ML20195H941
| ML20195H941 | |
| Person / Time | |
|---|---|
| Site: | Duane Arnold  |
| Issue date: | 11/22/1988 |
| From: | Hannon J Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20195H948 | List: |
| References | |
| NUDOCS 8812010124 | |
| Download: ML20195H941 (9) | |
Text
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UNITED STATES E
NUCLEAR REGULATORY COMMISSION WASHINGTON. D. C. N465 i
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IOWA ELECTRIC LIGHT AND POWER COMPANY CENTRAL IOWA POWER COOPERATIVE CORN BELT POWER COOPERATIVE DOCKET NO. 50-331 DUANE ARNOLD ENERGY CENTER AMENDHENT TO FACILITY OPERATING LICENSE Amendment No. 154 License No. DPR-49 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Iowa Electric Light and Power.
1 Company, et al., dated August 19, 1988 complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations set forth in 10 CFR Chapter I; B.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; 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 Commission's regulations; D.
The is;uance 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 Commission'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:
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.g-(2) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No.154, are hereby incorporated in the license.
The licensee shall operate the facility in*
accordance with the Technical Specifications.
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The license amendment is effective as of the date of issuance and shall be implemented within 30 days of the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION l
$k John N. Hannon, Director i
Project Directorate III-3 Division of Reactor Projects - III, t
IV, V and Special Projects
Attachment:
Changes to the Technical t
Specifications Date of Issuance: November 22, 1988 I
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ATTACHMENT TO LICENSF; AMENDMENT NO. 154 FACILITY OPERATING LICENSE NO. DPR-49 DOCKET NO. 50-331 Replace the following pages of the Appendix A Technical Specifications with the enclosed pages.
The revised areas are indicated by marginal lines.
Pagg,s vii 1.1-1 3.5-26 3.12-10 3.12-13 3.12-19 l
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i DAEC-1 TECHNICAL SPECIFICATIONS LIST OF FIGURES Figure t
Numbsr Title i
9 1.1-1 Power / Flow Map 1.1-2 Deleted 2.1-1 APRM Flow Biased Scram and Rod Blocks 2.1-2 Deleted l
4.1-1 Instrument Test Interval Determination Curves 4.2-2 Probability of Systcin Unavailability Vs. Test Interval 3.4-1 Sodium Pantaborate Solution Volume Concentration Requirements 3.4-2 tiinimum Temperature of Sodium Pentaborate Solution 3.6-1 DAEC Operating Limits 4.8.C-1 DAEC Emergency Service Water Flow Requirement 3.12-1 Flow-Dependent Minimum Critical Power Ratio (MCPR )
p 3.12 2 Power-Dependent Minimum Critical Power Ratio Multiplier (K )
p 3.12-3 Minimum Critical Power Ratio (MCPR) versus t l
(Fuel Types: BP/P8X8R, CE 8X8EB. LTA-311 and ELTA) j I
3.12-4 Limiting Average Plenar Linear lieat Generation Rate (Fuel Type: BD303A) l t
3.12-5 Limiting Average Planar Linear Heat Generation Rate (Fuel Type: LTA 311) l 3.12-6 Limiting Average Planar Linear. Heat Generation Rate (Fuel Type: BP/P8DRB301L)
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3.12-7 Limiting Average Planar Linear Heat Generation Rate
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(Fuel Type: BD299A) 3.12-8 Limiting Average Planar Linear Heat Generation Rate I
(FuelTypes:
BP/PSDRB299 and ELTA) l 3.12-9 Limiting Average Planar Linear Heat Generation Rate (Fuel Type BD3248) l l
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vii Amendment No.129.)A2,15),154 I
i DAEC-1 SAFETY LIMIT LIMITING SAFETY SYSTEM SETTING 1.1 FUEL CLADDING INTEGRITY 2.1 FUEL CLADDING INTEGRITY Applicability:
Applicability:
i Applies to the inter-related Applies to trip settings of the variables associated with fuel instruments and devices which are thermal behavior.
provided to prevent the reactor system safety limits from being exceeded.
Objective:
Objective:
To establish limits which To define the level of the process ensure the integrity of the variables at which automatic fuel cladding.
protective action is initiated to prevent the fuel cladding integ-i r.ity safety limits from being exceeded.
_ Specifications:
Specifications:
The limiting safety system settings shall be as specified below:
A.
Reactor Pressure > 785 asig A.
Neutror. Flux Trips end Core Flow > 10% of Rated i
l The existence of a minimum 1.
