRESSURE (psig)
TEMPERATURE (F) 387 156 1278 170 1312 173 1412 181 TABLE 3.2.2.d MINIMUM TEMPERATURE FOR PRESSURIZATION DURING HYDCOSTATIC TESTING (REACTOR CRITICAL)
FOR UP TO TEN EFFECTIVE FULL POWER YEARS OF CORE OPERATION
]-
BASES FOR 3.2.2 AND 4.2.2 MINIMUM REACTOR VESSEL TEMPERATURE FOR PRESSURIZATION Figures 3.2.2.a and 3.2.2.b are plots of pressure versus temperature for a heat-up and cool down rate of 100F/hr. maximum.
(Specificati al 3.2.1).
Figures 3.2.2.c and 3.2.2.d are plots of pressure versus temperature f or hydrostatic testing.
These curves are based on calculations of stress intensity factors according te Appendix G cf Section III of the ASME Boiler and Pressure Vessel Code 1980 Editi m with Winter 1982 Addenda.
In additi m, temperature shifts due to integrated neutron flux at ten effective full power years of operation were incorporated into the figures. These shifts were calculated from the f o mula presented in Regulatory Guide 1.99, Revision I and the copper / phosphorus content of the reactor vessel. These curves are applicable to the beltline region at low and elevated temperatures and the vessel flange at intermediate temperatures. Reacter vessel flange / reactor head flange boltup is governed by other criteria as stated in Specification 3.2.2.d.
The pressure readings on the figures have been adjusted to reflect the calculated elevation head difference between the pressure sensing instrument locations and the pressure sensitive area of the core beltline region.
The reactor vessel head flange and vessel flange in conbination with the double "0" ring type seal are designed to provide a leak-tight seal when bolted together. When the vessel head is placed on the reactor vessel, only that porti cn of the head flange near the inside of the vessel rests on the vessel flange. As the head bolts are replaced and tensioned, the vessel head is flexed slightly to bring together the entire contact surfaces adiacent to the "0" rings of the head and vessel flange. Both the head and vessel and flange have a NDT temperature of 40F and they are not subject to any appreciable neutron radiati al exposure. Theref cre, the minimum vessel head and head flange temperature for bolting the head flange and vessel flange is established as 40 + 60F or 100F.
Figures 3.2.2.a, 3.2.2.b, 3.2.2.c and 3.2.2.d have incorporated a temperature shif t due to the calculated integrated neutron flux.
The integrated neutron flux at the vessel wall is calculated from core physics data and has been measured using flux mcnitors installed inside the vessel. The curves are aoplicable f cr up to ten effective full power years of operation.
Vessel material surveillance samples are located within the core regi al to permit periodic mcnitoring of exposure and material properties relative to control samples. The material sample program conforms with ASTM E 185-66 except for the material withdrawal scheduled which is specified in Specificati on 4.2.2.b.
82b W
MDMM l
Lukens Steel Company j_
c Coatesvne, PA 19320 June 30, 1983 Mr. M. Mosier Niagara Mohawk Power Corporation 300 Eric Boulevard, West Syracuse, NY 13202
Dear Sir:
Attached are copies of the Lukens Steel Company " Chemical 4
Laboratory llent Analysis" records.
All non-applicable information has been deleted from these copics.
i We hope this will satisfy your request.
i Sincerely, LUKENS STEEL COMPANY r
J John P. Sunukjian Supt., Q.A. Inspection JPS:wik i
Attachments I
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