ML20116H215
| ML20116H215 | |
| Person / Time | |
|---|---|
| Site: | Duane Arnold  |
| Issue date: | 04/18/1985 |
| From: | Vassallo D Office of Nuclear Reactor Regulation |
| To: | Corn Belt Power Cooperative, Central Iowa Power Cooperative, Iowa Electric Light & Power Co |
| Shared Package | |
| ML20116H217 | List: |
| References | |
| DPR-49-A-118 NUDOCS 8505020128 | |
| Download: ML20116H215 (14) | |
Text
'
c t,
UNITED STATES h
NUCLEAR REGULATORY COMMISSION e
WASHINGTON, D. C. 20555 i
IOWA ELECTRIC LIGHT AND POWER COMPANY CENTRAL IOWA POWER COOPERATIVE CORN BELT POWER COOPERATIVE DOCKET NO. 50-331 DUANE ARN0LD ENERGY CENTER AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.ll8 License No. DPR-49 1.
'The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment by Iowa Electric Light & Power Company, et al, dated December 7, 1984, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Comission's rules and regulations set forth in 10 CFR Chapter I; 8.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Comission; C.
There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Comission's regulations; D.
The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Comission's regulations and all applicable requirements have been satisfied.
2.
Accordingly, the license is amended by changes to the Technical Specifi-cations as indicated in the attachment to this license amendment and paragraph 2.C.(2) of Facility Operating License No. DPR-49 is hereby amended to read as follows:
8505020 g $\\0N 31 PDR AD PDR P
2-(2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.118, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
3.
The license amendment is effective as of the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION Domenic B. Vassallo, Chief Operating Reactors Branch #2 Division of Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance: April 18, 1985 1
- ~, - - -
,r-,
.a.
,---.n n--
n.-
ATTACHMENT TO LICENSE AMENDMENT NO. 118 FACILITY OPERATING LICENSE NO. OPR-49 DOCKET NO. 50-331 Revise the Appendix A Technical Specifications by removing the current pages and inserting the revised pages listed below. The revised areas are identified by vertical lines.
LIST OF AFFECTED PAGES vii 3.12-1 3.12-2 3.12-3 3.12-6 3.12-7 3.12-8 3.12-13 3.12-14*
3.12-16*
3.12-19
- New page.
8
+
--e--T----
~
- '~ ' '
DAEC-1 TECHNICAL SPECIFICATIONS LIST OF FIGURES Figure Number Title 1.1-1 Power / Flow Map 1.1-2 Deleted 2.1-1 APRM Flow Biased Scram and Rod Blocks 2.1-2 Deleted 4.1-1 Instrument Test Interval Determination Curves 4.2-2 Probability of System Unavailability Vs. Test Interval 3.4-1 Sodium Pentaborate Solution Volume Concentration Requirements 3.4-2 Saturation Temperature of Sodium Pentaborate Solution 3.6-1 DAEC Operating Limits 4.8.C-1 DAEC Emergency Service Water Flow Requirement 3.12-1 Kf as a Function of Core Flow 3.12-2 Minimum Critical Power Ratio (MCPR) versus T (Fuel Types:
BP/P8X8R and ELTA) 3.12-3 Minimum Critical Power Ratio (MCPR) versus t (Fuel Type:
LTA 311) 3.12-4 Deleted 3.12-5 Limiting Average Planar Linear Heat Generation Rate (Fuel Type:
LTA 311) 3.12-6 Limiting Average Planar Linear Heat Generation Rate (Fuel Type BP/P8DRB301L) 3.12-7 Limiting Average Planar Linear Heat Generation Rate (Fuel Type P8DPB289) 3.12-8 Limiting Average Planar Linear Heat Generation Rate (Fuel Types:
BP/P80RB299 and ELTA) l 3.12-9 Limiting Average Planar Linear Heat Generation Rate (Fuel Type P80RB284H) 6.2-1 DAEC Nuclear Plant Staffing l
Amendment No. 118 Vii l
l-
i DAEC-1 LIMITING CONDITION FOR OPERATION SURVEILLANCE REQUIREMENT -3.12 CORE THERMAL LIMITS 4.12 CORE THERMAL LIMITS Applicability Applicability The Limited Conditions for The Surveillance Requirements l,
Operation associated with the apply to the parameters which fuel rods apply to those monitor the fuel rod operating parameters which monitor the conditions, fuel rod operating conditions.
Objective Objective The Objective 'of the Limiting The Objective of the Conditions for Operation is to Surveillance Requirements is to-7 assure the performance of the specify the type and frequency fuel rods.
of surveillance to be applied l'
to the fuel rods.
Specifications Specifications A.
Maximum Average Planar Linear A.
Maximum Average Planar Linear
_ Heat Generation Rate (MAPLHGR)
Heat Generation Rate (MAPLHGR)
During reactor power The MAPLHGR for each type of operation, the actual MAPLHGR fuel as a function of average t_
for each type of fuel as a p1anar exposure shall be 2
function'of average planar determined daily during reactor exposure shall not exceed the operation at > 25% rated limiting value shown in Figs, thermal power ~and following any l
3.12-5, -6, -7, -8 and -9.
