ML20083Q657
| ML20083Q657 | |
| Person / Time | |
|---|---|
| Site: | Duane Arnold  |
| Issue date: | 05/18/1995 |
| From: | Marcus G NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20083Q660 | List: |
| References | |
| NUDOCS 9505260113 | |
| Download: ML20083Q657 (10) | |
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UNITED STATES eo 7
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WASHINGTON. D.C. 2006 Hoot 49.....,o IES UTILITIES INC.
CENTRAL IOWA POWER C00PERATIy1
[_0RN BELT POWER COOPERATIVE DOCKET NO. 50-331 DUANE ARNOLD ENERGY CENTER AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 210 License No. DPR-49 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by IES Utilities Inc., et al.,
dated March 1, 1995, 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 Specifi-cations as indic ted 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:
l 9505260113 950518 DR ADOCK 050003 1
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' t (2) Technical Soecifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 210, are hereby incorporated in the license.
The licensee shall operate the facility in accordance with the Technical Specifications.
3.
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 lD'l I
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Gail H. Marcus, Project Director Project Directorate III-3 Division of Reactor Projects III/IV Office of Nuclear Reactor Regulation.
Attachment:
Changes to the Technical Specifications Date of issuance: May 18, 1995 i
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ATTACHMENT TO LICENSE AMENDMENT NO. 210
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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 vertical. lines.
Remove Insert 3.5-1 3.5-1 3.5 3.5-3 3.5-5 3.5-5 3.5-6 3.5-6 3.5-12 3.5-12 3.5-23 3.5-23 3.8-6 3.8-6 i
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DAEC-1 LIMITING CONDITION FOR OPERATION SURVEILLANCE REQUIREMENT 3.5 CORE AND CONTAINMENT COOLING 4.5 CORE AND CONTAINMENT COOLING
. SYSTEMS SYSTEMS Acolicability:
Acolicability:
l Applies to the operational status Applies to the Surveillance of the core and suppression pool Requirements of the core and cooling subsystems, suppression pool cooling subsystems which are required when the corresponding Limiting Condition.for Operation is in effect.
Obiective:
Ob.iective:
To assure the operability of the To verify the operability of the core and suppression pool cooling core and suppression pool cooling subsystems under all conditions subsystems under all conditions for which this cooling capability for which this cooling capability is an essential response, is an essential response to station abnormalities.
Specification:
Soecification:
A.
Core Sorav and LPCI Subsystems A.
Core Sorav and LPCI Subsystems 3.
Both core spray subsystems shall I.
Core Spray Subsystem Testing.
be OPERABLE whenever irradiated fuel is in the vessel'and prior 11gm Freauency to reactor startup from a COLD CONDITION, except as specified in a.
Simulated Annual 3.5.A.2 and 3.5.G.3 below.
Automatic Actuation test.
b.
Pump As specified in Operability the IST Program c.
Motor-As specified in Operated the IST Program Valve Operability 210 Amendment No. 443 4607 3.5-1 7
DAEC-1 LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS 3.
The LPCI Subsystem shall be 3.
LPCI Subsystem Testing shall be OPERABLE whenever irradiated fuel as follows:
is in the reactor vessel, and prior to reactor startup from a llam Freauency COLD CONDITION, except as specified in 3.5. A.4, 3.5.A.5 and a.
Simulated Annual 3.5.G.3 below.
Automatic Actuation Test b.
Pump As specified in Operability the IST Program c.
Motor Operated As specified in Valve the IST Program Operability d.
Pump Flow Rate Once/3 months Three LPCI pumps shall deliver 14,400 gpm against a system head corresponding to a vessel pressure of 20 psig based on individual pump tests.
e.
Once per shift visually inspect and verify that RHR valve panel lights and instrumentation are functioning normally.
4.
With one RHR (LPCI) pump inoperable, provided the remaining RHR (LPCI) active components, both Core Spray subsystems, the containment spray subsystem, and the diesel generators are verified to be OPERABLE, restore the inoperable RHR (LPCI) pump to OPERABLE status within 30 days.
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AMENDMENT NO.139r160,174,200, 210 3.5-3
DAEC-1 LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS C.
Residual Heat Removal (RHR) Service C.
Surveillance of the RHR Service Water System Water System 1.
Except as specified in 3.5.C.2, 1.
Surveillance of the RHR service 3.5.C.3, 3.5.C.4, and 3.5.G.3 water system shall be as follows:
below, both RHR service water subsystem loops shall be operable RHR Service Water Subsystem whenever irradiated fuel is in the Testing-reactor vessel and' reactor coolant temperature is greater than 212*F.
11gm Freauency a.
Pump and Motor As specified in operated valve the IST Program operability.
b.
Flow Rate after major Test-Each pump RHR service maintenance water pump and every 3 shall deliver months at least 2040 gpm at a TDH of 610 ft. or more.
2.
With one RHRSW pump inoperable, provided the remaining active components of both RHRSW subsystems are verified to be OPERABLE, restore the inoperable pump to OPERABLE status within 30 days or be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD SHUTDOWN within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
3.
With one RHRSW pump in each subsystem inoperable, provided the i
remaining active components of both RHRSW subsystems and the diesel generators are verified to be OPERABLE, restore at least one inoperable pump to OPERABLE status within 7 days or be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD SHUTDOWN within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
AMENDMENT fl0. 403,439,170,174 199-210 3.5-5 7
DAEC-1 LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS 4.
