ML20023C147
| ML20023C147 | |
| Person / Time | |
|---|---|
| Site: | Duane Arnold  |
| Issue date: | 04/25/1983 |
| From: | Vassallo D Office of Nuclear Reactor Regulation |
| To: | Iowa Electric Light & Power Co, Central Iowa Power Cooperative, Corn Belt Power Cooperative |
| Shared Package | |
| ML20023C148 | List: |
| References | |
| DPR-49-A-088 NUDOCS 8305110556 | |
| Download: ML20023C147 (20) | |
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UNITED STATES j y)*.r. ( [ (g -
gg NUCLEAR REGULATORY COMMISSION E
WASHINGTON. D. C. 20555 5 * \\.
- 9. D '[/1 8 gvo.... f IOWA ELECTRIC LIGHT AND POWER COMPANY CENTRAL IOWA POWER COOPERATIVE CORN BELT POWER COOPERATIVE
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DOCKET NO. 50-331 4
DUANE ARNOLD ENERGY CENTER AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.88 l
License No. DPR-49 l
1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Iowa Electric Light & Power Company, et al, dated January la,1983, as supplemented April 7,1983, complies with the standards and requirements of the Atomic Energy Act of 1954 as amended (the Act), and the Commission's rules and regulaticas set forth in 10 CFR Chapter I; S.
The facility will o.perate ir co'nformity with the application, the provisions of tne 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 ccmpliance with the Commission'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 Commission's regulatio'ns and all applicable requirements have been satisfied.
E 2.
Accordingly, the license is amended by changes to the Technical Spec ~
n ifications as indicated in the attachment to this license amendment 08 n-l and paragraph.2.C.(2) of Facility Operating License No. DPR-49 is e
hereby amended to read as follows:
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(2) Technical Scecifications o8 CE The Technical Specifications contained in AppendicesLA and B, as revised through' Amendment.No.88, are hereby, incorporated hhg' in the license. 'The licensee shall operate the facility. in-accordance with the -Technical Specifications.
3.
This license amendment is effective as of the date of issuanca.
l FOR THE NUCLEAR. REGULATORY COMMISSI0ft
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.r-v Domenic 3. Vassallo, Chief Operating Reactors Branch #2 Division of Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance: April 25,1983.
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ATTACHMENT TO LICENSE AMENDMENT NO.88 i
FACILITY OPERATING LICENSE NO. DPR DOCKET NO. 50-331 i
t Revise the Appendix A Technical Specifications by removir.g the pages
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listed below and inserting new pages attached.
The revised area is identified by a vertical line.
List of Pages Affected vii 3.12-5 1
1.0-5 3.12-Sa
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1.1-2 3.12-9a.
3.5-14 3.12-11 3.5-26 3.12 13 3.12-1 3.12-14 3.12-2 3.12-15 3.12-4 3.12-19*
3.12-20*
4
- New pages
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l TECHNICAL SPECIFICATIONS l~
LIST OF FIGURES I'
Figure Number-Title
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1.1-1 Power / Flow Map I
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 Conce.1tration Requirements 3.4-2 Saturation Temperature of Sodium Pentaborate Solution 3.0-1 DAEC Operating Lidits 6.2-1 DAEC Nuclear Plant-Staffing 3.12-1 Kf as a Function of Core Flow l
3.12-2 Deleted 3.12-3 Deleted 3.12-4
-Deleted 3.12-5 Limiting Average Planar: Linear Heat Generation Rate-(Fuel Type 80274L) 3.12-6 Limiting Average Planar Linear Heat-Generation Rate (Fuel Type 80274H) 3.12-7 Limiting Average Planar Linear Heat Generation Rate-(Fuel Type PSOPS2S9)
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3.12-8 Limiting Average Planar Linear Heat Generation Rate (Fuel Type P80RB299) 3.12-9 Limiting Average Planar Linear Heat Generation Rate.
.(Fuel Type P80RB284H)
. Amendment'No. 88 yji
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DAEC-1 l
q 19.
ALTERATION OF THE REACTOR CORE (CORE ALTERATION)
The addition, removal, relocation or movement of fuel, sources, incore j
instruments or reactivity controls within the reactor pressure vessel with the vessel head removed and fuel in the vessel.
Suspension of CORE ALTERATIONS shall not preclude completion of the movement of a component to a safe conservative position.
- 20. ' REACTOR VESSEL PRESSURE Unless otherwise indicated, reactor vessel pressures listed in the Technical Specifications are those measured by the reactor vessel steam space detectors.
- 21. THERMAL PARAMETERS a.
