ML20134H538
| ML20134H538 | |
| Person / Time | |
|---|---|
| Site: | Millstone  |
| Issue date: | 07/18/1985 |
| From: | NORTHEAST NUCLEAR ENERGY CO. |
| To: | |
| Shared Package | |
| ML20134H537 | List: |
| References | |
| NUDOCS 8508290026 | |
| Download: ML20134H538 (29) | |
Text
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ITEM 3.
REACTIVITY CONTROL SYSTEMS JUL 181 cot 3/4.1.2 BORATION SYSTEMS g
FLOW PATH - SHUTDOWN LIMITING CONDITION FOR OPERATION 3.1.2.1 As a minimum, one of the f011'owing boron injection flow paths shall be OPERABLE and capable of being powered from an OPERABLE emergency power source:
S ySYm a.
A flow path from the boric acid 4aMee-via either a boric acid transfer pump or a gra'vity feed connection and a charging pump to the Reactor Coolant System if the boric acid storage tank in Specification 3.1.2.5a. is OPERABLE, or b.
The flow path from the refueling water storage tank via a charging pump to the Reactor Coolant System if the refueling water storage tank in Specification 3.1.2.5b. is OPERABLE.
APPLICABILITY:
MODES 5 and 6.
ACTION:
With nane of the above flow paths OPERABLE or capable of being powered from an r
OPERABLE emergency power source, suspend all operations involving CORE
\\
ALTERATIONS or positive reactivity changes.
SURVEILLANCE REQUIREMENTS r
4.1.2.1 At least one of the above required flow paths shall be demonstrated OPERABLE:
a.
At least once per 7 days by verifying that the Boric Acid Transfer Pump Room temperature and the boric acid storage tank solution temperature' are greater than or equal to 67'F when a flow path from the boric acid tanks is used, and b.
At least once per 31 days by verifying that each valve (manual, power-operated, or automatic) in the flow path that is not locked, sealed, or otherwise secured in position, is in its correct position.
MILLSTONE - UNIT 3 3/4 1-7 i.
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ITEM 4.
l I
REACTIVITY CONTROL SYSTEMS JUL181'"
FLOW PATHS - OPERATING 4
(<
LIMITING CONDITION FOR OPERATION 3.1.2.2 At least two* of the following three boron injection flow paths shall be OPERABLE:
CyskwN The flow path from the boric acid tc..i. via a boric acid transfer a.
pump and a charging pump to the Reactor Coolant System (RCS), and b.
Two flow paths from the refueling water storage tank via charging pumps to the RCS.
APPLICABILITY:
MODES 1, 2, 3, and 4.
~
ACTION:
With only one of the above required boron injection flow paths to the RCS OPERABLE, restore at least two baron injection flow paths to the RCS to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or be in at least HOT STANDBY and borated to a SHUTDOWN MARGIN equivalent to at least 2% Ak/k at 200*F within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />; restore at least two flow paths to OPERABLE status within the next 7 days or be in COLD SHUTDOWN within the next 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
SURVEILLANCE REQUIREMENTS
'h 4.1.2.2 At least two of the above required flow paths shall be demonstrated OPERABLE:
e At least once per 7 days by verifying that the Boric Acid Transfer a.
Pump Room temperature and the boric acid storage tank solution temperature are greater than or equal to 67'F when it is a required water source; b.
At least once per 31 days by verifying that each valve (manual, power-operated, or automatic) in the flow path that is not locked, sealed, or otherwise secured in position, is in its correct position; At least once per 18 months during shutdown by verifying that each c.
automatic valve in the flow path actuates to its correct position on i
a Safety Injection test signal; and d.
At least once per 18 months by verifying that the flow path required by Specification 3.1.2.2a. delivers at least 33 gpm to the RCS.
- *0nly one boron injection flow path is required to be OPERABLE whenever the temperature of one or more of the RCS cold legs is less than or equal to i
350*F.
(
MILLSTONE - UNIT 3 3/4 1-B
ITEM 6.
