ML20247A740
| ML20247A740 | |
| Person / Time | |
|---|---|
| Site: | Fermi  |
| Issue date: | 04/27/1998 |
| From: | DETROIT EDISON CO. |
| To: | |
| Shared Package | |
| ML20247A728 | List: |
| References | |
| NUDOCS 9805060223 | |
| Download: ML20247A740 (10) | |
Text
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- to NRC-98-0065 Page 2 l
l I
I ENCLOSURE 3 - PART 1 PROPOSED TECIINICAL SPECIFICATION MARK-UP PAGES INCLUDED PAGE(S):
TS PAGE 6-16b TS PAm. BASES 3-1 i
I i
i l
9805060223 900427 PER ADOCK 05000341
.p PDR
ADMINISTRATIVE CONTROLS PROCEDLriES AND PROGRAMS (Continued) f.
DELETED l
, g.
Primary Containment Leakage Rate Testinw Program A program shall be established to implement the leakage rate testing of the containment as required by 10 CFR 50.54(O) and 10 CFR 50, Appendix J, Option B as modified by approved exemptions. 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,.
I L
h fi' The provisions of Specification 4.0.2 do not apply to the test i
M frequencies specif ed in the Primary Containment Leakage Rate i
Testing Program.
The provisions of Specification 4.0.3 are vpplicable to the Primary Containment Leakage Rate Testinq Program.
6.8.6 Administrative controts snall be oeveloped and implemented to limit the working hours of personnel wno periorm safety related functions (e.g., senior reactor operators, reactor operators, auxiliary operators, health physicists. and l
key maintenance personnett The controls shall include guide!ines on working
{
hours that ensure that acecuate snitt coverage is maintained without routine i
heavy use of overtime f or individuals.
l Arr/ dtviation from Ine worksng nour guidelines shall be authorized in advanco by the Plant Manager or nis cesignee. in accordance with approved administrative procecures, or oy nigner levels of management. in accordance with established procecures anc witn occumentation of the basis for granting the'ceviation. Controis snall be included in the procedures such that individual overtime snall be reviewee montnly by tne Plant Manager or his designee to ensure that excessive nours nave not been assigned. Routine deviation from the aoove guicettnes snali not De autnorized.
FERMI UNIT 2 616b Amendment No. SG. 448. !!3
INSERT Configuration Risk Management Program
)
The Configuration Risk Management Program (CRMP) provides a proceduralized risk informed assessment to manage the risk associated with equipment inoperability. The program applies to technical specification structures, systems, or components for which a risk-informed allo ved-outage-time (AOT) 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.
2.
Provisions for performing an assessment prior to entering the LCO ACTION STATEMENT for preplanned activities.
3.
Provisions for performing an assessment after ent: ring the LCO ACTION STATEMENT for unplanned entry into the LCO ACTION STATEMENT.
4.
Provisions for assessing the need for additional actions aller the discovery of additional equipment out of service conditions while in the LCO ACTION STATEMENT.
5.
Provisions for considering other applicable risk significant contributions such as Level 2 PRA issues and external events qualitatively, or quantitatively.
I
4 3/4.8 ELECTRICAL POWER SYSTEMS BASES 3/4.8.1. M4.8.2 and 3/4.8.3 A.C. SOURCES. D.C. STRCES and DNSITE p0WER DISTRIBUT: ON 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 shutdown of the facility and (2) the mitigation and control of accider.'
conditions within the facility.
The minimum specified independent anc 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.
The ACTION requirements specified for the levels of degradation of the power sources provide restriction upon continued facility operation commensurate with the level of degradation.
The OPERABILITY of the power sources is consistent with the initial condition assumptions of the safety analyses and is based upon maintaining at least one of the onsite A.C. nd the corresponding D.C. power sources and associated distribution systems OPERABLE during accident conditions coincident with an assumed loss of offsite t c.er and single failure of the other onsite A.C. or D.C. source.
h The A.C. and D.C. source allowable out-of-service times are based on Regulatory Guide 1.93, " Availability of Electrical Power Sources",
I h
December 1974.
