ML20036A766
| ML20036A766 | |
| Person / Time | |
|---|---|
| Site: | Clinton  |
| Issue date: | 05/04/1993 |
| From: | Dyer J Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20036A767 | List: |
| References | |
| NUDOCS 9305140163 | |
| Download: ML20036A766 (2) | |
Text
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UNITED STATES fl[.j
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i NUCLEAR REGULATORY COMMISSION 4
j WASHINGTON D.C. 20rEMX101 ILLINDIS POWER COMPANY. ET AL.
DOCKET NO. 50-461 CLINTON POWER STATION. UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 73 License No. NPF-62 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Illinois Power Company' (IP),
l and Soyland Power Cooperative, Inc. (the licensees) dated l
October 16, 1992, complies with the standards and 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; 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 j
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 J
Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
1 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.
9305140163 930504 PDR ADOCK 05000461 P
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2.
Accordingly, the license is amended by changes to the Facility Operating License and to the Technical Specifications as indicated in
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the attachment to this license amendment, and paragraphs 2.C.(2) and l
2.0. of Facility Operating License No. NPF-62 are hereby amended to read l
as follows:
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(2)
Technical Specifications and Environmental Protection Plan 5
The Technical Specifications contained in Appendix A and the i
Environmental Protection Plan contained in Appendix B, as revised through Amendment No.
, are hereby incorporated into this t
license.
Illinois Power Company shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan, i
i D.
The facility requires exemptions from certain requirements of l
10 CFR Part 50 and 10 CFR Part 70. These include:
(a) an j
exemption from the requirements of 10 CFR 70.24 for the i
criticality alarm monitors around the fuel storage area; (b) an 1
exemption from the requirement of paragraph III.D.2(b)(ii) of l
1 Appendix J, substituting the seal leakage test at Pa of paragraph i
{
III.D.2(b)(iii) for the entire airlock test at Pa of paragraph III.D.2(b)(ii) of Appendix J when no maintenance has been i
performed in the airlock that could affect its sealing capability l
(Section 6.2.6 of SSER 6); (c) an exemption from the requirement l
of paragraph III.C.3 of Appendix J, exempting the measured leakage rates from the main steam isolation valves from inclusion in the combined leak rate for the local leak rate tests (Section 6.2.6 of i
SSER 6); and (d) an exemption from the requirements of paragraph III.B.3 of Appendix J, exempting leakage from the valve packing and the body-to-bonnet seal of valve IE51-F374 associated with containment penetration IMC-44 from inclusion in the combined l
leakage rate for penetrations and valves subject to Type B and C tests.
The special circumstances regarding each exemption, except for Items (a) and (d) above, are identified in the referenced section of the safety evaluation report and the supplements
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threto.
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The special circumstances regarding the exemption identified in Item (d) above are identified in the safety evaluation accompanying Amendment No. 62 to this license.
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2 Pages 5 and 6 are attached, for convenience, for the composite license to reflect this change.
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. These exemptions are authorized by law, will not present an undue risk to the public health and safety, and are consistent with the common defense and security. The exemptions in items (b) and (c) above are granted pursuant to 10 CFR 50.12. With these exemptions, the facility will operate, to the extent authorized herein, in conformity with the application, as amended, the provisions of the Act, and the rules and regulations of the Commission.
3.
This license amendment is effective as of its date of issuance.
l FOR THE NUCLEAR REGULATORY COMMISSION 4444 - lW James E. Dyer, Director l
Project Directorate III-2 l
Division of Reactor Projects - III/IV/V Office of Nuclear Reactor Regulation Attachments:
1.
License pages 5 and 6 2.
Changes to the Technical Specifications Date of Issuance: May 4, 1993 l
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(8)
Post-Fuel loadina Initial Test Procram (Section 14. SER. SSER_5 and SSER 6) i l
Any changes to the initial test program described in Section 14 of i
the FSAR made in accordance with the provisions of 10 CFR 50.59 shall be reported in accordance with 50.59(b) within one month of such change.
(9)
[meroency Response Capabilities (Generic Letter 82-33. Supplement I to NUREG-0737. Section 7.5.3.1. SSER 5 and SSER 8. and Section 18.
SER. SSER S and Safety Evaluation Dated April 17. 1987) a.
