ML20058E232
| ML20058E232 | |
| Person / Time | |
|---|---|
| Site: | Clinton  |
| Issue date: | 11/01/1990 |
| From: | Hannon J Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20058E236 | List: |
| References | |
| NUDOCS 9011070087 | |
| Download: ML20058E232 (6) | |
Text
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uq[0, UNITED STATES
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' {',3 NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20656
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ILLINDIS POWER COMPANY, ET AL.
L DOCKET NO. 50-461 CLINTON POWER STATION, UNIT NL. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 52
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License No. NPF-62 i
L 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by 1111nois power Company * (IP),
andSoylandPowerCooperative,Inc.(thelicensess) dated November 20, 1989 complies with the standards and requirements of l
the Atomic Energy Act of 1954, as amended (the Act), and the Com-mission'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 i
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.1 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.
AccordinglyIndicatedintheattachmenttothislicenseamendment,andthe license'is 2.
cations as paragraph 2.C.(2) of_ Facility Operating License No NPF-62 is hereby amended to read as follows:
L
- Illinois Power Company is authorized to act as agent for Soyland Power Cooperative, Inc. and has exclusive responsibility and control over the L
physical construction, operation and maintenance of the facility.
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9011070087 901101 PDR ADOCK 05000461 P
PNV
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(2) Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A and the i
Environmental Protection Plan contained in Appendix B, as revised through Amendment No. 52, are hereby incorporated into this license.
Illinois Power Company shall operate the facility in accordance with the Technical Specifications and the tuvironmental Protection Plan.
3.
This license amendment is effective as of its date of issuance.
FOR THE NUCLEAR REGULATORY COMMIS$10N John N. Hannon, Director Project Directorate 111 3 Division of Reactor Projects. III, IV, V and Special Projects Office of Nuclear Reactor Regulation Attachnent:
Changes to the Technical Specifications E
- Date of Issuance: November 1, 1990 u
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SG.
ATTACHMENT TO LICENSE AMENDMENT NO. 52 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. Overleaf pages are provided to maintain document completeness.
Remove Insert 3/4 3-103 3/4 3-103 B 3/4 3-9 B 3/4 3-9
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INSTRUMENTATION 3/4.3.10 NUCLEAR SYSTEM PROTECTION SYSTEM - SELF TEST SYSTEM LIMITING CONDITION FOR OPERATION 3.3.10.The SELF TEST SYSTEM (STS) of the Nuclear System Protection System shall be OPERABLE and operating in the fully automatic mode.*
APPLICABILITY:
OPERATIONAL CONDITIONS 1, 2, 3, 4, and 5.
ACTION:
I With the STS not operating in the fully automatic mode, initiate action a.
within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> to restore the STS to automatic operation for the maximum number of divisions available, and 1.
In OPERATIONAL CONDITION 1, 2 or 3:
i a)
Restore the STS to fully automatic operation within 30 days, or i
b)
Within the next 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> and at least once per 7 days i
thereafter, operate the STS manually to perform all required tests not being performed in the automatic mode until the STS is restored to fully automatic operation, 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 />; 2.
In OPERATIONAL CONDITION 4 or 5:
a)
Restore the STS to fully automatic operation within 90 days, or b)
Within the next 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> and at least once per 90 days thereafter, operate the STS manually to perform all required tests not being performed in the automatic mode until the STS e
is restored to fully automatic operation, Otherwise, suspend CORE ALTERATIONS and all operations with a
-potential for draining the reactor vessel, verify all insertable L
control rods to be fully inserted and lock the reactor mode switch in the Shutdown position within one hour, b.
The provisions of-Specification 3.0.4 are not applicable.
SURVEILLANCE REQUIREMENTS:
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4.3.10 Status indications of the STS shall be obtained at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, whenever the STS is operating in the fully or partially automatic j
mode.
- The STS may be periodically taken.out of the fully automatic mode of operation l
for up to 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> for the purpose of performing surveillance testing and pre-ventative or corrective maintenance to satisfy technical specification requirements for those components the STS is designed to monitor.
CLINTON - UNIT 1 3/4 3-103 Amendment No.
