ML20070D748
| ML20070D748 | |
| Person / Time | |
|---|---|
| Site: | Clinton  |
| Issue date: | 02/22/1991 |
| From: | Hannon J Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20070D750 | List: |
| References | |
| NUDOCS 9103010137 | |
| Download: ML20070D748 (5) | |
Text
3 t.p@ ttouq jo, UNITED STATES
[.
3.c, (
y NUCLEAR REGULATORY COMMISSION
.L
- - l W ASHW3 TON, D. C. 20555 t
a 4....*
ILLINDIS POWER COMPANY, ET AL2 DOCKET NO. 50-461 CLINTON POWER STATION, UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 57 License No. NPF-62 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by 1111nois Power Company * (IP),
and Soyland Power Cooperative, Inc. (the licensees) dated January 18, 1991, complies with the standards aad 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 Connission'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 as follows:
- Illinois Power Company is authorized 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.
9103010137 910222 PDR ADDCK 0S000461 P
=-.
2 (2) Technical 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. 57
, 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
/
L John N. Hannon, Director Project Directorate 111-3 Division of Reactor Projects lil/IV/V
Attachment:
Changes to the Technical Specifications Date of issuance: February 22, 1991
s ATTACHMENT TO LICENSE AMENDMENT NO. 57 FACILITY OPERATING LICENSE NO. NPF-62 DOCKET NO. 50-461 Replace the following page of the Appendix "A" Technictil 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 is provided to maintain document completeness.
Remove Insert 3/4 6-2 3/4 6-2
+.r..
3/4.6 CONTA1NMENT SYSTEMS 3/4.6.1 PR,IMARY CONTAINMENT PRIMARY CONTAINMENT INTEGRITY LIMITING CONDITION FOR OPERATION 3.6.1.1 PRIMARY CONTAINMENT INTEGRITY shall be maintained.
APPLICABILITY: OPERATIONAL CONDITIONS 1, 2*, and 3.
ACTION:
Without PRIMARY C0hTAINMENT INTEGRITY, restore PRIMARY CONTAINMENT INTEGRITY within I hour or be in at least HOT SHUT 00VN 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 />.
I l
SURVEILLANCE REQUIREMENTS i
l 4.6.1.1 PRIMARY CONTAINMENT INTEGRITY shall be demonstrated:
After each closing of each penetration subject tt Type B testing, except a.
the primary containmsnt air locks, if opened following Type A or B test, by leak rate testing the seals with gas at Pa, 9.0 psig, and verifying i
i that when the measured leakage rate for these seals is added to the leakage rates determined pursuant to Surveillance Requirement 4.6.1.2.d l
i for all 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 detetivated 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 !s in compliance with the requirements of Specification 3.6.3.1.
l l
l
- See 3pecial Test Exception 3.10.1
- 2xcept valves 1HG016 and 1HG017 and valves, blind flanges, and deactivated automatic valves which are located inside the primary containment, steam l
tunnel, or drywell, and are, locked, sealed or otnerwise 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 l
CONTAINMENT' SYSTEMS PRIMARY CONTAINMENT LEAKAGE LIMITING CONDITION-FOR OPERATION 3.6.1.2 Primary cor.tainment-leakage rates shall.be limited to:
a.
An overall integrated leakage rate of less than or equal to:
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 /> at Pa, 9.0 psig.
b.# A combined leakage rate 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 Table 3.6.4-1 of Specification 3.6.4 as secondary :ontain-ment bypass leakage 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:
With:
a.
The measured overall integrated primary containment leakage rate exceeding 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 c.
The measured leakage rate exceeding 28 scf per hour for any one main steam 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 e.
The measured combined. leakage rate for all containment isolation valves in 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.
- The leakage-rates of valves IP.U-F032A and B are not required to be included until startup from the third refueling outage in accordance with an approved exemption to Appendix J of 10 CFR50.
- The leakage rates of_ valves IB21-F032A and B are not required to be included
-until startup from the third refueling outage.
l l:
CLINTON - UNIT 1 3/4 6-2 Amendment No. 57
- -