IP in accordance with the commitment contained in a letter dated December 11, 1986, shall install and have operational separate power sources for each of the fuel zone level channels as provided for in Regulatory Guide 1.97 prior to l
startup following the first refueling outage.
i b.
IP shall submit a detailed control room design final supple-mental summary report within 90 days of issuance of the full power license that completes all the remaining items identified in Section 18.3 of the Safety Evaluation dated April 17, 1987.
D.
The facility requires exemptions from certain requirements of 10 CFR Part 50 and 10 CFR Part 70.
These include:
(a) an exemption from the requirements of 10 CFR 70.24 for the criticality alarm monitors around the fuel storage area; (b) an exemption from the requirement of l
paragraph III.D.2(b)(ii) of Appendix J, substituting the seal leakage i
test at Pa of paragraph III.D.2(b)(iii) for the entire airlock test at 1
Pa of paragraph III.D.2(b)(ii) of Appendix J when no maintenance has i
been performed in the airlock that could affect its sealing capability (Section 6.2.6 of SSER 6); (c) an exemption from the requirement of l
paragraph III.C.3 of Appendix J, exempting the measured leakage rates from the main steam isolation valves from inclusion in the combined leak rate for the local leak rate tests (Section 6.2.6 of SSER 6); and (d) an l
exemption from the requirements of paragraph III.B.3 of Appendix J, 4
exempting leakage from the valve packing and the body-to-bonnet seal of valve IE51-F374 associated with containment penetration IMC-44 from inclusion in the combined leakage rate for penetrations and valves i
subject to Type B and C tests. The special circumstances regarding each exemption, except for Items (a) and (d) above, are identified in the l
referenced section of the safety evaluation report and the supplements thereto.
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Amendment No. 73 4
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An exemption was previously granted pursuant to 10 CFR 70.24. The exemption was granted with NRC materials license No. SNM-1886, issued November 27, 1985, and relieved IP from the requirement of having a criticality alarm system.
IP is hereby exempted from the criticality alarm system provision of 10 CFR 70.24 so far as this section applies to the storage of fuel assemblies held under this license.
i The special circumstances regarding the exemption identified it. A i )
l d
above are identified.a the safety evaluation accompanying Amendment No. 62 to this license.
These exemptions are authorized by law, will not present an undue risk to the public health and safety, and are consistent with the common defense and security. The exemptions in items (b) and (c) above are l
granted pursuant to 10 CFR 50.12. With these exemptions, the facility will operate, to the extent authorized herein, in conformity with the i
application, as amended, the provisions of the Act, and the rules and 3
regulations of the Commission.
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E.
The licensees shall fully implement and maintain in effect all provisions of the Commission-approved physical security plan, guard training and qualification, and safeguards contingency plans including amendments made pursuant to provisions of the Miscellaneous Amendments and Search Requirements revisions to 10 CFR 73.55 (51 FR 27817 and 27822) and to the authority of 10 CFR 50.90 and 10 CFR 50.54(p). The i
plans, which contain Safeguards Information protected under 10 CFR 73.21, are entitled:
"Clinton Power Station Physical Security Plan,"
with revisions submitted through October 8, 1992; "Clinton Power Station Training and Qualification Plan," with revisions submitted through July 2,1990; and "Clinton Power Station Safeguards Contingency Plan,"
with revisions submitted through July 2,1990. Changes made in accordance with 10 CFR 73.55 shall be implemented in accordance with the schedule set forth therein.
__J F.
IP shall implement and maintain in effect all provisions of the approved fire protection program as described in the Final Safety Analysis Report as amended, for the Clinton Power Station, Unit No. 1, and as approved in the Safety Evaluation Report (NUREG-0853) dated February 1982 and Supplement Nos. I thru 8 thereto subject to the following provision:
IP may make changes to the approved fire protection program without prior approval of the Commission only if those changes would not adversely affect the ability to achieve and maintain i
safe shutdown in the event of a fire.
G.
Except as otherwise provided in the Technical Specifications or Environmental Protection Plan, IP shall report any violations of the requirements contained in Section 2.C of this license in the following manner:
initial notification shall be made within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> to the NRC Operations Center via the Emergency Notification System with written followup within thirty days in accordance with the procedures described in 10 CFR 50.73(b), (c), and (e).