APRM High Flux Scram When In critical power ratio (MCPR) less Run Mode, than 1.04 for two recirculation i
loop operation [1.07 for SINGLE The APRM scram trip setpoint LOOPOPERATION(SLO)]shall shall be as shown on Figure constitute violation of the tue) 2.1-1 and shall be:
cladding integrity safety limit.
S < (0.58W + 62)
B.
Core Thennal Power Limit with a maximum setpoint of l
Reactor Fressure < 785 psin 120% rated power at 100%
or Core Flow < 10% of Rated rated recirculation flow or
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greater for two recirculation l
loop operation and l
When the reactor pressure is
< 785 psig or core flow is Tess than or equal to 10% of S < (0.58W + 58.5) l l
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i rated, the core thermal power for SLO shall not exceed 25 percent of l
l rated thermal power.
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Amendment No. J29, 154 1.1 1 I
DAEC-1
3.5 REFERENCES
1.
Jacobs, I.M., Guidelines for Determinino Safe Test intervals and Reoair Times for Enoineered Safecuaras, General Electric Company, APEO, April 1968 (APE 0 5736).
2.
General Electric Conpany, The GESTR-LOCA and SAFER Models for' the Evaluation of loss-of-Coolant Accident, NEDC-23785-P, October 1984 3.
General Electric, Duane Arnold Eneroy Center SAFER /GESTR-LOCA Loss-of-Coolant Accident Analysis, NEDC-31310P, June, 1955.
l 4
General Electric Company, Analysis of Reduced RHR Service Water Flow at the Duane Arnold Eneroy Center, NEDE-30051-P, January 1983.
5.
General Electric Company, Duane Arnold Enerny Center Sucoression Pool Temoerature Resoonse, NEOC-220e2-P, Maren 1902.
3.5-26 Amendment No. JJ5,JA2,154
.J DAEC-1 l
3.12 REFERENCES 1.
General Electric Standard Aeolication for Reactor Fuel, NEDE-240ll-P-A*.
2.
Duane Arnold Energy Center SAFER /GESTR-LOCA Loss-of-Coolant Accident l
Analysis, NEDC-31310P, June 1988.
3.
Supplemental Reload L'icensino Submittal for Ouane Arnold Atomic Energy Center, Unit 1.**
4.
Duane Arnold Eneroy Center Single Loop Operation, NE00-24272, July 1980.
5.
Average Power Rance Monitor, Rod Block Monitor and Technical Specification Imorovement (ARTS) Proaram for the Ouane Arnold Enercy Center, NEOC-3081J-P, Decemoer 1964.
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- Approved revision number at time reload fuel analyses are performed.
- Analysis is cycle-dependent; see the report for the current operating cycle / reload.
3.12-10 Amendment No.120.J/2,154 i
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t DAEC-1 a..
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Option R
Ootion A
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1.30 -
- 1.30 6
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l 1.25 -
- 1.25 1.20 -
- 1.20
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1.15 -
- 1.15 1.10 -
- 1.10 0.0 n!2 I
O!4 I
O!6 O!8 I
10 T
(based on tested measured scram time as defined in Reference 1)
DUANE ARNOLO ENERGY CENTER IOWA El.ECTRIC LIGHT AND POWER COMPANY TECHNICAL SPECIFICATIONS MINIMIN CRITICAL POWER RATIO AT RATED POWER [MCPR(100)] VERSUS,
FilEL TYPES:
RP/P8X8R, GE8X8ER, LTA-311 and ELTA FIGURE 3.12-3 3.12-13 Amendment No. JJ2 J20,JA2,154
p DAEC-1 MAPLHGR vs FUEL EXPOSURE 14.0 U 1 ti;1 33,o lh 8
t' 12.0 1
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10.0 W
p.0
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s bf k
a.0 s
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- /.0 E
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s.0 0.0 3.0 7.0 10.0 12.5 20.0 25.0 35.0 45.0 50.0 Plonor Averege Dposure (GC/ST)*
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- 1 Gid/t = 1000 mwd /t
- These values are nominal values to be used for manual calculations. The actual lattice-type dependent values are modeled in the process computer.
l OUANE ARNOLD ENERGY CENTER 10WA ELECTRIC LIGHT AND POWER COMPANY f
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TECHNICAL SPECIFICATIONS i
i LIMITING AVERAGE PLANAR LINEAR HEAT I
GENERATION RATE AS A FUNCTION OF PLANAR AVERAGE EXPOSURE i
1 FUEL TYPE:
803242 L
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FIGURE J.12-9 I
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3.12-19 Amendment No.120. 154
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