ML20065N908
| ML20065N908 | |
| Person / Time | |
|---|---|
| Site: | Clinton  |
| Issue date: | 12/11/1990 |
| From: | Hannon J Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20065N910 | List: |
| References | |
| NUDOCS 9012120358 | |
| Download: ML20065N908 (7) | |
Text
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UNITED $TATES
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ILLINOIS POWER COMPANY, ET AL.
LOCKET NO. 50-461 CLINTON POWER STATION, UNIT NO. 1 MENDMENT TO FACILITY OPERATING LICENSE Amendment No.56 License No. NPF-62 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Illinois Power Company * (IP),
and Soyland Power Cooperative, Inc. (the licensees) dated June 30, 1989, complies with tie standards and re Energy Act of 1954, as amended (the Act)quirements of the Atomic
, and the Comission'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 Comission; C.
There is reasonable assurance (1) 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 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 Specif1-cations as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. NPF-62 is hereby amended to read as follows:
- Illinois Power Company is authorized to act as agent for Scyland Power Cooperative, Inc. and has exclusive responsibility and control over-the physical construction, operation and maintenance of the facility.
9012120358 901211 PDR ADOCK 05000461 P
(2) Technical Specifications and Lnvironmental Protection Plan The Technical Specifications contained in Appendix A and the Environmental Protection Plan contained in Appendix B, as revised through Amendment No. 56, are hereby incorporated into this license.
Illinois Power Company shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
3.
This license amendment is effective as of its date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION kh M John N. Hannon, Director Project Directorate III-3 Division of Reactor Projects - III, IV, V and Special Projects Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of issuance:
December 11, 1990 1
k ATTACHMENT TO LICENSE AMENDMENT NO. 56 FACILITY OPERATING LICENSE NO. NPF-62 DOCKET _NO. 50-461 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.
Remove In, sert 3/4 5-5 3/4 5-5 3/4 9-17 3/4 9-17 3/4 9-18 3/4 9-18 J
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EMERGENCY CORE COOLING SYSTEMS 3/4.5.2 ECCS - SHUTDOWN LIMITING CONDITION FOR OPERATION 3.5.2 At least two of the following shall be OPERABLE and capable of being powered from a diesel generator of Specification 3.8.1.2.b.
a.
The low pressure core spray (LPCS) system with a flow path capable of taking suction from the supprossion pool and transferring the water through the spray sparger to the reactor vessel.
b.
Low pressure coolant injection (LPCI) subsystem "A" of the RHR system with a flow path capable of taking suction from the suppression pool and trans-ferring the water to the reactor vessel.
c.
Low pressure coolant injection (LPCI) subsystem "B" of the RHR system with a flow path capable of taking suction from the suppression pool and trans-ferring the water to the reactor vessel, d.
Low pressure coolant injection (LPCI) subsystem "C" of the RHR system with a flow path capable of taking suction from the suppression pool and trans-ferring the water to the reactor vessel, e.
The high pressure core spray (HPCS) system with a flow path capable of taking suction from one of the following water sources and transferring the water through the spray sparger to the reactor vessel:
1.
From the suppression pool, or 2.
When the suppression pool level is less than the limit or is drained, from the RCIC storage tank containing at least 125,000 available gallons of water, equivalent to a level of 95%.
APPLICABILITY:
OPERATIONAL CONDITIONS 4 and 5*,
ACTION:
a.
With one of the above required subsystems / systems inoperable, restore at least two subsystems / systems to OPERABLE status within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> or suspend all operations that have a potential for draining the reactor vessel.
The provisions of Specification 3.0.4 are not appiicable.
b.
With both of the above required subsystens/ systems inoperable, suspend CORE ALTERATIONS and all operations that have a potential for draining the reactor vessel.
Restore at least one subsystem / system to OPERABLE status within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> or establish PRIMARY CONTAINMENT INTEGRITY within the next 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.
- The ECCS is not required to be OPERABLE provided that the reactor vessel head is removed, the cavity is flooded, the reactor cavity to steam dryer pool gate is open and water level in these upper containment pools is maintained within the limits of Specification 3.9.8 and 3.9.9.
CLINTON - UNIT 1 3/4 5-5 Amendment No. 56 l
KRGENCYCORECOOLINGSYSTEMS ECCS - SHUTDOWN SURVEILLANCE REQUIREMENTS 4.5.2.1 At least the above required ECCS shall be demonstrated OPERABLE per Surveillance Requirement 4.5.1.
4.5.2.2 The HPCS system shall be determined OPERABLE at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> by verifying the RCIC storage tank required volume when the RCIC storage tank is required to be OPERABLE per Specification 3.5.2.e.
CLINTON - UNIT 1 3/4 5-6 l
REFUELING OPERATIONS 3/4.9.11 RESIDUAL HEAT REMOVAL AND COOLANT CIRCULATION HIGH WATER LEVEL LIMITING CONDITION FOR OPERATION 3.9.11.1 At least one shutdown cooling mode loop of the residual heat removal (RHR) system shall be OPERABLE and in operation
- with at least:
a.
One OPERABLE RHR heat exchanger.
APPLICABILITY:
OPERATIONAL CONDITION 5, when irradiated fuel is in the reactor vessel and the water level is greater than or equal to 23 feet above the top of the reactor pressure vessel flange.
ACTION:
a.
With no RHR shutdown cooling --de OPERABLE, within one hour and at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> thereafter, demonstrate the operability of at least one alternate method capable of decay heat removal. Otherwise, suspend all operations involving an increase in the reactor decay heat load and establish SECONDARY CONTAINMENT INTEGRITY within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />, b.
With.no RHR shutdown cooling mode loop in operation, within one hour establish reactor coolant circulation by an alternate method and monitor reactor coolant temperature at least once per hour.
c.
The provisions of Specification 3.0.4 are not applicable.
l SURVEILLANCE REQUIREMENTS 4.9.11.1 At least one shutdown cooling mode loop of the residual heat removal system or alternate method shall be verified to be in operation and circulating reactor coolant at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
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- The shutdown cooling loop may be removed from operation for up to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> per 8-hour period.
CLINTON - UNIT 1 3/4 9-17 Amendment No. 56 t.
REFUELING OPERATIONS LOW WATER LEVEL LIMITING CONDITION FOR OPERATION 3.9.11.2 -Two shutdown cooling mode loops of the residual heat removal-(RHR) system shall be OPERABLE and at least one loop shall be in operation
- with each train consisting of at least:
. a.
One OPERABLE RHR heat exchanger.
APPLICABILITY: - 0PERATIONAL CONDITION 5, when irradiated fuel is in the reactor vessel and the water level is less than 23 feet above the top of the reactor pressure vessel flange.
ACTION:
a.
With less than the above required shutdown cooling mode loops of the RHR system OPERABLE, within one hour and at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> thereaf ter, demonstrate the operability of at least one alternate method capable of decay heat removal.for each inoperable RHR shutdown cooling mode train.
b.
With no RHR shutdown cooling mode loop in operation, within one hour establish reactor coolant circulation by an alternate method and monitor reactor coolant temperature at least once per hour.
c.
The provisions of Specification 3.0.4 are not applicable.
l SURVEILLANCE REQUIREMENTS 4.9.11.2 -At least one shutdown cooling mode-loop of the resivaal heat removal system or' alternate method shall be verified to L9 in_ operation and circulating reactor coolant at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
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- The shutdown cooling pump may_be removed from operation for up to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> per l
8-hour period.
CLINTON - UNIT 1 3/4 9-18 Amendment No 56 -
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