ML20116K634
| ML20116K634 | |
| Person / Time | |
|---|---|
| Site: | Brunswick  |
| Issue date: | 04/26/1985 |
| From: | CAROLINA POWER & LIGHT CO. |
| To: | |
| Shared Package | |
| ML20116K608 | List: |
| References | |
| NLS-85-129, NUDOCS 8505030341 | |
| Download: ML20116K634 (17) | |
Text
a i
ENCLOSURE 1 TO SERIAL NLS-85-129 PROPOSED TECHNICAL SPECIFICATION PAGES BRUNSWICK-1 v.
i l
l l
i 8505030341 85h325 DR ADOCK 05 p
SUMMARY
LIST OF REVISIONS PAGE NUMBER DESCRIPTION OF CHANGE 3/42-2 Graph of MAPLHGR vs. Average Planar Exposure for Fuel Type 2 (8 x 8) has been deleted. Proposed page is repaginated and Figure Ne revised.
3/42-3 Repaginated.
Figure Number revised.
3/42-4 MAPLHGR values corresponding to Planar Average Exposures of 35000 and 40000 mwd /t added.
Repaginated.
Figure No. revised.
3/42-5 MAPLHGR values corresponding to Planar Average Exposures of 35000 and 40000 mwd /t added.
Repaginated.
Figure No. revised.
3/42-6 Repaginated.
Figure No. revised.
3/42-7 MAPLHGR value corresponding to Planar Average Exposure of 45000 mwd /t added.
Repaginated.
Figure No. revised.
3/42-8 New graph of MAPLHGR vs. Average Planar Exposure for the new BP8 x 3R fuel added.
3/42-9 Reference to 8 x 8 fuel deleted and BP8 x 8R fuel added.
3/42-10 MCPRs revised.
Reference to 8 x 8 fuel deleted and BP8 x 3R fuel added.
3/4 2-14 MCPRs revised.
Reference to 8 x 8 fuel deleted and BP8 x 8R fuel added.
PAGE NUMBER DESCRIPTION OF CHANGE 3/4 2-16 Reference to 8 x 8 fuel deleted and BP8 x 8R fuel added.
3/4 3-42 Reference to 8 x 8 fuel deleted and BP8 x 8R fuel added.
B3/42-3 Reference to 8 x 8 fuel deleted and BP8 x 8R fuel added.
5-1 Reference to 8 x 8 fuel deleted and BP8 x 8R fuel added.
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MAXIMUM AVERAGE PLANAR LINEAR HEAT j
GENERATION RATE (MAPLHGR)
M VERSUS AVERAGE PLANAR EXPOSURE n
i 13.0 E
G 1
11.1 11.1 12.1 1
i i
li'9 2.0 11.6 11.6 u
10.7 1
h er.. ;f t ne.
lu 10.0 Permissib]e Region 3
of Operation
- s. 6-
- 9. 0 eo.
2 E
y
- 8. 0 0
5000 10000 15000 20000 25000 30000 35000 40000 AVERAGE PLANAR EXPOSURE (mwd /t)
Fuel Type 80RB265L (8X8R)
FIGURE 3.2.1-1
E MAXIMUM AVERAGE PLANAR LINEAR HEAT l
GENERATION RATE (MAPLHGR)
M VERSUS AVERAGE PLANAR EXPOSURE 7:
)
i 13.0 i
E i
n 12.1
)
11.0
,3 12 0 it-ii.8
/
\\
11.1 11.0 -- 11.2 Y
\\
gKW/ft 3
d 10 4 l
10.0 i
)
l ermissible Region
- 9. 8 3
j of Operation 1
- 9. 0
! r a
!?
- 8. 0 O
5000 10000 15000 20000 25000 30000 35000 40000 AVERAGE PLANAR EXPOSURE (mwd /t)
Fuel Type 80RB283 (8X8R)
' FIGURE 3.2.1-2 l
E MAXIMUM AVERAGE PLANAR LINEAR HEAT l
GENERATION RATE (MAPLHCR)
M VERSUS AVERAGE PLANAR EXPOSURE n
- i 13.0 4
3 12.2 12.0 ii,
' t. 8
/
\\
ii.o 11.0 y
g
,3,o i"
10.9 A KW/ft 10.0 8
3ermissible Region of Operation N. 2
)
- 9. 0
'i i
a i
if
- 8. 0 O
5000 10000 15000 20000 25000 30000 35000 40000 AVERAGE PLANAR EXPOSURE (mwd /t)
Fuel Type P80RB285 (P8X8R)
FIGURE 3.2.1-3
l MAXIMUM AVERAGE PLANAR LINEAR HEAT 12 GENERATION RATE (MAPLHGR) y VERSUS AVERAGE PLANAR EXPOSURE i
13.0 E
i p
]
11.I 12.I 3
U N
12.0 W
M 1
N*
l
!!. 6
\\
1 R
11.0 i
10.7 I
'f
" KW/ft 10.3\\
10.0 3ermissible Region
)
of Operation
- 9. 6
- 9. O li E.
