ML20095F752
| ML20095F752 | |
| Person / Time | |
|---|---|
| Site: | Point Beach  |
| Issue date: | 12/13/1995 |
| From: | Link B WISCONSIN ELECTRIC POWER CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| Shared Package | |
| ML20095F756 | List: |
| References | |
| GL-88-16, VPNPD-95-103, NUDOCS 9512190222 | |
| Download: ML20095F752 (12) | |
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1 Wisconsin Electnc POWER COMPANY 231 W Michigart Po Box 2046. Wwoukee. WI 53201-2046 (414)221 2345 VPNPD-95-103 10 CFR 50.4 10 CFR 50.90 December 13, 1995 Document Control Desk U.S. NUCLEAR REGULATORY COMMISSION Mail Station P1-137 Washington, D.
C.
20555^
Gentlemen:
DOCKETS 50-266 AND 50-301 TECHNICAL SPECIFICATIONS CHANGE RENJEST 185 CORE OPERATING LIMITS REPORT POINT BEACH NUCLEAR PLANT, UNITS 1 AND 2 In accordance with the requirements of 10 CFR 50.4 and 50.90, Wisconsin Electric Power Company (Licensee) hereby requests amendments to Facility Operating Licenses DPR-24 and DPR-27 for Point Beach Nuclear Plant (PBNP) Units 1 and 2, respectively, to incorporate changes to the plant Technical Specifications.
The proposed revisions will implement a Core Operating Limits Report (COLR) in accordance with Generic Letter 88-16, " Removal of Cycle-Specific Parameter Limits From Technical Specifications," and WCAP 14483, " Generic Methodology for Expanded Core Operating Limits Report."
Various editorial changes are also included.
mar'ed-up Technical Specifications pages, a safety k
A sample.COLR, evaluation, and the no significant hazards consideration are enclosed.
DESCRIPTION OF CURRENT LICENSE CONDITION
- 1. Technical Specification (TS) Section 15.1, " Definitions,"
contains definitions of frequently used terms applicable to PBNP.
- 2. TS Section 15. 2.1,
" Safety Limit, Reactor Core," Specification i states that the combination of thermal power level,. coolant pressure, and coolant temperature shall not exceed the limits shown on Figures 15.2.1-1 and 15.2.1-2,
" Reactor Core Safety Limits," for Units 1 and 2 respectively.
Figures 15.2.1-1 and 15.2.1-2 represent the loci of points of thermal power, reactor coolant system pressure, and average 9512190222 951213 PDR ADOCK 05000266 P
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Document Control Desk December 13, 1995 Page 2 temperature for which the calculated departure from nucleate boiling ratio (DNBR) is no less than the design limit DNBR or the average enthalpy at the vessel exit is less than the enthalpy of saturated liquid.
- 3. TS Section 15.2.3,
" Limiting Safety System Settings, Protective Instrumentation, " Specification 1.B (4) gives the Overtemperature Delta T reactor trip setpoint function and parameter values. Specification 1.B(5) gives the Overpower Delta T reactor trip setpoint function and parameter values.
- 4. TS Section 15. 3.1. F,
" Minimum Conditions for Criticality,"
Specifications 1 and 2 give the requirements for moderator i
temperature coefficient.
TS Section 15.3.1.G,
" Operational Limitations," gives the departure from nucleate boiling (DNB) parameters which must be i
observed during rated power operation.
5.TS Section 15.3.3,
" Emergency Core Cooling System, Auxiliary Cooling Systems, Air Recirculation Fan Coolers, and Containment Spray," Specification A.1.a gives the requirements for refueling water storage tank capacity and boron concentration.
Specification A.1.b gives the requirements for accumulator pressure, capacity, and boron concentration.
- 6. TS Section 15. 3. 8,
" Refueling," Specification 5 gives the requirements for primary coolant system boron concentration during refueling operations.
- 7. TS Section 15. 3.10, " Control Rod and Power Distribution Limits," Specification A.1 gives shutdown bank insertion limits.
Specification A.2 gives control bank insertion limits.
Specifications A.3 and 4 give limits on shutdown margin.