REACTIVITY CONTROL SYSTEMS BORATED WATER SOURCE - SHUTDOWN THIS PAGE OPEN PENDING RECEIPT OF INFORMATION FROM THE APPLICANT LIMITING CONDITION FOR OPERATION 3.1.2.5 As a minimum, one of the following borated water sources shall be OPERABLE:
a.
A Boric Acid Storage System with:
1)
A minimum contained borated water volume of f o@ gallons, 2)
A boron concentration between 6300 and 7175 ppm, and 3)
A minimum solution temperature of 67'F.
b.
The refueling water storage tank (RWST) with:
O g
1)
A minimum contained borated water volume of
- gallons, 2)
A minimum boron concentration of 2000 ppm, and 3)
A minimum solution temperature cf 35'F.
APPLICABILITY: MODES 5 and 6.
ACTION:
With no borated water source OPERABLE, suspend all operations involving CORE ALTERATIONS or positive reactivity changes.
/
SURVEILLANCE REQUIREMENTS 4.1.2.5 The above required borated water source shall be demonstrated OPERABLE:
' At least once per 7 days by:
a.
1)
Verifying the boron concentration of the water, 2)
Verifying the contained borated water volume, and 3)
Verifying the Boric Acid Transfer Pump Room temperature and I
the boric acid storage tank solution temperature when it is the source of borated water.
b.
At least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> by verifying the RWST temperature when it is the source of borated water and the outside air temperature is less than 35'F.
MILLSTONE - UNIT 3 3/4 1-11 i
ITEM 7.
JUL 181985 REACTIVITY CONTROL SYSTEMS BORATED WATER SOURCES - OPERATING THIS PAGE UPEN PENDING itECEIPT OF 0
INFORMATION FROM THE APPUCANT LIMITING CONDITION FOR OPERATION 3.1.2.6 As a minimum, the following borated water source (s) shall be OPERABLE as required by Specification 3.1.2.2:
a.
A Boric Acid Storage System with:
u >e. b ic 21010 1)
A minimum certM M borated water volume of
- gallons, 2)
A boron concentration between 6300 and 7175 ppm, and
^
3)
A minimum solution temperature of 67'F.
b.
The refueling water storage tank (RWST) with:
1)
A minimum contained borated water volume of 1,166,000 gallons, 2)
A boron concentration between 2000 and 2200 ppm, 3)
A minimum solution temperature of 40*F, and 4)
A maximum solution temperature of 50*F.
(
APPLICABILITY:
MODES 1, 2, 3, and 4.
ACTION:
With the Bpric Acid Storage System inoperable, restore the system to a.
OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or be in at least HOT STANDBY within
'the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and borated to a SHUTDOWN MARGIN equivalent to at least 2% Ak/k at 200*F; restore the Boric Acid Storage System to OPER-ABLE status within the next 7 days or be in COLD SHUTDOWN within the next 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
b.
With the CWST inoperable, restore the tank to OPERABLE status within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
C MILLSTONE - UNIT 3 3/4 1-12
ITEM 15.
TABLE 3.3-4 ESF ACTUATION SYSTEM INSTRUMENTATION TRIP SET POINTS FUNCTIONAL UNIT TOTAL
~
SENSOR TRIP SET ALLOWABLE Z
ALLOWANCE (TA)
ERROR (S)
POINT VALUE Item #8. Loss of Power a) 4.16 KV 2800 VOLTS 2720 VOLTS Emergency Bus for 2 sec.
under voltage N.A.
N.A..
12%
1 (loss of volta'ge) b) 4.16 KV Emergency Bus under voltage N.A.
N.A.
