ML20217K946
| ML20217K946 | |
| Person / Time | |
|---|---|
| Site: | Duane Arnold  |
| Issue date: | 03/31/1998 |
| From: | Richard Laufer NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20217K951 | List: |
| References | |
| NUDOCS 9804070342 | |
| Download: ML20217K946 (7) | |
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7 1 UNITED STATES g
.j NUCLEAR REGULATORY COMMISSION s,..... /[
o, WA$HINGTON, O.C. 20$66 0001 IES UTILITIES INC CENTRAL IOWA POWER COOPERATIVE CORN BELT POWER COOPERATIVE DOCKET NO. 50-331 DUANE ARNOLD ENERGY CENTER AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 221 License No. DPR-49 1.
The Nuclear Regulatory Commission (the Commissicn) has found that:
A.
The application for amendment by the IES Utilities Inc., et al., dated February 3, 1998, 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 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 regulations and all applicable requirements have been satisfied.
2.
Accordingly, the license is amended by changes to the Technical Specifications 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:
9804070342 980331 DR ADOCK 0500 1
(2)
Technical Soecifications
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The Technical Specifications contained in Appendix A, as rev; sed through Amendment No.221, are hereby incorporated in the license. The licensee shall i
operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective as of its date of issuance and shall be implemented within 120 days of the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION w{
Richard J. Laufer, Project Manager Project Directorate lll-3 Division of Reactor Projects lil/IV Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date ofissuance: March 31,1998 4
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ATTACHMENT TO LICENSE AMENDMENT NO.221 FACILITY OPERATING LICENSE NO. DPR-49 DOCKET NO. 50-331 Replace the following pages of the Appendix "A" Technical Specifications with the attached pages. The revised pages are identified by amendment number and contain vertical lines indicating the area of change.
l Remove Insert 1.0-2 1.0-2 4
1.0-3 1.0-3 1.0-11 1.0-11 3.17-1 1
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DAEC-1
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- 5. OPERABLE-OPERABILITY A system, subsystem, train, component or device shall be OPERABLE or have OPERABILITY when it is capable of performing its specified functions (s). Implicit in this definition shall be the assumption that all necessary attendant instrumentation, controls, normal and emergency electrical power sources, cooling or seal water, lubrication or other auxiliary equipment that are required for the system, subsystem, train, component or device to perform it functions (s) are also capable of performing their related support functions (s).
A verification of OPERABILITY is an administrative check, by examination of appropriate plant records (logs, surveillance test records), to determine that a system, subsystem, train, component or devise is not inoperable.
- 6. OPERATING Operating means that a system or component is performing its intended functions in its required manner.
- 7. IMMEDIATE lmmediate means that the required action will be initiated as soon as practical considering the safe operation of the unit and the importance of the required action.
- 8. REACTOR POWER OPERATION Reactor power operation is any operation with the mode switch in the "Startup" or "Run" position with the reactor critical and above 1% rated power, a)
SINGLE LOOP OPERATION (SLOk REACTOR POWER OPERATION with only one of the two recirculation loops in operation.
- 9. HOT STANDBY CONDITION Hot standby condition means operation with coolant temperature greater than 212*F, j
reactor vessel pressure less than 1055 psig, and the mode switch in the Startup/ Hot Standby position.
- 10. COLD CONDITION Reactor coolar't temperature equal to or less than 212*F. During the performance of vessel hydrostatic pressure and leak testing the reactor coolant temperature may be 1
considered NA, the resctor may be pressurized above atmospheric, and the reactor may be considered to remain in a COLD CONDITION / COLD SHUTDOWN if the requirements of 3.17.A are met.
- 11. HOT SHUTDOWN The reactor is in the shutdown mode and the reactor coolant temperature greater than 212*F.
1.0-2 Amendment No. 120,174 221
a DAEC-1
- 12. COLD SHUTDOWN The reactor is in the shutdown mode, the reactor coolant temperature equal to or less than 212'F, and the reactor vessel is vented to atmosphere. During the performance of vessel hydrostatic pressure and leak testing the reactor coolant temperature may be considered NA, the reactor may be pressurized above atmospheric, and the reactor may be considered to remain in a COLD CONDITION / COLD SHUTDOWN if the requirements of 3.17.A are met.
- 13. MODE OF OPERATION A reactor mode switch selects the proper interlocks for operational status of the unit. The following are the modes and interlocks provided:
Startup/ Hot Standby Mode - In this mode the reactor protection scram trips, a.
initiated by main steam line isolation valve closure, are bypassed. The reactor protection system is energized with IRM neutron monitoring system trip, the -
i APRM 15% high flux trip, and control rod withdrawal interlocks in service. The lower pressure MSIV closure 850 psig trip is also bypassed. This is intended to imply the Startup/ Hot Standby position of the mode switch.
b.