Minimum Critical Power Ratio (MCPR) - The value of critical power ratio (CPR) for that fuel bundle having the icwest CPR.
b.
Critical Power Ratio (CPR) - The ratio of that fuel bundle power which would produce boiling transition to the actual fuel bundle power.
Transition Sciling - Transition bciling means the ooiling regime
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c.
between nucleate and film boiling., Transition bciling is the regime in which both nucleate and film boiling occur intermittently with neither type being compl_etely stable.
d.
Deleted e.
Linear Heat Generation Rate the heat output per unit leng'.h of fuel pin.
f.
Fraction of Limiting Power Density (FLPD) - The fraction of limiting power density is the ratio of the linear heat generation rate (LHGR) existing at a given location to the design LHGR for that bundle type.
g.
Maximum Fraction of Limiting Power Density (MFLPD) - The maximum fraction of limiting power density is the highest value existing in the core of the fraction of limiting. power density (FLPD).
h.
Fraction of Rated Power (FRP) - The fraction of rated power is the ratio of core thermal power to rated thermal power of 1593 MWth.
1.
Total Peaking Factor (T?F) - The ratio of local LHGR for any specific location on a fuel rod divided by the core average LHGR associated with the fuel bundles of the same type op.erating at the core average bundle power, t
J.
Maximum Total Peaking Factor (MTPF) - The largest TPF which exists in the core for a given class of fuel for a given operating.
condition.
Amendment No. 88 1.0-5
DAEC-1 SAFETY LIMIT LIMITING SAFETY SYSTEM SETTING i
C.
Power Transient Where:
S = Setting in percent of rated power (1,593 MWt)
To ensure that the S afety Limits established in Specification W = Recirculation loop flow l.l.A and 1.1.B are not exceeded, in percent of rated flow.
each required scram shall be Rated recirculation loop initiated by its primary source flow is that
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signal.
A Safety Limit shall be recirculation loop flow i
assumed to be exceeded when scram which corresponds to 6
is accomplished by a means other 49x10 lb/hr core flow.
i than the Primary Source Signal.
For a MFLPD greater than FRP, the D.
With irradiated fuel in the APRM scram setpoint shall be:
reactor vessel, the water level shall not be less than 12 in, pgp above the top of the normal S < (0.66 W + 54)
MFLPD active fuel zone.
Top of the active fuel zone is defined to be j
344.5 inches above vessel zero NOTE:
These settings assume
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(see Bases 3.2).
operation within the basic thermal design criteria.
These criteria are thGR < 13.4 KW/ft i
13x8 array) and MCPR > values as indicated in Table 3.12-2 times K, where Kf is defined f
by Figure 3.12-1.
Therefore, at
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5 full power, operation is not i
allowed with MFLPD greater than unity even if tne scram setting is reduced.
If it is determined that either of these ~ design l
criteria is t,eing vielated during operation, action must be taken 3
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immediately to return to operation within these criteria.
i 2.
APRM High Flux Scram When in the REFUEL or STARTUP and HOT STANDBY MODE, the APR*4 scram shall be set at.less than or equal to 15 percent of rated power.
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Amendment No. 88
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DAEC-1 i
3.5 BASES
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A.
" Core Spray and LPCI Subsystems This specification assures-that adequate emergency cooling capability is available whenever irradiated fuel is'in the reactor vessel.
Based on the loss-of-coolant accident (LOCA) evaluation models described in-General Electric Topical Report NE00-20566 (Ref. 2), the results of the LOCA analysis given in Referer,ce 3 and Subsectica 5.3 of the Updated FSAR and in accordance with the acceptance criteria of 10CFR50.46, any of the following cooling systems provides sufficient cooling to the core to dissipate the energy associated with the loss-of-coolant accident, to limit calculated l. fuel clad temperature to less than 2200*F to assure that core geonetry I
remains intact, and to limit clad metal-water reaction to less than 1%;
either of the two core spray subsystems and the LPCI subsystem.
l The limiting conditions of operation in Specification 3.5.A.1 through 3.5.A.6 specify the combinations of operable subsystems to ' assure-the availability of the minimum cooling. systems noted above.
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-Amendment No.'S8,8 3.5-14
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3.5 REFERENCES
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1.
Jacobs, I.M., "Guicelines for Determining Safe Test Intervals and Repair Times for Engineered Safeguards", General Electric Company, APED, April 1968 (APED 5736).
1 2.