Specification B.1.a gives the limits for the hot channel factors.
Specification B.2 gives the requirements for axial flux difference.
- 8. TS Section 15. 6. 9,
" Plant Reporting Requirements," gives the requirements for the reporting of operating information to the
'!dclear Regulatory Commission.
DESCRIPTION OF PROPOSED CHANGES
- 1. TS Section 15.1:
Technical Specification Section 15.1 is being modified to add the definition of a COLR as follows:
o*
Document Control Desk December 13, 1995 Page 3 "Q.
Core Ooeratino Limits Reoort The Core Operating Limits Report is the document that provides core operating limits for the current operating reload cycle.
These cycle-specific core operating limits shall be determined for each reload cycle in accordance with specification 15.6.9.1.D.
Plant operation within these operating limits is addressed in individual specifications."
- 2. TS Section 15.2.1:
Existing Specification 15.2.1.1 is being deleted.
New Specifications 15.2.1.1 and 2 are being added to read as follows:
"1.
During power operation, the departure from nucleate boiling ratio (DNBR) shall be maintained 21.17 for the WRB-1 DNB correlation.
2.
During power operation, the peak fuel centerline temperature shall be maintained <5080 F,
decreasing by 58 F per 10,000 MWD /MTU of burnup."
Figures 15.2.1-1 and 15.2.1-2 are being deleted as they are being replaced by proposed new Specifications 15.2.1.1 and 2 listed above.
The Applicability section and Basis for TS Section 15.2.1 are being modified to reflect the changes to Specification 15.2.1.1 and the deletion of Figures 15.2.1-1 and 15.2.1-2,
- 3. TS Section 15. 2. 3 :
Specification 15. 2. 3.1.B (4 ) is being modified to relocate the i
values for the cycle-specific parameters to the COLR.
Specification 15.2.3.1.B(5) is being modified to relocate the values for the cycle-specific parameters to the COLR.
The Basis for TS Section 15.2.3 is being modified to delete references to Figures 15.2.1-1 and 15.2.1-2.
- 4. TS Section 15.3.1:
Specification 15.3.1.F.1 is being modified to read as follows:
1 Document Control Desk l
December 13, 1995
.Page 4 "1.
The moderator temperature coefficient shall be within the limits specified in the COLR."
Specification 15.3.1.F.2 is being deleted as it is incorporated into the COLR.
Specifications 15.3.1.F.3, 4,
and 5 are being renumbered to 15.3.1.F.2, 3,
and 4 respectively.
Specification 15.3.1.G is being modified to read as follows:
"The following DNB related parameters shall be maintained within the limits specified in the COLR during Rated Power operation:
1.
Tavg-2.
Reactor Coolant System (RCS) pressurizer pressure.
3.
Reactor Coolant System raw measured Total Flow Rate (See Basis)."
The Basis for Specification 15.3.1.G is being modified to delete references to the specific values.
1
- 5. TS Section 15.3.3 :
Specification 15.3.3.A.1.a is being modified to read as follows:
"a.
The refueling water tank contains not less than 275,000 gal, of water with a boron concentration within the limits specified in the COLR."
Specification 15.3.3.A.1.b is being modified to read as follows:
"b.
Each accumulator is pressurizgd to at least 700 psig angcontainsat least 1100 ft but no more than 1136 ft of water with a boron concentration within the limits specified in the COLR.
Neither accumulator may be isolated.
- 6. TS Section 15. 3. 8 :
Specification 15.3.8.5 is being modified to read as follows:
"5.
During reactor vessel head removal and while loading and unloading fuel from the reactor, boron concentration in the primary coolant system shall be maintained within the limits specified in the COLR."
- 7. TS Section 15.3.10 :
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Document Control Desk December 13, 1995 Page 5 i
1
)
. Specification 15.3.10.A,1 is being modified to read as follows:
1 "1.
The shutdown bank shall within the limits specified in I
the COLR."
The footnote at the bottom of page 15.3.10-1 is being deleted as it is incorporated into the COLR.
i
)
Specification 15.3.10.A.2 is being modified to read as-follows:
l i
"2.
