ML19294B946
| ML19294B946 | |
| Person / Time | |
|---|---|
| Site: | Duane Arnold  |
| Issue date: | 02/13/1980 |
| From: | Ippolito T Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML19294B940 | List: |
| References | |
| NUDOCS 8003060438 | |
| Download: ML19294B946 (11) | |
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NUCLEAR REGULATORY COMMISSION 3
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IOWA ELECTRIC LIGHT AND POWER COMPANY CENTRAL IOWA POWER COOPERATIVE CORN BELT POWER COOPERATIVE DOCKET N0. 50-331 DUANE ARN0LD ENERGY CENTER AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 56 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 Company, Central Iowa Power' Cooperative, and Corn Belt Power Cooperative (the licensees) dated May 21, 1976, as supplemented October 12, 1977 and October 10, 1979, 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 con.pliance with the Commission's regulations; D.
The issuance of this snendnent 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 Spec-ifications 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:
(2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 56, are hereby incorporated in the license. The licensee shall operate the facility in oV accordance with the Technical Specifications.
6003000 30
. 3.
This license amendment is effective as of the date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION l'
th# d.b Thoma
. Ippolito, Chief Operating Reactors Branch #3 Division of Operating Reactors
Attachment:
Changes to the Technical Specifications Date of Issuance: February 13, 1980
ATTACHMENT TO LICENSE AMENDMENT NO. 56 FACILITY OPERATING LICENSE N0. DPR-49 DOCKET N0. 50-331 Replace the following pages of the Appendix "A" Technical Specifications with the enclosed pages. The revised pages are identified by Amendment number and contain vertical lines indicating the area of change.
Remove Replace 3.6-1/3.6-2 3.6-1 3.6-11/3.6-12 3.6-2 3.6-13/3.6-14 3,6-11 3.6-33 3.6-12 Figure 3.6-1 3,6-13 3.6-14 3.6-33 Figure 3.6-1
LIMITING CONDITIONS FOR OpERATICN SURVEILLANCE REQUIREMENT 3.6 PRIMARY SYSTEM BOUNDARY 4.6 PRIMARY SYSTEM BOUNCARY Acolicability:
Acolicability:
Applies to the operating Applies to the periodic status of the reactor examination and testing.
coolant system.
requirements for the reactor cooling system.
Objective:
Objective:
To assure the integrity To determine the condition and safe operation of the of the reactor coolant reactor coolant system.
system and the operation of the safety devices related to it.
Specification:
Specification:
A.
Thermal and Pressurization A.
Thermal and Pressurization Limi tations Limitations 1
The average rate of reactor 1.
During heatups and cooldcwns, coolant temperature change the following temperatures during nonnal heatup or shall be logged at least every cooldown shall not exceed 15 minutes until 3 consecutive 0
100 F/hr when averaged readings at each given location over a one-hour period.
are within 5 F.
~ 2.
The reactor vessel shall be ai.
Reactor vessel shell adjacent to vented and power operation shall shell flange.
not be conducted unless the reactor vessel temperature is b.
Reactor vessel bottom drain.
equal to or greater than that shown in Curve C of Figure 3.6.1. c.
Recirculation loops A and B.
Operation for hydrostatic or leakage tests, during heatup d.
Reactor vessel bottom head temperature.
or cooldown, and with the core critical shall be conducted 2.
Reactor vessel metal temperature only when vessel temperature at the outside surface of the bottom is equal to or above that shown head in the vicinity of the control red in the appropriate curve of drive housing and reactor vessel shell Fig. 3.6.1.
Figure 3.6.1 is adjacent to shell flange shall be effective through 6 effective recorded at least every 15 minutes full power years. At least six during inservice hydrostatic or leak months prior to 6 effective testing when the vessel pressure is full power years new curves will
>312 psig.
be submitted.
Amendment No.
56 3.6-1
LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REOUIREMPUS 3.
The reactor vessel head Test specimens of the reactor bolting studs shall not be vessel base, weld and heat under tension unless the affected zone metal subjected temperature of the vessel to the highest fluence of head flange and the head is greater than 1 MeV neutrons greater than 1000 F.
shall be installed in the reactor vessel adjacent to the 4.