With one RHRSW subsystem inoperable, provided the remaining RHRSW subsystem and its associated j
diesel generator are verified to be OPERABLE, restore the inoperable system to OPERABLE status with at least one OPERABLE pump within 7 days or be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in
. COLD SHUTDOWN within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
D.
HPCI Subsystem D.
HPCI Subsystem 1.
The HPCI Subsystem shall be 1.
HPCI Subsystem testing shall be OPERABLE whenever there is performed as follows:
irradiated fuel in the reactor vessel, reactor pressure is greater 11gm Frecuency than 150 psig, and prior to reactor startup from a COLD CONDITION, a.
Simulated Annual except as specified in 3.5.D.2 Automatic below.
Actuation Test b.
Pump As specified in Operability the IST Program c.
Motor Operated As specified in Valve the IST Program Operability d.
At rated reactor Once/3 Months pressure demonstrate ability to deliver rated flow at a discharge pressure greater than or equal to that pressure required to accomplish vessel injection if vessel pressure were as high as 1040 psig, i
AMENDMENT NO. +1hl43716hif4199-210 3.5-6 7
DAEC-1 LIMITING CONDITION FOR OPERATION SURVEILLANCE REQUIREMENT J.
fLiver Water Sunoly System J.
River Water Supolv System 1.
Except as specified in 3.5.J.2 1.
River Water Supply System Testing:
below, at.least one pump in each river water supply system loop 1.tas frecuency shall be OPERABLE whenever irradiated fuel is in the reactor a.
Simulated Once/ operating vessel and reactor coolant automatic cycle temperature is greater than 212*F.
actuation test.
4 b.
Pump and motor As specified in operated valve the IST Program operability.
c.
Flow Rate Test Each river After major pump water supply maintenance and system pump once per shall deliver 3 months at least 6000 gpm at TDH Daily when river of 46 ft, or elevation is more.
less than 727 feet.
d.
Operating Pump Flow Rate Demonstration Each Operating Daily River Water Supply System Pump shall deliver at least 6000 gpm.
2.
With one river water supply loop inoperable, provided the other river water supply loop and its associated diesel generator are verified to be OPERABLE, restore at least one pump in the inoperable loop to OPERABLE status within 7 days or be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD SHUTDOWN within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
3.5-12 Amendment No. 70rL39443rgop210
DAEC-1 4.5 BASES Core and Containment Cooling Systems Surveillance Frequencies The testing interval for the core and containment cooling systems is based on industry practice, quantitative reliability analysis, judgement and practicality.
The core cooling systems have not been designed to be fully testable during operation.
For example, in the case of the HPCI, automatic initiation during power operation would result in pumping cold water into the reactor water vessel which is not desirable.
Complete ADS testing during power operation causes an undesirable loss-of-coolant inventory. To increase the availability of the core and containment cooling systems, the components which make up the system, i.e., instrumentation, pumps, valves, etc., are tested frequently.
The test intervals are based upon Section XI of the ASME Code. A simulated automatic actuation test once per year combined with frequent tests of the pumps and injection valves is deemed to be adequate testing of these systems.
When components and subsystems are out-of-service, overall core and containment cooling reliability is maintained by evaluating the operability of the renaining equipment.
The degree of evaluation depends on the nature of the reason for the out-of-service equipment.
For routine out-of-service periods caused by preventative maintenance, etc., the evaluation may consist of verifying the redundant equipment is not known to be inoperable and applicable surveillance intervals have been satisfied.
However, if a failure due to a design deficiency caused the outage, then the evaluation of operability should be thorough enough to assure that a generic problem does not exist.
The RHR valve power bus is not instrumented.
For this reason surveillance requirements require once per shift observation and verification of lights and instrumentation operability.
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Amendment No. ed43d60d?+, 210 3.5-23 i
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,- ' c,5 DAEC-1 LIMITING' CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS
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4, E.
Emeraency-Service Water System E.
Emeroency Service Water System
- 1..Except as required in Specification
-1.
Emergency Service Water System 3.8.E.2 below, both Emergency surveillance shall be as follows:
Service Water System loops shall be OPERABLE whenever irradiated fuel a.
Simulated auto once/
is in the reactor vessel and matic actuation OPERATING CYCLE I:
reactor coolant-temperature is test.
1 greater than 212*F.
b.
Pump and motor As specified in p
operated valve the IST Program
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c.
Flow Rate Test Each Emergency After major pump Service Water maintenance and pump shall once per 3 months, deliver at except weekly least that flow during periods of determined from time the river Figure 4.8.E-1 water temperature for the exceeds 80'F.
existing river water temperature.
2.
With one of the Emergency Service 2.
With one Emergency Service Water Water System pumps or loops System pump or loop inoperable, the inoperable, REACTOR POWER OPERATION OPERABLE pump and loop shall be must-be limited to seven days verified to be OPERABLE.
In unless OPERABILITY of that system addition, the requirements of is restored within this period.
Specification 4.5.G.1 shall be met.
During such seven days all active components of the other Emergency Service Water System shall be OPERABLE, provided the requirements of Specification 3.5.G are met.
3.
If the requirements of Specification 3.8.E cannot be met, be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD SHUTDOWN within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
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Amendment No.10,32,139d43d40d9h 10 3.8-6 2
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