10.1%
3710 VOLTS 3706 VOLTS (Grid Degraded voltage) 8 second delay for alarm 8 second or less if ESF Actuation signal coincide with' Bus Degradation 300 sec delay for trip
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ITEM 23 DMR 3/4.5 EMERGENCY CORE COOLING SYSTEMS JUL 181985 3/4.5.1 ACCUMULATORS THIS PAGE OPEN PENDING RECEIPT OF LIMITING CONDITION FOR OPERATION INFORMATION FROM THE APPLICANT 3.5.1 Each Reactor Coolant System (RCS) accumulator shall be OPERABLE with:
The isolation valve open, a.
&Gs2.
A contained borated water volume of between E4190] an b.
] gallons, A boron concentration of between 1900 and 2100 ppm, and c.
- 63G, MY d.
A nitrogen cover pressure of between-615-and-665 psia.
APPLICABILITY:
MODES 1, 2, and 3*.
ACTION:
With one accumulator inoperable, except as a result of a closed a.
isolation valve, restore the inoperable accumulator to OPERABLE status within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and reduce pressurizer pressure to less than 1000 psig within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
b.
With one accumulator inoperable due to the isolation valve being closed, either immediately open the isolation valve or be in at least HOT STANDBY within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and reduce pressurizer pressure to less than 1000 psig within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
SURVEILLANCE REOUIREMENTS 4.5.1.1 Each accumulator shall be demonstrated OPERABLE:
At least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> by:
a.
1)
Verifying the contained borated water volume and nitrogen cover pressure in the tanks to be within the above limits, and 2)
Verifying that each accumulator isolation valve is open, b.
At least once per 31 days and within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> after each solution volume increase of greater than or equal to 1% of tank volume by verifying the boron concentration of the accumulator solution; and
- Pressurizer pressure above 1000 psig.
MILLSTONE - UNIT 3 3/4 5-1 4
ITE't 25.
EMERGENCY CORE COOLING SYSTEMS THIS PAGE OPEN PENDING RECElPT OF INFORMATION FROM THE APPLICANT SURVEILLANCE REOUIREMENTS (Continued)
ECCS Throttle Valves Valve Numoer Valve Number 3SIH*V8 3SIH*V107 3SIH*V9 3SIH*V108 3SIH*V21 3SIH*V109 3SIH*V23 3SIH*V111 h.
By performing a flow bala'nce test, during shutdown, following com-pletion of modifications to the ECCS subsystems that alter the
~
subsystem flow characteristics and verifying that:
1)
For centrifugal charging pump lines, with a single pump running:
a)
The sum of the injection line flow rates, excluding th highest flow rate, is greater than or equal to g g L 33cg and b)
The total pump flow rate is less than or equal to 'I 6 O gpm.
2)
For Safety Injection pump lines, with a single pump running:
(~
a)
The sum of the injection line flow rates, excluding the highest flow rate, is greater than or equal to 462 gpm, and b)
The total pump flow rate is less than or equal to $ 20 gpm. f _ ne A pg g,a g50 9Pm -F*
%3 Pump, 3)
For RHR pump lines, with a single pump running, the sum of the injection line flow rates is greater than or equal to 3976 gpm.
L MILLSTONE - UNIT 3 3/4 5-6
UMThl 1 CONTAINMENT SYSTEMS ITEM 30.
Jgg ig jggg CONTAINMENT A2R LOCKS
(~
LIMITING CONDITION FOR OPERATION 3.6.1.3 Each containment air lock shall be OPERABLE with:
Both doors closed except when the air lock is being used for normal a.
transit entry and exit through the containment, then at least one air lock door shall be closed, and b.
An overall air lock leakage rate of less than or equal to 0.05 L at P,, 54.1 psia (39.4 psig).
APPLICABILITY:
MODES 1, 2, 3, and 4.,
ACTION:
With one containment air lock door inoperable:
a.
1.
Maintain at least the OPERABLE air lock door closed and either restore the inoperable air lock door to OPERABLE status within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or lock the OPERABLE air lock door closed.
2.
Operation may then continue until performance of the next required overall air lock leakage test provided that the OPERABLE air lock door is verified to be locked closed at least once per 31 days, 3.
Otherwise, be in at least HOT STANOBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />, and 4.