General Electric Company, General Electric Company Analytical Model for Loss-of-Coolant Analysis in Accordance with 10CFR50, Accendix K, NEDO-20566, 1974, and letter MFN-255-77 from Darrell G. Eisenhut, NRC, to I
E.D. Fuller, GE, Documentation of the Reanalysis Results for the loss-of-Coolant Accident (LOCA) of Lead and Non-lead Plants, dated June 30,
- 1977, 3.
General Electric, Loss-of-Coolant Accident Analysis Recort for Duane i
Arnold Eneray Center (Lead Plant), NED0-21082-02-1A, Rev. 2, June 1932.
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.l' Amendment:No.L88 3.5.
DAEC-1 LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS 3.12 CORE THERMAL LIMIfS 4.12 CORE THERMAL LIMITS Acolicability' Acolicability The Limited Conditions for The Surveillance Requirements apply to Operation associated with the the parameters which monitor the fuel fuel rods apply to those rod operating conditions.
parameters which monitor the fuel rod operating conditions.
Objective Objective The Objective of the Limiting The Objective of the Surveillance Conditions for Operation is to Requirements is to specify the type and assare the performance of the frequency of surveillance to be applied fuel rods.
to the fuel rods.
Soecifications Sjecifications A.
Maximum Average Planar Linear A.
Maxixem Aveyage Planar Linear Heat Heat Generation Rate (MAPLHGR)
Generatico date (MAPLHGR)
The MAPLHGR for each type of fuel as a During reactor power operation, tne actual MAPLHGR for each type function of average planar exposure of fuel as a function of average shall be determined daily during '
planar exposure shall not exceed reactor operation at > 25% rated the limiting value shown in Figs, thermal power and following any change l
3.12-5, -6, -7, -8 and -9.
If at in power level cr distribation that at any time during reactor power would cause operation with a Itmiting operation it is determined by control rod pattern as described in the normal surveillance that the bsses for Specification 3.3.2.
During limiting value for MAPLHGR operation with a limiting control rod (LAPLHGR) is being exceeded, pattern, the MAPLHGR shall be action shall then be initiated determined at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
within 15 minutes to restore operation to within the prescribed 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 < 25Y. of Rated Thermal Power within the next 4-hours.
Surveillance and corresponding action shall continue until the prescribed limits are again being met.
l Amendment No. 88 3.12-1
DAEC-1 i
l LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENT B.
Linear Heat Generation Rate B.
Linear Heat Generation Rate (LHGR)
.(LHGR) l 1.
'Ouring reactor power The LHGR as a function of core l
operation the linear heat height shall be checked daily l
generation rate (LHGR) of any during reactor operation at > 25%
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- rod in any 8x8 fuel assembly thermal power and following any shall not exceed.13.4 KW/ft.
change in power level or distribution that would cause If at any time during reactor operation with a limiting control power operation it is rod pattern as described in the determined by normal bases for Specification 3.3.2.
i surveillance that the During operation with a limiting limiting value for LHGR is control rod pattern the LHGR being exceeded, action shall shall be determined at least once then be initiated within 15 per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
minutes to restore operation to within the prescribed limits.
If the LHGR is'not returned to within the l
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 r. ext 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 '
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continue'until the prescribed limits are again being met.
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Amendment No. 88~
~3.12-2'
DAEC-1 3.12 BASES:
CORE THERMAL LIMITS
'A.
Maximum Average Planar Linear Heat Generation Rate (MAPLHGR)
This specificaticn assures that the peak cladding temperature following the postulated design basis loss-of-coolant accident will not exceed the limit specified in 10CFR50.46.
l The peak cladding temperature following a postulated loss-of-coolant accident is pr,imarily a function of the average heat generation rate of all rods of a fuel assembly at any axial location and is only dependent-secondarily on the rod to rod power distribution within an assembly.
Since expected local variations in power distribution within a fuel assembly affect the calculated peak clad temperature by less than + 20*F relative to the peak temperature for a typical fuel design, the limit on the average linear heat generation rate is sufficient to. assure that calculated temperatures are within the 10CFR50.46 limit.
l The calculational procedure used to establish the MAPLHGRs is based on a loss-of-coolant accident analysis.
The analysis was performed using General Electric-(GE) calculational models which are consistent with the requirements of' Appendix K to 10CFR Part 50.
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DAEC 1 B.
Linear Heat Generation Rate (LHGR)
This specification assures that the linear heat generation rate in m
any rod is less than the design linear heat eneration rate and that the fuel cladding 1% plastic diametral strain linear heat' generation rate is not exceeded during any abnormal operating transient if fuel pellet densification is postulated.