When one diesel generator is inoperable, there is an v) additional ACTION requirement to verify that all required systems, subsystems, trains, components and aevices, that depend en the remaining OPERA 8LE diesel L
generator as a source of emergency power, are also DPERABLE.
This requirement i
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 administratively 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.
The OPERABILITY of the minimu= 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-Oll Systems for Standby Diesel Generators", Revision 1, October 1979, as modiff ad by Generic Letter 94-01, " Removal of Accelerated Testing and Special Reporting Requirements for Emergency Diesel Generators," May 1994.
FERMI a UNIT 2 B 3/4 8-1 Amendment No.107
INSERT When one or both diesel generators ia an electrical power division are inoperable, the allowed-outage-time (AOT) 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 managcment 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 AOT and cannot be restored to OPERABLE status, the diesel generator AOT 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.
. to NRC-98-0065 Page 3 l
ENCLOSURE 3 - PART 2 PROPOSED TECIINICAL SPECIFICATION REVISED PAGES INCLUDED PAGE(S):
l TS PAGE 6-16b TS PAGE 6-16e
{
TS PAGE HASES 8-1 TS PAGE BASES 8-la
)
l I'
l
L ADMINISTRATIVE CONTROLS PROCEDURES AND PROGRAMS (Continued) f.
DELETED g.
Primary Containment Leakage Rate Testing Program A program shall be established to implement the leakage rate 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.
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 assessment to manage the risk associated with equipment inoperability. The program applies to technical specification structures, systems, or conponents 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, intacoal events PRA-informed methodology. The assessment shall be capable of evaluating the applicable plant configuration.
2.
Provisions for performing an assessment prior to entering the LC0 ACTION STATEMENT for preplanned activities.
3.
Provisions for performing an assessment after entering the LC0 ACTION STATEMENT for unplanned entry into the LC0 ACTION STATEMENT.
4.
Provisions for assessing the need for additional actions after the discovery of adittional equipment out of service conditions while in the tCO ACT13N STATEMENT.
l l
FERMI - UNIT 2 6-16b Amendment No. $J, J##, IJ),
l l
9 ADMINISTRATIVE CONTROLS l
PROCEDURES AND PROGRAMS (Continued) l 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 l
working hours of personnel who perform safety-related functions (e.g., senior i
reactor operators, reactor operators, auxiliary operators, health physicists, and key maintenance personnel). The controls shall include guidelines on 1
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 ar.d with documentation of the basis for granting the deviation.
Controls shall be included in the procedures such that I
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.
6.9 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 REPORT 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 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 I
nuclear, thermal, or hydraulic performance of the unit.
6.9.1.2 The startup report shall address each of the tests identified in Subsection la.1.4.8 of the Final Safety Analysis Report and shall include a i
description of the measured values of the operating conditions or i
characteristics obtained during the test program and a comparison of these l
values with design predictions and specifications. Any corrective actions j
l-that were required to 1
FERMI - UNIT'2 6-16c Amendment No. JSS,
3/4'8 ELECTRICAL POWER SYSTEMS
-BASES 3/4.8.1. 3/4.8.2 and 3/4.8.3 A.C. SOURCES. D.C. SOURCES and ONSITE 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 shutdown of the facility _and-(2) the mitigation and control' of accident
)
conditions within the' facility. The minimum :.ecified 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.
The ACTION requirements specified for the levels of degradation of the
)
power sources provide restriction upon continued facility operation commensurate with the level of degradation. The OPERABILITY of the power sources is consistent with the initial condition assumptions of the safety analyses and is based upon maintaining at least one of the onsite 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 I
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 4
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 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 asturance 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 admi2nistratively 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.
- FERMI - UNIT 2 B 3/4 8-1 Amendment No.JJJ, t
4 1
. ELECTRICAL POWER SYSTEMS BASES l-t 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~
l associated distribution systems during shutdown and refueling onsures 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 - UNIl 2 B 3/4 8-la Amendment No.