ML20148C761
| ML20148C761 | |
| Person / Time | |
|---|---|
| Site: | Fermi  |
| Issue date: | 01/12/1988 |
| From: | Holahan G Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20148C766 | List: |
| References | |
| NUDOCS 8801250253 | |
| Download: ML20148C761 (8) | |
Text
8[
UNITED STATES NUCLEAR REGULATORY COMMISSION o
g
-p WASHINGTON, D. C. 20555
%,...../
DETROIT EDISON COMPANY WOLVERINE POWER SUPPLY COOPERATIVE, INCORPORATED DOCKET NO. 50-341 FERMI-2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.14 License No. NPF-43 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by the Detroit Edison Company (the licensee) dated January 6, 1988, 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; 8.
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.
Theissuanceofthisamendmenkwillnotbeinimicaltothecommon 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 Specifica-tions as indicated in the attachment to this license amendment and paragraph 2.C.(2) of the Facility Operating License No. NPF-43 is hereby amended to read as follows:
Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No.14, and the Environmental Protection Plan contained in Appendix B, are hereby incorporated in the license.
DECO shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
h!bDbh f
P
2-3.
This license amendment is effective as of the date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION Y} Wl Gary M. Holahan, Assistant Director for Regions III and V Div?sion of Reactor Projects - III, IV, V
& Special Projects
Attachment:
Changes to the Technical Specifications Date of Issuance: January 12, 1988 4
I 1
i e
mr
,.em
__m
--.~-nmy
,.yp-
-,=w--<ww-
ATTACHMENT TO LICENSE AMENDMENT NO.14 FACILITY OPERATING LICENSE NO. NPF-43 DOCKET NO. 50-341 Replace the following pages of the Appendix "A" Technical Specifications with the enclosed pages.
The revised pages are identified by Amendment number and contain a vertical line indicating the area of change.
The corresponding overleaf pages are also provided to maintain document completeness.
REMOVE INSERT 3/4 4-12 3/4 4-:2 8 3/4 4-2 B 3/4 4-2 B 3/4 4-2a J
a I
~
~
[
J SURVEILLANCE REQUIREMENTS 4.4.3.2.1 The reactor coolant system leakage shall be demonstrated to be within l
each of the above limits by:
Monitoring the primary containment atmospheric gaseous radioactivity a.
at least once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />,*
b.
Monitoring the primary containment sump flow rate at least once per p
4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />, Monitoring the drywell floor drain sump level at least once per c.
4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />, and 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 />.*
Each reactor coolant system pressure isolation valve specified in 4.4.3.2.2 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 1
specified limit:
a.
At least once per 18 months, and Prior to returning the valve to service following maintenance, b.
repair or replacement work on the valve which could affect its leakage rate.
The provisions of Specification 4.0.4 are not applicable for entry into OPERATIONAL CONDITION 3.
The high/ low pressure interface valve leakage pressure monitors 4.4.3.2.3 shall be demonstrated OPERABLE with alarm setpoints per Table 3.4.3.2-2 by performance of a:
CHANNEL FUNCTIONAL TEST at least once per 31 days, and a.
b.
CHANNEL CALIBRATION at least once per 18 months.
w F
- Not a means of quantifying leakage.
'N
'3/4 4-11 FERMI - UNIT 2
TABLE 3.4.3.2-1 REACTOR COOLANT SYSTEM PRESSURE ISOLATION VALVES VALVE NUMBER VALVE DESCRIPTION I
1.
RHR System E11-F015A LPCI Loop A Injection Isolation Valve LPCI Loop B Injection Isolation Valve E11-F015B E11-F050A LPCI Loop A Injection Line Testable Check Valve E11-F0508 LPCI Loop B Injection Line Testable i
Check Valve E11-FU23 RPV Head Spray Outboard Isolation Yalve E11-F022 RPV Head Spray Inboard Isolation Valve Shutdown Cooling RPV Suction Outboard E11-F008 Isolation Valve E11-F009 Shutdown Cooling RPV Suction Inboard Isolation Valve E11-F608 Shutdown Cooling Suction Isolation Valve 2
Core Spray System E21-F005A Loop A Inboard Isolation Valve E21-F005B Loop B Inboard Isolation Valve E21-F006A Loop A Containment Check Valve E21-F006B Loop B Containment Check Valve 3.
High Pressure Coolant Injection System E41-F007 Pump Discharge Outboard Isolation Valve E41-F006 Pump Discharge Inboard Isolation Valve 4.
