ML20134F695
| ML20134F695 | |
| Person / Time | |
|---|---|
| Site: | Fermi  |
| Issue date: | 11/05/1996 |
| From: | Kugler A NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20134F697 | List: |
| References | |
| NUDOCS 9611070142 | |
| Download: ML20134F695 (7) | |
Text
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p ua 0-1 UNITED STATES j
j NUCLEAR REGULATORY COMMISSION f
WASHINGTON, D.C. 20066-0001 4
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DETROIT EDISON COMPANY DOCKET NO. 50-341 FERMI-2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.109 License No. NPF-43 1.
The Nuclear Regulatory Commission (the Comission) has found that:
A.
The application for amendment by the Detroit Edison Company (the j
licensee) dated September 5, 1996, as supplemented by letters dated October 14, 1996, October 23, 1996, October 29, 1996, and i
October 31, 1996, 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; i
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 i
defense and security or to the health and safety of the public; i
and 1
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.
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I 9611070142 961105 PDR ADOCK 05000341 P
2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment and paragraph 2.C.(2) of Facility Operating License No. NPF-43 is hereby j
amended to read as follows:
Technical Snecifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No.109, 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 l
Specifications and the Environmental Protection Plan.
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This license amendment is effective as of the date of its issuance with full implementation within 45 days.
FOR THE NUCLEAR REGULATORY COMISSION ad Andrew J. Kugler, Project Manager Project Directorate 111-1 Division of Reactor Projects - III/IV i
Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance:
November 5, 1996
i ATTACHMENT TO LICENSE AMENDMENT NO.109 FACILITY OPERATING LICENSE NO. NPF-43 DOCKET NO. 50-341 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.
REMOVE INSERT 2-1 2-1 d
2-2 2-2*
3/4 4-1 3/4 4-1 3/4 4-2 3/4 4-2*
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- 0verleaf page provided to maintain document completeness. No changes contained on these pages.
2.0 SAFETY LIMITS AND LIMITING SAFETY SYSTEM SETTINGS 1
2.1 SAFETY LIMITS l
l IHERMAL POWER. Low Pressure or Low Flow l
2.1.1 THERMAL POWER shall not exceed 25% of RATED THERMAL POWER with the i
reactor vessel steam dome pressure less than 785 psig or core flow less than j
10% of rated flow.
4 APPLICABILITY: OPERATIONAL CONDITIONS I and 2.
AGIlQli:
i With THERMAL POWER exceeding 25% of RATED THERMAL POWER and the reactor vessel steam dome pressure less than 785 psig or core flow less than 10% of rated j
flow, be in at least HOT SHUTDOWN within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> and comply with the j
requirements of Specification 6.7.1.
l THERMAL POWER. Hiah Pressure and Hiah Flow
- 2.1.2' The MINIMUM CRITICAL POWER RATIO (MCPR) shall not be less than the Safety Limit MCPR of 1.09 for two recirculation loop operation and shall not i
be less than the. Safety Limit MCPR of 1.11 for single loop operation with the reactor vessel steam dome pressure greater than 785 psig and core flow greater than 10% of rated flow.
i APPLICABILITY: OPERATIONAL CONDITIONS 1 and 2.
ACTION:
With MCPR less than the Safety Limit MCPR of 1.09 for two recirculation loop i
operation or less than the Safety Limit MCPR of 1.11 for single loop operation i
and with the reactor vessel steam dome pressure greater than 785 psig and core
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flow greater than 10% of rated flow, be in at least HOT SHUTDOWN within 2 l
hours and comply with the requirements of Specification 6.7.1.
l REACTOR COOLANT SYSTEM PRESSURE 2.1.3 The reactor coolant system pressure, as measured in the reactor vessel i
steam dome, shall not exceed 1325 psig.
APPLICABILITY: OPERATIONAL CONDITIONS 1, 2, 3 and 4.
{
ACTION:
With the reactor coolant system pressure, as measured in the reactor vessel steam dome, above 1325 psig, be in at least HOT SHUTDOWN with reactor coolant system pressure less than or equal to 1325 psig within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> and comply with 4
l the requirements of Specification 6.7.1.
a
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- MCPR val es in Technical Specification 2.1.2 are applicable for Cycle 6 operation u
only.