Amendment No. 73
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ATTACHMENT TO LICENSE AMENDMENT NO. 73 FACII.ITY OPERATING LICENSE NO. NPF-62 DOCKET NO. 50-461 f
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.
The corresponding overleaf pages, as indicated by an asterisk, are provided to maintain document completeness.
Remove Paces Insert Paaes i
4 3/4 5-5 3/4 5-5
- 3/4 5-6
- 3/4 5-6 i
3/4 5-7 3/4 5-7
- 3/4 5-8
- 3/4 5-8 i
+3/4 8-21
- 3/4 8-21 3/4 8-22 3/4 8-2E 3/4 9-19 3/4 9-19 3/4 9-20 3/4 9-20 l
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l
EMERGENCY CORE COOLING SYSTEMS 3/4.5.2 ECCS - SHUTDOWN LIMITING CONDITION FOR OPERATION 3.5.2 At least two of the following shall be OPERABLE and capable of being powered from a diesel generator of Specification 3.8.1.2.b.
i a.
The low pressure core spray (LPCS) system with a flow path capable of taking suction from the suppression pool and transferring the water through the spray sparger to the reactor vessel.
b.
Low pressure coolant injection (LPCI) subsystem "A" of the RHR system with a flow path capable of taking suction from the suppression pool and transferring the water to the reactor vessel.
c.
Low pressure coolant injection (LPCI) subsystem "B" of the RHR system with a flow path capable of taking suction from the suppression pool and transferring the water to the reactor vessel.
d.
Low pressure coolant injection (LPCI) subsystem "C" of the RHR system with a flow path capable of taking suction from the suppression pool and transferring the water to the reactor vessel.
e.
The high pressure core spray (HPCS) system with a flow path capable of taking suction from one of the following water sources and transferring the water through the spray sparger to the reactor vessel:
1.
From the suppression pool, or 2.
When the suppression pool level is less than the limit or is j
drained, from the RCIC storage tank containing at least 125,000 t
available gallons of water.
l APPLICABILITY:
OPERATIONAL CONDITIONS 4 and 5*.
ACTION:
a.
With one of the above required subsystems / systems inoperable, restore at least two subsystems / systems to OPERABLE status within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> or suspend i
all operations that have a potential for draining the reactor vessel.
The provisions of Specification 3.0.4 are not applicable.
i b.
With both of the above required subsystems / systems inoperable, suspend CORE ALTERATIONS and all operations that have a potential for draining the reactor vessel. Restore at least one subsystem / system to OPERABLE status within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> or establish PRIMARY CONTAINMENT INTEGRITY within the next 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.
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h The ECCS is not required to be OPERABLE provided that the reactor vessel head is removed, the cavity is flooded, the reactor cavity to steam dryer pool gate is open and water level in these upper containment pools is maintained within the limits of Specification 3.9.8 and 3.9.9.
j CLINTON - UNIT 1 3/4 5-5 Amendment No. 73
EMERGENCY CORE COOLING SYSTEMS ECCS - SHUTDOWN SURVEILLANCE REQUIREMENTS 4.5.2.1 At least the above required ECCS shall be demonstrated OPERABLE per Surveillance Requirement 4.5.1.
4.5.2.2 The HPCS system shall be determined OPERABLE at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> by verifying the RCIC storage tank required volume when the RCIC storage tank is required to be OPERABLE per Specification 3.5.2.e.
CLINTON - UNIT 1 3/4 5-6
l EMERGENCV CORE COOLING SYSTEMS 1
l 3/4.5.3 SUPPRESSION POOL e
LIMITING CONDITION FOR OPERATION 3.5.3 The suppression pool shall be OPERABLE:
a.
In OPERATIONAL CONDITIONS 1, 2, and 3 with a contained water volume of at least 146,400 ft*, equivalent to a level of 18'11".
l b.
In OPERATIONAL CONDITIONS 4 and 5* with a contained water volume of at least 98,700 ft3, equivalent to a level of 12'8", except that the I
suppression pool level may be less than the limit or may be drained pro-vided that.
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1.
No operations are performed that have a potential for draining the i
reactor vessel, 2.
