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Category:TECHNICAL SPECIFICATIONS
MONTHYEARML20212G1611999-09-22022 September 1999 Proposed Tech Specs,Requesting one-time Extension of Unit 2 Surveillance Interval for Snubber Functional Testing ML20212F6611999-09-20020 September 1999 Proposed Tech Specs,Revising Surveillance Std to Which Ventilation Charcoal Must Be Laboratory Tested as Recommended by GL 99-02 ML20210B8981999-07-15015 July 1999 Final Typed Pages for LARs 109 & 115,previously Submitted by 990615 & 28 Ltrs.Revised Pages Replace Those Previously Provided for LARs 109 & 115 ML20210B8771999-07-15015 July 1999 Final,Typed TS (Pages for LARs 262 & 135,previously Submitted with Editorial Changes Identified by ML20210B8401999-07-15015 July 1999 Proposed Tech Specs Revising Surveillance Frequency for Quench & Recirculation Spray Systems Nozzle Air Flow Test from 5 Years to 10 Years,Per Guidance Provided in GL 93-05 ML20209C1941999-06-28028 June 1999 Typed,Final TS Pages for LAR 115.Summary Description of Editorial Changes Incorporated in Addition to Those Addressed in Previously Provided marked-up Pages ML20196G3871999-06-22022 June 1999 Proposed Final Tech Spec Pages for LARs 259 & 131 ML20196F6881999-06-17017 June 1999 Proposed Tech Specs Updating Heatup,Cooldown & Overpressure Protection Curves & Bases to Apply for Up to 15 EFPYs ML20196F0191999-06-17017 June 1999 Proposed Tech Specs Pages for LARs 262 & 135 ML20195K1821999-06-15015 June 1999 Proposed Tech Specs Pages for LAR 109 Re RCS ML20207E1851999-05-27027 May 1999 Proposed Tech Specs,Revising Frequency Notation for Manual Functions Specified in ESFAS to More Clearly Denote Appropriate Refueling Frequency for Testing ML20207E2331999-05-27027 May 1999 Proposed Tech Specs 3/4.3.3.3,relocating Seismic Instrumentation Requirements to Licensing Requirements Manual Based on Guidance Provided in GL 95-10 ML20207E2081999-05-27027 May 1999 Proposed Revised Tech Specs for LARs 259 & 131,revising Qualifications for Operations Mgt & Incorporating Generic Position Titles ML20205H5121999-03-31031 March 1999 Proposed Tech Specs Changes to Index Page Xvii,Changing Wording of Title for Table 3.7-1.Table 3.7-2 Will Be Changed to Be Consistent with Title of Table 3.7-3 ML20204E3851999-03-16016 March 1999 Proposed Tech Specs LCO 3.7.1.3,increasing Min Vol in Primary Plant DW to 127,500 Gallons,Adding New Footnote & Revising Wording Contained Action Statements ML20204E4381999-03-16016 March 1999 Proposed Tech Specs Bases Section 3/4.7.13,adding Wording Which Discusses Design Bases of Sys in Greater Depth ML20207K1331999-03-0303 March 1999 Proposed Tech Specs Changing Qualifications for Operations Mgt & Incorporating Generic Titles to Eliminate Need to Develop Amend Request When Corresponding plant-specific Titles Are Changed ML20207E6261999-02-26026 February 1999 Proposed Typed,Final Tech Specs Pages for LAR 111 ML20199G5431999-01-18018 January 1999 Proposed Tech Specs Re Limiting Safety Sys Settings 2.2.1 & Associated Table 2.2-1 ML20206N9541998-12-24024 December 1998 Proposed Tech Specs,Modifying Applicable Sections by Removing Rod Position Deviation Monitor,Rod Insertion Limit Monitor,Afd Monitor & QPTR Monitor ML20198F9661998-12-24024 December 1998 Proposed Tech Specs Section 3/4.8.1, AC Sources, Clarifying EDG Fuel Oil Storage Requirements by Addition of Term Usable & Increasing EDG Largest Single Load Rejection Test Requirements ML20198D6711998-12-14014 December 1998 Proposed Typed,Final Tech Specs Pages for LARs 246 & 116, Consisting of Editorial Changes Due to Pagination,Changes Incorporated by Previous Amends & Corrected Typos ML20155J0161998-11-0303 November 1998 Proposed Tech Specs Page 3/4 1-15,re Reactivity Control Sys ML20155B9681998-10-23023 October 1998 Proposed Final,Typed Tech Specs Bases Pages for LARs 260 & 133 Re Limiting Safety Sys Settings ML20154Q8021998-10-15015 October 1998 Proposed Tech Specs,Deleting Two License Requirements, Modifying One LCO Applicability,Modifying Three Definitions, Changing Action Statement Number & Deleting Meteorological Monitoring Spec ML20154Q4341998-10-15015 October 1998 Proposed Tech Specs,Adding Discussion That Explains Why Use of Time Constants,Expressed as Equality,Such as T = X Seconds,Are Acceptable ML20154D6381998-09-30030 