The control banks shall'be within the limits specified in the COLR."
3 Specification 15.3.10.A.3 is being modified to read as follows:
?
l "3.
The shutdown margin shall be within the limits j
specified in the COLR."
l Specification 15.3.10.A.4 is being deleted as it is l
incorporated into the COLR.
Specification 15.3.10.5 is being 4
renumbered to 15.3.10.4.
1 l
Specification 15.3.10.B.1.a is being modified to read as j
follows:
"a.
The height dependent heat flux hot channel factor (F )
q
[
and the nuclear enthalpy rise hot channel factor (/ha) i shall be within the limits specified in the COLR."
l l
Specifications 15.3.10.B.2.a, b, and c are being modified to l
replace references to Figure 15.3.10-4 with a reference to the i
COLR or specification 15.3.10.B.2.a as appropriate.
l l
The Basis for TS Section 15.3.10 is being modified to replace l
references to specific limits with a reference to the COLR.
Figures 15.3.10-1, 2,
3, and 4 are being deleted from the j
Technical Specifications as they are being placed in the COLR.
- 8. TS Section.15. 6. 9 :
New specification 15.6.9.1.D is being added to read as follows:
g "D.
Core Operating Limits Report (COLR) i
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Document Control Desk December 13, 1995 Page 6 1.
Core operating limits shall be established prior i
to each reload cycle, or prior to any remaining portion of a reload cycle, and shall be documented in the COLR for the following specifications:
15.3.10.A.3 Shutdown Margin 15.3.1.F.1 Moderator Temperature Coefficient 15.3.10.A.1 Shutdown Bank Insertion-Limit 15.3.10 A.2 Control Bank Insertion Limits 15.3.10.B.1.a Height Dependent Heat Flux Hot Channel Factor (Fo) and Nuclear Enthalpy Rise' Hot Channel Factor (I?aH) l 15.3.10.B.2.a Axial Flux Difference 15. 2. 3.1. B ( 4 )
Overtemperature AT Setpoint
- 15. 2. 3.1. B (5 )
Overpower AT Setpoint 15.3.1.G RCS Pressure, Temperature, and Flow Departure From Nucleate Boiling (DNB) Limits 15.3.3.A.1.b Accumulator Boron Concentration 15.3.3.A.1.a Refueling Water Storage Tank
~(
(RWST) Boron Concentration 15.3.8.5 Refueling Boron Concentration 2.
The analytical methods used to determine the core operating limits shall be those previously reviewed and approved by the NRC.
The NRC-approved methodologies are listed below for each of the core operating limits l
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L Document Control Desk December 13, 1995 Page 7 COLR Parameter NRC Approved Methodology Section 2.1 Shutdown Margin WCAP-9273-NP-A, " Westinghouse Reload Safety Evaluation Methodology," July 1985 2.2 Moderator Temperature WCAP-9273-NP-A, " Westinghouse Reload j
Coefficient Safety Evaluation Methodology," July 1985 2.3 Shutdown Bank Insertion WCAP-9273-NP-A, " Westinghouse Reload Limit Safety Evaluation Methodology," July 1985 2.4 Control Bank Insertion WCAP-9273-NP-A, " Westinghouse Reload j
Limits Safety Evaluation Methodology," July 1985 2.5 Height Dependent Heat Flux WCAP-9273-NP-A, " Westinghouse Reload Hot Channel Factor (F )
Safety Evaluation Methodology," July 1985 Q
and Nuclear Enthalpy ise Hot Channel Factor ( AH)
Thadani to Johnson, " Acceptance for Reference of Licensing Topical Report, WCAP-10924, ' Westinghouse Large Break LOCA Best Eatimate Methodology,' Addendum 4,
'Model Revisions ', " February 1991 2.6 Axial Flux Difference WCAP-9273-NP-A, " Westinghouse Reload Safety Evaluation Methodology," July 1985 2.7 Overtemperature AT WCAP-9273-NP-A, " Westinghouse Reload Setpoint Safety Evaluation Methodology," July 1985 2.8 Overpower AT Setpoint WCAP-9273-NP-A, " Westinghouse Reload Safety Evaluation Methodology," July 1985 2.9 RCS Pressure, Temperature, WCAP-9273-NP-A, " Westinghouse Reload and Flow Departure From Safety Evaluation Methodology," July 1985 Nucleate Boiling (DNB)
Limits WCAP-11397-P-A, " Revised Thermal Design Procedure," April 1989 2.10 Accumulator Boron WCAP-9273-NP-A, " Westinghouse Reload Concentration Safety Evaluation Methodology," July 1985 2.11 Refueling Water Storage WCAP-9273-NP-A, " Westinghouse Reload Tank (RWST) Boron Safety Evaluation Methodology," July 1985 Concentration 2.12 Refueling Boron WCAP-9273-NP-A, " Westinghouse Reload Concentration Safety Evaluation Methodology," July 1985
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i Document Control Desk December 13, 1995 Page 8 4
3.
