ML20056E989
| ML20056E989 | |
| Person / Time | |
|---|---|
| Site: | Clinton  |
| Issue date: | 08/05/1993 |
| From: | Dyer J Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20056E990 | List: |
| References | |
| NUDOCS 9308250383 | |
| Download: ML20056E989 (11) | |
Text
_.
/ p asc q'o UNITED STATES o
[' 3,,
g
~
NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 a
%,..../
ILLINOIS POWER COMPANY. ET AL.
DOCKET NO. 50-461 ClINTON POWER STATION. UNIT NO. 1 i
AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 82 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 December 27, 1991, 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 3
provisions of the Act, and the rules and regula ions 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:
- 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.
9308250383 930805 PDR ADOCK 05000461 P
_2_
+
1
(?)
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. 82, are hereby incorporated into this license.
Illinois Power Company shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
l 3.
This license amendment is effective as of its date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION i
d
. ' kI l
James E. Dyer, Director Project Directorate III-2 Division of Reactor Projects - III/IV/V i
Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications l
i Date of Issuance: August 5, 1993 l
t e
t I
i
?
~
l i
I
ATTACHMENT TO LICENSE AMENDMENT NO. 82 FACILITY OPERATING LICENSE NO. NPF-62 i
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 i
contain vertical lines indicating the area of change. The corresponding l
overleaf pages, as indicated by asterisks, are provided to maintain document completeness.
Remove Paoes Insert Paoes 3/4 7-3 3/4 7-3 I
3/4 7-4*
3/4 7-4*
~
3/4 7-5*
3/4 7-5*
i 3/4 7-6 3/4 7-6 The following pages are corrected pages from Amen:imr,t No. 79 or Amendment No. 81.
3/4 1-8 3/4 1-8 3/4 3-67 3/4 3-67 3/4 5-4a 3/4 5-5 3/4 5-5 3/4 5-6 3/4 5-6 l
1 i
1 4
4
P PLANT SYSTEMS 3/4.7.2 CONTROL ROOM VENTILATION SYSTEM LIMITING CONDITION FOR OPERATION 3.7.2 Two independent Control Room Ventilation Systems shall be OPERABLE.1 l
l APPLICABillTY: OPERATIONAL CONDITIONS 1, 2, 3, and *.
ACTION:
a.
In OPERATIONAL CONDITION 1, 2 or 3 with one Control Room Ventilation System inoperable, restore the inoperable system 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 /> 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 />.
t l
b.
In OPERATIONAL CONDITION *:
l 1.
With one Control Room Ventilation System inoperable, restore the inoperable system to OPERABLE status within 7 days. Otherwise, i
immediately initiate and maintain operation of the OPERABLE system in the high radiation mode of operation or suspend CORE ALTERATIONS, handling of irradiated fuel in the secondary containment and t
operations with a potential for draining the reactor vessel.
The provisions of Specification 3.0.4 are not applicable for entry into OPERATIONAL CONDITION 4 or 5.
I 2.
With both Control Room Ventilation Systems inoperable, immediately l
suspend CORE ALTERATIONS, handling of irradiated fuel in the secondary containment and operations with a potential for draining the reactor vessel.
i i
3.
The provisions of Specification 3.0.3 are not applicable.
SURVEILLANCE REQUIREMENTS 4.7.2 Each Control Room Ventilation System shall be demonstrated OPERABLE:t a.
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 that the control room air
[
temperature is less than or equal to 86*F.
b.
At least once per 31 days on a STAGGERED TEST Basis by initiating, from the control room, flow through the HEPA filters and charcoal adsorbers and verifying that the makeup filter system operates continuously for at least 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> with the heaters operating; and with flow through the recirculation charcoal adsorber for at least 15 minutes.
- During movement of irradiated fuel assemblies in the primary or secondary containment, during CORE ALTERATIONS, or during operations with a potential for draining the reactor vessel.
