ML20006E074
| ML20006E074 | |
| Person / Time | |
|---|---|
| Site: | Clinton  |
| Issue date: | 01/30/1990 |
| From: | Jocelyn Craig Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20006E075 | List: |
| References | |
| NUDOCS 9002160201 | |
| Download: ML20006E074 (5) | |
Text
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~k UNITED STATES F
I NUCLEAR REGULATORY COMMIS$10N
'h WASHINGTON, D. C. 20665 ILLINOIS POWER COMPANY. ET AL.
DOCKET NO. 50-461 CLINTON POWER STATION, UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 29 License No. NPF-62 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment by 111inois Power Company * (IP),
Soyland Power Cooperative, Inc., and Western Illinois Power Cooperative, Inc. (the licensees) dated October 30, 1987 complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), 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 authori:ed 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 Specifications asindicatedintheattachmenttothislicenseamendment,andparagraph2.C.(2) of Facility Operating License No. NPF-62 is hereby amended to read as follows:
Mllinois Power company is authorized to act as agent for Soyland Power Cooperative, Inc. and Western Illinois Power Cooperative, Inc. and has exclusive responsibility and control over the physical construction, operation and maintenance of the facility.
'9002160201 900130 ADOCK0500g1 PDR P
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Technica1Jpecifications i
i The Technical Specifications contained in Appendix A and the Environmental Protection Plan contained in Appendix B, as revised through Amendment No. 29. are hereby incorporated into this license. Illinois Power Company shall operate the facility in accordance with the Technical Specifications and the Environmental 2
Protection Plan, f
3.
This license amendment is effective as of its date of issuance.
OR THE NUCLEAR REGULATORY COMMISSION O L/
lirojectDirectorate111-2) ohn W. Craig, Director Division of Reactor Projects - 111, IV, Y and Special Projects
Attachment:
Changes to the Technical Specifications Date of Issuance: January 30, 1990 I'
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ATTACHMENT TO LICENSE AMENDMENT NO. 29 f,ACILITYOPERATINGLICENSENO.NPF-62 00,CKET NO. 50-461 Replace the following lages of the Appendix 'A' Technical Specifications with the attached pages. Tie revised pages are identified by Amendment number and contain vertical lines indicating the area of change.
Remove Insert 3/4 3-87 3/4 3-87 3/4 3-88 3/4 3-88 l
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TABLE 3.3.7.5-1 r-
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ACCIDENT MONITORING INSTRUMENTATION E
[
MINIMUM APPLICABLE 3
REQUIRED NUMBER CHANNELS OPERATIONAL
-4 INSTRUMENT OF CHANNELS OPERA 8LE CONDITIONS ACTION w
1.
Reactor Vessel Pressure 2
1 1, 2, 3 80 2.
1 1,2,3 80 3.
Suppression Pool Water Level 4
2 1, 2, 3 80 4.
Suppression Pool Water Temperature 2/quadrantt 1/quadrantt 1, 2, 3 80 5.
Drywell Pressure 2
1 1,2,3 80 6.
Drywell Air Temperature 2
1 1,2,3 80 7.
Drywell/ Containment Hydrogen and Oxygen Concentration Analyzer and Monitor 2
1 1,2,3 80 l
8.
Containment Pressure ##
2/ division 1/ division 1, 2, 3 80 R
9.
Containment Temperature 2
1 1,2,3 80
- 10. Safety / Relief Valve Acoustic Monitor 1/ valve ***
1/ valve ***
1,2,3 80 Y
- 11. Containment /Drywell High Range Gross Gamma 4
Radiation Monitors 4**
2*
1,2,3 81
- 12. HVAC Stack High Range Radioactivity Monitor #
1 1
1,2,3 81
- 13. SGTS Exhaust High Range Radioactivity Monitor #
1 1
1, 2, 3 81
- 14. Primary Containment Isolation Valve Position Indication it 2/ valve 1/ valve 1, 2, 3 82 TABLE NOTATIONS
- One each for containment and drywell.
- Two each for containment and drywell.
E
- Thermocouples in the SRV discharge line can serve as backup to the acoustic tall pipe monitors indication 3
should one channel of the position indication become inoperable.
- High range noble gas monitors and iodine / particulate sampler.
E
- For Divisions I and II only.
t These instruments monitor suppression pool water temperature when pool water level is below instruments E
of Specification 3.6.3.1.
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it One channel consists of the open limit switch, and the other channel consists of the closed limit switch for each automatic isolation valve in Table 3.6.4-1 Part 1, " Automatic Isolation Valves."
TABLE 3.3.7.5-1 (Continued) i ACCIDENT MONITORING INSTRUMENTATION ACTION ACTION 80 -
a.
With the number of OPERABLE accident monitoring instrumenta-tion channels less than the Required Number of Channels shown in Table 3.3.7.5-1, restore the inoperable channel (s) to OPERABLE status within 7 days 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 />.
The provisions of Specifica-tion 3.0.4 are not applicable.
b.
With the number of OPERABLE accident monitoring instrumen-i tation thannels less than the Minimum Channels OPERABLE rerr;irements of Table 3.3.7.5-1, restore the inoperable channel (s) to OPERABLE status within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> 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 />.
ACTION 81 -
With the number of OPERABLE Channels less than required by the Minimum Channels OPERABLE requirement, either restore the l
inoperable Channel (s) to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />, or:
a.
Initiate the' preplanned alternate method of monitoring the appropriateparameter(s),and b.
Prepare and submit a Special Report to the Commission pur-suant to Specification 6.9.2 within 14 days following the event outlining the action taken, the cause of the inopera-bility and the plans and schedule for restoring the system to OPERABLE status.
c.
The provisions of Specification 3.0.4 are not applicable.
' ACTION 82 -
a.
With the number of OPERABLE accident monitoring instrumentation channels less than the Required Number of Channels shown in Table 3.3.7.5-1, verify the valve (s) position by use of alter-nate indication methods; restore the inoperable channel (s) to OPERABLE status within 30 days 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 fol-lowing 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
b.
With the number of OPERABLE accident monitoring instrumentation i
channels less than the Minimum Channels OPERABLE requirements of Table 3.3.7.5-1, verify the valve (s) position by use of alternate indication methods; restore the inoperable channel (s) to OPERABLE status within 7 days or be in at least HOT SHUT-DOWN 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 />.
c.
The provisions of Specification 3.0.4 are not applicable.
CLINTON - UNIT 1 3/4 3-88 Amendment No. 29
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