The provisions of Specification 3.0.4 are not applicable.
b.
With the containment air lock inoperable, except as the result of an inoperable air lock door, maintain at least one air lock door closed; restore the inoperable air lock to OPERABLE status within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
e MILLSTONE - UNIT 3 3/4 6-5
&e==
eeesymee e
e e
ITEM 30.
CONTAINMENT SYSTEMS Page 2 of 2
~
Jt}L 181985
$URVEILLANCE REQUIREMENTS
- 4. 6.1. 3 Each containment air lock shall be demonstrated OPERABLE:
Within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> following each closing, except when the air lock is a.
being used for multiple entries, then at least once per 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />, by verifying that the seal leakage is less than 0.01 L,as determined by precision flow measurements when measured for at least 30 seconds with the voltane between the seals at a constant pressure of 54.1 psia (39.4 psig);
b.
By conducting overall air lock leakage tests at not less than P,,
54.1 psia (39.4 psig), and verifying the overall air lock leakage rate is within its limit:
1)
At least once per 6 months,* and 2)
Prior to establishing CONTAINMENT INTEGRITY when maintenance has been performed on the air lock that could affect the air lock sealing capability."*
At least once per 6 months by verifying that only one door in each c.
air lock can be opened at a time.
('
~
Q vu;Fp oc
/mhme na ete.+ eeMie s e.. '
b pn:.wa o%g c den de va(se y
Ac&s,
-Ale c{co-
. (,
is p au.sw ie A sc.
epcd to re/ ps > a (Nmh cycc&~
A o-fs,.
af Ied IE m inude.r "The provisions of Specification 4.0.2 are not applicable.
- This represents an exemption to Appendix J, paragraph III.D.2.(b)(11), of 10 CFR Part 50.
[ Applicant must request this exemption.]
J MILLSTONE - UNIT 3 3/4 6-6
ITEM 37.
JUN 2 61985 PLANT SYSTEMS s
THIS PAGE OPEN PENDING RECEIPT OF 3/4. 7. 6 FLOOD PROTECTION INFORMATION FROM THE APPLICANT LIMITING CONDITION FOR OPERATION
-fl e
- > e M e e e 6-pp CA.< le s-h 1 co.7.6 Flood protection shall be provided for cli ';f ay R.MedSjet-3 mponents, - " -'-"-'"-- when the water level ef + ha L u.lij tt uniii.i.. i.si. ;..L] exceeds /W o #' Mean Sea Level, USGS datum, at T/,,.
(/nM3 APPLICABILITY: At all times.
[
ACTION:
With the water level at#:ol abo've ggp t t,l} Mean Sea Level, USGS datum:
I protection measures: Q lo/d hitiete e.4 6 b.
/
lan pen t]
nd E'#
'9
"'3 of _bcfG s cv v r e ude p
2.
[P td nden ccdut/c.r w.'8Im
/ 5 w ;.,,, g SURVEILLANCE REQUIREMENTS t he (jwd 3 IAlit Tre&c 4.7.6 The water' level at A shall be determined to be within the limits by:
a.
Measurement at ler.st once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> when the water level is below elevation B J f Mean Sea Level, USGS datum, and
- e.~
b.
Measurement at least once per 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> when the water level is equal to or above elevation Mean Sea Level, USGS datum.
8-0%k. r.
m MA
_-,M
/"\\.O A
[
e j Th' s
if cati
' notjrequired ff the faci)t t4 acc/gn na ity/ces adequate passive' fl od oht 1lp ectfon featdres suf icien ood den ifti n Ifeaulato/y Guide.59/ Audust/1973.ommod te ths/Desigf Baris
/
/
WVV UjV j
V l./'
MILLSTONE - UNIT 3 3/4 7-14
[.
1 d
j ITEM 38.