The core operating limits shall be determined such 1
that all applicable limits (e.g.,
fuel thermal mechanical limits, core thermal hydraulic limits, emergency core cooling system limits, nuclear limits such as shutdown margin, transient analysis limits, and accident analysis limits) of the i
safety analysis are met.
4.
The COLR, including any mid-cycle revisions or supplements, shall be provided to the NRC upon issuance for each reload cycle."
BASIS AND JUSTIFICATION The reactor physics parameters for each core reload cycle differ depending on such variables as the previous cycle burnup, number and enrichment of new fuel assemblies, and expected cycle length.
Several of the Technical Specifications address limits which are associated with reactor physics parameters that may change with each reload, requiring the processing of changes to the Technical Specifications to update these limits each fuel cycle.
In Generic Letter 88-16, " Removal of Cycle-Specific Parameter Limits From Technical Specifications," the NRC provided guidance for removal of cycle specific reactor physics parameters that are calculated using NRC approved methodologies from the Technical Specifications.
The generic letter provides for removal of these parameters by placing them in a Core Operating Limits Report (COLR) that would be submitted to the NRC following any change in the reactor physics parameters.
WCAP 14483, Generic Methodology for Expanded Core Operating Limits Report," provides guidance for relocating DNB, Overtemperature Delta T, and Overpower Delta T parameters to the COLR and for replacing the Reactor Core Safety Limits figures with text that describes the safety limits.
The COLR is being established at PBNP in accordance with GL 88-16 and WCAP 14483 to avoid the unnecessary burden of changing limits which are developed using an NRC approved methodology.
We have determined that the proposed amendments do not involve a I
significant hazards consideration, authorize a significant change in the types or total amounts of any effluent release, or result in any significant increase in individual or cumulative occupational exposure.
Therefore, we conclude that the proposed amendments meet the requirements of 10 CFR 51.22 (c) (9) and that an environmental impact statement or negative declaration and environmental impact appraisal need not be prepared.
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i Document Control Desk December 13, 1995 Page 9 As stated in Westinghouse Owner's Group (WOG) to NRC letter dated December 1, 1995, we are the lead plant for the expanded COLR.
i In order to support our schedule, and that of other WOG utilities that have indicated their desire to implement similar changes, we request approval of this amendment request by March 29, 1996.
If you require additional information, please contact us.
Sincerely, i
/
Bob Link Vice President Nuclear Power mmr/KVA Attachment cc:
NRC Regional Administrator NRC Resident Inspector
^
Public Service Commission of Wisconsin J
Subscribed and sworn b ore me on this nW day of mh 1995.
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LIA RLo d
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N y (public, State of Wisconsin My commission expires lo/Ja /t(,
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1
TECHNICAL SPECIFICATIONS CHANGE REQUEST 185 SAFETY EVALUATION INTRODUCTION Wisconsin Electric Power Company (Licensee) has applied for amendments to Facility Operating Licenses DPR-24 and DPR-27 for Point Beach Nuclear Plant (PBNP) Units 1 and 2.
The proposed revisions will implement a Core Operating Limits Report (COLR) in accordance with Generic Letter 88-16, " Removal of Cycle-Specific Parameter Limits From Technical Specifications," and WCAP 14483,
" Generic Methodology for Expanded Core Operating Limits Report."
