ML20071Q598
| ML20071Q598 | |
| Person / Time | |
|---|---|
| Site: | Waterford  |
| Issue date: | 08/03/1994 |
| From: | Beckner W Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20071Q601 | List: |
| References | |
| NUDOCS 9408110291 | |
| Download: ML20071Q598 (8) | |
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(4j NUCLEAR REGULATORY COMMISSION
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UNITED STATES
'f WASHINoTON, D.C. 20566-0001
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ENTERGY OPERATIONS. INC.
DOCKET N0. 50-382 WATERFORD STEAM ELECTRIC STATION. UNIT 3 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 97 License No. NPF-38 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Entergy Operations, Inc. (the licensee) dated December 14, 1993, 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.
9408110291 940803 PDR ADOCK 05000382 P
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. 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-38 is hereby amended to read as follows:
(2) Technical Soecifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No. 97, and the Environmental Protection Plan contained in Appendix B, are hereby incorporated in the license.
The licensee shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
3.
This license amendment is effective as of its date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION yhL D
$d=--
William D. Beckner, Director Project Directorate IV-1 Division of Reactor Projects - III/IV Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance:
August 3, 1994 1
6 4
ATTACHMENT TO LICENSE AMENDMENT NO. 97 TO FACILITY OPERATING LICENSE NO. NPF-38 QOCKET NO. 50-382 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 areas of change.
The corresponding overleaf pages are also provided to maintain document completeness.
REMOVE PAGES INSERT PAGES 3/4 2-4 3/4 2-4 B 3/4 2-2 B 3/4 2-2 B 3/4 2-3 B 3/4 2-3 I
n POWER DISTRfBUTION LIMITS 3/4.2.3 AZIMUTHAL POWER TILT - Ty LIMITING CONDITION FOR OPERATION 3.2.3 The AZIMUTHAL POWER TILT (T ) shall be less than or equal to the q
FOLLOWING LIMITS:
a.
AZIMUTHAL POWER TILT Allowance used in the Cere Protection Calculators (CPCs) and b.
0.03%.
APPLICABILITY: MODE 1 above 20% of RATED THERMAL POWER.*
AG. TION:
a.
With the measured AZIMUTHAL POWER TILT determined to exceed the AZIMUTHAL POWER TILT Allowance used in the CPCs within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> l
either correct the power tilt or adjust the AZIMUTHAL POWER TILT Allowance used in the CPCs to greater than or equal to the measured value, b.
With the measured AZIMUTHAL POWER TILT determined to exceed 0.03:
l 1.
Due to misalignment of either a part length or full length CEA, within 30 minutes verify that the Core Operating Limit Supervisory System (COLSS) (when COLSS is being used to monitor the core power distribution per Specifications 4.2.1.2 and 4.2.4.2) is detecting the CEA misalignment.
2.
Verify that the AZIMUTHAL POWER TILT is within its limit within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> (24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> for a CEA misalignment event) or l
reduce THERMAL POWER to less than 50% of RATED THERMAL POWER l
within the next 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> and reduce the Liriear Power Level -
High trip setpoints to less than or equal to 55% of RATED 1
THERMAL POWER within the next 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.
\\
3.
Identify and correct the cause of the out of limit condition prior to increasing THERMAL POWER; subsequent POWER OPERATION above 50% of RATED THERMAL POWER may proceed provided that the AZIMUTHAL POWER TILT is verified within its limit at least once per hour for 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> or until verified acceptable at 95% or greater RATED THERMAL POWER.
- See Special Test Exception 3.10.2.
WATERFORD - UNIT 3 3/4 2-4 AMEtDMENT NO. 97 l
POWER DISTRIBUTION LIMITS 3/4.2.2 PLANAR RADIAL PEAKING FACTORS - F LIMITING CONDITION FOR OPERATION 3.2.2 The measured PLANAR RADIAL PEAKING FACTORS (F* ) shall be less than or y
c equal to the PLANAR RADIAL PEAKING FACTORS (Fxy) used in the Core Operating Limit Supervisory System (COLSS) and in the Core Protection Calculators (CPC).
APPLICABILITY:
MODE 1 above 20% of RATED THERMAL POWER.*
ACTION:
With a F*
exceeding a corresponding F
, within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> either:
c Adjust the CPC addressable constants to increase the multiplier a.
applied to planar radial peaking by a factor equivalent to greater than or equal to F* /F and restrict subsequent operation so that a margin to the COLSS operating limits of at least [F* /Fc ) - 1.0]
x 100% is maintained; or AdjusttheaffectedPLANARRADIALPEAKINGFACTORS(F[y)usedinthe b.