8 E
E
- 8. 0 0
5000 10000 15000 20000 25000 30000 35000 40000 AVERAGE PLANAR EXPOSURE (mwd /t)
Fuel Type P80R8265H (P8X8R)
FIGURE 3.2.1-4
l MAXIMUM AVERAGE PLANAR LINEAR HEAT y
GENERATION RATE (MAPLHCR) y VERSUS AVERAGE PLANAR EXPOSURE g
13.0 4
i
~
l
- 11. 0 12.0 12.0 8
1.
- 11. 1 11.0
- l.2 g
'i' KW/f t 10 4 10.0 Jermissible Region of Operation
)
- 9. 0 9.1 Ei i
k 8
E i
z
- 8. 0 j
0 5000 10000 15000 20000 25000 30000 35000 40000 AVERAGE PLANAR EXPOSURE '(HWd/t)
Fuel Type P80R8284H (P8X8R)
FIGURE 3.2.1-5
E MAXIMUM AVERAGE PLANAR LINEAR HEAF GENERATION RATE (MAPLHGR)
R VERSUS AVERAGE PLANAR EXPOSlJRE I
13.0 E
4 ru 3 12.2 a
~
12.0
!!.5 11.5 11.0 11.0 11.0 g N
10.9 4 KW/ft 10.3 10.0 9.7 i
3ermissible Region t
of Operation I
- 9. 0 I
k 0
+
a l
8 a"
l B. O m
l.
0 5000 10000 15000 20000 25000 30000 35000 40000 45000 i
AVERAGE PLANAR EXPOSURE (mwd /t)
Fuel Type P80RB299 (P8X8R)
FIGURE 3.2.1-6
l MAXIMUM AVERAGE PLANAR LINEAR HEAT g
GENERATION RATE (MAPLHGR) y VERSUS AVERAGE PLANAR EXPOSURE 13.0 E
G iL 3
~
12.2 12.0 11 5 ii.s 11.0 w
2 T
'i' KW/ft 10,9
=
- o.3 10.0
\\,
- 9. 7
- 'ermissible Region 1
of Operation
- 9. 0 l
- 9. 0
.8
?
z -
- 8. 0 0
5000 10000 15000 20000 25000 30000 35000 40000 45000 AVERAGE PLANAR EXPOSURE (mwd /t)
Fuel Type BP80RB299 (BP8X8R)
FIGURE 3.2.1-7
(BSEP-1-60)
POWER DISTRIBUTION LIMITS 3/4.2.2 APRM SETPOINTS LIMITING CONDITION FOR OPERATION 3.2.2 The flow-biased APRM scram trip setpoint (S) and rod block trip set point (SRB) shall be established according to the following relationships
'S $ (0.66W + 54%) T SRB $ (0.66W + 42%) T where:
S and S are in percent of RATED THERMAL POWER.
RB W = Loop recirculation flow in percent of rated flow, T = Lowest value of the ratio of design TPF divided by the MTPF obtained for any class of fuel in the core (T $ 1.0), and Design TPF for:
8 x 8R fuel = 2.39 P8 x 8R fuel = 2.39 BP8 x 8R fuel = 2.39 APPLICABILITY: OPERATIONAL CONDITION 1, when THERMAL POWER is greater than or equal to 25% of RATED THERMAL POWER.
ACTION:
With S or S exceeding the allowable value, initiate corrective action within RB 15 minutes and continue corrective action so that S and S are within the requiredlimitswithin4hoursorreduceTHERMALPOWERtofessthan25%of R
RATED THERMAL POWER within the next 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.
SURVEILLANCE REQUIREMENTS 4.2.2 The MTPF for each class of fuel shall be determined, the value of T calculated, and the flow biased APRM trip setpoint adjusted, as required:
a.
At least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, b.
