ML20117D257
| ML20117D257 | |
| Person / Time | |
|---|---|
| Site: | Point Beach  |
| Issue date: | 08/22/1996 |
| From: | Link B WISCONSIN ELECTRIC POWER CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| Shared Package | |
| ML20117D261 | List: |
| References | |
| VPNPD-96-058, VPNPD-96-58, NUDOCS 9608280225 | |
| Download: ML20117D257 (7) | |
Text
1 Wisconsin Electnc POWER COMPANY 231 W Michgan. PO Box 2046. Mdwoukee. WI 53201-2046 (414)221-2345 VPNPD-96-058 10 CFR 50.4 10 CFR 50.90 August 22,1996 Document Control Desk US NUCLEAR REGULATORY COMMISSION Mail Station PI-137 Washington,DC 20555 Gentlemen:
DOCKETS $0-266 AND 50-301 TECHNICAL SPECIFICATIONS CHANGE REOUEST 190 ADMINISTRATIVE CHANGE REGARDING LICENSED POWER LEVEL 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 (Licensce) hereby requests amendments to Facility Operating Licenses DPR-24 and DPR-27 for Point Beach Nuclear Plant (PBNP) Units I and 2, respectively, to incorporate changes to the Facility Operating Licenses and plant Technical Specifications. The proposed resisions will correct the Facility Operating Licenses DPR-24 and DPR-27 to reflect that licensed power level for cach unit is actually 1518.5 megawatts thermal (MWt), as stated in the Technical Specifications, instead of 1518 MWt as currently indicated. The Bases for Technical Specifications Section 15.3.1, " Reactor Coolant System," Specification B,
" Pressure / Temperature Limits," will be revised to make a similar correction. This change is necessary to proside consistency within the PBNP license.
Marked-up Facility Operating Licenses and Technical Specifications pages, a safety evaluation, and the no significant hazards consideration are enclosed.
DESCRIPTION OF CURRENT LICENSE CONDITION Section 3. A, " Maximum Power Levels," of Facility Operating Licenses DPR-24 and DPR-27 states:
"The licensee is authorized to operate the facility at reactor core power levels not in excess of 1518 megawatts thermal."
Technical Specification Definition 15.1 j, " Rated Power," states:
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" Rated power is here defined as a steady sate reactor core output of 1518.5 MWT."
The Bases for TS 15.3.1.B states, in pan:
"The maximum integrated fast neutron exposure of the vessel is computed to be 2.5 x 10" neutrons /cm 2 for 40 years of operation at 1518 MWt and 80 percent load factor."
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Document Control Desk August 22,1996 Page 2 I
l DESCRIPTION OF PROPOSED CHANGES l
Section 3.A of Facility Operating Licenses DPR-24 and DPR-27 will be revised to read as follows:
"The licensee is authorized to operate the facility at reactor core power levels not in excess of 1518.5 megawatts thermal."
The Bases for TS 15.3.1.B will be revised, in part, to read as follows:
2 "The maximum integrated fast neutron exposure of the vessel is computed to be 2.5 x 10" neutrons /cm for 40 years of operation at 1518.5 MWt and 80 percent load factor."
l BASIS AND JUSTIFICATION This change is an administrative change to correct an error in the Facility Operating Licenses for PBNP Units 1 and 2 regarding licensed power level. The Facility Operating Licenses incorrectly indicate that licensed power level for both units
- is 1518 MWt. Actual licensed power level for both units is 1518.5 MWt. This change also corrects a similar error in the Bases for one specification in the PBNP Technical Specifications.
We have determined that the proposed amendments do not involve a 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 exporure. 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.
j If you require additional information, please contact us.
Sincerely, Bob ink Vice Presi ent Nuclear Power cc:
NRC Resident inspector NRC Regional Administrator PSCW Subscribed and sworn to before me i
this 21 day of Ama),1996.
Y W
ry $blic, State of Wisconsin My Commission expires )D/M /R.
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TECHNICAL SPECIFICATIONS CHANGE REOUEST 190 SAFETY EVALUATION INTRODUCTION Wisconsin Electric Power Company (L,icensee) has applied for amendments to Facility Operating l
Licenses DPR-24 and DPR-27 for Point Beach Nuclear Plant Units 1 and 2. The proposed l
revisions will correct the Facility Operating Licenses DPR-24 and DPR-27 to reflect that licensed i
power level for each unit is actually 1518.5 megawatts thermal (MWt), as stated in the Technical Specifications, instead of 1518 MWt as currently indicated. The Bases for Technical Specifications Section 15.3.1, " Reactor Coolant System," SpeciScation B, " Pressure /
Temperature Limits," will be revised to make a similar correction.
EVALUATION i
This change provides consistency within the Facility Operating Licenses for PBNP Units 1 and 2.
l The proposed change will reflect a licensed power level 1518.5 MWt within licenses DPR-24 and DPR-27, as well as the Appendix A Technical Specifications.
f This is an administrative change only; there is no safety implication. Technical Specifications Section 15.1, " Definitions," itemj., defines rated power as 1518.5 MWt. The FSAR clearly i
states that both units are designed to produce a reactor thermal output of 1518.5 MWt and that all plant safety systems, including containment and engineered safety features, are designed and l
evaluated for operation at 1518.5 MWt. This power rating is also used in the analyses of postulated accidents described in the FSAR. Furthermore, Section 1.5.1 of the FSAR states that the " license application power level" is 1518.5 MWt.