FERMI - UNIT 2 2-1 Amendment No. M, y,109 I
i SAFETY LIMITS AND LIMITING SAFETY SYSTEM SETTINGS SAFETY LIMITS (Continued)
2.1.4 The reactor vessel water level shall be above the top of the active irradiated fuel.
APPLICABILITY: OPERATIONAL CONDITIONS 3, 4 and 5 i
I ACTION:
With the reactor vessel water ~'evel at or below the top of the active irradiated fuel, manually initJate the ECCS to restore the water level, after depressurizing the reactor vessel, if required.
Comply with the requirements of Specification 6.7.1.
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FERMI - UNIT 2 2-2
3/4.4 REACTOR COOLANT S1SIEM 3/4.4.1 RECIRCULATION SYSTEM RECIRCULATION LOOPS LIMITING CONDITION FOR OPERATION l
3.4.1.1 Two reactor coolant system recirculation loops shall be in operation.
APPLICABILITY: OPERATIONAL CONDITIONS I and 2*.
ACTION:
I a.
With one reactor coolant system recirculation loop not in operation:
1.
Within 4 hour4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />s:
a)
Place the individual recirculation pump flow controller for the operating recirculation pump in the Manual mode.
b) Reduce THERMAL POWER to less than or equal to 67.2% of RATED THERMAL POWER.
c)
Limit the speed of the operating recirculation pump to less than or equal to 75% of rated pump speed.
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d)
Increase the MINIMUM CRITICAL POWER RA'i!O (MCPR) Safety Limit to the value for single loop operation required by Specification 2.1.2.
e)
Reduce the Average Power Range Monitor (APRM) Scram and Rod Block Trip Setpoints and Allowable Values to those applicable for single recirculation loop operation 8 per Specifications 2.2.1 and 3.3.6.
f)
Perform Surveillance Requirement 4.4.1.1.4 if THERMAL POWER is less than or equal to 30% of RATED THERMAL DOWER or the recirculation loop flow in the operating loop is less than or equal to 50% of rated loop flow.
2.
Otherwise, 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 />, b.
With no reactor coolant system recirculation loop in operation while in OPERATIONAL CONDITION 1, immediately place the Reactor Mode Switch in the SHUTDOWN position.
c.
With no reactor coolant system recirculation loops in operation, while in OPERATIONAL CONDITION 2, initiate measures to place the unit in at least HOT SHUTDOWN within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />, l
- See Special Test Exception 3.10.4.
8APRM gain adjustments may be made in lieu of adjusting the APRM Flow Bia:ed l
Setpoints to comply with the single loop values for a period of up to 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />.
FERMI - UNIT 2 3/4 4-1 Amendment No. JJ,JJ,JJ,JJ,J/,109 1
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SURVEILLANCE REQUIREMENTS 4.4.1.1.1 Each pump discharge valve shall be demonstrated OPERABLE by cycling each valve tirough at least one complete cycle of full travel during j
each STARTUP* prior to THERMAL POWER exceeding 25% of RATED THERMAL POWER.
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4.4.1.1.2 Each pump MG set scoop tube mechanical and electrical stop shall be demonstrated OPERABLE with overspeed setpoints less than or equal to 110%
i and 107%, respectively, of rated core flow, at least once per 18 months.
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4.4.1.1.3 With one reactor coolant system recirculation loop not in j
operation, at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> verify that:
I a.
THERMAL POWER is less than.or equal to 67.2% of RATED l
THERMAL POWER, and b.
The individual recirculation pump flow controller for the
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operating recirculation pump is in the Manual mode, and l
c.
The speed of the operating recirculation pump is less than or equal to 75% of rated pump speed.
l 4.4.1.1.4 With one reactor coolant system loop not in operation with THERMAL i
POWER less than or equal to 30% of RATED THEPML POWER or witF. recirculation j
loop flow in the operating loop less than or soual to 50% of rated loop flow, verify the following differential temperature requirements are met within no j
l more than 15 minutes prior to either THERMAL POWER increase or recirculation i
flow increase:
a.
Less than or equal to 145'F between reactor vessel steam l
space coolant and bottom head drain line coolant, and i
b.
Less than or equal to 50'F between the reactor coolant L
within the loop not in operation and the coolant in the reactor pressure vessel **, and c.
Less than or equal to 50*F between the reactor coolant j
within the loop not in operation and the eperating loop.**
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- If not performed within the previous 31 days.
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- Requirement does not apply when the recirculation loop not in operation is j
isolated from the reactor pressure vessel.
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FERMI - UNIT 2 3/4 4-2 Amendment No. J), #7,87 4
SEP 9 1992 j
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