PLANT SYSTEMS
]
3/4.7.12 FIRE RATED ASSEMBLIES p
LIMITING CONDITION FOR OPERATION 3.7.12 All fire rated assemblies (walls, floor / ceilings, cable tray enclosures, and other fire barriers) separating safety-related fire areas or separating portions of redundant i
systems important to safe shutdown within a fire area and all sealing devices in fire rated assembly penetrations (fire doors, fire windows, fire dampers, cable, piping, and ventila-i tion duct penetration seals shall be OPERABLE.
APPLICABILITY: At all times.
ACTION:
a.
With one or more of the above required fire rated assemblies and/or sealing devices inoperable, within I hour either establish a continuous fire watch on at least one side of the affected assembly, or verify the OPERABILITY of fire detectors on at least one side of the inoperable assembly and establish an
- hourly fire watch patrol.
i b.
The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.
i SURVEILLANCE REQUIREMENTS e
4.7.12.1 At least once per 18 months the above required fire rated assemblies and penetration sealing devices shall be verified OPERABLE by performing:
l a.
A visual inspection of the exposed surfaces of each fire rated assembly.
b.
A functional test of at least 10% of fire dampers installed in fire rated floor / wall assemblies. If functional testing acceptance criteria is not met, functional testing of an additional 10% of fire dampers will be performed.
This testing process will continue until a 10% sample of fire dampers has been found to satisfy acceptance criteria. Functional testing of fire dampers will be performed so that a 100% verification of the operability of the fire dampers will be achieved every 15 years.
c.
A visual inspection of at least 10% of the total number of fire rated penetration seals that are normally accessible for visual inspection.
If apparent changes in appearance or abnormal degradations are found, a visua!
l inspection of an additional 10% of the accessible penetration seals shall be j
made. This inspection process shall continue until a 10% sample with no apparent changes in appearance or abnormal degradation is found. Samples shall be selected such that each penetration will be inspected every 15 years.
?
l
ITEM 47.
REFUELING OPERATIONS JUL 18185 i
3/4. 9. 6 REFUELING MACHINE THIS PAGE OPEN PENDING RECEIPT OF i
INFORMATION FROM THE APPLICANT i
LIMITING CONDITION FOR OPERATION J
3.9.6 The refueling machine and auxiliary hoist shall be used for movement of drive rods or fuel assemblies and shall be OPERABLE with:
The refueling machine used for movement of fuel assemblies having:
a.
\\
4 00 o 1)
A minimum capacity ofJP907 pounds, and t
3900 "An overload cutoff limit less than or equal to g pounds.
2) b.
The auxiliary hoist used for latching and unlatching drive rods having:
3000 1)
A minimum capacity of M pounds, and 2)~
A load indicator which shall be used to prevent lifting loads 4
in excess of,4600T pounds.
Dewing mov/000 APPLICABILITY:
ement of drive rods or fuel assemblies within the reactor vessel.
i ACTION:
With the requirements for crane and/or hoist OPERABILITY not satisfied, suspend use of any inoperable manipulator crane and/or auxiliary hoist from operations involving the ' movement of drive rods and fuel assemblies within the reactor vessel.
- 2 SURVEILLANCE REQUIREMENTS 4.9.6.1 Each manipulator crane used for movement of fuel assemblies within the reactor vessel shall be demonstrated OPERABLE within 100 hours0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br /> prior to y#
the start of such operations by performing a load test of at lea ~stJ.2MOTpounds and demonstrating an automatic load cutoff when the crane load exceeds teourpounds.
