ML20248K914
| ML20248K914 | |
| Person / Time | |
|---|---|
| Site: | Fermi  |
| Issue date: | 06/02/1998 |
| From: | Kugler A NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20248K916 | List: |
| References | |
| NUDOCS 9806100339 | |
| Download: ML20248K914 (11) | |
Text
e pn ace y
t UNITED STATES s
j NUCLEAR REGULATORY COMMISSION t
WASHINGTON, D.C. - anat
"%...../
DETROIT EDISON COMPANY DOCKET NO. 50-341 FERMl 2 AMENDMENT TO FAC!LITY OPERATING LICENSE Amendment No.119 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 November 22,1995 (NRC-95-0124), as supplemented February 19, April 19, May 3, June 12, and December 4,1996, January 30 and August 7, 1997, and April 27 and May 22,1998, 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; 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.
9906100339 900602 PDR ADOCK 05000341
E
, 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 amended to read as follows:
Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No.119, 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 l
Protection Plan.
3.
This license amendment is effective as of the date of its issuance with full implementation within 60 days.
FOR THE NUCLEAR REGULATORY COMMISSION I
Andrew J. Kugler, Project Manager Project Directorate 111-1 Division of Reactor Projects - lil/IV Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of issuance: June 2, 1998 i
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1 l
l l
ATTACHMENT TO LICENSE AMENDMENT NO.119 FACILITY OPERATING LICENSE NO. NPF-43 DOCKET NO. 50-341 Replace the fo!!owing pages of the Appendix "A" Technical Specifications with the attached pages. The revised pages are identified by amendment number and contain verticallines indicating the area of change.
l REMOVE INSERT 3/4 8-1 3/4 8-1 3/4 8-2 3/4 8-2 B 3/4 8-1 B 3/4 8-1 B 3/4 8-1a B 3/4 8-1a B 3/4 8-1b B 3/4 8-1b B 3/4 8-2 8 3/4 8-2*
6-16b 6-16b 6-16c 6-16c
' Overleaf pages provided to maintain document completeness. No changes contained on these pages.
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,3/4.8 ELECTRICAL POWER SYSTEMS 3/4.8.1 A.C. SOURCES-A.C. SOURCES - OPERATING LIMITING CONDITION FOR OPERATION 3.8.1.1 As a minimum, the following A.C. electrical power sources shall be OPERABLE:
a.
Two physically independent circuits between the offsite transmission network and the onsite Class IE distribution system, and b.
Two separate and independent onsite A.C. electrical power sources, Division I and Division II, each consisting of two emergency diesel generators, each diesel generator with:
1.
A separate day fuel tank containing a minimum of 210 gallons of fuel, 2.
A separate fuel storage system containing a minimum of 35,280 gallons of fuel, and 3.
A separate fuel transfer pump.
APPLICABILITY: OPERATIONAL CONDITIONS 1, 2, and 3.
ACTION:
a.
With one or both offsite circuits of the above required A.C.
electrical power sources inoperable, be in at least HOT SHUTDOWN within 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 next 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />; demonstrate the OPERABILITY of the remaining A.C. sources by performing Surveillance Requirement 4.8.1.1.1. within one hour and at least once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> thereafter and, b.
With one or both diesel generators in one of the above required onsite A.C. electrical power divisions inoperable; 1.
Demonstrate the OPERABILITY of the remaining A.C. sources by performing Surveillance Requirement 4.8.1.1.1 within one hour and at least once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> thereafter, and if the diesel generator (s) became inoperable due to any cause other than an ir. operable support system, an independently testable component, or preplanned preventive maintenance or testing, by performing Surveillance Requirement 4.8.1.1.2.a.4 for one diesel generator at a time within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, unless the absence of any potential common mode failure for the remaining diesel generators is determined, and I'
FERMI UNIT.2 3/4 8-1 Amendment No. M,119
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ELECTRICAL POWER SYSTEMS LIMITING CONDITION FOR OPERATION (Continued)
ACTION (Continued) 2.