- , 52
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INSTRUMENTATION BASES 3/4.3.9 PLANT SYSTEMS ACTUATION INSTRUMENTATION (Continued) fluctuations are accounted for in the trip setpoints and allowable values speci-fled for drywell and containment pressure-high.
A 10-minute minimum, 13-minute maximum time delay exists between initiation of LPCI and containment spray actuation.
A high reactor water level, level 8, signal will actuate the feed-water system / main turbine trip system.
The suppression pool makeup system is automatically initiated on a low low suppression pool water level signal with a concurrent LOCA signal or following a specified time delay after receipt of a LOCA signal, 3/4.3.10 NUCLEAR SYSTEM PROTECTION SYSTEM - SELF TEST SYSTEM This specificatior; provides the limiting conditions for operation necessary to preserve the STS's ability to perform its intended function of detecting and determining the location of a fault in the functional NSPS.
The Self Test Systea (STS) is an overlay testing and surveillan",e subsystem which provides the capability to continuously and automatica11;r perform testing of all active circuitry within the NSPS panels, essential to t te safe shutdown of the reactor.
The primary purpose of the STS is to enhance the availability of the NSPS by optimizing the time to detect and determine tho location of a failure in the functional system.
Each of the four NSPS cabinets, with one cabinet associated with each of the four Class IE powered NSP', divisions, con-tains its owr. controller (STC).
The STS will be used for post-maintenance test-ing and to augment conventional testina methods which include CHANNEL CHECKS, CHANNEL FUNCTIONAL TESTS, CHANNEL CALIBRATIONS, RESPONSE TIME TESTS and LOGIC SYSTEM FUNCTIONAL TESTS.
Under the provision of the ACTION statement, with the STS. inoperable or not operating in the fully automatic mode of operation, 30 days is allowed to restore the STS to fully automatic operation during OPERATIONAL CONDITIONS 1, 2, 3; 90 days is allowed during OPERATIONAL CONDITIONS 4, 5.
Additionally, the ACTION includes an allowance for manually operating the STS to perform testing equivalent to that which is normally performed during automatic operation if the STS cannot be restored to fully automatic operation within the required time limits.
Manual STS testing is required to be performed at least once per 7 days during OPERATIONAL CONDITIONS 1, 2, 3 and at least once per 90 days dJring OPERATIONAL CONDITIONS 4, 5.
These frequencies and the above allowed out-of-service times have been shown by analysis to be acceptable for supporting adequate overall availability of the NSPS. Maintaining the STS in a partially automatic mode as much as possible (whenever it is not operating in the fully automatic mode) provides further enhancement of the NSPS availability.
CLINTON - UNIT 1 8 3/4 3-9 Amendment No.52
d.
I o007 NOTE: SCALE IN INCHES ASOVE VEBSEL ZERO WATER LEVEL NOMENCLATUlf, 000 MinGHT A'irVE VES6F',2ERO NO.
.m.1 READING
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(.i t.n. 2
. 2.0 722.76 - WSSEL -
EONOI 4
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700 (3) 529.52
+ 8.9 (2) 476.12
-45.8 (1) 375.12
-145.5 660
- F "'.6 - MAIN STEA UNE 400 = =
C
DS) + 82.0
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(8)
- 30,0 HIGH LEVEL ALARM (4) + 30.4 LOW LEVEL ALARM INSTRUMENT (3)
- 8.9 REACTOR SCRAM
- 520.62 0-
-- 0 IERO CONThatVTE TO AOS FEED 483.6 (2)-46.8 WATER
=
= INITIATE RCIC
-466.0 - CORE HPCS, TRIP RECIRC PUMPS, SPRAY CLOSE PRIMARY SYSTEM 460 - -
ISO VLV EXCEPT RHR SHUTDOWN ISO VLV AND MSIVs 400 - -
(1) -146.5 C
-160-INITIATE RHR. CS START DIESEL 350 -"5358.66 CONTRituTE TO ADS, CLost MsiVs 300 ACTIVE FUEL 260 goo
- 20s.66, eg
-# RECiRC
- "15 l
- OUTLET tes.s -
NO22LE q N0Z2LE 150 100 60 1
Bases Figure B 3/4.31 Reactor Vessel Water Level t
CLINTON-UNIT 1 B 3/4 310 1