2%O 4.9.6.2 Each auxiliary hoist and associated load indicator used for movement 2
of drive rods within the reactor vessel shall be demonstrated OPERABLE within 100 hours0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br /> prior to the start of such operations by performing a load test of at least,J5407 pounds.
l
.3OOD i
i 4
i MILLSTONE - UNIT 3 3/4 9-6
(FULLY WITHDRAWN)
(0.28,228) 228 (O.78,228)
/
/
200
- BANK B (0.Q164)
(1.0,164) t-150 O
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g SANK C E
s
/
100
/
g g
h
- BANK D SO (0.0,50)
(0.28,0)
O O
O.2 0.4 0.6 0.8 1.0 (FULLY INSERTED)
FRACTION OF RATED THERMAL POWER FicuRE 3.1-1 ROD BANK [NSERTION LIMITS VERSUs THERMAL POWER FOUR LOOP OPERATION
. ~
i (FULLY WITHDRAWN)
(0.07228)
(0.57228) 228 BANKB (O,212) 200
/
z O
C 150 di
/- BANK C e
a (0.65,132)
N m
s<m 100 C
(0,0.98) m
-BANK D 50 gL (0020)
O O.2
- 0. 4 Q6 0.8 1.0 (FULLY INSERTED)
FRACTION OF RATED THERMAL POWER FIGURE 3.1-2 ROD BANK [NSERTION Limits VERSus THERMAL POWER l
THREE LOOP OPERATION
[
i l
A p
P-6 8 $
m
' 2 O
a:
$ N o
w 10 0 I
l l
l UNACCEP LE
(-11. 90)
(11,90)
UNACCEPTABLE pp OPERATION 80
/
ACCEPTABLE OPERATION 60
/
(-31,50)
(31,5 0) 40 20 O
-50
-40
-30
-20
-10 0
10 20 30 40 50 FLUX DIFFERENCE (OT)*/.
FicuRE 3.2-1a AXIAL Ftux DIFFERENCE LIMITS As A FUNCTION OF RATED THERMAL POWER FCUR LOOP OPERATION
7.
5 o
3:
d 2 0 4
' s 0
a:W t-
? E 10 0 80 UNACCEPTABLE
(-8,65)
(8,65 )
UNACCEPTABLE OPERATION OPERATION eo ACCEPTABLE OPERATION ao I
(
/
\\
( 24 5,32)
(245,32) 20 0
-50 40'
-30 20
-10 0
10 20 30 40 50 FLUX DIFFERENCE (6I)*/.
FIGURE 3.2 -1b AXIAL Flux DIFFERENCE LIMITS As A FUNCTION OF RATEo THERMAL POWER THREE LOOP OPERATION w
1.50 1.25 - -
C
{o 1.00 S
3 0.75 -
7 7^'
2.320 2
CORE HEIGHT K(Z) 8z O.000 1.000 a
O.50 -
6 000 1 000 ti 10.600 0.94 0 x
12.000 0.647 0.25 - -
O.00 1
I I
I I
s s
O 2
4 6
8 10 12 CORE HEIGHT (FT)
FIGURE 3.2-2 K(Z) - NORMAllZED FO(Z) As A FUNCTION OF CORE HEIGHT FOUR LOOP OPERATION l
l t
1.50 1.25 -
A
[a 1.00 Pa 3
0.75 -
70 *-
2.600 g
CORE HEIGHT K(Z)
O O.000 1.000 A
O.50 -
60*
10%
ti 10.800 0.940 12.000 0.577 0.25 - -
i I
I i
O.00 i
i O
2 4
6 8
10 12 CORE HEIGHT (FT)
FIGURE
MATERIAL PROPERTY 8 ASIS CONTROLLING MATERIAL PLATE METAL COPPER CONTENT CONSERVATIVELY ASSUMED TO BE O.10 WT*/.
PHOSPHORUS CONTENT O.010 WT*/.