Verify within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> and at least once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> thereafter, that CTG 11-1 is OPERABLE. Restore the inoperable division 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 />.
g 3.
If the requirements of ACTION b.2. above for CTG 11-1 cannot be met, either restore the inoperable division to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> (not to exceed 7 days from the time the division became inoperable); or, satisfy the requirements of ACTION b.2 above within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> and restore the inoperable division to OPERABLE status within 7 days from the time the division became inoperable; 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 />.
c.
With one or both diesel generators in one of the above required onsite A.C. electrical power divisions inoperable, in addition to ACTION b, above, verify within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> that all required systems, subsystems, trains, components and devices that depend on the remaining onsite A.C. electrical power division as a source of emergency power are also OPERABLE; 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 /> 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 />.
d.
With both of the above required onsite A.C. electrical power divisions inoperable; 1.
Demonstrate the OPERABILITY of the remaining A.C. sources by performing Surveillance Requirement 4.8.1.1.1 within one hour and at least once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> thereafter; and 2.
Restore at least one of the above required inoperable divisions to OPERABLE status within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> 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 />; and 3.
Restore the second of the above required divisions to OPERABLE status within the time required by Action b above from the time of initial loss 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 />.
FERMI - UNIT 2 3/4 8-2 Amendment No.119
3/4.8 ELECTRICAL POWER SYSTEMS BASES l
3/4.8.1. 3/4.8.2 and 3/4.8.3 A.C. SOURCES. D.C. SOURCES and DNSITE POWER DISTRIBUTION SYSTEMS The OPERABILITY of the A.C. and D.C. power sources and associated distribution systems during operation ensures that sufficient power will be available to supply the safety related equipment required for (1) the safe l
shutdewn of the facility and (2) the mitigation and control of accident conditions within the facility. The minimum specified independent and redundant A.C. and D.C. power sources and distribution systems satisfy the requirements of General Design Criteria 17 of Appendix "A" to 10 CFR 50.
j The ACTION requirements specified for the levels of degradation of the power sources provide restriction upon continued facility coeration commensurate with the level of degradation. The OPERABILITY of the power sources is consistent with the initial condition assumptions cJ the safety analyses and is based upon' maintaining at least one of the onsi w A.C. and the corresponding D.C. power sources and associated distribution systems OPERABLE during accident conditions coincident with an assumed loss of offsite power and single failure of the other onsite A.C. or D.C. source.
When one or both diesel generators in an electrical power division are inoperable, the allowed-outage-time (A0T) is extended from 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> to 7 days if CTG 11-1 is verified to be OPERABLE. As required by Section 6.8.5.h, a configuration risk management program is implemented when applying this ACTION. CTG 11-1 verification (by administrative check of breaker status, line availability and CTG 11-1 status) will confirm that CTG 11-1 is capable of supplying power to Division I loads. The verification is performed prior to taking the diesel generator out of service for extended maintenance.
If CTG 11-1 becomes inoperable during the 7 day A0T and cannot be restored to OPERABLE status, the diesel generator A0T reverts back to 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> not to exceed a total of 7 days from the time the diesel generator originally became inoperable.
The A.C. and D.C. source allowable out-of-service times are based, in part on Regulatory Guide 1.93, " Availability of Electrical Power Sources", December 1974. When one diesel generator is inoperable, there is an additional ACTION requirement to verify that all required systems, subsystems, trains, components and devices, that depend on the remaining OPERABLE diesel generator as a source of emergency power, are also OPERABLE. This requirement is intended to provide assurance that a loss of offsite power event will not
. result in a complete loss of safety function of critical systems during the period one of the diesel generators is inoperable. The term verify as used in this context means to administrative 1y check by examining logs or other information to determine if certain components are out-of-service for maintenance or other reasons.