Reactor Core Isolation Cooling System E51-F012 Pump Discharge Isolation Valve E51-F013 Pump Discharge to Feedwater Header Isolation Valve TABLE 3.4.3.2-2 REACTOR COOLANT SYSTEM INTERFACE VALVES LEAKAGE PRESSURE MONITORS ALARM SETPOINT 1
VALVE NUMBER SYSTEM (psia)
E11-F015A & B, E11-F022, F023, RHR LPCI
< 449
~
E11-F050A & B E11-F008, F009, F608 RHR Shutdown Cooling
< 135 E21-F005A & B, E21-F006A & B Core Spray 7 452 E41-F006, F007 HPCI i 71 E51-F012, F013 RCIC 5 71 FERMI - UNIT 2 3/4 4-12 Amendment No.14 1
[
3/4.4 REACTOR COOLANT SYSTEM BASES 3/4.4.1 RECIRCULATION SYSTEM Operation with one reactor core coolant recirculation loop inoperable is l
prohibited until an evaluation of the performance of the ECCS during one loop operation has been performed, evaluated, and determined to be acceptable.
An inoperable jet pump is not, in itself, a sufficient reason to declare a recirculation loop inoperable, but it does, in case of a design-basis-accident, increase the blowdown area and reduce the capability of reflooding the core;
[
thus, the requirement for shutdown of the facility with a jet pump inoperable.
Jet pump failure can be detected by monitoring jet pump performance on a prescribed schedule for significant degradation.
Recirculation pump speed mismatch limits are in compliance with the ECCS
.I LOCA analysis design criteria.
In order to prevent undue stress on the vessel nozzles and bottom head region, the recirculation loop temperatures shall be within 50 F of each other prior to startup of an idle loop.
The loop temperature must also be within 50 F of the reactor pressure vessel coolant temperature to prevent thernal 4
shock to the recirculation pump and recirculation nozzles.
Since the coolant in the bottom of the vessel is at a lower temperature than the coolant in the upper
~
M regions of the core, undue stress on the vessel would result if the temperature difference was greater than 145 F.
Q 3/4.4.2 SAFETY / RELIEF VALVES g
The safety valve function of the safety / relief valves operate to prevent the reactor coolant system from being pressurized above the Safety Limit of i
1325 psig in accordance with the ASME 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.
Demonstration of the safety / relief valve lift settings will occur only during shutdown and will be performed in accordance with the provisions of Specification 4.0.5.
J The low-low set system ensures that a potentially high thrust load (desig-nated as load case C.3.3) on the SRV discharge lines is eliminated during sub-sequent actuations.
This is achieved by automatically lowering the closing set-point of two valves and lowering the opening setpoint of two valves following the initial opening.
Sufficient redundancy is provided for the low-low set system such that failure of any one valve to open or close at its reduced setpoint does not violate the design basis.
FERMI - UNIT 2 B 3/4 4-1
.1 REACTOR COOLANT SYSTEM BASES i
3/4.4.3 REACTOR COOLANT SYSTEM LEAKAGE 3/4.4.3.1 LEAKAGE DETECTION SYSTEMS The RCS leakage detection systems required by this specification are provided to monitor and detect leakage from the reactor coolant pressure 1
boundary.
These detection systems are consistent with the recommendations of Regulatory Guide 1.45, "Reactor Coolant Pressure Boundary Leakage Detection Systems", May 1973.
3/4.4.3.2 OPERATIONAL LEAKAGE The allowable leakage rates from the reactor coolant system have been based on the predicted and experimentally observed behavior of cracks in pipes.
The normally expected background leakage due to equipment design and the detection capability of the instrumentation for determining system leakage was also con-sidered.
The evidence obtained from experiments suggests that for leakage somewhat 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 specified or the leakage is located and known to be PRESSURE BOUNDARY LEAKAGE, the reactor will be shutdown to allow further investigation and corrective action.
Service sensitive reactor coolant system Type 304 and 316 austenitic stainless steel piping; i.e., those that are subject to high stress or that contain relatively
]
stagnant, intermittent, or low flow fluids, requires additional surveillance i
and leakage limits.
l The purpose of the RCS interface valves leakage pressure monitors (LPMs) is to provide assurance of the integrity of the Reactor Coolant System pres-sure isolation valves which form a high/ low pressure boundary.
The LPM is designed to alarm on increasing pressure on the low pressure side of the high/
low pressure interface to provide indication to the operator of abnormal interface valve leakage.
The Surveillance 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 isolation 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 ccerosion to occur is not present so a 0.5 ppm concentration of chlorides is not considered harmful during these periods.
FERMI - UNIT 2 B 3/4 4-2 Amendment No.14
REACTOR COOLANT SYSTEM BASES CHEMISTRY (Continued)
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 also be within their acceptable limits. With the conductivity meter inoperable, additional samples must be analyzed to ensure that the chlorides are not exceeding the limits.
The surveillance requirements provide adequate assurance that concentrations in excess of the limits will be detected in sufficient time to take corrective action.
21 M
h ny m
Jah y
1 1
FERMI - UNIT 2 B 3/4 4-2a Amendment No. 14 1
-____.___m__,
,, _.,