ML20055F821
| ML20055F821 | |
| Person / Time | |
|---|---|
| Site: | Clinton  |
| Issue date: | 07/16/1990 |
| From: | Hannon J Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20055F822 | List: |
| References | |
| NUDOCS 9007190244 | |
| Download: ML20055F821 (7) | |
Text
.
l'f S
UNITED STATES NUCLEAR REGULATORY COMMISSION N,
W ASHING TON. D. C. 20555
DOCKET NO. 50-461 CLINTON POWER STATION, UNIT NO. 1 i
AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 39 License No. NPF.62 1.
The Nuclear Regulatory Comissica (the Comission) has found that:
l l
A.
The application for amendment by 1111nois Power Company * (IP),
andSoylandPowerCooperative,Inc.(thelicensets) 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; l
B.
The facility will operate in conformity with the application, the 4
provisions of. the Act, and the rules and regulations of the Comission; C.
There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of tae public, and (ii) that such activities will be conducted in compliance with the Comission's regulations; i
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 l
of the Comission'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 i
paragraph 2.C.(2) of Facility Operating License No. NPF-62 is hereby
.1 l
amended to read as follows:
l
- 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.
J
[.OO3bbbb p1 P
I
4 8
i 2
(2) Technical Specifications 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. ' 39. are hereby incorporated into this 1
license.
Illinois Power Company shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
3.
This license amendrent is effective as of its date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION v c%
John N. Hannon, Director Project Directorate 111-3 Division of Reactor Projects - III, IV, Y and Special Projects Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of issuance: July 16, 1990 e
l
s ATTACHMENT TO LICENSE AMENDMENT NO. 39 FACILITY OPERATING LICENSE NO. NPF-62 DOCKET NO. 50-461 Replace the following anges 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. Corresponding overleaf pages are provided to maintain document completeness.
Remove Insert 3/4 4-13 3/4 4-13 B 3/4 4-3 B 3/4 4-3 l
B 3/4 4-4 B 3/4 4-4 9
4 4
I 6
L
s REACTOR COOLANT SYSTEM OPERATIONAL LEAKAGE LIMITING. CONDITION FOR OPERATION 3.4.3.2 Reactor coolant system leakage shall be limited to:
a.
b.
5 gpm UNIDENTIFIED LEAKAGE.
25 gpm IDENTIFIED LEAKAGE (averaged over any 24-hour period),
c.
d.
0.5 gpm leakage per nominal inch of valve size up to a maximum of 5 gpm from any reactor coolant system pressure isolation valve specified in Table 3.4.3.2-1, at rated reactor pressure.
APPLICABILITY: OPERATIONAL CONDITIONS 1, 2, and 3.
ACTION:
a.
With any PRESSURE BOUNDARY LEAKAGE be in at least HOT SHUTDOWN within 12hoursandinCOLDSHUTOOWNwithInthenext24 hours, b.
With any reactor coolant system leakage greater than the limits in b and/or c, above, reduce the leakage rate to within the limits within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> or 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 SilVTDOWN within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
With any reactor coolant system pressure isolation valve leakage greater c.
than the above limit, isolate the high pressure portion of the affected system from the low pressure portion within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> by use of at least two other closed manual or deactivated automatic valves, 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 SHUT 00WN within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
SURVEILLANCE REQUIREMENTS 4.4.3.2.1 The reactor coolant system leakage shall be demonstrated to be within each of the above limits by:
a.
Monitoring the drywell atmospheric particulate and gaseous radio-activity at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> (not a means of quantifying leakage),
j b.
Monitoring the drywell floor and equipment drain sump flow rate at least l
once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, c.
Monitoring the drywell air coolers condensate flow rate at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, and CLINTON - UNIT 1 3/4 4-13 Amendment No. 39 s
w-m
_. _ _ _ _ _________.j
4 REACTOR COOLANT SYSTEM OPERATIONAL LEAKAGE SURVEILLANCE REQUIREMENTS (Continued) 4.4.3.2.1 (Continued) d.
Monitoring the reactor vessel head flange leak detection system at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
4.4.3.2.2 Each reactor coolant system pressure isolation valve specified in Table 3.4.3.2 1 shall be demonstrated OPERABLE by leak testing pursuant to Specification 4.0.5 and verifying the leakage of each valve to be within the specified limit:
a.
At least once per 18 months.*
l b.
Prior to returning the valve to service following maintenance, repair, or replacement work on the valve or its associated actuator.
As outlined in ASME Code,Section XI, paragraph IWV 3427(b).
c.
The provisions of Specification 4.0.4 are not applicable for entry into OPERATIONAL CONDITION 3.
i l
l I'
l f
i I
i
- The requirements of this specification for valves 1E12F023, IE51F066, and IE51F013 will not be completed until prior to startup following the first refueling outage.
t CLINTON - UNIT 1 3/4 4-14 Amendment No.1
m
.~
+
8ASES 3/4.4.1 RECIRCULATION SYSTEM (Continued) l The recirculation flow control valves provide regulation of individual recir-culation loop drive flows; which, in turn,istent with the rod nattern and re-will vary the flow rate of coolant I
through the-reactor core over a range cons circulation pump speed.