It does not mean to perform the surveillance requirements needed to demonstrate the OPERABILITY of the component.
l FERMI UNIT 2 B 3/4 8 1 Amendment No.JU,119 E__
ELECTRICAL POWER SYSTEMS BASES A.C. SOURCES. D.C. SOURCES. and ONSITE POWER DISTRIBUTION SYSTEMS (Continued)
The OPERABILITY of the minimum specified A.C. and D.C. power sources and
~ associated distribution systems during shutdown and refueling ensures that (1) the facility can be maintained in the shutdown or refueling condition for extended time periods and (2) sufficient instrumentation and control capability is available for monitoring and maintaining the unit status.
The surveillance requirements for demonstrating the OPERABILITY of the diesel generators are in accordance with the recommendations of Regulatory Guide 1.9, " Selection of Diesel Generator Set Capacity for Standby Power Supplies", December 1979; Regulatory Guide 1.108, " Periodic Testing of Diesel Generator Units Used as Onsite Electric Power Systems at Nuclear Power Plants", Revision 1, August 1977; and Regulatory Guide 1.137, " Fuel-011 Systems for Standby Diesel Generators", Revision 1, October 1979, as modified by Generic Letter 94-01, " Removal of Accelerated Testing and Special Reporting Requirements for Emergency Diesel Generators," May 1994.
FERMI - UNIT 2 B 3/4 8-la Amendment No. 107. 119
l THIS PAGE INTENTIONALLY LEFT BLANK l
FERMI - UNIT 2 B 3/4 8-Ib Amendment No.119
ELECTRICAL POWER SYSTEMS i
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BASES A.C. SOURCES. D.C. SOURCES. and DNSITE POWER DISTRIBUTION SYSTEMS (Continued)
The surveillance requirements for demonstrating the OPERABILITY of the unit batteries are in accordance with the recommendations of Regulatory Guide 1.129 " Maintenance Testing and Replacement of Large Lead Storage Batteries for Nuclear Power Plants,' February 1978, and IEEE Std 450-1972, 'IEEE Recommended Practice for Maintenance. Testing, and Replacement of Large Lead Storage Batteries for Generating Stations and Substations."
Verifying average electrolyte temperature above the minimum for which the battery was sized, total battery terminal voltage on float charge, connection resistance values and the performance of battery service and discharge tests ensures the effectiveness of the charging system, the ability to handle high discharge rates and compares the battery capacity at that time with the rated capacity.
Table 4.8.2.1-1 specifies the normal limits for each designated pilot cell and each connected cell for electrolyte level, float voltage and specific gravity. The limits for the designated pilot cells float voltage and specific gravity, greater than 2.13 volts and 0.015 below the manufacturer's full charge specific gravity or a battery charger current that had stabilized at a low value, is characteristic of a charged cell with adequate capacity. The normal limits for each connected cell for float voltage and specific gravity, greater than 2.33 volts and not more than 0.020 below the manufacturer's full charge specific gravity with an average specific gravity of all the connected cells not more than 0.010 below the manufacturer's full charge specific gravity, ensures the OPERABILITY and capability of the battery.
Operation with a battery cell's parameter outside the normal limit but within the allowable value specified in Table 4.8.2.1-1 is permitted for up to 7 days. During this 7 day period:
(1) the allowable values for electrolyte level ensures no physical damage to the plates with an adequate electron transfer capability; (2) the allowable value for the average specific gravity of all the cells, not more than 0.020 below the manufacturer's recommended full charge specific gravity ensures that the decrease in rating will be less than the safety margin provided in sizing; (3) the allowable value for an individual cell's specific gravity ensures that an individual cell's specific gravity will not be more than 0.020 below the manufacturer's full charge specific gravity and that the overall capability of the battery will be maintained within an acceptable limit; and (4) the allowable value for an individual cell's float voltage, greater than 2.07 volts, ensures the battery's capability to perform its design function.
The battery chargers and A.C. distribution systems rely on the Ene ency Equipment Cooling Water (EECW) system to cool the associated rooms where his I
I equipment is located.
Thesecomhonentsretainsubstantialcapabilitywithout I
cooling following an accident.
ased upLn this capability, rovisions have been made to delay the ACTION requirements for the inoperabi ity of these I
components if caused by the lack of EECW cooling.