September 1998 Proposed Tech Specs Re Revised Typed Bases for LAR 235 ML20154C6501998-09-24024 September 1998 Proposed Tech Specs Section 3.1.2.8,eliminating Potential for non-conservative Interpretation of Values of RWST & Bat Min Contained Volume & Eliminating Need for Plant Administrative Controls ML20197C5711998-09-0808 September 1998 Proposed Typed,Final TS Pages Re Surveillance Requirements for LAR 235 ML20236S4921998-07-15015 July 1998 Proposed Tech Specs 3/4 3 Re Reactor Trip Sys & ESF Sys Instrumentation ML20236S2881998-07-13013 July 1998 Proposed Tech Specs Revising BVPS-1 UFSAR Pages 9.7-7 & 8 & BVPS-2 UFSAR Pages 3.6-11 & 12 Re Potential Flooding of Intake Structure Pump Cubicles ML20236P7761998-07-0909 July 1998 Proposed Tech Specs 3/4 3-2,3/4 3-11 & B 3/4 3-1b,modifying Source Range Neutron Flux Requirements to Allow Use of Alternate Detectors ML20236P8051998-07-0909 July 1998 Proposed Tech Specs Revising TS 3.7.1.1, Svs, Incorporating Improved STS Guidance of NUREG-1431 & Recommendations of W Nuclear Safety Advisory 94-01,dtd 940120 ML20249C4531998-06-23023 June 1998 Final Tech Specs Pages for LARs 256/126 ML20249C3161998-06-19019 June 1998 Proposed Tech Specs Modifying Channel Calibr Definition to Exclude RTDs & Thermocouples from TS Channel Calibr Requirements ML20247L3071998-05-14014 May 1998 Proposed Tech Specs,Final Pages for License Amend Requests 249/118 & 254/123,as Amends A-249,A-118,A-254 & A-123, Respectively ML20216G7011998-03-17017 March 1998 Proposed Tech Specs,Revising Engineered Safety Feature Actuation Sys Instrumentation Table 3.3-3,action 34 & Associated Bases Section ML20216G0801998-03-16016 March 1998 Proposed Tech Specs,Exempting Neutron Flux Detectors from Channel Calibr Requirements ML20216G1011998-03-16016 March 1998 Proposed Tech Specs Adding New LCO 3.0.6 to Section 3/4.0, Applicability ML20199J4391998-01-29029 January 1998 Proposed Tech Specs Re Radiological Doses for Locked Rotor Accident ML20198D4081997-12-19019 December 1997 Proposed Tech Specs,Modifying Neutron Flux Requirements to Allow Use of Alternate Detectors ML20198P6571997-11-0404 November 1997 Proposed Tech Specs Table 3.3-4 Re Emergency Bus Undervoltage Trip Setpoint,Allowable Valve & Time Delay for DG Start ML20212C8881997-10-22022 October 1997 Proposed Tech Specs 3.4.8,reducing RCS Specific Activity Limits Per GL 95-05 ML20217A9801997-09-11011 September 1997 Proposed Tech Specs Implementing line-item Improvements Provided in GL 93-08 for Removal of Response Times from TS ML20210L4381997-08-13013 August 1997 Proposed Tech Specs Revised Typed Pages for TS Change Requests 213 & 80,requiring Addl Revs from Pages Submitted in ML20141K5371997-05-23023 May 1997 Proposed Tech Specs Re Typed Paged for Change Request 213 & 80 ML20137C9111997-03-14014 March 1997 Proposed Tech Specs Re Administrative Controls Related to QA ML20147E6511997-03-10010 March 1997 Proposed Tech Specs Modifying Specification 3.4.5 to Allow SG Tube Sleeving Using Framatome Process ML20136G2091997-03-10010 March 1997 Proposed Tech Specs,Modifying Spec 3.4.5 to Allow SG Tube Sleeving Using CE Process ML20147E6301997-03-10010 March 1997 Proposed Tech Specs Modifying Unit 1 Design Feature Section 5.2.1 to Add ZIRLO as Fuel Assembly Matls & Adds Ref to NRC Approved WCAP-12610 to Administrative Control 6.9.1.12 for Both Units 1999-09-22
[Table view] Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML20212G1611999-09-22022 September 1999 Proposed Tech Specs,Requesting one-time Extension of Unit 2 Surveillance Interval for Snubber Functional Testing ML20212F6611999-09-20020 September 1999 Proposed Tech Specs,Revising Surveillance Std to Which Ventilation Charcoal Must Be Laboratory Tested as Recommended by GL 99-02 ML20210B8771999-07-15015 July 1999 Final,Typed TS (Pages for LARs 262 & 135,previously Submitted with Editorial Changes Identified by ML20210B8981999-07-15015 July 1999 Final Typed Pages for LARs 109 & 115,previously Submitted by 990615 & 28 Ltrs.Revised Pages Replace Those Previously Provided for LARs 109 & 115 ML20210B8401999-07-15015 July 1999 Proposed Tech Specs Revising Surveillance Frequency for Quench & Recirculation Spray Systems Nozzle Air Flow Test from 5 Years to 10 Years,Per Guidance Provided in GL 93-05 ML20209C1941999-06-28028 June 1999 Typed,Final