ML20133G359
| ML20133G359 | |
| Person / Time | |
|---|---|
| Site: | Wolf Creek  |
| Issue date: | 01/08/1997 |
| From: | Stone J NRC (Affiliation Not Assigned) |
| To: | Carns N WOLF CREEK NUCLEAR OPERATING CORP. |
| References | |
| TAC-M97494, NUDOCS 9701160010 | |
| Download: ML20133G359 (5) | |
Text
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January 8,1997 4
Mr. Neil S. Carns President and Chief Executive Officer Wolf Creek Nuclear Operating Corporation Post Office Box 411 Burlington, Kansas 66839
SUBJECT:
WOLF CREEK GENERATING STATION - TECHNICAL SPECIFICATION BASES CHANGE (TAC NO. M97494)
Dear Mr. Carns-The staff has incorporated the revision of the technical specification Bases provided by your letter of December 20, 1996, into the Wolf Creek Generating Station Technical Specifications.
The revision better defines the time restraints associated with Technical Specification 3.8.1.1, " Electrical Power Systems - A.C. Sources," Actions b and c.
The staff has reviewed the change and finds the revision to the associated technical specification Bases to be acceptable.
The overleaf page is provided to maintain document completeness.
Sincerely, Original Signed By James C. Stone, Senior Project Manager Project Directorate IV-2 Division of Reactor Projects III/IV Office of Nuclear Reactor Regulation i
Docket No. 50-482 DISTRIBUTION:
' Docket?
GHill (2)
Enclosure:
Bases Page PUBLIC CGrimes j
PDIV-2 Reading WJohnson, Region IV j
cc w/ encl:
See next page JRoe LHurley, Region IV EAdensam
^JKilcrease, Region IV WBateman
- JCalvo, JStone.
EPeyton OGC
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ACRS Document Name:
97494.WC 3
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i NAME EPEfEaYr JStone n
DATE 1/ 8 /96 1/7/96 0FFICIAL RECORD COPY
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Mr. Neil S. Carns January 8, 1997 cc w/ enc 1:
Jay Silberg, Esq.
Vice President Plant Operations Shaw, Pittman, Potts & Trowbridge Wolf Creek Nuclear Operating Corporation 2300 N Street, NW P. O. Box 411 Washington, D.C.
20037 Burlington, Kansas 66839 Regional Administrator, Region IV Supervisor Licensing U.S. Nuclear Regulatory Commission Wolf Creek Nuclear Operating Corporation 611 Ryan Plaza Drive, Suite 1000 P.O. Box 411 Arlington, Texas 76011 Burlington, Kansas 66839 Senior Resident Inspector U.S. Nuclear Regulatory Commission U.S. Nuclear Regulatory Commission Resident Inspectors Office P. O. Box 311 8201 NRC Road Burlington, Kansas 66839 Steedman, Missouri 65077-1032 Chief Engineer Supervisor Regulatory Compliance Utilities Division Wolf Creek Nuclear Operating Corporation Kansas Corporation Commission P.O. Box 411 1500 SW Arrowhead Road Burlington, Kansas 66839 Topeka, Kansas 66604-4027 Office of the Governor State of Kansas Topeka, Kansas 66612 Attorney General Judicial Center 301 S.W. 10th 2nd Floor Topeka, Kansas 66612 County Clerk Coffey County Courthouse Burlington, Kansas 66839 Public Health Physicist Bureau of Air & Radiation Division of Environment Kansas Department of Health and Environment Forbes Field Building 283 Topeka, Kansas 66620
3/4.8 ELECTRICAL POWER SYSTEMS
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BASES 3/4.8.1. 3/4.8.2. and 3/4.8.3 A.C. SOURCES. D.C. M!DCES. AND ONSITE POWER DISTRIBUTION l
The OPERA 81LITY of the A.C. and D.C power sources and associated distri-i bution systems during operation ensures that sufficient power will be avail-able to supply the safety-related equipment required for:
(1) the safe shut-down of the facility, and (2) the mitigation and control of accident condi-tions within the facility. The minimum specified independent and redundant i
A.C. and D.C. power sources and distribution systems satisfy the requirements j
of General Design Criterion 17 of Appendix A to 10 CFR Part 50.