1 Automatic transfer to the chlorine mode is not required when chlorine containers having a capacity of 150 pounds or less are stored 100 meters or more from the control room or its fresh air inlets.
i CLINTON - UNIT 1 3/4 7-3 AMENDMENT NO. 82 i
i
L PLANT SYSTEMS CONTROL ROOM VENTILATION SYSTEM SURVEILLANCE REQUIREMENTS (Continued) 4.7.2 (Continued)
At least once per 18 months or (1) after any structural maintenance on the c.
makeup or recirculation HEPA filters or charcoal adsorber housings, or (2) following painting, fire or chemical release in any ventilation zone comunicating 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.S.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.5.a and C.S.d of Regulatory Guide 1.52, Revision 2 March 1978*, and the system flow rate is 64,000 cfm i 10%.
3.
Verifying, within 31 days after removal, that a laboratory analysis of a representative carbon sample obtained in accordance with Regula-tory 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% for sakeup filter system carbon ad-sorber and 6% for recirculation filter system carbon adsorber when tested; in accordance with ASTM D3803-79 methods, with the following parameters:
Make Up Filter System a) Bed Depth 4 inches b) Velocity 40 fpm c) Temperature 30*C d) Relative Humidity 70%
Recirculation Filter System i
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 opera-j tion when tested in accordance with ANSI H510-1980.
- ANSI N510-1980 shall be used in place of ANSI H510-1975 as referenced in Regulatory Guide 1.52, Revision 2, March 1978.
CLINTON - UNIT 1 3/4 7-4
. PLANT SYSTEMS C0h7ROL ROOM VEhTILATION 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 af ter 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 test-ing criteria of Re sion 2, March 1978gulatory Position C.6.a of Regulatory Guide 152, Revi-
, for a methyl iodide penetration of less than 0.175%
for the makeup filter system carbon adsorber and 6% for the recirculation filter system carbon adsorber when tested; in accordance with ASTM D3803-79 methods, with the following parameters:
Make Up 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%
At least once per 18 months by:
e.
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 cakeup 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 code of operation and the dampers c1,ose within 2 seconds.***
l 3.
Verifying that the control room leak rate is limited to < 4000 cfm i 10% at > 1/8-inch Water Gauge (W.G.) with respect to a~djacent 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 H510-1975 as referenced in Regulatory Guide 1.52,* Revision 2, March 1978.
- This specification is not applicable after all chlorine containers having a capacity 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 No.12
PLANT SYSTEMS CONTROL ROOM VENTILATION SYSTEM SURVEILLANCE REQUIREMENTS (Continued) 4.7.2 (Continued) the control room is maintained at a positive pressure of at least 1/8-inch W.G. with respect to adjacent areas during system operation l
at a flow rate less than or equal to 3000 cfm.
6.
Verifying that the makeup filters heaters dissipate at least 14.4 kW when tested in accordance with ANSI N510-1980.
f.
After each complete or partial replacement of a HEPA filter bank in the makeup filter system, 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 N510-1980 while operating the system at a flow rate of 3000 cfm i 10%.
g.
After each complete or partial replacement of a charcoal adsorber bank in the makeup or recirculation filter systems, by verifying that the char-coal adsorber bank satisfies the in-place penetration and bypass leakage testing acceptance criteria of less than 0.05% for the makeup filter system and 2% total bypass leakage for the recirculation filter system in accordance with ANSI N510-1980 for a halogenated hydrocarbon refrigerant test gas while operating the makeup system at a flow rate of 3000 cfm 10% and the recirculation filter system at a flow rate of 64,000 10%.
4 h.
At least once per 18 months by verifying that the air inleakage rate into the negative pressure portions of the Main Control Room Ventilation System ductwork located outside the Main Control Room habitability boundary between fan OVC04CA(B) and isolation dampers OVC03YA(B)
)
inclusive, and fire dampers OVC042YA(E), 0VC042YB(F), OVC042YC(G) and j
OVC042YD(H) to be s 650 cfm when tested in accordance with an NRC-l approved test raethod.
