ML20070K790
| ML20070K790 | |
| Person / Time | |
|---|---|
| Site: | Clinton  |
| Issue date: | 07/22/1994 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20070K793 | List: |
| References | |
| NUDOCS 9407270189 | |
| Download: ML20070K790 (8) | |
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DOCKET NO. 50-461 CLINTON POWER STATION, UNIT NO. 1 AMEN 0 MENT TO FACILITY OPERATING LICENS1 Amendment No. 91 License No. NPF-62 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Illinois Power Company * (IP), and Soyland Power Cooperative, Inc. (the licensees) dated April 18, 1994, as supplemented by letter dated June 16, 1994, 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; 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 Commission'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:
- lllinois 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.
9407270189 940722 PDR ADOCK 05000461 P
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. (2)
Technical Soecifications 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.
91, 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 amenda.ont is effective as of its date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
%kV 6M John N. Hannon, Director Project Directorate III-3 Division of Reactor Projects - III/IV Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical
)
Specifications Date of Issuance:
July 22, 1994 1
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ATTACHMENT TO LICENSE AMENDMENT NO. 91 FACILITY OPERATING l.ICENSE N0. NPF-62 DOCKET NO. Sb 151 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, indicated by an asterisk, are provided to maintain document completeness.
Remove Paaes Insert Paaes 3/4 6-39 3/4 6-39 3/4 6-40*
3/4 6-40*
3/4 7-4 3/4 7-4 3/4 7-5 3/4 7-5 B 3/4 7-1 B 3/4 7-1 I
i
I i
CONTAINMENT SYSTEMS STANDBY GAS TREATMENT SYSTEM SURVEILLANCE REOUIREMENTS (Continued) 4.6.6.3 (Continued) 1.
Verifying that the subsystem satisfies the in-place penetration and bypass leakage testing acceptance criteria of less than 0.05% and uses the test procedure guidance in Regulatory Positions C.5.a, C.5.c and C.5.d of Regulatory Guide 1.52, Revision 2, March 1978*,
and the system flow rate is 4000 cfm 10%.
2.
Verifying, within 31 days after removal, that a laboratory analysis of a representative carbon sample obtained in accordance with l
Regulatory Position C.6.b of Regulatory Guide 1.52, Revision 2, March 1978*, meets the laboratory testing criteria of Regulatory Position C.6.a of Regulatory Guide 1.52, Revision 2, March 1978*,
for a methyl iodide penetration of less than 0.175%; when' tested in accordance with ASTM D3803-89 methods, with the following parameters:
a)
Bed Depth
- 4 inches b)
Velocity
- 40 fpm c)
Temperature
- 30' C d)
Relative Humidity - 70%
ar.d 3.
Verifying a subsystem flow rate of 4000 cfm 10% during system operation when tested in accordance with ANSI N510-1980.
c.
After every 720 hours0.00833 days <br />0.2 hours <br />0.00119 weeks <br />2.7396e-4 months <br /> of charcoal adsorber operation, by verifying, within 31 days after removal, that a laboratory analysis of a representative carbon si sie cbtained in accordance with Regulatory Position C.6.b of Reguicce,i Guide 1.52, Revision 2, March 1978*, meets l
the laboratory testing:.,iteria of Regulatory Position C.6.a of Regulatory Guide 1.52, P.evision 2, March 1978*, for a methyl iodide penetration of less than 0.175%; in accordance with ASTM D3803-89 l
methods, with the following parameters:
a)
Bed Depth
- 4 inches b)
Velocity
- 40 fpm l
c)
Temperature
- 30' C l
d)
Relative Humidity - 70%
TANSI N510-1980 shall be used in place of ANSI N510-1975 as referenced in Regulatory Guide 1.5?, Revision 2, March 1978.
(
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CLINTON - UNIT 1 3/4 6-39 Amendment No. 46,6B,91
)
CONTAINMENT SYSTEMS STANDBY GAS TREATMENT SYSTEM SURVEILLANCE RE0VIREMENTS (Continued) 4.6.6.3 (Continued) d.
At least once per 18 months by:
1.
Performing a system functional test which includes simulated auto-matic actuation of the system throughout its emergency operating sequence for the:
a)
LOCA, and b)
Fuel handling accident.
2.
Verifying that the pressure drop across the combined HEPA filters and charcoal adsorber banks is less than 6.0 inches Water Gauge while operating the filter train at a flow rate of 4000 cfm t 10%.
