ML20245K304
| ML20245K304 | |
| Person / Time | |
|---|---|
| Site: | Duane Arnold  |
| Issue date: | 08/15/1989 |
| From: | Hannon J Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20245K309 | List: |
| References | |
| NUDOCS 8908180391 | |
| Download: ML20245K304 (6) | |
Text
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g NUCLEAR REGULATORY COMMISSION -
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10WA ELECTRIC LIGHT AND POWER COMPANY CENTRAL IOWA POWER COOPERATIVE CORN BELT POWER COOPERATIVE DOCKET NO. 50-331 DUANE ARNOLD ENERGY CENTER AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.162 License No. DPh49
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The Nuclear Regulatory Comission (the Commission) has found that:
A.
The application-for amendment by Iowa Electric Light and Power Company, et'al., dated June 30, 1987 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; The facility w'the Act, and the rules and. regulations of theill-operate in confo B.
previsions of 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, ano (ii) that such activities will be conducted in compliance with the Comission's regulations; L
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; L-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 indicated in the attachment to this license amendment and paragraph 2.C.(2) of Facility Operating License No. DPR-49 is hereby smended to read as follows:
I a9081e0392 e90em hDR ADOCK 05000331 I
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L (2)'TechnicalSpecifications.
e The Technical Specifications. contained in Appendix A, as revised through Amendment No.162, 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 W
'/ John N. ' Hannon, Director Project Directorate III-3 Division of Reactor Projects - III, IV, V and Special Projects Office of Nuclear Reactor Regulation Attachnent:
Char.5es to the Technical Specifications Date of Issuance: August, 15, 1989
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' ATTACHMENT =TO LICENSE AMENDMENT NO. 162 h
FACILITY CPERATING LICENSE NO. DPR-49 0
DOCKET NO. 50-331 r.
Rep 16ce the following pages of the Appendix A Technical Specifications with the enclosed pages. The revised areas are. indicated by marginal lines.
Pages Remove-Insert-3.5-101 3'.5-10 3.5-10a-3.5-10a-23.5 3.5-23 t
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DAEC-1 a
LIMITING CONDITIONS FOR'0PERATION SURVEILLANCE REQUIREMENT that.the remaining diesel generator
-and all'the low pressure core and.
~ containment' cooling subsystems
' supported.by the OPERABLE diesel L
generator are OPERABLE.
If this L
requirement cannot be met, an orderly
. SHUTDOWN shall be initiated and the reactor shall be placed in the COLD.
SHUTDOWN Condition within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
,2_'Any combination of inoperable components in the' core and contain-ment cooling' systems shall not defeat the capability of-the remain-ing OPERABLE components to fulfill the cooling functions.
3.
When irradiated fuel is in the-reactor vessel and the reactor is
'in the COLD SHUTDOWN Condition or Refuel: Mode:
a.
If no. work is being performed
'which has the potential for draining the reactor vessel,
~both core spray and RHR systems may be inoperable; or b.
If work is being' performed which has the potential for draining the reactor vessel, at least two of any combination of core spray and/or RHR (LPCI or shutdown cooling mode) pumps shall be OPERABLE (including the capabil-ity to inject water into the reactor vessel with suction from the suppression pool) except as specified in Specification 3.5.G.3.b(1) and (2), below.
A diesel generator required for operation of at least one of these pumps shall be OPERABLE.
(1) With one of the two pumps inoperable, restore the inoperable pump to OPERABLE status within four hours or suspend all operations with a potentiat for draining the reactor vessel.
3.5-10 Amendment No. EJ,739, 162
DAEC-1
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LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENT.
(2) With botn pumps inoperable, i
suspend all operations with a potential for draining the reactor vessel.
4.
During a refueling outage, CORE ALTERATIONS may continue with the suppression pool volume below the minimum values specified in Specifi-cation 3.7.A.1 provided all of the following conditions are met:
.(a) The reactor head is removed, the cavity is flooded, the spent fuel pool gates are removed and spent fuel pool water level is maintained within the limits of Specifi-cation 3.9.C.
(b) At least one core spray subsystem is operable with suction aligned to the condensate storage tank (s).
(c)Thecondensatestoragetanks contain at least 75,000 gallons of water which is available to the core spray. subsystem.
Condensate storage tank (s) level shall be recorded at least every 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
(d) No work is being performed which has the potential for draining the reactor vessel.
5.
If the requirements of Specification 3.5.G.4 cannot be met, suspend CORE ALTERATIONS.
3.5-10a Amendment No. N,162 1
DAEC-1 4
G.
Minimum Low Pressure Cooling and Diesel Generator Availability The purpose of Specification G is to assure that adequite core cooling equipment is available at all times.
It is during refueling outages
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that major maintenance is performed and during such time that all low pressure core cooling systems may be out of service. This specifica-tion provides that should this occur, no work will be performed on the primary system which could 1 sad to draining the vessel. This work would include work on certain control rod drive components and
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recirculation system. Thus, the specification precludes the events I
which could require core cooling.
If work must be performed which
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has the potential for draining the vessel, Specification 3.5.G.3.b requires that certain low pressure core cooling subsystems be avail-
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able and capable of injecting water into the reactor vessel from the suppression pool water supply.
The condensate storage tanks are not considered to be an appropriate water suppy as they are not safety related and could provide makeup water for core cooling for only a finite period of time.
The makeup capability of either one core spray pump or one low pressure coolant injection (LPCI) pump is more than double the leakage rate expected from a postulated failure of the control rod velocity limiter section.
Since the systen cannot be pressurized during refueling, the potential need for core flooding only exists and the specified combination of the core spray or the LPCI system can provide this.
Specification 3.8 must also be consulted to determine other requirements for the diesel generators. To prevent extensive wear and stress on the diesel engines, the diesels are manually started and the speed incrementally increased to synchronous speed.
H.
Maintenance of Filled Discharge Pipe If the discharge piping of the core spray, LPCI subsystem, HPCI, and RCIC are not filled, a water hammer can develop 3.5-23 Amendment No US,162 w