In addition, visually verify the integrity of the Recirculation Filter Housing flexible connection to fan OVC03CA(B).
l l
CLINTON - UNIT 1 3/4 7-6 AMENDMENT NO. 82
REACTIVITY CONTROL SYSTEMS CONTROL R0D MAXIMUM SCRAM INSERTION TIMES SURVEILLANCE RE0VIREMENTS 4.1.3.2.1 The maximum scram insertion time of the control rods shall be l
demonstrated through measurement with reactor coolant pressure greater than or equal to 950 psig and, during single control rod scram time tests, the control rod drive pumps isolated from the accumulators:
a.
For all control rods prior to THERMAL POWER exceeding 40% of RATED THERMAL POWER following CORE ALTERATIONS or after a reactor shutdown that is greater than 120 days, b.
For at least 10% of the control rods, on a rotating basis, at least once l
per 120 days of POWER OPERATION.
4.1.3.2.2 The maximum scram insertion time for specifically affected individual control rods following maintenance on or modification to the control rod or control rod drive system which could affect the scram insertion time of those specific control rods shall be demonstrated through measurement with reactor coolant pressure greater than or equal to 950 psig.
Alternatively, those specific control rods may be determined OPERABLE with reactor coolant pressure less than 950 psig by demonstrating an acceptable i
scram insertion time to notch position 13. The scram time acceptance criteria i
for this alternate test shall be determined by linear interpolation between 0.95 seconds at a reactor coolant pressure of 0 psig and 1.40 seconds at 950 psig.
If this alternate test is utilized, the individual scram time shall also be measured with reactor coolant pressure greater than or equal to 950 psig prior to exceeding 40% of RATED THERMAL POWER.
For each of the above single control rod scram time tests, the control rod drive pumps shall be isolated from the accumulators.
i
'The provisions of Specification 4.0.4 are not applicable for entry into OPERATIONAL CONDITION 2 provided this surveillance requirement is completed prior to entry into OPERATIONAL CONDITION 1.
CLINTON - UNIT 1 3/4 1-8 Amendment No. 81
TABLE 3.3.6-2 (Continued)
CONTROL R0D BLOCK INSTRUMENTATION SETPOINTS TABLE NOTATIONS These are turbine first stage pressure values.
The Average Power Range Monitor rod block function is varied as a function of recirculation loop flow (W). The trip setting of this function must be maintained in accordance with note (a) of Table 2.2.1-1.
- Instrument zero is 758' 5" msl.
- Instrument zero is 758' 4 1/2" msl.
i i
l I
?
)
J e
)
CLINTON - UNIT 1 3/4 3-67 Amendment No. 79
GP EMERGENCY CORE COOLING SYSTEMS ECCS - OPERATING SURVElllANCE REQUIREMENTS (Continued) 4.5.1 (Continued) b.
There is a corresponding change in the measured steam flow, or I
c.
The acoustic tail-pipe monitor alarms.
t 4.
At least once per 18 months, performing a CHANNEL CALIBRATION of the accumulator low pressure alarm system and verifying an alarm setpoint of 2 140 psig on decreasing pressure.
r i
1 P
CLINTON - UNIT 1 3/4 5-4 a Amendment No. 81
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.
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) sub'ystem "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.
The high pressure core spray (HPCS) system with a flow path capable of e.
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 drained, from the RCIC storage tank containing at least 125,000 available gallons of water.
l i
APPLICABILITY:
OPERATIONAL CONDITIONS 4 and 5*.
ACTION:
With one of the above required subsystems / systems inoperable, restore at a.
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 all operations that have a potential for draining the reactor vessel.
The provisions of Specification 3.0.4 are not applicable.
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 l
the next 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.
I 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 i
maintained within the limits of Specification 3.9.8 and 3.9.9.
CLINTON - UNIT 1 2/4 5-5 Amendment No. 73 MAY 1 153
EMERGENCV CORE COOLING SYSTEMS
=
i 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 I
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.
t t
l
[
1 i!
i r
i L
l b
i i
l
}
i 1
r a
CLINTON - UNIT 1 3/4 5-6 I
1
- l