3.
Verifying that the filter train starts and isolation dampers open on receipt of the following test signals:
a)
Manual initiation from the control room, and b)
Simulated automatic initiation signal.
4.
Verifying that the filter cooling bypass dampers can be manually opened and the fan can be manually started.
5.
Verifying that the heaters dissipate at least 18.0 kW when tested in accordance with ANSI N510-1980.
e.
Af ter each complete or partial replacement of a HEPA filter bank, by verifying that the HEPA filter bank satisfies the in-place penetration and bypass leakage testing acceptance criteria of less than 0.05% in accordance with ANSI l
N510-1980 while operating the system at a flow rate of 4000 cfm i 10%.
f.
After each complete or partial replacement of a charcoal adsorber bank by verifying that the charcoal adsorber bank satisfies the in-place penetration and bypass leakage testing acceptance criteria of less than 0.05% in accordance with ANSI N510-1980 for a halogenated hydrocarbon refrigerant test gas while operating the system at a flow rate of 4000 cfm i 10%.
CLINTON - UNIT 1 3/4 6-40 Amendmggg,gogjjhg 68 l
PLANT SYSTEMS CONTROL ROOM VENTILATION SYSTEM SURVElllANCE RE0VIREMENTS (Continued) 4.7.2 (Continued) c.
At least once per 18 months or (1) after any structural maintenance on the makeup or recirculation HEPA filters or charcoal adsorber housings, or (2) following painting, fire or chemical release in any ventilation zone communicating with the makeup or recirculation filter system by:
1.
Verifying that the makeup filter system satisfies the in-place penetration and bypass leakage testing acceptance criteria of less than 0.05% and uses the test procedure guidance in Regulatory Positions C.S.a, C.5.c, and C.5.d of Regulatory Guide 1.52, Revision 2, March 1978*, and the system flow rate is 3000 cfm i 10%.
2.
Verifying that the recirculation filter system satisfies bypass leakage testing acceptance criteria of less than 2% total bypass and uses test procedure guidance in Regulatory Positions C.S.a and C.5.d of Regulatory Guide 1.52, Revision 2, March 1978*, and the system flow rate is 64,000 cfm 10%.
3.
Verifying, within 31 days after removal, that a laboratory analysis of a representative carbon sample obtained in accordance with Regulatory Position C.6.b of Regulatory Guide 1.52, Revision 2, March 1978*, meets the laboratory testing criteria of Regulatory Position C 6.a of Regulatory Guide 1.52, Revision 2, March 1978*,
for a methyl iodide penetration cf less than 0.175% for makeup i
filter system carbon adsorber and 6% for recirculation filter system carbon adsorber when tested; in accordance with ASTM D3803-89 methods, with the following parameters:
Make Vo Filter System a)
Bed Depth
- 4 inches b)
Velocity 40 fpm c)
Temperature 30'C i
d)
Relative Humidity - 70%
Recirculation Filter System a)
Bed Depth 2 inches b)
Velocity
- 80 fpm c)
Temperature
- 30*C d)
Relative Humidity 70%
4.
Verifying flow rate of 3000 cfm i 10% for the makeup filter system and 64,000 cfm i 10% for the recirculation filter system during operation when tested in accordance with ANSI N510-1980.
- ANSI N510-1980 shall be used in place of ANSI Nbl0-1975 as referenced in i
Regulatory Guide 1.52, Revision 2, March 1978.
CLINTON - UNIT 1 3/4 7-4 AMENDMENT N0.91
PLANT SYSTEMS CONTROL ROOM VENTILATION SYSTEM SURVEILLANCE REQUIREMENTS (Continued) 4.7.2 (Continued) d.
After every 720 hours0.00833 days <br />0.2 hours <br />0.00119 weeks <br />2.7396e-4 months <br /> of charcoal adsorber operation, by verifying within 31 days after removal, that a laboratory analysis of a representative carbon sample obtained in accordance with Regulatory Position C.6.b of Regulatory Guide 1.52, Revision 2, March 1978*, meets the laboratory testing criteria of Regulatory Position C.6.a of Regulatory Guide 1.52, Revision 2, March 1978*, for a methyl iodide penetration of less than C.175% for the makeup filter system carbon adsorber and 6% for the recirculation filter system carbon adsorber when tested; in accordance with ASTM 03803-89 methods, with the following parameters:
Make Vo Filter System a)
Bed Depth
- 4 inches b)
Velocity 40 fpm c)
Temperature
- 30*C d)
Relative Humidity - 70%
Recirculation Filter System a)
Bed Depth
- 2 inches b)
Velocity
- 80 fpm c)
Temperature
- 30*C d)
Relative Humidity -
70%
e.