If change in peer level or at any time during reactor distribution that would cause power operation it is operation with a limiting determined by normal control rod pattern as surveillance that the limiting described in the bases for value,for MAPLHGR (LAPLHGR) is Specification 3.3.2.
During being exceeded, action shall operation with a limiting i
then be initiated within 15 control rod pattern, the minutes to restore operation MAPLHGR shall be determined at to within the prescribed least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, limits.
If the MAPLHGR (LAPLHGR) is not returned to within the prescribed limits within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />, reduce reactor power to < 25% of Rated Thermal Swer within the next 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.
Surveillance and corresponding action shall continue'until the prescribed limits are again being met.
6 AmendmentNo.)MI,JMI,118 3.12-1 j $-
u._ _ _,, _ __ __ _._ _.._ _ _ _
DAEC-1 LIMITING CONDITIONS FOR OPERATION SURVEILLANCE RE0VIREMENT B.
Linear Heat Generation Rate B.
Linear Feat Generation Rate (LHGR)
(LHGR) 1.
During reactor power The LHGR as a function of core operation the linear heat height shall be checked daily generation rate (LHGR) of any during reactor operation at > 25%
rod in any P8X8R, BP8X8R or thermal power and following any ELTA fuel assembly shall not change in power level or exceed 13.4 KW/ft, while the distribution that would cause LHGR of any rod in an LTA 311 operation with a limiting control fuel assembly shall not rod pattern as described in the exceed 14.4 KW/ft.
bases for Specification 3.3.2.
During operation with a limiting If at any time during reactor control rod pattern the LHGR power operation it is shall be determined at least once determined by normal per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
4 surveillance that the limiting value for LHGR is being exceeded, action shall then be initiated within 15 minutes to restore operation to within the prescribed limits.
If the LHGR is not returned to within the prescribed limits within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />, reduce reactor power to < 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 and corresponding action shall continue until the prescribed limits are again being met.
i
(
Amendment No. AdI,118 3.12-2
DAEC-1
~
LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENT C.
Minimum Critical Power Ratio C.
Minimum Critical Power Ratio (MCPR)
(MCPR)
During reactor power MCPR shall be determined daily operations, MCPR shall be >
during reactor power operation values as indicated in at > 25% rated thermal power and
~
Figures 3.12-2 and -3 at fo1 Towing any change in power rated power and flow.
If at level or distribution that would any time during reactor power cause operation with a limiting operation it is determined by control rod pattern as described normal surveillance that the in the bases for Specification limiting value for MCPR is 3.3.2.
During operation with a being exceeded, action shall limiting control rod pattern, then be initiated within 15 the MCPR shall be determined at minutes to restore operation least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
to within the prescribed limits.
If the operating MCPR is not returned to within the prescribed limits within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />, reduce reactor power to < 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 and corresponding action shall continue until the prescribed limits are again being met.
For core flows other than rated the MCPR shall be >
values as indicated in Figures 3.12-2 and -3 times K, where Kf is as shown fin Figure 3.12-1.
Amendment No.,&6',118 3.12-3 l
DAEC-1 limits were derived by using the GE 678 scram times, given in Sectior 3.3.C, which are based upon extensive operating plant data, as well as GE test data. The ODYN Option B scram insertion times were statistically derived from the 678 data to ensure that the resulting Operating Limit from the transient analysis would, with 95% probability at the 95% confidence level, result in the Safety Limit MCPR not being exceeded. The scram time parameter (T), as calculated by the following formula, is a measure of the conformance of the actual plant control rod drive performance to that used in the ODYN Option-8 licensing basis:
T ave - Tb T =
T
-T g
h where: Tave = average scram insertion time to Notch 38, as measured by surveillance testing h
scram insertion time to Notch 38 used in T
=
the ODYN Option-8 Licensing Basis.
a 678 scram insertion time to Notch 38 T
=
)
1 As the average scram time measured by surveillance testing (Tave), exceeds the ODYN Option B scram time (Tb),the Operating Limit MCPRs must be adjusted using Figures 3.12-2 and -3.
i Amendment No. f f,J W, 118 3.12-6
DAEC-1 2.
MCPR Limits for Core Flows Other than Rated Flow The purpose of the Kf factor is to define operating limits at other than rated flow conditions. At less than 100% flow the required MCPR is the product of the operating limit MCPR and the Kf factor. Specifically, the Kf factor provides the required thermal margin to protect against a flow increase transient. The most limiting transient initiated from less than rated flow conditions is the recirculation pep speed up caused by a motor-generator speed control failure.
For operation in the automatic flow control mode, the Kf factors assure that the operating limit MCPR of values as indicated in Figures 3.12-2 and -3 will l
not be violated should the most limiting transient occur at less than rated flow.
