ML20148H141
| ML20148H141 | |
| Person / Time | |
|---|---|
| Site: | Clinton  |
| Issue date: | 03/21/1988 |
| From: | Muller D Office of Nuclear Reactor Regulation |
| To: | Illinois Power Co |
| Shared Package | |
| ML20148H147 | List: |
| References | |
| NPF-62-A-002 NUDOCS 8803290328 | |
| Download: ML20148H141 (7) | |
Text
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ILLINDIS POWER COMPANY, ET AL DOCKET NO. 50-461 1
CLINTON POWER STATION, UNIT NO. 1 1
AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 2 ~~
License No. NPF-62 l
1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment by the Illinois Power Company * (IP),
Soyland Power Cooperative, Inc. and Western Illinois Power l
Cooperative, Inc. (the licensees) dated October 30, 1987 complies with the standards and req 0irements of the Atomic Energy Act of 1954, as amenced (the Act), and the Consnission's rules and regulations set forth in 10 CFR Chapter I; j
B.
The facility will operate in confonnity with the application, the provisions of the Act, and the rules and regulations of the Comission; C.
There is ref.sonable assurance (1) that the activities authorized
)
by this anEndment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be l
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 Specifications 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:
Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A and the Environmental Protection Plan contained in Appendix B, as revised
- Illinois Power Company is authorized to act as agent for Soyland Power Cooperative, Inc. and Western Illinois Power Cooperative, Inc. and has exclusive esponsibility and control over the physical construction, operation and maintenance of the facility.
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2 through Amendment No. 2, are hereby incorporated into this license.
IP 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 hed 'YL ly (CL
- 4.,
Daniel R. Muller, Director
. Project Directorate III-2
' Division of Reactor Projects - III, IV, V and Special Projects
Attachment:
Changes to the Technical Specifications Date of Issuance: March 21, 1988
ATTACHMENT TO LICENSE AMENDHENT N0. 2 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 identifed by Amendment number and contain vertical lines indicating the area of change. Overleaf page(s) are provided to mairitain document completeness.
Remove Insert 3/4 6-29 3/4 6-29 3/4 6-51 3/4 6-51 3/4 6-52 3/4 6-52 3/4 6-61 3/4 6-61 I
l i
1 h
I s
CONTAINMENT SYSTEMS 3/4.6.4 CONTAINMENT ISOLATION VALVES LIMITING CONDITION FOR OPERATION 3.6.4 The containment isolation valves and the instrumentation line excess flow check valves shown in Table 3.6.4-1 shall be OPERABLE # with isolation times l
1ess than or equal to those shown in Table 3.6.4-1.
APPLICABILITY: As shown in Table 3.6.4-1.
ACTION:
a.
With one or more of the containment isolation valves shown in Table 3.6.4-1 inoperable, maintain at least one isolation valve OPERABLE in eacn affected penetration that is open and within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> either:
1.
Restore the inoperable valve (s) to OPERABLE status, or 2.
Isolate each affected penetration by use of at least one deactivated automatic valve secured in the isolated position,*t or 3.
Isolate each affected penetration by use of at least one closed manual valve or blind flange.*t The provisions of Specification 3.0.4 are not applicable provided the affected penetration is isolahd in accordance with ACTION a.2 or a.3 above, and provided the associated system, if applicable, is declared inoperable or appropriate ACTION statements for that system are performed.
Otherwise be in at least HOT SHUTOOWN 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 />.
Otherwise, in OPERATIONAL CONDITION **, suspend all operations involving CORE ALTERATIONS, handling irradiated fuel in the secondary containment, or with a potential for draining the reactor vessel.
The provisions of Specification 3.0.3 are not applicable.
- Isolation valves closed to satisfy these requirements may be reopened on an intermittent basis under administrative controls.
i
- When handling irradiated fuel in the secondary containment and during CORE ALTERATIONS and operations with a potential for draining the reactor vessel.
tContainment Isolation Valves can have dual functions in that they provide both containment isolation and Emergency Core Cooling functions. Any inoperable dual function valve could degrade the valves' other function.
- ee Note (h) in Table of Notations for Table 3.6.4-1.