Various editorial changes are also included.
EVALUATION The relocation of the cycle-specific parameters from the PBNP Technical Specifications to the COLR does not affect the operation of PBNP.
The appropriate actions required if the limits are exceeded will remain in the Technical Specifications.
Revisions to the COLR will be made in accordance with 10 CFR 50.59.
This will ensure that changes to the COLR do not compromise safety since the cycle-specific changes will be reviewed and evaluated in accordance with an established and accepted process.
The NRC will be notified of all revisions to the COLR in accordance with proposed Specification 15.6.9.D,
" Core Operating Limits Report."
Any change to the cycle-specific parameter values contained in the COLR will be based on NRC-approved methodologies.
The NRC-approved methodologies used to determine the values of the parameters contained in the COLR are listed in proposed Specification 15.6.9.D.
CONCLUSION The proposed revisions to the PBNP Technical Specifications are administrative in nature since they do not change any of the limits or surveillance requirements.
The use of a COLR provides more flexibility for operations and core design, in that it allows changes of the parameters to be made consistent with the burnup and energy constraints of the cycle without requiring a License Amendment, yet it assures that the NRC is informed of the reactor physics parameters that are being used for each cycle.
s TECHNICAL SPECIFICATION CHANGE REQUEST 185 NO SIGNIFICANT RAZARDS CONSIDERATION In accordance with the requirements of 10 CFR 50.91(a), Wisconsin Electric Power Company (Licensee) has evaluated the proposed changes against the standards of 10 CFR 50.92 and has determined that the operation of Point Beach Nuclear Plant, Units 1 and 2, in accordance with the proposed amendments does not present a significant hazards consideration.
The analysis of the requirements of 10 CFR 50.92 and the basis for this conclusion are as follows:
1.
Operation of this facility under the proposed Technical Specifications will not create a significant increase in the probability or consequences of an accident previously evaluated.
The relocation of the cycle-specific parameters from the Point Beach Nuclear Plant (PBNP) Technical Specifications to the Core Operating Limits Report (COLR) has no impact on plant operation or accident analyses.
The proposed changes are administrative in nature.
The Technical Specifications will continue to require operation within the core operational limits for each cycle reload calculated by the NRC-approved reload design methodologies.
The appropriate actions required if limits are exceeded will remain in the Technical Specifications.
The reload report presents the results of a cycle-specific evaluation of accidents and transients addressed in the PBNP Final Safety Analysis Report (FSAR).
The cycle-specific evaluation demonstrates that changes in the unit's fuel cycle design and corresponding COLR parameters do not involve a significant increase in the probability or consequences of an accident previously evaluated.
Therefore, these changes do not involve a significant increase in the probability or consequences of any accident previously evaluated.
2.
Operation of this facility under the proposed Technical Specifications will not create the possibility of a new or different kind of accident from any accident previously evaluated.
The proposed change to relocate the cycle-specific parameters from the Technical Specifications to the COLR is administrative in nature.
No change to the design, configuration, or method of operation of the plant is made by this change.
The cycle-specific parameters will be determined using NRC-approved methodologies.
The Technical Specifications will continue to require operation within the core operating limits and appropriate actions will be taken
if the limits are exceeded.
Therefore, these changes do not create the possibility of a new or different kind of accident from any accident previously evaluated.
3.
Operation of this facility under the proposed Technical Specifications will not create a significant reduction in a margin of safety.
Existing Technical Specification operability and surveillance requirements are not reduced by the proposed changes to relocate cycle-specific parameters from the Technical Specifications to the COLR.
The cycle-specific COLR limits for reloads will continue to be developed based on NRC-approved methodologies, thereby maintaining accepted margins of safety.
The Technical Specifications will still require that the core be operated within these limits and specify appropriate actions to be taken if the limits are violated.
Each reload undergoes a 10CFR50.59 safety review to assure that operating the unit within the cycle-specific limits will not involve a significant reduction in a margin of safety.
Therefore, these changes do not involve a significant reduction in the margin of safety.
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