The reactor mode switch is locked in the Shutdown or Refuel
- position, 3.
The RCIC storage tank contains at least 125,000 available gallons of
=;
water, and l
4.
The HPCS system is OPERABLE per Specification' 3.5.2 with an OPERABLE flow path capable of taking suction from the RCIC storage tank and transferring the water through the spray sparger to the reactor j
vessel.
1 APPLICABILITY: OPERATIONAL CONDITIONS 1, 2, 3, 4, and 5*.
j ACTION:
a.
In OPERATIONAL CONDITION 1, 2, or 3 with the suppression pool water level less than the above limit, restore the water level to within the limit within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 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 /> 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 />.
b.
In OPERATIONAL CONDITION 4 or 5* with the suppression pool water level less than the above limit or drained and the above required conditions not satisfied, suspend CORE ALTERATIONS and all operations that have a potential for draining the reactor vessel and lock the reactor mode switch in the Shutdown position.
Establish SECONDARY CONTAINMENT INTEGRITY within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.
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- The suppression pool is not required to be OPERABLE provided that the reactor vessel head is removed, the cavity is flooded, the reactor cavity to steam dryer pool gate is open, and the water level in these upper containment pools is maintained within the limits of Specifications 3.9.8 and 3.9.9.
CLINTON - UNIT 1 3/4 5-7 Amendment No. 73 l
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EMERGENCY CORE COOLING SYSTEMS SUPPRESSION POOL SURVEILLANCE REQUIREMENTS 4.5.3.1 The suppression pool shall be determined OPERABLE by verifying the water level to be greater than or equal to a.
18'11" at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, in OPERATIONAL CONDITIONS 1, 2, or 3.
b.
12'8" at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, in OPERATIONAL CONDITIONS 4 and 5.
4.5.3.2 With the suppression pool level less than the above limit or drained in OPERATIONAL CONDITIONS 4 or 5*, at least once per 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />s:
a.
Verify the required conditions of Specification 3.5.3.b to be sati'sfied, or b.
Verify footnote conditions
- to be satisfied.
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- The suppression pool is not required to be OPERABLE provided that the reactor vessel head is removed, the cavity is flooded, the reactor cavity to steam dryer pool gate is open, and the water level in these upper containment pools is maintained within the limits of Specifications 3.9.8 and 3.9.9.
CLINTON - UNIT 1 3/4 5-8
ELECTRICAL POWER SYSTEMS DISTRIBUTION - SHUTDOWN LIMITING CONDITION FOR OPERATION 3.8.3.2 As a minimum, the following power distribution system divisions shall be energized:
l a.
For AC power distribution, Division I or Division II, and when the HPCS system is required to be OPERABLE, Division III and Division IV, with:
1.
Division I consisting of:
l a) 4160-volt AC Bus 1A1.
b) 480-volt Unit Substations A and 1A.
1)
Aux. Bldg. MCCs 1A1, lA2, 1A3, 1A4.
2)
3) 0.G. MCC 1A.
I 4)
Control Bldg. MCCs El, E2, and G 5)
Damper MCC A d) 120-volt AC distribution panels in Auxiliary Building 480-volt MCC 1A1 and Control Building MCC E2.
e) 120-volt AC uninterruptible distribution panels energized from IC71-5001A, which is fed from Control Building MCC E2 and from Auxiliary Building 480-volt MCC 1A1 through 125-volt DC MCC IDC13E.
2.
Division II consisting of:
I a) 4160-volt AC Bus IBl.
b) 480-volt Unit Substations B and 1B.
c) 480-volt AC HCCs 1)
Aux. Bldg. MCCs 1B1, 1B2, 183, 1B4 2)
D.G. MCC 1B 4)
Control Bldg. MCCs F1, F2, and H 5)
Damper MCC B d) 120-volt AC distribution panels in Auxiliary Building 480-volt MCC 181 and Control Building MCC F2.
e) 120-volt AC uninterruptible distribution panels energized from IC71-5001B, which is fed from Control Building MCC F2 and from Auxiliary Building 480-volt MCC 181 through 125-volt DC MCC IDC14E.