In the manual flow control mode, the Kf factors assure that the Safety Limit MCPR will not be violated for the same postulated transient event.
The Kf factor curves shown in Figure 3.12-1 were developed generically and are applicable to all BWR/2, BWR/3 and BWR/4 reactors. The Kf factors were derived using the flow control line corresponding to rated thermal power at rated core flow.
For the manual flow control mode, the Kf factors nre calculated such that at the maximum flow state (as limited by the pep scoop tube set point) and the corresponding core power (along the rated flow control line), the limiting bundle's relative power was adjusted until the MCPR was slightly above the Safety Limit. Using this relative bundle power, the MCPR's were calculated at different points along the rated flow control line corresponding to different core flows. The ratio of the MCPR calculated at a given point of core flow, divided by the operating limit MCPR determines the value of K.
f Amendment No.g,118 3.12-7
F DAEC-1.
For operation in the automatic flow control mode, the same procedure was employed
'excapt the initial power distribution was established such that the MCPR was equal to the operating limit MCPR at rated power and flow.
The K factors shown in Figure 3.12-1 are conservative for Duane Arnold f
operation because the operating limit MCPR of values as indicated in Figures 3.12-2 and -3 is greater than the original 1.20 operating limit MCPR used for the generic derivation of K.
f Amendment No % 118 3.12-8
i DAEC-1 Option 8
Option A
1.30 -
- 1.30
~
1.26 1.25 -
- 1.25 t=0.75 1.20 -
- 1.20
~
1.15 -
- 1.15 1.10 -
_ 1,10 I
O!2 I
0}4 I
I I
0.0 06 08 10 (based on tested measured scram time as defined in Reference 11)
DUANE ARN0LD ENERGY CENTER IOWA ELECTRIC LIGHT AND POWER COMPANY TECHNICAL SPECIFICATIONS MINIMUM CRITICAL POWER RATIO (MCPR)
VERSUS T FUEL TYPES: BP/P8X8R and ELTA FIGURE 3.12-2 d
Amendment No. J, % 118 3.12-13
DAEC-1 Option B
Option A
1.30 -
- 1.30
- 1.28 1.25 -
- 1.25 1.21 -
1.20 -
- 1.20 1.15 -
- 1.15 1.10 -
_ 1.10 0.0 O!2 O!4 I
O!6 0.' 8 1.0 t
(based on tested measured scram time as defined in Reference 11)
DUANE ARNOLD ENERGY CENTER IOWA ELECTRIC LIGHT AND POWER C0fiPANY TECHNICAL SPECIFICATIONS MINIMUM CRITICAL POWER RATIO (MCPR)
VERSUS T FUEL TYPE: LTA 311 FIGURE 3.12-3 Amendment No. g, 118 3.12-14
MAPLHGR vs FUEL EXPOSURE LTA311 N~I 12.5 12.5 I
13.0
.O 3
7 u
/
-.2 12.0 is
\\
c 1.4 11.0 b
N.s k
10.0 g
g 3
E u
y 9.0 9
3 s.O O.O O.2 1.0 5.0 10.0 15.0 20.0 25.0 30.0 35.0 40.0 45.0 50.0 Planar Average Exposure (GWd/t)*
-1/ When core flow is equal to or less than 70% of rated, the MAPLHGR shall not exceed 95% of the limiting values shown.
- 1 GWd/t = 1000 mwd /t DUANE ARN0LD ENERGY CENTER IOWA ELECTRIC LIGHT AND POWER COMPANY TECHNICAL SPECIFICATIONS LIMITING AVERAGE PLANAR LINEAR HEAT 1
GENERATION RATE AS A FUNCTION OF PLANAR AVERAGE EXPOSURE FUEL TYPE: LTA 311 FIGURE 3.12-5 Amendment No.g,%,lVI,118 3.12-16
MAPLHGR vs FUEL EXPOSURE I
13.0 --
P80RB299/ELT/.
E 133 5
15 2W u
M
- 1 12.0 j
o kh 11 q.5 11 01C *
'C '
e m
?c 5
p h C.3 L
u.
.i y
\\
9,
k o.O -
s.O O.0 0.2 1.0 5.0 10.0 15.0 20.0 25.0 30.0 35.0 40.0 45.0 Planar Average Exposure (GWd/t)*
~1/ When core flow is equal to or less than 70% of rated, the MAPLHGR shall not exceed 95% of the limiting values shown.
- GWd/t = 1000 mwd /t DUANE ARNOLD ENERGY CENTER IOWA ELECTRIC LIGHT AND POWER COMPANY TECHNICAL SPECIFICATIONS LIMITIllG AVERAGE PLANAR LINEAR HEAT
'GENERAT:0N RATE AS A FUNCTION OF PLANAR AVERAGE EXPOSURE FUEL TYPES: BP/P80RB299 and ELTA FIGURE 3.12-8 Amendment No. JW, }M, JFI,118 3.12-19 l'
-