COLSS and CPC to a value greater than or equal to the measured PLANAR RADIAL PEAKING FACTORS (F* ) or y
c.
Be in at least HOT STANDBY.
SURVEILLANCE REQUIREMENTS 4.2.2.1 The provisions of Specification 4.0.4 are not applicable.
4.2.2.2 The measured PLANAR RADIAL PEAKING FACTORS (F* ) obtained by using y
the incore detection system, shall be determined to be less than or equal to the PLANAR RADIAL PEAKING FACTORS (Fxy), used in the COLSS and CPC at the following intervals:
a.
After each fuel loading with THERMAL POWER greater than 40% but prior to operation above 70% of RATED THERMAL POWER, and b.
At least once per 31 effective full power days (EFPD).
- See Special Test Exception 3.10.2.
WATERFORD - UNIT 3 3/4 2-3
POWER DISTRIBUTION LIMITS BASES 3/4.2.2 PLANAR RADIAL PEAKING FACTORS Limiting the values of the PLANAR RADIAL PEAKING FACTORS (F used in the COLSS and CPCs to values equal to or greater than the measur(ed) PLANAR RADIAL PEAKING FACTORS (F"y) provides assurance that the limits calculated by COLSS and the CPCs remain valid.
Data from the incore detectors are used for determining the measured PLANAR RADIAL PEAKING FACTORS. A minimum core power at 20% of RATED THERMAL POWER is assumed in determining the PLANAR RADIAL PEAKING FACTORS. The 20% RATED THERMAL POWER threshold is due to the neutron flux detector system being inaccurate below 20% core power.
Core noise level at low power is too large to obtain usable detector readings.
The periodic Surveillance Requirements for determining the measured PLANAR RADIAL PEAKING FACTORS provide assurance that the PLANAR RADIAL PEAKING FACTORS used in COLSS and the CPCs remain valid throughout the fuel cycle. Determining the measured PLANAR RADIAL PEAKING FACTORS after each fuel loading prior to exceeding 70% of RATED THERMAL POWER provides additional assurance that the core was properly loaded.
3/4.2.3 AZIMUTHAL POWER TILT - T y The limitations on the AZIMUTHAL POWER TILT are provided to ensure that design safety margins are maintained.
The LCO places a 3% limit on the maximum azimuthal tilt during normal steady state power operation. With AZIMUTHAL POWER TILT greater than 3%, operation is restricted to only those conditions required to identify the cause of the tilt. However, Action item b.2 allows 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> to restore the tilt to less than 3% following a CEA misalignment event (i.e., CEA drop). A CEA misalignment event causes an asymmetric core power generation and an increase in xenon concentration in the vicinity of the dropped rod.
This event may cause the azimuthal tilt to exceed 3%.
The 2 hour2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> action time to reduce core power is not sufficient to recover from the xenon transient.
The 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> period allows for correction of the misaligned CEA and allows time for the xenon redistribut' ion effects to dampen out due to radioactive decay and absorption. The reduction in xenon concentration (which is aided by operation at full power) will in turn reduce the tilt below the 3% limit.
The 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> period is applicable only to a CEA misalignment where the cause of the tilt has been identified.
It is based on the time required or the expected xenon transient to dampen out. All other conditions (not due to a CEA misalignment) where the azimuthal tilt exceeds 3% require action within the specified 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.
The tilt is normally calculated by COLSS. A minimum core power of 20% of RATED THERMAL POWER is assumed by the C M s in its input to COLSS for calculation of AZIMUTHAL POWER TILT.
The 20% RATED THERMAL POWER threshold is due to the neutron flux detector system being inaccurate below 20% core power.
Core noise level at low power is too large to obtain usable detector readings.
The Surveillance Requirements specified when COLSS is out of service provide an acceptable means of detecting the presence of a steady-state tilt.
It is necessary to explicitly account for power asymmetries in the COLSS and CPCs because the radial peaking factors used in the core power distribution calculations are based on an untilted power distribution.
WATERFORD - UNIT 3 8 3/4 2-2 AMENDMENT N0. 97
POWER DISTRIBUTION LIMITS BASES AZIMUTHAL POWER TILT - Ta (Continued)
I AZIMUTHAL POWER TILT is measured by assuming that the ratio of the power at any core location in the presence of a tilt to the untilted power at the location is of the form:
P
/P,n, = 1 + T g cos (0 - 0,)
tut q
where:
T is the peak fractional tilt amplitude at the core periphery y
9 is the radial normalizing factor 0 is the azimuthal core location 0, is the azimuthal core location of maximum tilt P,n,/P,,n, is the ratio of the power at a core location in the presence of a tilt to the power at that location with no tilt.