Analyses documented in the Point Beach Nuclear Plant Final Facility Description and Safety Analysis Report at the time the operating licenses were issued, were performed at a power level of 1518.5 MWt. The operating licenses were issued based in part on the review of these analyses.
Subsequent safety evaluations and analyses to support license amendments have been performed based on a power level of 1518.5 MWt. Recent examples include evaluations to support Amendments 156 and 160 issued October 28,1994, for PBNP Units 1 and 2, respectively which approved a reduced reactor coolant system raw measured total flow rate limit for Unit 2; and amendments 120 and 123 issued May 8,1989, to incorporate higher core power peaking factors.
NRC review and approval of these license amendments is documented in the corresponding Safety Evaluation Reports.
Fluence calculations performed to support License Amendments 168 and 172 for PBNP Units 1 and 2 were reviewed to determine the sensitivity of the calculations to an input of 1518.5 MWt vice 1518 MWt. It has been determined that the change has a negligible affect on the calculations.
In addition, monitoring of vessel fluence via the cavity dosimetry program will continue to ensure all regulatory requirements will be met.
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CONCLUSION These changes are administrative in nature and have no safety impact. The changes simply restore consistency within the PBNP licenses and licensing basis documents. Therefore, approval of this change request will not adversely affect the continued safe operation of Point Beach Nuclear Plant.
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TECHNICAL SPECIFICATION CHANGE REOUEST 190 NO SIGNIFICANT HAZARDS 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.
l There is no physical change to the facilities as a result of the proposed license amendment and all Limiting Conditions for Operation, Limiting Safety System Settings and Safety Limits specified in the Technical Specifications remain unchanged. The proposed change is administrative only and restores consistency within the PBNP license and licensing basis.
l Therefore, this amendment will not cause a signi6 cant increase in the probability or i
consequences of an accident previously evaluated.
l 2.
Operation of this facility under the proposed Technical Specifications change will not create the possibility of a new or different kind of accident from any accident previously evaluated.
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The proposed amendment has no effect on the physical configuration of the facilities or the manner in which they operate. The design and design basis of the plants remains the same. The current plant safety analysis therefore remains complete and accurate in j
addressing the design basis events and in analyzing plant response and consequences for the facilities. The Limiting Conditions for Operation, Limiting Safety System Settings and Safety Limits specified in the Technical Specifications for the facilities are not affected by the proposed license amendment. The plant conditions for which the design basis accident analysis have been performed remain valid. Therefore, the proposed license amendment l
cannot create the possibility of a new or different kind of accident from any accident i
previously evaluated.-
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l 3.
Operation of this facility under the proposed Technical Specifications change will not create a significant reduction in a margin of safety.
Plant safety margins are established through Limiting Conditions for Operation, Limiting Safety System Settings and Safety !.mits specified in the Technical Specifications. Since there is no change to the physical design or operation of the plant, there is no change to any of these margins. Thus, the proposed license amendment does not involve a reduction m any margm of safety.
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U nit 1. L.i ce.ns e, Wisconsin Electric Power Company 3.
This amended license shall be deemed to contain and is subject to the conditions specified in the following Commission regulations:
10 CFR Part 20, Section 30.34 of 10 CFR Part 30, Section 40.41 of 10 CFR part 40, Sections 50.54 and 50.59 of 10 CFR Part 50, and Section 70.32 of 10 CFR Part 70; and is subject to all applicable provisions of the Act and to the rules, regulations, and orders of the Commission now or hereafter in effect; and is subject to the additional conditions specified below:
A.
Maximum Power Levels The licensee is authorized to operate the facility at reactor core power levels not in excess of 1518J megawatts thermal.
B.
Technical Soecifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.168, are hereby incorporated in the license. The licensee shall operate the facility in accordance with Technical Specifications.
C.
Report The licensee shall make certain reports in accordance with the requirements of the Technical Specifications.
D.
Records The licensee shall keep facility operating records in accordance with the requirements of the Technical Specifications.
E.
Soent Fuel Pool Modification The licensee is authorized to modify the spent fuel storage pool to increase its storage capacity from 351 to 1502 assemblies as described in licensee's application dated March 21,1978, as supplemented and amended. In the event that the on-site verification check for poison material in the poison assemblies discloses any missing boron plates, the NRC shall be notified and an on-site test on every poison assembly shall be performed.
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l Witconsin Electric Power Company 3.
This amended license shall be deemed to contain and is subject to the conditions specified in the following Commission regulations:
10 CFR Part 20, Section 30.34 of 10 CFR Part 30, Section 40.41 of 10 CFR part 40, Sections 50.54 and 50.59 of 10 CFR Part 50, and Section 70.32 of 10 CFR Part 70; and is subject to all applicable l
provisions of the Act and to the rules, regulations, and orders of the Commission now or hereafter in effect; and is subject to the additional conditions specified below:
A.
Maximum Power Levels The licensee is authorized to operate the facility at reactor core power levels not in excess of 1518J megawatts thermal.
l B.
Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.172, are hereby incorporated in the license. The licensee shall operate the facility in accordance with Technical Specifications.
C.
Report
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l The licensee shall make certain reports in accordance with the requirements of the Technical Specifications.
i D.
Records The licensee shall keep facility operating records in accordance with the requirements of the Technical Specifications.
E.
Spent Fuel Pool Modification l
l The licensee is authorized to modify the spent fuel storage pool to increase its storage capacity from 351 to 1502 assemblies as described in licensee's application dated March 21,1978, as supplemented and amended. In the event that the on-site verification check for poison material in the poison assemblies discloses any missing boron plates, the NRC shall be notified and an on-site test on every poison assembly shall be performed.
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