Within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after completion of a THERMAL POWER increase of at least 15% of RATED THERMAL POWER, and Initially and at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> when the reactor is c.
operating with a LIMITING CONTROL ROD PATTERN for MTPF.
BRUNSWICK UNIT - 1 3/4 2-9 Amendment No.
1 (BSEP-1-60)
POWER DISTRIBUTION LIMITS 3/4.2.3 MINIMUM CRITICAL POWER RATIO i
- LIMITING CONDITION FOR OPERATION 3.2.3.1 The MINIMUM CRITICAL POWER RATIO (MCPR), as a function of core flow, shall be equal to or greater than the MCPR limit times the Kg shown in 4
Figure 3.2.3-1 with the following MCPR limit adjustments:
Beginning-of-cycle (BOC) to end-of-cycle (EOC) minus 2000 MWD /t with
.a..
4 ODYN OPTION A analyses in effect, the MCPR limits are listed below:
i 1.
MCPR for 8 x 8R fuel = 1.25 2.
'MCPR for P8 x 8R fuel = 1.27 3.
MCPR for BP8 x 8R fuel = 1.27 b.
EOC minus 2000 MWD /t to EOC with ODYN OPTION A analyses in effect, the MCPR limits are listed below:
1.
MCPR for 8 x 8R fuel = 1.36 2.
MCPR for P8 x 8R fuel = 1.39 3.
MCPR for BP8 x 8R fuel = 1.39 BOC to EOC minus 2000 MWD /t with ODYN OPTION B analyses in effect, c.
the MCPR limits are listed below:
1.
MCPR for 8 x 8R fuel = 1.24 2.
MCPR for P8 x 8R fuel = 1.24 3.
MCPR for BP8 x 8R fuel = 1.24 d.
EOC minus 2000 MWD /t to EOC with ODYN OPTION B analyses in effect, the MCPR limits are listed below:
1.
MCPR for 8 x 8R fuel = 1.25 2.
MCPR for P8 x 8R fuel = 1.27 3.-
MCPR for BP8 x 8R fuel = 1.27 APPLICABILITY: OPERATIONAL CONDITION 1 when THERMAL POWER is greater than or equal to 25% RATED THERMAL POWER IN
-ACT O :
With MCPR, as a function of core flow, less than the applicable limit
+
determined from Figure 3.2.3-1 initiate corrective action within 15 minutes and restore MCPR to within the applicable limit within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> or reduce
. THERMAL POWER to less than 25% of RATED THERMAL POWER within the next 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.
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1 BRUNSWICK UNIT - 1 3/4 2.-10 Amendment No.
... _ _. _ _. _ _ _. _ -, _. - - -, _ ~. _ _
TABLE 3.2.3.2-1 (BSEP-1-60) e TRANSIENT OPERATING LIMIT MCPR VALUES 5
r, E
TRANSIENT FUEL TYPE 4
8x8R P8x8R BP8x8R i
w NONPRESSURIZATION TRANSIENTS BOC + EOC 1.24 1.24 1.24 TURBINE TRIP / LOAD REJECT WITHOUT BYPASS MCPR MCPR MCPR MCPR MCPR MCPR A
B A
B A
B 2
BOC + EOC - 2000 1.25 1.08 1.27 1.08 1.27 1.08 EOC - 2000 + EOC 1.36 1.24 1.39 1.27 1.39 1.27 FEEDWATER CONTROL FAILURE MCPR MCPR MCPR MCPR HCPR HCPR A
B A
B A
B BOC + EOC - 2000 1.21 1.15 1.21 1.15 1.21 1.15 EOC - 2000 + EOC 1.32 1.25 1.34 1.27 1.34 1.27 e
8n
(BSEP-1-60)
POWER DISTRIBUTION LIMITS 3/4.2.4 LINEAR HEAT CENERATION RATE LIMITING CONDITION FOR OPERATION 3.2.4 The LINEAR HEAT CENERATION RATE (LHCR) shall not exceed 13.4 kw/ft for 8 X 8R, P8 X 8R, and BP8 x 8R fuel assemblies.
APPLICABILITY: OPERATIONAL CONDITION 1, when THERMAL POWER is greater than or equal to 25% of RATED THERMAL POWER.
ACTION:
With the LHGR of any fuel rod exceeding the above limit, initiate corrective action within 15 minutes and continue corrective action so that the LHGR is within the limit within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />, or reduce THERMAL POWER to less than 25% of RATED THERMAL POWER within the next 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.
