ML20071H062

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Amend 90 to License NPF-62,changes TS 3/4.4.3.1., RCS Leakage Lds, to Permit Continued Plant Operation W/Inoperable Drywell Floor Drain Sump Flow Rate Monitoring Instrumentation
ML20071H062
Person / Time
Site: Clinton Constellation icon.png
Issue date: 07/08/1994
From: Hannon J
Office of Nuclear Reactor Regulation
To:
Shared Package
ML20071H068 List:
References
NUDOCS 9407130310
Download: ML20071H062 (5)


Text

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(Q *t0y li 3 r)m 2

UNITED STATES l 's NUCLEAR REGULATORY COMMISSION v

W ASHINGTON. D.C. 20555 4 01 ILLIN0IS POWER COMPANY. ET AL.

DOCKET NO. 50-461 CLINTON POWER STATION. UNIT NO. 1 AMEN 0 MENT TO FACILITY OPERATING LICENSE Amendment No. 90 License No. NPF-62 l.

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 20, 1994, 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. lhe 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 h:ve 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. NPF-62 is hereby amended to read as follows:

  • lllinois Power Company is authorized tr act as agent for Soyland Power Cooperative, Inc. and has exclusive responsibility and control over the physical construction, operation and maintenance of the facility.

9407130310 94070s PDR ADOCK 05000461 P

PDR

. (2) Inchnical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A and the Environmental Protection Plan contained in Appendix B, as revised through Amendment No.

90, 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 John N. Hannon, Director Project Directorate 111-3 Division of Reactor Projects - Ill/lV Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications Date of Issuance: July 8, 1994

1 ATTACliMENT TO LICENSE AMENDMENT N0. 90 fAcIllTY OPERATING LICENSE NO. NPF-62 Q.0CKET NO. 50-461 Replace the following page of the Appendix "A" Technical Specifications with the attached page.

The revised page is identified by amendment number and contains vertical lines indicating the area of change.

The corresponding overleaf page, indicated by an asterisk, is provided to maintain document completeness.

Remove Panes Insert Paaes 3/4 4-12 3/4 4-12 3/4 4-12a*

3/4 4-12a*

i

=.

REACTOR COOLANT SYSTEM 3/4.4.3 REACTOR COOLANT SYSTEM LEAKAGE LEAKAGE DETECTION SYSTEMS LIMITING CONDITION FOR OPERATION 3.4.3.1 The following reactor coolant system leakage detection systems shall be OPERABLE:

The drywell atmosphere particulate radioactivity monitoring system, a.

b.

The drywell sump flow monitoring system, and c,

Either the drywell atmosphere gaseous radioactivity monitoring system or the drywell air coolers condensate flow rate monitoring system.

APPLICABILITY:

OPERATIONAL CONDITIONS 1, 2, and 3.

AlllD!i:

With only two of the above required leakage detection systems OPERABLE, operation may continue for up to 30 days when the drywell atmosphere a.

particulate radioactivity monitoring system is inoperable provided grab samples of the drywell atmosphere are obtained and analyzed at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

b, operations may continue:

1.

with the drywell equipment drain sump flow monitoring subsystem inoperable provided the drywell equipment drain sump flow rate is monitored and determined by alternate means at least once per 12

hours, 2.

for up to 30 days' with the drywell ficor drain sump flow monitoring subsystem inoperable provided the drywell floor drain sump flow rate is monitored and determined by alternate means at least once per 8

hours, c.

operation may continue for up to 30 days when the drywell atmosphere gaseous radioactivity monitoring system and the drywell air coolers condensate flow rate monitoring system are inoperable provided grab samples of the drywell atmosphere are obtained and analyzed at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

Otherwise, 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 />.

' Operation may continue af ter July 10, 1994, until the next COLD SHUTDOWN, provided the drywell floor drain sump flow rate is monitored and determined by alternate means at least once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />. Additionally, the drywell atmosphere particulate and gaseous radioactivity monitoring systems may be periodically taken out-of-service to perform scheduled preventive maintenance, surveillances and testing without entering the shutdown requirements of the ACTION statement.

CLINTON - UNIT 1 3/4 4-12 Amendment No. 65,g3,90

__m.

REACTOD COOLANT SYSTEM

)!4.8.3 REACTOR COOLANT SYSTEM LEAR. AGE LEArJS! DETECTION SYSTEMS SURVEILLANCE RE0VIREMENTS 4.4.3.)

The reactor coolant system leakage detection systems shall be demon-strated OPERABLE by:

I Drywell atmosphere particulate and gaseous monitoring systems-performance a.

of a CHANNEL CHECK at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, a CHANNEL FUNCTIONAL TEST at least once per 31 days and a CHANNEL CALIBRATION at least once per 18 months.

b.

Drywell sump flow monitoring system-performance of a CHANNEL FUNCTIONAL TEST at least once per 31 days and a CHANNEL CAllBRATION TEST at least once per 18 months.

Drf. ell air cooler condensate flow rate monitoring system performance-of a C-Y.E. FUNCTIONAL TEST at least once per 31 days and a CHANNEL CAllBRATION least once per 18 months.

a F10. testing the drywell floor drain sump inlet piping for blockage at d.

least once every 18 months during shutdown, CLINTON - UNIT 1 3/4 4-12a Amendment No. 65 J3 21 liS2