ML20099G330
| ML20099G330 | |
| Person / Time | |
|---|---|
| Site: | Fermi  |
| Issue date: | 07/31/1992 |
| From: | Marsh L Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20099G332 | List: |
| References | |
| NUDOCS 9208140222 | |
| Download: ML20099G330 (5) | |
Text
.
/p* %9'o UNITE D STATES Ig
[' 3 m g
NUCLEAR RF.GULATORY COMMISSION g
C WASHINGTON, D, C, 70555 I
%,...../
DETROIT EDISON COMPANY
)
FERMI-2 DOCKET NO. 50-341 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 85 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 l
licensee) dated January 30, 1992, complies with the standards and recuirements of the Atomic Energy Act of 1954, as amended (the Act),
anc the Commission's rules and regulations set forth in 10 CFR Chapter I;
B.
The facility will op rate in conformity with the application, the provisions of the Act,- and the rules and regulations of the Commission; C.
There is reasonable assurance (1) 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 correnon 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 Facility Operating License No. NPF-43 is hereby amended to read as follows:
Technical Specifications and Environmental Proteatfon Plan The Technical Specifications contained in Appendix A, as revised
.orough Amendment No._85, and the Environmental Protection Plan contained in Appendix B, are hereby incorporated in the license.
Deco shall or s ate the facility in accordance with the Technical Specifi lons and the Environmental Protection Plan.
9200140222 920731 PDR ADOCK 05000341 P
PDR u
- 3.
This license amendment is effective as of the date of its issuance with full implementation within 30 days.
FOR THE NUCLEAR REGULATORY COMMISSION Ledyard B. Marsh, Director Project Directorate 111-1 Division of Reactor Projects Ill/IV/V Office of Nuclear Reacto* Regulation
Attachment:
Changes to the lechnical Specifications Date of Issuance:. July 31, 1992
\\
ATTACHMENT TO LICENSE AMENDMENT NO. 85 FAClllTY OPERATING LICENSE NO. NPF-43 DOCKET NO. 50-341 Replace the following page of the Appendix "A" Technical Specifications with the attached page.
The revised page is identified by Amendment number and contains a vertical line indicating the area of change.
The corresponding overleaf page is also provided to maintain document completeness.
REMOVE INSERT 3/4 4-11*
3/4 4-11*
3/4 4-12 3/4 4-12
- 0verleaf page provided to maintain document completeness. No changes are contained in this page.
REACTOR COOLANT SYSTEM SURVEILLANCE REQUIREMENTS l
4.4.3.2.1 The reactor coolant system leakage shall be demonstrated to be within each of the above limits by:
Monitoring the primary containment atmo pheric 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 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />, c.
Mcnitoring the drywell floor drain sump level at least once per 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 />.*
4.4.3.2.2 Each reactor coolant system pressure isolatica 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:
r a.
At least once per 18 months, and b.
Prior to returning the valve to service following paintenance, 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.
4.4.3.2.3 The high/ low pressure interface valve leakage pressure monitors
-shall be-deronstrated OPERABLE with alare 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.
"Not a means of quantifying leakage.
i
- FERMI - UNIT 2 3/4 4-11
+
_T_ABLE 3.4.3.2-1 REACTOR COOLANT SYSTEM PRESSURE ISOLATION VALVES VALVE NUMBER VALVE DESCRIPTION 1.
RHR System Ell F015A LPCI loop A Injection Isolation Valve E11-F015B LPCI Loop B Injection Isolation Valve E11-F050A LPCI Loop A Injection Line Testable Check Valve Ell-F050B LPCI toop B Injection Line Testable Check Valve l
t Ell F008 Shutdown Cooling RPV Suction Outboard Isolation Valve E11 F009 Shutdown Cooling RPV Suction inboard Isolation Valve Ell-F608 -
Shutdown Cooling Suction Isolation Valve 2.
' Core-Spray System L
E21-F005A Loop A Inboard Isolation Valve E21-F005B Loop B Inboard Isolation Valve E21-F006A Loop A Containment Check Valve L
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 ~lsolation Cooling System E51 F012 Pump Disch_*ge Isolation Valve E51 F013 Pump Disci "Je to feedwater Header Isolation Valve TABLE 3.4.3.2-2 REACTOR COOLANT SYSTEM INTERFACE VALVES jEAXAGE PRESSURE MONITORS ALARM SETPOINT VALVE NUMBER SYSTEM
_fosia)._
Ell-F015A & B, Ell-F050A & B RHR LPCI s 449-
_j Ell-F008, F009, F608 RHR Shutdown Cooling s 135 E21 F005A & B, E21-F006A & B Core Spray s 452 E41-F006, F007 HPCI s 71 E51-F012,-.r013 RCIC s 71 FERMI - UNIT 2-3/4 4-12 Amendment No. U, 85
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