S CLIN'ON - UNIT 1 3/4 6-29 AMENDMENT N0. 2
TABLE 3.6.4-1 (untinued) n C
CONTAINMENT ISOLATION VALVES zy MAXIMUM SECONDARY APPLICABLE ISOLATION CONTAINMENT TEST 8
VALVE PENETRATION ISOLATION OPERATIONAL TIME BYPASS PATH PRESSURE g
NUMBER NUMBER SIGNALt C_0NDITIONS iseconds)
(YES/NO)
(psig)*
Test Connections, Vents and Drains (a) (Continued)
- 64) Drywell Pressure NA 1, 2, 3(a)
NA No
- 9. 0 1CM076 151 1C4077 203
- 65) Reactor Pressure 151 NA 1, 2, 3(a)
NA No
- 9. 0 1CM072 1CM073
- 66) Reactor Pressure 160 NA 1, 2, 3(a)
NA No
- 9. 0 D
1CM074 9
1CM075
- 67) Equipment Hatch 1
NA 1, 2, 3(a)
NA No 9.0 1CM099
- 68) Suppression Pool Level 177 NA 1, 2, 3(a)
NA No
- 9. 0 1E51 - F437A(h) 1E51 - F437B(h)
- 69) Suppression Pool Level 179 NA 1, 2, 3(a)
NA No 9.0 1E22 - F381A((h) h)
1E22 - g 1B 4"
1SM027A 9
ISM 0278(h) o 1
g
- 70) Suppression Pool Level 181 NA 1, 2, 3(a)
NA No 9.0 ISM 026A((h) 4 h) 5 1SM027B
- 71) Suppression Pool Level 183 NA 1, 2, 3(a) m NA No.
- 9. 0 1CM100A(h)
ICM100B(h) l
TABLE 3.6.4-1 (Continued)
[]
CONTAINMENT ISOLATION VALVES "i
o MAXIMUM SECONDARY APPLICABLE ISOLATION CONTAINMENT TEST a
c:
VALVE PENETRATION ISOLATION OPERATIONAL TIME BYPASS Paid PRESSURE
{}
NUMBER NUMBER SIGNAlt CONDITIONS (Seconds)
(YES/NO)
(psig)*
Other Isolation Valves (Continued) t 4.
Other Isolation Valves 1)
Main Steam Line C 5
1,2,3 NA No 9.0 IE32-F001J NA L
2)
Main Steam Line A 6
1,2,3 NA No 9.0 1E32-F001A NA 3)
Main Steam Line D 7
1, k, 3 NA No 9.0 as 1E32-F001N NA di 4)
Main Steam Line B 8
1,2,3 NA No 9.0 1E32-F001E NA 5)
Feedwater/RHR Line A 9
NA 1,2,3 NA
.Yes 9.0 1821-F010A 1821-F06SA 6)
Feedwater/RHR Line B 10 NA 1,2,3 NA Yes 9.0 1821-F010B 1B21-F065B Eg; 7)
RHR A Suction Line 11 NA 1,2,3 NA No 9.9 E
1E12-F004A(*)
E2
~* 8)
RHR B Suction Line 12 NA 1,2,3 NA No 9.9 IE12-F004B(*)
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TABLE 3.6.4-1(Continued]
CONTAINMENT ISOLATION VALVES 1
TABLE NOTATIONS (a) May be opened on an intermittent basis under administrative control.
(b) Excess flow check valve actuation differential pressure.
(c) Isolation valving for instrument lines which penetrate the containment con-form to the requirements of NRC Regulatory Guide 1.11.
The in-service in-spection program will provide assurance of the operability and integrity of these isolation provisions.
Type "C" testing will not be performed on the instrument line isolation valves.
The instrument lines will be within the boundaries of the Type "A" test, open to the media (containment atmo-sphere or suppression pool water) to which they will be exposed under pos-tulated accident conditions.
Instrument taps from the process line located between the process isolation valves and the renetration, and not them-selves penetrating containment, will be Type "A" and/or "C" tested along with the process line isolation valves.
j (e) The RHR system may be operating in the shutdown cooling mode during the Type A test.
These valves are tested using water but the results are not required to be added to the Type A test results.
The LPCS, HPCS, and RHR may be aligned in the normal standby or injection mode during the Type A test.
This will expose the closed loop outside containment to containment pressure through the suppression pool.
This is the closest valve alignment to the post-LOCA alignment possible.
Type C water test results on these suction valves will not be added to the Type A test results.
(f) Valves shall be closed in accordance with SECONDARY CONTAINMENT INTEGRITY.
(g) Valves shall be "sealed closed" by utilizing mechanical devices to seal or lock the valve closed or to prevent power from being supplied to the valve operator.
(h) OPERABILITY of these valves is not required until completion of corresponding plant modification.
When handlir.g irradiated fuel in secondary containment and during CORE ALTERATIONS and operations with a potential for draining the reactor vessel.
Isolates on RCIC low steam line pressure only.
t Isolation signal descriptions are provided in Table 3.6.4-2.
For test pressure = 9.0 psig, the valve (s) shall be pressurized using air or nitrogen, and for test pressure = 9.9 psig, the valve (s) shall be pressurized using water.
With any control rod withdrawn.
Not applicable to any control rods removed per Specification 3.9.10.1 or 3.9.10.2.
CLINTON - UNIT 1 3/4 6-61 AMENDMENT NO. 2
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