3/4.2.4 DNBR MARGIN The limitation on DNBR as a function of AXIAL SHAPE INDEX represents a conservative envelope of operating conditions consistent with the safety analysis assumptions and which have been analytically demonstrated adequate to maintain an acceptable minimum DNBR throughout all anticipated operational occurrences.
Operation of the core with a DNBR at or above this limit provides assurance that an acceptable minimum DNBR will be maintained.
Either of the two core power distribution monitoring systems, the Core Operating Limit Supervisory System (COLSS) and the DNBR channels in the Core Protection Calculators (CPCs), provides adequate monitoring of the core power distribution and is capable of verifying that the DNBR does.not violate its 4
limits. The COLSS performs this function by continuously monitoring the core power distribution and calculating a core operating limit corresponding to the allowable min' mum DNBR.
The COLSS calculation of core power operating limit i
based on the minimum DNBR limit includes appropriate penalty factors which provide a 95/95 probability / confidence level that the core power calculated by COLSS, based on the minimum DNBR limit, is conservative with respect to the actual core power limit.
These penalty factors are determined from the uncer-tainties associated with planar radial peaking measurements, state parameter i
measurement, software algorithm modelling, computer processing, rod bow, and core power measurement.
Parameters required to maintain the margin to DNB and total core power are also monitored by the CPCs. Therefore, in the event that the COLSS is not being used, operation within the limits of Figure 3.2.2 or Figure 3.2-3 can be maintained by utilizing a predetermined DNBR as a function of AXIAL SHAPE INDEX and by monitoring the CPC trip channels.
The above listed uncertainty and penalty factors plus those associated with startup test acceptance criteria are also included in the CPCs which assume a minimum core power of 20% of RATED THERMAL POWER.
The 20% RATED THERMAL POWER threshold is due to the neutron flux detector system being less accurate below 20% core power.
Core noise level at low power is too large to obtain usable detector readings.
WATERFORD - UNIT 3 B 3/4 2-3 AMENDMENT NO. 4 h 97 J
l
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POWER DISTRIBUTION LIMITS 4
BASES DNBR MARGIN (Continued)
A DNBR penalty f actor has been included in the COLSS and CPC DNBR calcula-l tions to accommodate the effects of rod bow.
The amount of rod bow in each I
assembly is dependent upon the average burnup experienced by that assembly.
Fuel assemblies that incur higher average burnup will experience a greater magnitude of rod bow.
Conversely, lower burnup assemblies will experience less rod bow.
In design calculations, the penalty for each batch required to l
compensate for rod bow is determined from a batch's maximum average assembly burnup applied to the batch's maximum integrated planar-radial power peak.
A single net penalty for COLSS and CPC is then determined from the penalties associated with each batch, accounting for the offsetting margins due to the lower radial power peaks in the higher burnup batches.
3/4.2.5 RCS FLOW RATE i
This specification is provided to ensure that the actual RCS total flow rate is maintained at or above the minimum value used in the LOCA safety analyses, and that the DNBR is maintained within the safety limit for Anti-cipated Operational Occurrences (A00).
3/4.2.6 REACTOR COOLANT COLD LEG TEMPERATURE This specification is provided to ensure that the actual value of reactor coolant cold leg temperature is maintained within the range of values used in the safety analyses, with adjustment for instrument accuracy of 12 F, and that the peak linear heat generation rate and the moderator temperature coefficient effects are validated.
3/4.2.7 AXIAL SHAPE INDEX This specification is provided to ensure that the actual value of AXIAL SHAPE INDEX is maintained within the range of values used in the safety analyses, to ensure that the peak linear heat rate and DNBR remain within the safety limits for Anticipated Operational Occurrences (A00).
3/4.2.8 PRESSURIZER PRESSURE This specification is provided to ensure that the actual value of pressurizer pressure is maintained within the range of values used in the safety analyses.
The inputs to CPCs and COLSS are the most limiting.
The values are adjusted for an instrument accuracy of i 25 psi.
The sensitive events are SGTR, LOCA, FWLB and loss of condenser vacuum to initial high pressure, and MSLB to initial low pressure.
WATERFORD - UNIT 3 83/42-4 AMENDMENT NO. 12
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