ML20086R581
| ML20086R581 | |
| Person / Time | |
|---|---|
| Site: | Duane Arnold  |
| Issue date: | 02/14/1984 |
| From: | Vassallo D Office of Nuclear Reactor Regulation |
| To: | Iowa Electric Light & Power Co, Central Iowa Power Cooperative, Corn Belt Power Cooperative |
| Shared Package | |
| ML20086R586 | List: |
| References | |
| DPR-49-A-093 NUDOCS 8402290432 | |
| Download: ML20086R581 (12) | |
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UNITED STATES j,[,&s'. f [. {
NUCLEAR REGULATORY COMMISSION Q@g,:.{}g WASHINGTON, D. C. 20555 IOWA ELECTRIC LIGHT AND POWER C0f;PANY CENTRAL IOWA P01/ER COOPERATIVE
_CORll BELT POWER COOPERATIVE DOCKET fl0. 50-331 DUAf1E ARNOLD ENERGY CENTER AMENDl1ENT TO FACILITY OPERATING LICENSE Amendment No. 93 License No. DPR-49 1.
The Nuclear Regula;ory Commission (the Comission) has found that:
A.
The application for anendment by Iowa Electric Light & Power
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Company, et al, dated November 10, 1981, corplies with the standards and requirements of the Atomic Energy...t of 1954, as anended (the Act), and the Comission's rules and regula-tions 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 amendnent can be conducted without endangering the health and safety of the public, end (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 anended to read as follows:
8402290432 840214 PDR ADOCK 05000331 p
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(2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.
93, are hereby incorporated in the license. The licensee shall operate the facility in i
accordance with the Technical Specifications.
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3.
Tiie license amendment is effective as of the date of issuance.
i FOR THE NUCL R REGULATORY COMMISSION i
4 Domenic B. Vassallo, Chief j
Operating Reactors Branch #2 i
Division of Licensing
Attachment:
i Chances to the Technical Specifications
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Date of Issuance:
February 14, 1984 L
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ATTACHf/ENT TO LICENSE AMEf;DMEt!T f!0. 93 FACILITY OPERATIf!G LICEllSE NO. DPR-49 DOCKET NO. 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 changes.
AFFECTED PAGE-3.2-4 3.2-23 d
3.13-4 6.9-1 6.9-2 6.9-3 6.9-4 6.11-11 ADD PAGE 6.9-5
t DAEC-1 LfMITING CONDITION FOR OPERATION SURVEILLANCE REOUIREMENT G.
Recirculatibn Pumo Trio G.
Recircul at ion' Pumo Trip (ATWS)
Instrumentation and logic shall be function-ally tested, calibrated, The limiting conditions for.
and response time tested operation for the instrumentation as indicated on Table th at trips the recirculation 4.2-G.
pumps as a means of limiting the consequences of a failure to scram during an anticipated transient are given in Table 3.2-G.
(EOC)
The limiting conditions for operation for the instrumen-t ation th at, trips the recir-c ul at i o n pumps during turbine stop valve or control valve fast closure for transient margin improvement (especially for end of cycle) are given in Tabla 3.2-G.
H.
Accident Monitorina H.
Accident Monitorina instrumentation instrumentation The limiting conditions for operation for the accident Instrumentation shall be monitoring instrumentation checked and calibrated are given in Table 3.2-H.
as indicated in Table 4.2-H.
g Amendment flo. 93 3.2-4
DAEC-1 TABLE 3.2-G INSTRUMENTATION THAf INITIATES RECIRCULATION PUMP TRIP Minimum Number Number of of Operable Instrument Instrument Channel s Channels ; er Provided by Trip System (1)
Instrument Trip Lavel Setting Design Action 1
(ATWS) Reactor High
< 1120 psig 4
(2)
Pressure 1
(ATWS) Reactor low-Low
> -38.5 in.
4 (2)
Water Level indicated level 1
(EOC)
RPT Logic N/A 2
(3) 1 (EOC)
RPT System
< 140 msec (4) 2 (3)
(Response Time)
NOTES FOR TABLE 3.2-G 1.