FERMI - UNIT 2 8 3/4 8-2 Amendment No. J,80 N8 1992
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1 ADMINISTRATIVE CONTROLS PROCEDURES AND PROGRAMS (Continued) f.
DELETED g.
Primary Containment Leakage Rate Testing Program i
A program shall be established to implement the leakage rate I
testing of the containment as required by 10 CFR 50.54(0) and 10 CFR 50, Appendix J, Option B as modified by approved exemptions.
1 This program shall be in accordance with the guidelines contained in Regulatory Guide 1.163, " Performance-Based containment Leak-Test Program," dated September 1995.
The peak calculated containment internal pressure for the design basis loss of coolant accident, P., is 56.5 psig.
The maximum allowable primary containment leakage rate, L., shall be 0.5% of primary containment air weight per day at P..
The provisions of Specification 4.0.2 do not apply to the test frequencies specified in the Primary Containment Leakage Rate Testing Program.
The provisions of Specification 4.0.3 are applicable to the Primary Containment Leakage Rate Testing Program.
h.
Configuration Risk Manaaement Proaram The Configuration Risk Management Program (CRMP) provides a proceduralized risk informed arsessment to manage the risk associated with equipment inoperability. The program applies to technical specification structures, systems, or components for which a risk-informed allowed-outage-time has been granted (Specification 3.8.1.1.b.2).
The program shall include the following elements:
1.
Provisions for control and implementation of a level 1, at power, internal events PRA-informed methodology.
The assessment shall be capable of evaluating the applicable plant configuration.
l 2.
Provisions for performing an assessment prior to entering I
the LCO ACTION STATEMENT for preplanned activities.
3.
Provisions for performing an assessment after entering the l
LCO ACTION STATEMENT for unplanned entry into the LCO ACTION STATEMENT.
4.
Provisions for assessing the need for additional actions after the discovery of additional equipment out of service conditions while in the LCO ACTION STATEMENT.
i FERMI - UNIT 2 6-16b Amendment No. 5J, JJp, JJJ,119 -
ADMINISTRATIVE CONTROLS PROCEDURES AND PROGRAMS (Continued) 5.
Provisions for considering other applicable risk significant contributions such as Level 2 PRA issues and external events, qualitatively, or quantitatively.
6.8.6 Administrative controls shall be developed and implemented to limit the working hours of personnel who perform safety-related functions (e.g., senior reactor operators, reactor operators, auxiliary operators, health physicists, and key maintenance personnel). The controls shall include guidelines on working hours that ensure that adequate shift coverage is maintained without routine heavy use of overtime for individuals.
Any deviation from the working hour guidelines shall be authorized in advance by the Plant Manager or his designee, in accordance with approved administrative procedures, or by higher levels of management, in accordance with established procedures and with documentation of the basis for granting the deviation. Cont,rols shall be included in the procedures such that individual overtime shall be reviewed monthly by the Plant Manager or his designee to ensure that excessive hours have not been assigned. Routine deviation from the above guidelines shall not be authorized.
19 REPORTING REQUIREMENTS ROUTINE REPORTS 6.9.1 In addition to the applicable reporting requirements of Title 10, Code of Federal Regulations, the following reports shall be submitted to the Regional Administrator of the Regional Office of the NRC unless otherwise noted.
STARTUP REFORT 6.9.1.1 A summary report of plant startup and power escalation testing shall be submitted following (1) receipt of an Operating License, (2) amendment to i
i the license involving a planned increase in power level, (3) installation of fuel that has a different design or has been manufactured by a different fuel supplier, and (4) modifications that may have significantly altered the nuclear, thermal, or hydraulic performance of the unit.
6.9.1.2 The startup report shall address each of the tests identified in Subsection 14.1.4.8 of the Final Safety Analysis Report and shall include a description of the measured values of the operating conditions or characteristics obtained during the test program and a comparison of these values with design predictions and specifications. Any corrective actions that were required to FERMI - UNIT 2 6-16c Amendment No. Jp5/15.119