At least once per 18 months by:
1.
Verifying that the pressure drop across the combined HEPA filters and charcoal adsorber banks is less than 6 inches Water Gauge while operating the makeup filter system at a flow rate of 3000 cfm i 10%.
2.
Verifying that on a high chlorine actuation ** and a manual initia-tion test signal, the system automatically ** switches to the chlorine mcde of operation and the dampers close within 2 seconds.***
3.
Verifying that the control room leak rate is limited to s 4000 cfm i 10% at 2 1/8-inch Water Gauge (W.G.) with respect to adjacent areas.
4.
Verifying that on a smoke mode actuation test signal, the system automatically switches to the smoke mode of operation at a flow rate less than or equal to 64,000 cfm i 10%.
5.
Verifying that on a high radiation actuation test signal, the system automatically switches to the high radiation mode of operation and
- ANSI N510-1980 shall be used in place of ANSI N510-1975 as referenced in Regulatory Guide 1.52, Revision 2, March 1978.
- This specification is not applicable after all chlorine containers having a capar.ity of 100 pounds or greater are removed from the site including the chlorir.e containers located at the site sewage treatment plant.
CLINTON - UNIT 1 3/4 7-5 AMENDMENT N0.IZ,91
3/4.7 PLANT SYSTEMS BASES 3/4.7.1 SHUTDOWN SERVICE WATER SYSTEM The OPERABILITY of the shutdown service water system ensures that sufficient cooling capacity is available for continued operation of safety-related equip-ment during accident conditions. The redundant cooling capacity of these sys-tems, assuming a single failure, is consistent with the assumptions used in the accident analyses within acceptable limits.
The ultimate heat sink (UHS) specification ensure that sufficient cooling capacity is available for continued operation of safety-related equipment for at least 30 days to permit safe shutdown and cooldown of the reactor.
The surveillance requirements ensure that quantities maintained are consistent with the assumption used in the accident analysis as described in the USAR and the guidance provided in Regulatory Guide 1.27, January 1976.
3/4.7.2 CONTROL ROOM VENTILATION SYSTEM The OPERABILITY of the control room ventilation system ensures that 1) the ambient air temperature does not exceed the allowable temperature for continuous duty rating for the equipment and instrumentation cooled by this system and 2) the control room will remain habitable for operations personnel during and following all design basis accident conditions.
The OPERABILITY of this system in conjunction with control room design provisions is based on limiting the radiation exposure to personnel occupying the control room to 5 rem or less whole body, or its equivalent.
This limitation is consistent with the requirements of General Design Criterion 19 of Appendix "A",
Surveillance testing provides assurance that system and component performances continue to be in accordance with performance specifications for Clinton Unit 1, including applicable parts of ANSI N510-1980.
Continuous l
operation of the system with the heaters OPERABLE for 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> during each 31 day period is sufficient to reduce the buildup of moisture on the adsorbers and HEPA filters.
The specified heater dissipation is based on a bus voltage of 460 volts.
Heater test results shall be adjusted to account for actual bus voltage.
3/4.7.3 REACTOR CORE ISOLATION COOLING SYSTEM The reactor core isolation cooling (RCIC) system is provided to assure adequate core ceoling in the event of reactor isolation from its primary heat sink and the loss of feedwater flow to the reactor vessel without requiring actuation of any of the Emergency Core Cooling System equipment. The RCIC system is conservatively required to be OPERABLE whenever reactor pressure exceeds 150 psig. This pressure is substantially below that for which the low pressure core cooling systems can provide adequate core cooling for events requiring the RCIC system.
The RCIC system specifications are applicable during OPERATIONAL CONDITIONS 1, 2, and 3 when reactor vessel pressure exceeds 150 psig because RCIC is the primary (non-ECCS) source of emergency core cooling when the reactor is pressurized.
With the RCIC system inoperable, adequate core coolina is assured by the OPERABILITY of the HPCS system and justifies the specified 14 day out-of-service period.
Letter of 6/29/93 CLINTON - UNIT 1 B 3/4 7-1 Amendment No.91