CLINTON - UNIT 1 3/4 8-21
ELECTRICAL POWER SYSTEMS DISTRIBUTION - SHUTDOWN I
LIMITING CONDITION FOR OPERATION (Continued) 3.8.3.2 (Continued)
L 3.
Division III consisting of:
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a) 4160-volt AC Bus 1C1.
b)
Auxiliary Building 480-volt MCC IC and Auxiliary Building 480-volt MCC 101, and SSW MCC IC.
c) 120-volt AC distribution panels in Auxiliary Building 480-volt MCC IC and Auxiliary Building MCC 1C1.
l I
d) 120-volt AC uninterruptible distribution panels energized from IC71-S001C, which is fed from Auxiliary Building 480-volt MCC 10 i
and 125-volt DC Distribution Panel IE22-5001C.
l 4.
Division IV consisting of 120-volt AC uninterruptible distribution panel energized from IC71-S0010, which is fed from Auxiliary Building i
480-volt MCC-1B1 and 125-volt DC MCC IDC15E.
j b.
For DC power distribuMon, Division I or Division II, and when the HPCS system is required to be OPERABLE, Division III, and Division IV, with:
1.
Division I consisting of 125-volt DC Batteries IA,125-volt Battery Charger IA,125-volt DC MCC-1A, and distribution panel.
2.
Division II consisting of 125-volt DC Batteries 18,125-volt Battery Charger 18,125-volt DC MCC-18, and distribution panel.
3.
Division III consisting of 125-volt DC Batteries IC,125-volt Battery Charger 1C and distribution panel.
4.
Division IV consisting of 125-volt DC Battery ID,125-volt Battery Charger ID,125-volt DC MCC-ID, and distribution panel.
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APPLICABILITY: OPE. RATIONAL CONDITIONS 4, 5, and *.
ACTION:
4 a.
For AC power distribution:
1.
With both Division I and Division II of the above required AC dis-tribution system not energized, suspend CORE ALTERATIONS, handling of irradiated fuel in the secondary containment and operations with a potential for draining the reactor vessel.
When handling irradiated fuel in the secondary containment.
j CLINTON - UNIT 1 3/4 8-22 Amendment No. 73
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i REFUELING OPERATIONS 3/4,9.12 INCLINED FUEL TRANSFER SYSTEM LIMITING CONDITION FOR OPERATION 3.9.12 The inclined fuel' transfer system (IFTS) may be in operation provided that:
l The access doors" of all rooms through which the transfer system a.
penetrates are closed and locked.
b.
All access door
- interlocks are OPERABLE.
The blocking valve located in the fuel building IFTS hydraulic power unit c.
is OPERABLE.
l i
d.
At least one IFTS carriage position indicator is OPERABLE at each carriage position and at least one liquid level sensor is OPERABLE.
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e.
Any keylock switch that provides IFTS access control-transfer system j
lockout is OPERABLE.
APPLICABILITY: When the IFTS containment blank flange is removed.
l ACTION:
i With the recuirements of the above specification not satisfied, suspend IFTS operation with the IFTS at either terminal point.
The provisions of Specif_i-cation 3.0.3 are not applicable.
SURVEILLANCE RE0VIREMENTS i
4.9.12.1 Within I hour prior to the startup and at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> during operation of the IFTS, verify that no personnel are in areas immediately adjacent to the IFTS and that all access doors
- to rooms through which the IFTS penetrates are closed and locked.
4.9.12.2 Within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> prior to the operation of IFTS and at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> thereafter, verify that at least one IFTS carriage position indicator is OPERABLE at each carriage position and at least one liquid level indicator is OPERABLE.
_l Includes removable shields.
CLINTON - UNIT 1 3/4 9-19 Amendment No. 73
I REFUELING OPERATIONS 1
INCLINED FUEL TRANSFER SYSTEM s
SURVEILLANCE REQUIREMENTS (Continued) i 4.9.12.3 Within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> prior to the operation of the IFTS and at least once per 7 days thereafter, verify that:
l a.
All access door
- interlocks are OPERABLE.
b.
The blocking valve in the Fuel Building IFTS hydraulic power unit is l
I l
c.
The keylock switches which provide IFTS access or control-transfer system lockout are OPERABLE.
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l Includes removable shields.
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CLINTON - UNIT 1 3/4 9-20 Amendment No. 73
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