Whenever the reactor is in the CUN Mode, there shall be one operable trip system for each parameter for operating recirculation pump.
If this cannot be met, the indicated action shall be taken.
2.
Reduce power and place the mode selector-switch in a made other than the RUN Mode.
3.
Two EOC RPT systems exist, either of which will trip both recirculation pumps.
The systems will be individually functionally tested monthly.
If the test period for one RPT systems exceeds 2 consecutive hours, the system will be declared inoperable.
If both RPT systems are inoper able or if 1 RPT system is inoperable for more than 72 consecutive hours, an orderly power reduction shall be initiated and the reactor power shall be less than 85% within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.
4.
This response time is from initiation of Turbine control valve fast closure or Turbine stop valve closure to actuation of the breaker secondary (auxiliary) contact.
Amendment No. 93 3
3
DAEC-1
, LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REOUIREMENT h.
At least once per 18 months, during shutdown, by verifying the diesel starts from anbient conditions on the auto-start signal and operates for > 30 minutes while loaded with the fire pump.
1.
At least once per 31 days by verifying that the diesel day tank
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contains fuel -for two hours' operation.
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At least once per month by verifying that each valve in the flow path is in its correct position.
2.
When only one pumo is operable, restore 2.
When it is determined that only one the second fire pump to operable status pump is operable, that pumo shall be within 7 days or prepare and submit a demonstrated operable immediately Special Report to the Commission and daily thereafter until pursuant to specification 6.11 within Specification 3.13.B.1 can be met.
the next 30 days outlining the plans and procedures to be used to provide for the loss of redundancy in this system.
3.
If no Fire Suppression Water System is operable:
a.
Establish a backup fire suppression water system within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />; and b.
Submit a Special Report to the Commission pursuant to Specification 6.11 witnin 30 days outlining the cause of the inoperability and the olans for restoring the system to operable status.
c.
If 3a above cannot be fulfilled, place the reactor in Hot Standby within the next six (6) hours and in Cold Shutdown within the following thirty (30) hours.
4 When the maintenance on the circulating water / fire water pump pit is performed, the river water supply systen will be maintained in a condition to restore fire water supply within one hour and a roving fire watch will be established in all power block buildings.
3.13-4 Amendment No. 93
e 6.9 RADIOLOGICAL PROCEDURES 6.9.1 Procedures for personnel radiation protection shall be prepared consistent with the requirements of 10 CFR Part 20 and shall be approved, maintained and adhered to for all operations involving personnel radiation exposure.
6.9.2 HIGH RADIATION AREA In lieu of the " control device" or aldrm signal" required by paragraph 20.203(c)(2) of 10 CTR 20, each high r adi at i on area in which the intensity of radiation is greater than 100 mrem /hr but less than 1000 mrem /hr shall be barricaded and conspicuously posted as a high radiation area and entrance thereto shall be controlled by requiring issuance of a Radiation Work Permit.*
Any individual or group of individuals permitted'to enter such areas shall be provided with or accompanied by one or more of the following:
- a. A radiation monitoring device w'hich continuously indicates the radiation dose rate in the area.
- b. A radiation monitoring device which continuously integrates the radiation dose rate in the area and alarms when a preset integrated dose is received.
Entry into such areas with this monitoring device may be made af ter the dose rate level in the area has been established and personnel have been made knowledgeable of them.
- c. A health physics qualified individual (i.e., qualified in radiation protection procedures) with a radiation dose rate monitoring device who is responsible for providing positive control cver tne activities within the area and shall perform periodic radiation surveillance at the frequency specified by the facility Health Physics Supervisor in the Radiation Work Permit.
6.9.3 In addition to the requirements of 6.9.2, areas accessible to personnel with radiation levels such that a major-portion of the body could receive in one hour dose greater than 1000 mrem shall be provided with locked doors to prevent unauthorized entry, and the keys shall be maintained under the administrative control of the Shift Supervisor Engineer on duty and/or health physics supervision.
Doors shall remained locked except during 6.9-1 Amendment No. 93
6.9 RADIOLOGICAL PROCEDURES (Continued)'
I 2eriods of access by personnel under an approved Kadiation Work Permit which shall specify the dose rate levels in the immediate work area and the maximum allowable stay time for individuals in that area.