The ACTION requirements specified for the levels of degradation of the i
power sources provide restriction upon continued facility operation commen-surate with the level of degradation. The OPERABILITY of the power sources
}
are consistent with the initial condition assumptions of the safety analyses 1
and are based upon maintaining at least one redundant set of onsite A.C. ano i
D.C. power sources and associated distribution systems OPERA 8LE during acci-dont conditions coincident with an assumed loss-of-offsite power and single failure of the other onsite A.C. source. The A.C. source and D.C. source allowable out-of-service times are based on Regulatory Guide 1.93, i
l
" Availability of Electrical Power Sources", December 1974. When one diesel l
generator is inoperable, there is an additional ACTION requirement to verify j
that all required systems, subsystems, trains, components and devices, that i
depend on the remaining OPERA 8LE diesel generator as a source of emergency power, are also OPERABLE, and that the steam-driven auxiliary feedwater pump j
is OPERA 8LE. This requirement is intended to provide assurance that a loss-of-offsite power event will not result in a complete loss of safety function i
i of critical sytems during the period one of the diesel generators is 1
inoperable. The tem verify as used in this context means to administrative 1y 1
check by examining logs or other infomation to determine if certain components are out-of-service for maintenance or other reasons.
It does not i
mean to perform the Surveillance Requirements needed to demonstrate the j
OPERABILITY of the component.
The OPERABILITY of the minimum specified A.C. and D.C. power sources and i
usociated 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 are available for monitoring and maintaining the unit status.
When detemining compliance with action statement requirements, addition to the RCS of borated water with a concentration greater than or equal to the minimum required RWST concentration shall not be considered to be a positive reactivity change.
The surveillance requirements of Technical Specification 3/4.8.1 are 1
based upon, in part, the guidance of Generic Letter 94-01, " Removal of j
Accelerated Testing and Special Reporting Requirements for Emergency Diesel j
Generators from Plant Technical Specifications," Generic Letter 93-05, "Line-Item Technical Specifications Improvements to Reduce Surveillance Requirements i
for Testing During Power Operation," Regulatory Guide 1.9, " Selection, Design, i
Qualification, and Testing of Emergency Diesel Generator Units Used as Class IE Onsite Electrical Power Systems at Nuclear Power Plants," Revision 3, and
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WOLF CREEK - UNIT 1 B 3/4 8-1 Amendment No. 0,50,55,101 l
November 22, 1993 i
i i
3/4.8 ELECTRICAL POWER SYSTEMS l
RASES 3/4.8.1. 3/4.8.2. and 3/4.8.3 A.C. SOURCES. D.C. M ID_CES. AND ONSITE POWER 1
DISTRIBUTION l
The OPERASILITY of the A.C. and D.C power sources and associated distri-i bution systems during operation ensures that sufficient power will be avail-l able to supply the safety-related equipment required for:
(1) the safe shut-j down of the facility, and (2) the mitigation and control of accident condi-tions within the facility. The minimum specified independent and redundant i
A.C. and D.C. power sources and distribution systems satisfy the requirements j
of General Design Criterion 17 of Appendix A to 10 CFR Part 50.
The ACTION requirements specified for the levels of degradation of the l
power sources provide restriction upon continued facility operation commen-i surate with the level of degradation. The OPERA 8ILITY of the power sources are consistent with the initial condition assumptions of the safety analyses and are based upon maintaining at least one redundant set of onsite A.C. ano D.C. power sources and associated distribution systems OPERA 8LE during acci-dent conditions coincident with an assumed loss-of-offsite power and single i
failure of the other onsite A.C. source. The A.C. source and D.C. source i
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 j
depend on the remaining OPERABLE diesel generator as a source of emergency power, are also OPERABLE, and that the steam-driven auxiliary feedwater pump i
is OPERABLE. This requirement is intended to provide assurance that a loss-l of-offsite power event will not result in a complete loss of safety function i
of critical systems during the period one of the diesel generators is j
i inoperable. The tens 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 l
mean to perform the Surveillance Requirements needed to demonstrate the j
OPERABILITY of the component.