The recirculation flow control systein rensists of the electronic and hydraulic components necessary for the positioning of the two hydraulically actuated flow control valves.
Solid state control logic will generate a flow control valve " motion inhibit" signal in response to any-one of several hydr wlic power unit or analog control circuit failure signals.
The "stion inhe 't" signal causes hydraulic power unit shutdown and hydraulic isolation such t ht the flow con 6.' valve fails "as is."--This design feature insures that the flow control va h u to not respond to potentially erroneous L
control signals.
L Electronic limiters exist in the position control loop of each flow-control valve to limit the flow control valve stroking rate to 1011% per second in opening and closing directions on a control signal failure.
The analysis of f
the recirculation flow control failures on increasing and decreasing flow are i
presented in Sections 15.3 and 15.4 of the FSAR respectively.
The required surveillance interval is adequate to ensure that the flow control valves remain OPERABLE and not so frequent as to cause excessive wear on the system components.
3/4,4.2 SAFETY / RELIEF VALVES The safety valve function of the safety / relief valves (SRV) operate to prevent.
i the reactor coolant system from being pressurized above the Safety Limit of 1375 psig in accordance with the ASMc Code.
A total of 11 OPERABLE safety-relief, valves.is required to limit reactor pressure to within ASME III allowable values for the worst' case upset transient.
Any combination of 5 SRVs operating in the relief mode and 6 SRVs operating in the safety mode is acceptable.
Demonstration of the safety-relief valve lift settings will occur only during l-
' shutdown and will be performsd in accordance with the provisions of Specifica-L
- tion-4.0.5.
The low-low set system ensures that safety / relief valve discharges are minimized i
for a second opening of these valves,'following any overpressure transient.
L This is achieved by automatically lowering the closing setpoint of 5 valves and i
lowering the opening setpoint of 2 valves following the initial opening.
In l
this.wayIallyreduced..the frequency and magnitude of the containment blowdown dut substant Sufficient redundancy is provided for the low-low set-p system such that failure of any one valve to open or close at its reduced set-point does not violate the design basis.
3/4.4.3 REACTOR C0OLANT SYSTEM LEAKAGE 3/4.4.3.1 LEAKAGE DETECTION SYSTEMS The RCS leakage detection sy' stems required by this specification are provided to monitor and detect leakage from the reactor coolant pressure boundary.
l_
-These detection systems meet the intent of Regulatory Guide 1.45, l
~
CLINTON - UNIT 1 B 3/4 4-3 Amendment No.18,39
REACTOR COOLANT SYSTEM BASES 4
3/4.4.3.1 LEAKAGE DETECTION SYSTEMS (Continued)
" Reactor Coolant Pressure Boundary Leakage Detection Systems," May 1973 and are consistent with the recommendations of ANSI 567.03, " Standard for Light Water Reactor Coolant Pressure Boundary Leak Detection," 1982.
They provide the ability to detect and/or measure leakage froai fluid systems in the drywell.
3/4.A.3.2 OPERATIONAL LEAKAGE The allowable leakage rates from the reactor coolant system have been basr.d on the predicted and experimentally observed behavior of cracks in pipes.
'he normally expected background leakage due to equipment design and the detetion capability of the instrumentation for determining system leakage was also con-sidered.
The evidence obtained from experiments suggests that for leakage some-what greater than that specified for UNIDENTIFIED LEAKAGE the probability is small that the imperfection or crack associated with such leakage would grow rapidly.
However, in all cases, if the leakage rates exceed the values speci-fied or the leakage is located and known to be PRESSURE BOUNDARY LEAKAGE, the reactor will be shut down to allow further investigation and corrective action.
The Surveiilance Requirements for RCS pressure isolation valves provide added assurance of valve integrity thereby reducing the probability of gross valve failure and consequent intersystem LOCA.
Leakage from the RCS pressure isola-tion valves is IDENTIFIED LEAKAGE and will be considered as a portion of the allowed limit.
3/4.4.4 CHEMISTRY The water chemistry limits of the reactor coolant system are established to prevent damage to the reactor materials in contact with the coolant.
Chloride limits are specified to prevent stress corrosion cracking of the stainless steel.
The effect of chloride is not as great when the oxygen concentration in the coolant is low, thus the 0.2 ppm limit on chlorides is permitted during POWER OPERATION.
During shutdown and refueling operations, the temperature necessary for stress corrosion to occur is not present so a 0.5 ppm concentration of chlorides is not considered harmful during these periods.
Conductivity measurements are required on a continuous basis since changes in this parameter are an indication of abnormal conditions.
When the conductivity is within limits, the pH, chlorides and other impurities affecting conductivity must alsc be within their acceptable limits.
With the conductivity meter inoper-able, additional samples must be analyzed to ensure that the chlorides are not exceeding the limits.
The surveillance requirements provide adequate assucance that concentrations in excess of the limits will be detected in sufficient time to take corrective action.
CLINTON - UNIT 1 B 3/4 4-4 Amendment No. Jg, 39
_