RT INITIAL 60*F NOT RT AFTER 10 Em 1/M,122T NDT 3/4 T,101 *F CURVE APPLICABLE FOR HEATUP RATES UP TO 60*F/HR FOR THE SERVICE PERICO UP TO 10 EFPY AND CONTAINS MARGINS OF 10*F AND 60 PSIG FOR POSSIBLE INSTRUMENT ERRORS 3000.0 LEAK TEST LIMIT
@ 2000.0 Gib d
E 8
E9 1000.0 HEATUP "
-- CRITICALITY LIMIT CURVE BASED ON INSERVICE HYDROSTATIC TEST TEMPERATURE (266 *F)
FOR THE SERVICE PERICO UP TO 10 EFPY 0.0 0.0 1000 200.0 300O 400.0 500.0 INDICATES TEMPERATURE (DEG.F)
FIGURE 3.4-2 MILLSTONE UNIT 3 REACTOR COOLANT $YSTEM HEATUP LIMITATIONS APPLICABLE TO 10 EFPY
MATERIAL PROPERTV 8 ASIS CONTROLLING MATERIAL PLATE METAL COPPER CONTENT CONSERVATIVELY ASSUMED TO BE O.10 WT%
PHOSPHORUS CONTENT O.010WT*/.
RTNOT INITIAL 60*F RT AFTER 10 EFPY 1/4 T,122* F NDT 3/4 T 101*F CURVE APPLICABLE FOR COOLDOWN RATES UP TO PERIOD UP TO 10 EFPY AND CONTAINS MARGINS OF 10*
POSSIBLE INSTRUMENT ERRORS 3000 O
@2000.0 E
W S
d lE O
3 E9 9
4 1000.0 f
COOLDOWN RATES.
(*F/HR)
O 20 -
s.
60 -
10 0 -
0.C O.0 10 0.0 200.0 3000 4000 5000 INDICATED TEMPERATURE (CEG.F)
FIGURE 3.4-3 MILLSTONE UNIT 3 REACTOR COOLANT SYSTEM COOLDOWN APPLICABLE UP TO 10 EFPY
.i s a r
i i
11.0 l
l 1
10.8
.9 m
f 10.6 UN ACCEPTABLE' OPERATION hJ t
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R UJj 9.8 O"
- 9. 6 d
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E ACCEPTABLE OPERATION
<2 92 -
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NORTHEAST F
NUCLEAR ENERGY In COM PANY O
Z m
c PRESIDENT
- Z__
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O w
SE NIOR VICE PRESIDENT r--------
-i l
NE&O I
l I
I NUSCO I
l VICE PRESIDENT l
l NUCLEAR OPE RATIONS g
NUCLEAR I
REVIEW STATION NORTHEAST UTILITIES L-BOARDS SUPERINTENDENT SERVIC E COMPANY * *
(NUSCO)
% OVERALL CORPORATE RESPONSIBILITY FOR FIRE PROTECTIOtt
$ $ PROVIDES OPERATING AND Et1GINEERit1G SUPPORT BY CONTRACTUAL.ARRANGEME N T FIGURE 6.2.1 OFFSITE ORGANIZATIO;; FOR FACILITY MANAGEMEt1T AND TECHNICAL SUPPORT
r 8
X.
g-STATION
{
SUPE RI N TENDE t1T
-4 O
Z ADMINIS T RATIVE STAFF C
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-i UfJIT 3 SUPERit1TENDEt1T ORC UNIT I UtilT 2 STATION SUPERit4 TE NDEN T SUPERINTENDENT SUP Rt E JDEtJT SAME ORGANIZATION AS UNIT 3 I&C OPE RA T IONS ENGit4EERit4G MAINTENANCE STAFF SUPERVISOR SUPERVISOR SUPE RVISOR SUPERVISOR LSO Q A SUPERVISOR STAF F STAF F SECURITY SUPERVISOR SUP R SORLSO HEALTH PHYSICS SUPERVISOR CHEMtSTRY SUPERVISOR OTHER SITE SUPPORT SERVICES SUPERVISING CONTROL E tJ Gif1E E R S REACTOR OPERATORS NGINEER LO CONTROL OPERATORS LO LO - LICEt1 SED OPERATOR LSO-LICENSE D SEttlOR OPERATOR PLANT Mt -OVERALL SITE RESPONSIBILITY FOR EQUIPMENT FIRE PRO 1EC TiOt1 OPERATORS FACILITY ORGANIZATION-MILLSTONE NUCLEAR POWER STATION-UraiT 3 FIGURE 6.2.2