The OPERABILITY of the minimum specified A.C. and D.C. power sources and i
associated distribution systems during shutdown and refueling ensures that:
l (1) the facility can be maintained in the shutdown or refueling condition for extended time periods, and (2) sufficient instrumentation and control t
)
capability are available for monitoring and maintaining the unit status.
I When determining compliance with action statement requirements, addition j
to the RCS of borated water with a concentration greater than or equal to the minimum required RWST concentration shall not be considered to be a positive 4
j reactivity change.
The surveillance requirements of Technical Specification 3/4.8.1 are l
based upon, in part, the guidance of Generic Letter 94-01, " Removal of Accelerated Testing and Special Reporting Requirements for Emergency Diesel i
Generators from Plant Technical Specifications," Generic Letter 93-05, "Line-Item Technical Specifications Improvements to Reduce Surveillance Requirements j
for Testing During Power Operation," Regulatory Guide 1.9, " Selection, Design, Qualification, and Testing of Emergency Diesel Generator Units Used as Class j
IE Onsite Electrical Power Systems at Nuclear Power Plants," Revision 3, and WOLF CREEK - UNIT 1 B 3/4 8-1 Amendment No. 0,50,55,101 l
November 22, 1993 i
ELECTRICAL POWER SYSTEM 5 BASES A.C. SOURCES. D.C. SOURCES. AND ONSITE POWER DISTRIBUTION (Continued)
NUREG-1431, " Standard Technical Specifications - Westinghouse Plants." Also, the gridance of h0 MARC 87-00, " Guidelines and Technical Bases for NUMARC Initiatives Addressing Station Blackout at Light Water Reactors," Revision 1, and Regulatory Guide 1.160 has been adopted to formulate a comprehensive Emergency Diesel Generator Reliability Program.
Technical Specification 3.8.1.1, Action b and c, require, in part, the demonstration of the operability of the remaining operable emergency diesel generator by performing Technical Specification 4.8.1.1.2a.4.
This test is required to be complated regardless of when the inoperable emergency diesel l
generator is restored to operable status unless the emergency diesel generator was declared inoperable to do preplanned preventative maintenance, testing, or maintenance to correct a condition which, if left uncorrected, would not affect the operability of the emergency diesel generator. The requirement to test the remaining operable emergency diesel generator when one emergency diesel generator is inoperable is limited to those situations where the cause for inoperability cannot be conclusively demonstrated in order to preclude the potential for common mode failures.
The test is not required to be accomplished if the emergency diesel generator was declared inoperable due to L
an inoperable support system or an independently testable component. When such a test is required, it is required to be performed within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> for ACTION b and within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> for ACTION c of having determined that the emergency diesel generator is inoperable.
Technical Specification 4.8.1.1.2a.4 is considred to be a " Start Test" as described in Regulatory Guide 1.9, Revision 3.
A " Start Test" is performed to demonstrate proper startup from standby conditions and to verify that the required design voltage and frequency is attained.
For these tests, Regulatory Guide 1.9, Revision 3, recommends.that the emergency diesel generators ba slow started and allowed to reach rated speed on a prescribed schedule that is selected to minimize stress and wear.
Regulatory Guide 1.9, Revision 3, considers Technical Specification 4.8.1.1.2a.5 to be a " Load-Run Test".
A " Load-Run Test" demonstrates 90 to 100 percent (5580 to 6201 kilowatts) of the continuous rating (6201 kilowatts) of the emergency diesel generator for an interval of not less than 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> and until temperatura equilibrium has been attained. Inis test may be accomplished by synchronizing the generator with offsite power and the loading and unloading of a diesel generator during this test should be gradual and based on a prescribed schedule that is selected to minimize stress and wear on the diesel generator.
l Regulatory Guide 1.9, Revision 3, considers Technical Specification 4.8.1.1.2b to be a " Fast-Start Test".
A " Fast-Start Test" demonstrates that each emergency diesel generator starts from standby conditions.
If a plant normally has in operation keep warm systems designed to maintain lube oil and jacket water cooling at certain temperatures or prelubrication systems or both, this would constitute normal standby conditions for that plant.
Verification that the eroergency diesel generator reaches required voltage and frequency within acceptable limits and time is also required.
WOLF CREEK - UNIT 1 B 3/4 8-2 '
Amendment No. 101
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