ML20065E629
| ML20065E629 | |
| Person / Time | |
|---|---|
| Site: | Clinton  |
| Issue date: | 09/18/1990 |
| From: | Hannon J Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20065E635 | List: |
| References | |
| NUDOCS 9010020241 | |
| Download: ML20065E629 (5) | |
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ILLIN0IS POWER COMPANY, ET AL.
DOCKET NO. 50-461 CLINTON POWER STATION, UNIT NO. 1
. AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 46 License No. NPF-62 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
'The application for amendment by Illinois Power Company * (IP),
and Soyland Power Cooperative, Inc. (the licensees) dated November 20, 1989 complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Comissior's rules and regulations set forth in 10 CFR Chapter I; B.
The facility will operate in conformity with the arplication, the provisions.of the Act, and the rules and regulatirAs of the Comission; 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 Comission's regulations; D.
The issuance of-this amendment will not be-inimical-to the comon 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 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 ts followsi
- Illinois Power Company is auttorized to act as agent for Soyland Power Cooperative, Inc. and has exclusive responsibility and control over the physical construction, operation and maintenance of the facility.
9010020241 9009 3 ADOCK 0500 1
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- (2) Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A and the
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Environmental Protection Plan contained in Appendix B, as-revised through Amendment No. 46
, 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 79
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Jchn N. Hannon, Director Project Directorate III-3 Division of Reactor Projects - III, IV, Y and Special Projects ~
Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications
.Date of issuance: September 18, 1990 1
I
l ATTACHMENT TO LICENSE AMENDMENT NO. 46 FACILITY OPERATING LICENSE NO. NPF-62 DOCKET NO. 50-461 Replace the following > ages of the Appendix "A" Technical Specifications with the attached pages. T1e revised pages are identified by amendment number and contain vertical lines indicating the area of change.
Corresponding overleaf pages are. provided to maintain document completeness.
Remove Insert 3/4 6-1 3/4 6-1
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'I 3/4.6 CONTAINMENT SYSTEMS 3/4.6.1 PRIMARY CONTAINMENT PRIMARYCONTAINMENTINTEGR'TJ LIMITING CONDITION FOR OPERATION
- 3. 6.1.1 PRIMARY CONTAINMENT INTEGRITY shall be maintained.
APPLICABILITY:
OPERATIONAL CONDITIONS 1, 2*, and 3.
ACTION:
Without PRIMARY CONTAINMENT INTEGRITY, restore PRIMARY CONTAINMENT INTEGRITY within I hour 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 />.
SURVEILLANCE REQUIREMENTS
- 4. 6.1.1 PRIMARY CONTAINMENT INTEGRITY shall be demonstrated:
After each closing of each penetration subject to Type B testing, except a.
the primary containment air locks, if opened following Type A or B-test, by '"k rate testing the seals with gas at Pa, 9.0 psig, and verifying tha' > 'n the measured leakage rate for these seals is added to the leaktg ates determined pursuant to Surveillance Requirement 4.6.1.2.d for ali other Type B and C penetrations, the combined leakage rate is less than or equal to 0.60 La.
b.
At least once per 31 days by verifying that all containment penetrations **
not capable of being closed by OPERABLE containment automatic isolation valves and required to be closed during accident conditions are closed by valves, blind flanges, or deactivated automatic valves secured in position, except as provided-in Table 3.6.4-1 of Specification 3.6.4.
By verifying each primary containment air lock is in compliance with the c.
requirements of Specification 3.6.1.3.
d.
By' verifying the suppression pool is in compliance with the requirements of Specification 3.6.3.1.
- See Special Test Exception 3.10.1
- Except valves.1HG016 and 1HG017 and valves, blind flanges, and deactivated
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automatic valves which are located inside the primary containment, steam-tunnel, or drywell, and are locked, sealed or otherwise secured in the closed position.
These penetrations shall be verified closed during each COLD SHUTDOWN except such verification need not be performed more often than once per 92 days,
.CLINTON - UNIT 1 3/4 6-1 Amendment No. 46
CONTAINMENT SYSTEMS PRIMARY CONTAINMENT-LEAKAGE LIMITING CONDITION FOR OPERATION
- 3. 6.1. 2 Primary containment leakage rates shull be limited to:
An overall integrated leakage rate of less than or equal to:
a.
1.
La, 0.65% by weight of the containment air per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> ?t Pa, 9.0 psig.
b.
A combined leakage rete of less than or equal to 0.60 La, for all penetra-tions and all valves subject to Type B and C tests when pressurized to Pa, 9.0 psig.
c.*
Less than or equal to 28 scf per hour for any one main steam line through the isolation valves when tested at Pa, 9.0 psig.
d.
A combined leakage rate of less than or equal to 0.08 La, for all penetra-tions shown in Tabie 3.6.4-1 of Specification 3.6.4 as secondary contain-ment bypass leal. age paths when pressurized to Pa 9.0 psig, e.
A combined leakage rate of less than or equal to 1 gpm times the total number of containment isolation valves in hydrostatically tested lines per Table 3.6.4-1, which penetrate the primary containment, when tested at 1.10 Pa, 9.9 psig.
APPLICABILITY:
OPERATIONAL CONDITIONS 1, 2**, and 3.
ACTION:
' ith:
W The measured overall integrated primary containment leakage rate exceeding a.
0.75 La, or b.
The measured combined leakage rate for all penetrations and all valves subject to Type B and C tests exceeding 0.60 La, or The measured leakage rate exceeding 28 scf per hour for any one main steam c.
line through the isolation valves, or d.
The combined leakage rate for all penetrations shown in Table 3.6.4-1 as secondary containment bypass leakage paths exceeding 0.08 La; or The measured combined leakage rate for all containment isolation valves in e.
hydrostatically tested lines per Table 3.6.4-1 which penetrate the primary containment exceeding 1 gpm times the total number of such valves, restore:
- Exemption to Appendix J of 10 CFR 50.
- See Special Test Exception 3.10.1.
CLINTON - UNIT 1 3/4 6-2