For individual areas accessible to personnel with radi ation levels such that a major portion of the body could receive in one hour dose in excess of 1000 mrem ** that are located within large areas, where no enclosure exists for purposes of locking, and no enclosure can be reasonably constructed around the individual areas, then that area shall be roped off, conspicuously posted and a flashing light shall be activated as a warning device.
In lieu of the stay time specification of the RWP, direct or remote continuous surveillance may be made by personnel qualified in radiation protection procedures to provide positive exposure control over the activities within the area.
Health Physics personnel or personnel escorted by Health Phyiics personnel shall be exempt from the RWP issuance requirement during the performance of their assigned radiation protection duties, provided they are following plant radiation protection procedures for entry into high radiation areas.
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- Measurement made at 18" from source of radioactivity.
Amendment tio. 93
DAEC-1 2
SPECIFICATION SURVEILLANCE RE0VIREMENT 6.9.4 Source Leakage Test 7.9.4 Source Leakage Test Radioactive sources shall be leak tested for A.
Test for leakage and/or contamination.
The contamination shall be leakage test shall be performed by the capable of detecting the licensee or by other presence of 0.005 persons specifically microcurie of radioactive authorized by the materi'al on the test Commission or an sample.
If the test agreement State, as reveals the presence of follows:
0.005 microcurie or more of removable 1.
Each sealed source, 5
contamination, it sh all except startup sources immediately be withdrawn subject to core flux, from use, decontaminated containing radioactive and repaireo, or.be materi al,3, with other than Hydrogen a
disposed of in accordance with Commission half-life greater than regulations.
thirty days and in any form other.than gas Those quantities of by-shall be tested for product material that leakage and/or exceed the quantities contamination at listed in 10 CFR 30.71 intervals not to exceed Schedule B are to be leak s'x months.
tested in accordance with the schedule shown in 2.
The periodic leak test Surveillance requirec does not apply Requirements.
All other to sealed sources that sources (including alpha are stored and not emitters) containing being used.
The greater than 0.1 sources excepted from microcurie are also to be this test shall be leak tested in accordance tested for l e ak age with the Surveillance prior to any use or Requirements.
transfer to-another user unless they have been leak tested within six months prior-to the date of use or
-transfer.
In the absence - of-a certificate from-a transferor indicating that a test has been made within six months
. prior to the transfer, sealed sources shall not be put into use until tested.
Amendment No. 93 6.9-3
DAEC-1 SPECIFfCATION SURVEILLANCE REOUIREMENT 3.
St artup sources shall be leak tested prior to and following any repair or maintenance and before being
, subjected to core flux.
B.
Reporting Requirements Results of the leak tests performed on sources shall be included in the Annual Operating Report if the tests reveal the presence of 0.005 microcurie or more of removable contamination.
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Amendment No. 93 6.9 4 l
-DAEC-1 1
6.9.4 BASES i
Ingestien or inhalation of source mate-ial may give rise to total body or organ ' irradiation.
This specification assures that leakage from radioactive material sources does not exceed allowable limits.
In the unlikely event that those quantities of radioactive by-product materials of interest to this specification which are exe=pt from leaka~ge testing are ingested or inhaled, they represent less than one maximum permissible body burden for total body irradiatien.
The limits for all other sources (including alpha emitters) are based upon 10 CFR 70.39 (c) limits for plutonium.
4 t
s 6.9-5 Amendment No.
93
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4 a.
Reactor vessel base, weld and heat affected zone metal test specimens (Specification 4.6.A.2).
b.
I-131 dose equivalent exceeding 50% of equilibrium value (Specification 4.6.B.1.h),
c.
Inservice inspection (Specification 4.6.G).
d.
Rea'ctor Containment Integrated Leakace Rate Test (Specification a.7.A.2.f).
e.
Auxiliary Electrical System - Operation with inocerable components (Specification 3.8.B.4).
f.
Fire Protection Systems (Specifications 3.13.A.3, 3.13.B.2, 3.13.3.3, 3.13.C.3, and 3.13.0.3).
6.11 Amendment No. 93
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