ML20137C203

Proposed Tech Specs Bases Pp Reflecting Corrections to Ref Made on Those Pp

ML20137C203
Person / Time
Site:	Wolf Creek
Issue date:	03/19/1997
From:	WOLF CREEK NUCLEAR OPERATING CORP.
To:
Shared Package
ML20137C196	List: ML20137C193 ML20137C203
References
NUDOCS 9703240177
Download: ML20137C203 (3)

Text

.

Attachment to ET 97-0032 Page 1 of 3 l

l 1

i l

Markups of Affected Technical specification Bases Pages I

i i

l l-9703240177 970319 PDR ADOCK 05000482 l

P PDR I

Atiachment to ET 97-0032 Page 2 of 3 POWER DISTRIBUTION LIMITS BASES 3/4 2.2 and 3/4.2.3 HEAT FLUX HOT CHANNEL FACTOR AND NUCLEAR ENTHALPY RISE HOT CHANNEL FACTOR (Continued)

Each of these is meas' arable but will normally only be determined periodically as specified in Specifications 4.2.2 and 4.2.3. This periodic surveillance is su'ficient to insure that the limits are maintained provided:

a. Control rods in a single group move together with no individual rod insertion differing by more than ! 12 steps, indicated, from the group demand position, t

b. Control rod groups are sequenced with overlapping groups as described in Specification 3.1.3.6,

c. The control rod insertion limits of Specification 3.1.3 6 are maintained, and

d. The axial power distribution, expressed in terms of AXIAL FLUX DIFFERENCE, is maintained within the limits.

Fj, will be maintained within its limits provided Conditions a. through

d. above are maintained. The limits on the nuclear enthalpy rise hot channel factor, F[f, are specified in the COLR.

i F (Z)and Fjf are measured periodically to provide assurance that they i

o remain within their limits. A peaking margin calculation is performed, when l

necessary, to provide the basis for reducing THERMAL POWER or for reducing the j

width of the AFD limits. The hot channel factor F (Z)is measured p

periodically and increased by a cycle and height dependent factor, W(Z), to provide assurance that the limit of F (Z)is met. W(Z) accounts for the p

effects of normal operation transients and is determined from expected power control maneuvers over the full range of burnup conditions in the core. The W(Z) functions are specified in the Core Operating Limits Report.

3/4.2.4 OUADRANT POWER TILT RATIO The QUADRANT POWER TILT RATIO limit assures that the radial power distribution satisfies the design values used in the power capability analysis. Radial power distribution measurements are made during STARTUP testing and periodically during power operation.

The limit of 1.02, at which corrective ACTION is required, provides DNB and linear heat generation rate protection with x-y plane power tilts. A limit of 1.02 was selected to provide an allowance for the uncertainty associated with the indicated power tilt.

WOLF CREEK - UNIT 1 83/432-2 Amendment No. 4r64r64,92 l

e At'tachment to ET 97-0032 Page 3 of 3 ELECTRIC POWER SYSTEMS BASES A.C. SOURCES. D.C. SOURCES. AND ONSITE POWER DISTRIBUTION (Continued)

NUREG-1431 " Standard Technical Specifications - Westinghouse Plants." Also, the guidance of NUMARC 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 Epecification 4.8.1.1.2a.4. This test is required to be completed regardless of when the inoperable emergency diesel 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 j

test the remaining operable emergency diesel generator when one emergency diesel generator is inoperable is limited to those situations where the cause for inoperability can not 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 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 considered 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 be 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 i hour and i

until temperature equilibrium has been attained. This test may be accomplished by synchronizing the generator with offsite power and the loading and unloading of an dietel 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, 4.8.1O1.2fb R ulatory Guide 1.9, Revision 3, considers Technical Specification be a " Fast-Start Test". A " Fast-Start Test" demonstrates that l

each ncy diesel generator starts from standby conditions. If a plant normally has in operation keep warm systems designed to maintain lube oil and i

jacket water cooling at certain temperatures or prelubrication systems or both, this would constitute normal standby conditions for that plant.

Verification that the emergency 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