SURVEILLANCE REQUIREMENTS 4.2.4 LHCR shall be determined to be equal to or less than the limit:
a.
At least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, b.
Within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after completion of a THERMAL POWER increase of at least 15% of RATED THERMAL POWER, and c.
Initially and at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> when the reactor is operating on a LIMITING CONTROL ROD PATTERN for LHCR.
s BRUNSWICK UNIT - 1 3/4 2-16 Amendment No.
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(BSEP-1-60}
POWER DISTRIBUTION LIMITS BASES 3/4.2.2 APRM SETPOINTS The fuel cladding integrity Safety Limits of Specification 2.1 were based on a TOTAL PEAKING FACTOR of 2.39 for 8 x 8R, P8 x 8R, and BP8 x 8R fuel. The scram setting and rod block functions of the APRM instruments must be adjusted to ensure that the MCPR does not become less than 1.0 in the degraded situation. The scram settings and rod block settings are adjusted in accordance with the formula in this specification when the combination of THERMAL POWER and peak flux indicates a TOTAL PEAKING FACTOR greater than 2.39 for 8 x 8R, P8 x 8R, and BP8 x 8R fuel. This adjustment may be accomplished by increasing the APRM gain and thus reducing the slope and intercept point of the flow referenced APRM high flux scram curve by the reciprocal of the APRM gain change. The method used to determine the design TPF shall be consistent with the method used to determine the MTPF.
3/4.2.3 MINIMUM CRITICAL POWER RATIO The required operating limit MCPR's at steady state operating conditions as specified in Specification 3.2.3 are derived from the established fuel claddingintegritySafggJ.LimitMCPRof1.07,andananalysisofabnormal operational transients For any abnormal operating transient analysis evaluation with the initial condition of the reactor being at the steady state operating limit, it is required that the resulting MCPR does not decrease below the Safety Limit MCPR at any time during the transient, assuming instrument trip setting as given in Specification 2.2.1.
To assure that the fuel cladding integrity Safety Limit is not exceeded during any anticipated abnormal operational transient, the most limiting transients have been analyzed to determine which result in the largest reduction in CRITICAL POWER RATIO (CPR). The type of transients evaluated were loss of flow, increase in pressure and power, positive reactivity insertion, and coolant temperature decrease.
The required minimum operating limit MCPR of Specification 3.2.3 is obtained when the transient which yields the largest ACPR is added to the Safety Limit MCPR of 1.07.
Prior to analysis of abnormal operational transients, an initial fuel bundle MCPR was determined. This parameter is based on the modelasdescribedinSection4.4ofNEDO-20360ggystateflowdistribution-bundle flow calculated by a CE multichannel ste and on core parameters shown in Reference 3, response to Items 2 and 9.
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BRUNSWICK UNIT - 1 B 3/4 2-3 Amendment No.
(BSEP-1-60) 5.0 DESIGN FEATURES 5.1 SITE EXCLUSION AREA 5.1.1 The exclusion area shall be as shown in Figure 5.1.1-1.
LOW POPULATION ZONE 5.1.2 The low population zone shall be as shown in Figure 5.1.2-1, based on the information given in Section 2.2 of the FSAR.
5.2 CONTAINMENT CONFIGURATION 5.2.1 The PRIMARY CONTAINMENT is a steel-lined reinforced concrete structure composed of a series of vertical right cylinders and truncated cones which form a drywell. This drywell is attached to a suppression chamber through a series of vents. The suppression chamber is a concrete steel-lined pressure vessel in the shape of a torus. The primary containment has a minimum free air volume of (288,000) cubic feet.
DESIGN TEMPERATURE AND PRESSURE 5.2.2 The primary containment is designed and shall be maintained for:
a.
Maximum internal pressure 62 psig.
b.
Maximum internal temperature:
drywell 300 F.
suppression chamber 200 F.
c.
Maximum exte nal pressure 2 psig.
-5.3 REACTOR CORE FUEL ASSEMBLIES 5.3.1 The reactor core shall contain 560 fuel assemblies of 8 x 8R, P8 x 8R, and BP8 x 8R fuel types. Each fuel assembly contains 62 fuel rods. All fuel rods shall be cladded with Zircaloy 2.
Each fuel rod shall have a nominal active fuel length of 150 inches.
BRUNSWICK UNIT - 1 5-1 Amendment No.