The pump in an idle recircu-vessel wall at the core mid-lation loop shall not be plane level. The specimens started unless the tempera-and sample program shall confom tures of the coolant within to ASTM E 185-66 to the degree the idle and operating re-discussed in the FSAR.
circulatign loops are within 50 F of each other.
Samples sha?1 be withdrawn at one-fourth and three-fourths 5.
The reactor recirculation service life in accordance with pumps shall not be started 10CFR50, Appendix H.
unless the coolant tempera-Neutron flux wires shall be in-tures between the dome and stalled in the reactor vessel the bottom head drain are adjacent to the reactor vessel within 1450F.
wcil at the core midplane level.
The wires shall be removed and tested during the second re-fueling outage to experimen-tally verify the calculated values of neutron fluence at one-fourth of the beltline shell thickness that are used to determine the NDTT shift.
3.
When the reactor vessel head bolting studs are ten-sioned and the reactor is in a Cold Condition, the reactor vessel shell temperature immediately below the head flange shall be permanently recorded.
4.
Prior to and during startup of an idle recirculation loop, the temperature of the reactor coolant in the operating and idle loops shall be pemanently logged.
5.
Prior to starting a recirculation pump, the reactor coolant temper-atures in the dome and in the bottom head drain shall be compared and pemanently logged.
Amendment No. 56 3.6-2
DAEC-1 3.6.A & 4.6,A BASES:
Ther-nal and Pressurization Limitations The thennal limitations for the reactor vessel meet the requirements of 10CFR50, Appendix G.
The allowable rate of heatup and cooldown for the reactor vessel 0
contained fluid is 100 F per hour averaged over a period of one hour. This rate has been chosen based on past experience with operating power plants. The associated time period for heatup and cooldown cycles when the 100 F per hour rate is 0
limiting provides for efficient, but safe, plant operation.
Specific analyses were made based on a heating and cooling rate of 1000F/ hour applied continuously over a temperature 0
0 range of 100 F to 546 F.
Calculated stesses were within ASME Boiler and Pressure 1essel Code Section III stress intensity and fatigue limits even at the flange area where maximum stress occurs.
Chicago Bridge and Iron Company performed detailed stress analysis as shown in FSAR Appendix K, " Field Fabricated Reactor Vessel". This analysis includes more severe thennal conditions than those which would be encountered during normal heating and cooling operations.
The pennissible flange to adjacent shell temperature differ-0 ential of 145 F is the maximum calculated for 1000F hour heating and cooling rate applied continuously over a 1000F to Amendment No. 56 3.6-11
DAEC-1 0
550 F range. The differential is due to the sluggish temperature
. response of the flange metal and its value decreases for any lower heating rate or the same rate applied over a narrower range.
The coolant in the bottom of the vessel is at a lower temperature than that in the upper regions of the vessel when there is no recirculation flow. This colder water is forced up when recirculation pumps are started. This will not result in stresses which exceed ASME Boiler and Pressure Vessel Code,Section III limits when the temperature differential is not greater than 1450F.
The reactor coolant system is a primary barrier against the release of fission products *.o the environs.
In order to provide assurance that this barrier is maintained at a high degree of integrity, restrictions have been placed on the operating conditions to which it can be subjected.
The nil-ductility transition (NOT) temperature is defined as the temperature below which ferritic steel breaks in a brittle rather than ductile manner. Radiation exposure from fast l7 neutrons ( > l mev) above about 10 nyt may shift the NDT temperature of the vessel base metal above the initial value.
Extensive tests have established the magnitude of changes as a function of the integrated neutron exposure.
Neutron flux wires and samples of vessel material are in-stalled in the reactor vessel adjacent *1 the vessel wall at the core inidplane level. The wires and samples will.be Amendment No. 56 3.6-12
DAEC-1 removed and tested according to 10CFR50 Appendix H.
Results of these analyses will be used to adjust Figure 3.6-1 as appropriate.
As described in paragraph 4.2.5 of the Safety Analysis report, detailed stress analyses have been made on the reactor vessel for both steady state and transient conditions with respect to material fatigue. The results of these transients are com-pared to allowable stress limits.
Requiring the coolant temp-0 erature in an idle recirculation loop to be within 50 F of the operating loop temperature before a recirculation pump is started assures that the changes in coohnt temperature at the reactor vessel nozzles and bottom head region are acceptable.
Amendment No. 56 3.6-13
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Amendment No. 56
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Amendment No. 56 3.6-33