Run Mode - In this mode the reactor vessel pressure is at or above 850 psig and the reactor protection system is energized with APRM protection (excluding the 15% high flux trip) and RBM interlocks in sc.7 ice.
Shutdown Mode P. lacing the~ mode switch to the shutdown position initiates a c.
reactor scram ard power to the control rod drives is removed. After a short time period (about 10 seconds), the scram signalis removed allowing a scram reset and reatoring the normal valve lineup in the control rod drive hydraulic system; also, the main steam line isolation scram is bypassed.
d.
Refuel Mode - With the mode switch in the refuel position interlocks are established so that one control rod only may be withdrawn when the Source Range Monitor indicates at least 3 cps and the refueling crane is not over the reactor; also, the main steam line isolation scram is bypassed. If the refueling crane is over the reactor, all rods must be fully inserted and none can be withdrawn.
- 14. RATED POWER Rated power (100% power) refers to operation at a reactor power of 1658 Mwt.
Amendment No. 446; 221
DAEC-1 TABLE 1.0-1 v
OPERATING MODES REACTOR MODE SWITCH AVERAGE REACTOR COOLANT OPERATING MODE POSITION TEMPERATURE w
- 1. RUN/ POWER OPERATION Run NA
- 2. STARTUP Startup/ Hot Standby or NA Refuel (*)
- 3. HOTSHUTDOWN(*)
Shutdown (*X*
> 212*F
- 4. COLD SHUTDOWN (*)
Shutdown (*M")
s212'F
- 5. REFUELINGW Shutdown or Refuel (*"
NA (a) Fuel in the reactor vessel with the reactor vessel head closure bolts fully tensioned.
(b) Fuel in the reactor vessel with the vessel head closure bolts less than fully tensioned or with the head removed.
(c) The reactor mode switch may be placed in the Run, Startup/ Mot Standby or Refuel position to test the switch interlock functions and related instrumentation provided that the control rods are verified to remain fully inserted by a second licensed operator.
(d) The reactor mode switch may be placed in the Refuel position while a single control rod is being recoupled or withdrawn provided that the one-rod-out interlock is OPERABLE.
(e) Tne reactor mode switch may be placed in the Refuel position while a single control rod drive is being removed from the reactor pressure vessel per Specification 3.9.A.
(f) The reactor mode switch may be placed in the Startup position for demonstration of shutdown margin per Specification 4.3.A.1.
(g) During the performance of vessei hydrostatic pressure and leak testing the reactor coolant temperature may be considered NA and the reactor may be considered to remain in COLD SHUTDOWN if the requirements of 3.17.A are met.
Amendment No.498 221 1.0 11
DAEC-1
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LIMITING CONDITIONS FOR OPERATION tiURVEILLANCE REQUIREMENTS 3.17 VESSEL HYDROSTATIC PRESSURE 4.17 VESSEL HYDROSTATIC PRESSURE AND LEAK TESTING AND LEAK TESTING Anslicability :
Aoolicability:
Applies to the performance of ASME Applies to the surveillance requirements required reactor vessel hydrostatic during the performance of ASME required pressure and leak testing.
reactor vessel hydrostatic pressure and leak testing.
Soecification:
Soecificatior:
A.
Svstem Availability A.
System Availability 1.
Prior to and while exceeding 212*F during 1.
Channel checks shall be performed every the performance of vessel hydrostatic 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> on the Reactor Vessel Water pressure and leak testing, the following Level - Low, Refuel Floor Exhaust Duct -
requirements must be met:
High Radiatior;, and Reactor Building Exhaust Shaft - High Radiation trip a.
The Reactor Vessel Water Level-Low, fen:tions.
Refuel Floor Exhaust Duct - High Radiation, and Reactor Building Exhaust Shaft - High Radiation trip functions shall be operable and, b.
Secondary Containment shall be operable, and c.
Secondary Containment Automatic isolation Dampers shall be operable, and d.
Both trains of Standby Gas Treatment shall be operable, and e.
Two low pressure core cooling pumps (any combination of Core Spray and LPCI) shall be operable and capable of injecting into the vessel.
2.
If Specification 3.17.A.1 cannot be met, immediately suspend activities that could increase average reactor coolant temperature or pressure and reduce the average reactor coolant temperature to 212*F within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
I 3.17-1 Amendment No. 221 j
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