The power spike penalty specified is based on the analysis presented in Section 3.2.1 of Reference 3 and in References 4 and 5, and assumes a linearly increasing variation in axial gaps between core bottom and top, and assures with a 95% condifence, that no more than one fuel rod exceeds the design linear heat generation rate due to power spiking.
The LHGR as-a function of core height shall be checked daily during reactor operation at > 25% power to determine if fuel burnup, or control ro'd movement has caused changes in power distribution.
For LHGR to be a limiting value'below 25% rated thermal power, the Maximum Total Peaking Factor (MTPF) would have l
to be greater than 10 which is precluded by a considerable margin.
when employing any permissible control rod pattern.
C.
Minimum Critical Power Ratio (MCPR)-
-1.
Operating Limit-MCPR 4
The required operating limitfMCPR's at steady state operating
.'cond'itions as.. specified in Specification 3.12.C are
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3.12-5 E.
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DAEC-1 l
derived from the established fuel cladding integrity Safety Limit MCPR value, and an analysis of abnormal operational transients (2)
For any abnormal I
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 >EPR a any time during the transient assuming instrument trip settings given in Specification 2.1.
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I Amendment N'o.
88 3.12-Sa
DAEC-1 TABLE 3.12-2 MCPR LIMITS T
Fuel Tyoe 8x8 1.25 8 x SR/P8 x SR 1.27 i
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t 3.12-9a l'
Amendment No. 88
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DAEC-1 3.12 REFERENCES 1.
Duane Arnold Energy Center loss-of-Coolant Accident Analysis Report, NED0-21082-02-1A, Rev.2, June 1982.
l 2.
" Generic Reload Fuel Application," NEDE-240ll-P-A**.
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3.
" Fuel Densification Effects on General Electric Boiling Water Reactor Fuel," Supplements 6, 7 and 8, NEDM-19735, August 1973.
- 4. < Supplement 1 to Technical Reports on Densifications of General Electric
,' Reactor Fuels, December 14, 1973 (AEC Regulatory Staff).
- 5.. Communication:
V.A. Moore to I.S. Mitchell, " Modified GE Model for Fuel Der.sification," Docket 50-321, Ma'rch 27,1974 6.
R.B. Linford, Analytical Methods of Plant Transient Evaluations for the OE BWR, February 1973 (NED0-lC802).
7 General Electric Company Analytical Model for Loss-of-Coolant Analysis in Accordance with 10CFR50, Appendix K, NEDE-20566, August 1974 8.
Boiling Water Reactor Reload-3 Licensing Amendment for Duane Arnold Energy Center, NE00-24087, 77 NED 359, C1. ass 1, December 1977.
9.
Boiling Water Reactor Reload-3. Licensing Amendment for Duane Arnold Energy Center, Supplement 2:
Revised Fuel Loading Accident Analysis, NED0-24087-2.
- 10. Boiling Water Reactor Reload-3 Licensing Amendment for Duane Arnold Energy Center, Supplement 5:
Revised Operating Limits for Loss of Feedwater Heating, NED0-24987-5.
- Approved revision number at time reload fuel analyses are performed.
Amendment No.88 3.12-11
DAEC-1 4
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0ELETED Amendment No.
88 3.12-13
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~ 0 5.0 10.0 15.0 20.0 25.0 30.0 35.0 40.0 45.0 Planar Average Exposure (Gk'd/ t)
,1] kten core flew is equal to or less than.70% of rated the MAFLEGR shall 9
not exceed 95% of the ld-*:ing values shevn.
1 DUANE ARN01.D ENERGY CEhIER
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10k'A ** ' G.C LICHT AD 70k'ER COMPAhT TECENICAL S?ECITICATION3 LIMITING AVERAGE PLANAR LIh?JLR EEAT GENERATION RATE AS A FUNCTION OF PLANA?.
AVERAGE EIPOSURE FUEL TY?E: PSDR3299 FIGURE 3.12-8 i
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3.12-19 Amendment No. v8 o
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0 5.0 10.0 15.0 20.0 25.0 30.0 35.0 40.0 45.0 Planar Avebage Exposttre (Ck'd / t) 1/ khen core flew is equal :o or less than'70% of rated, the MATLEGR shall not exceed 95% of the li=iting values shavn.
DUANE ARNOLD ENERGY CENTER 10k'A "ECTRIC LIGHT AND PCL'ER COMPANY TECHNICAL 5?ICIFICATION3 LIMITING AVERAGE PLANAR LINEAR HEAT GENERATION RATE AS A FUNCTION OF PLANAR AVERAGE EIPOSURE FUEL TYPE: P8DR3284H
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FIGURE 3.12-9 1
3.12-20 Amendment No. 88
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