TS Pages for LAR 115.Summary Description of Editorial Changes Incorporated in Addition to Those Addressed in Previously Provided marked-up Pages ML20196G3871999-06-22022 June 1999 Proposed Final Tech Spec Pages for LARs 259 & 131 ML20196F0191999-06-17017 June 1999 Proposed Tech Specs Pages for LARs 262 & 135 ML20196F6881999-06-17017 June 1999 Proposed Tech Specs Updating Heatup,Cooldown & Overpressure Protection Curves & Bases to Apply for Up to 15 EFPYs ML20195K1821999-06-15015 June 1999 Proposed Tech Specs Pages for LAR 109 Re RCS ML20207E1851999-05-27027 May 1999 Proposed Tech Specs,Revising Frequency Notation for Manual Functions Specified in ESFAS to More Clearly Denote Appropriate Refueling Frequency for Testing ML20207E2331999-05-27027 May 1999 Proposed Tech Specs 3/4.3.3.3,relocating Seismic Instrumentation Requirements to Licensing Requirements Manual Based on Guidance Provided in GL 95-10 ML20207E2081999-05-27027 May 1999 Proposed Revised Tech Specs for LARs 259 & 131,revising Qualifications for Operations Mgt & Incorporating Generic Position Titles ML20205H5121999-03-31031 March 1999 Proposed Tech Specs Changes to Index Page Xvii,Changing Wording of Title for Table 3.7-1.Table 3.7-2 Will Be Changed to Be Consistent with Title of Table 3.7-3 ML20211N6651999-03-25025 March 1999 Issue 3,rev 3 to Bvps,Unit 1 Inservice Testing (IST) Program for Pumps & Valves ML20204E4381999-03-16016 March 1999 Proposed Tech Specs Bases Section 3/4.7.13,adding Wording Which Discusses Design Bases of Sys in Greater Depth ML20204E3851999-03-16016 March 1999 Proposed Tech Specs LCO 3.7.1.3,increasing Min Vol in Primary Plant DW to 127,500 Gallons,Adding New Footnote & Revising Wording Contained Action Statements ML20207K1331999-03-0303 March 1999 Proposed Tech Specs Changing Qualifications for Operations Mgt & Incorporating Generic Titles to Eliminate Need to Develop Amend Request When Corresponding plant-specific Titles Are Changed ML20207E6261999-02-26026 February 1999 Proposed Typed,Final Tech Specs Pages for LAR 111 ML20199G5431999-01-18018 January 1999 Proposed Tech Specs Re Limiting Safety Sys Settings 2.2.1 & Associated Table 2.2-1 ML20198F9661998-12-24024 December 1998 Proposed Tech Specs Section 3/4.8.1, AC Sources, Clarifying EDG Fuel Oil Storage Requirements by Addition of Term Usable & Increasing EDG Largest Single Load Rejection Test Requirements ML20206N9541998-12-24024 December 1998 Proposed Tech Specs,Modifying Applicable Sections by Removing Rod Position Deviation Monitor,Rod Insertion Limit Monitor,Afd Monitor & QPTR Monitor ML20198D6711998-12-14014 December 1998 Proposed Typed,Final Tech Specs Pages for LARs 246 & 116, Consisting of Editorial Changes Due to Pagination,Changes Incorporated by Previous Amends & Corrected Typos ML20205F6961998-11-30030 November 1998 Revs to Offsite Dose Calculation Manual ML20211K6871998-11-30030 November 1998 Issue 2,Rev 1 to Inservice Testing (IST) Program for Pumps & Valves ML20155J0161998-11-0303 November 1998 Proposed Tech Specs Page 3/4 1-15,re Reactivity Control Sys ML20155B9681998-10-23023 October 1998 Proposed Final,Typed Tech Specs Bases Pages for LARs 260 & 133 Re Limiting Safety Sys Settings ML20154Q8021998-10-15015 October 1998 Proposed Tech Specs,Deleting Two License Requirements, Modifying One LCO Applicability,Modifying Three Definitions, Changing Action Statement Number & Deleting Meteorological Monitoring Spec ML20154Q4341998-10-15015 October 1998 Proposed Tech Specs,Adding Discussion That Explains Why Use of Time Constants,Expressed as Equality,Such as T = X Seconds,Are Acceptable ML20154D6381998-09-30030 September 1998 Proposed Tech Specs Re Revised Typed Bases for LAR 235 ML20154C6501998-09-24024 September 1998 Proposed Tech Specs Section 3.1.2.8,eliminating Potential for non-conservative Interpretation of Values of RWST & Bat Min Contained Volume & Eliminating Need for Plant Administrative Controls ML20197C5711998-09-0808 September 1998 Proposed Typed,Final TS Pages Re Surveillance Requirements for LAR 235 ML20154D5241998-08-14014 August 1998 Issue 2,Rev 0C to Inservice Testing (IST) Program for Pumps & Valves ML20202G9831998-07-22022 July 1998 Issue 3,rev 2 to BVPS Unit 1 IST Program for Pumps & Valves ML20236S4921998-07-15015 July 1998 Proposed Tech Specs 3/4 3 Re Reactor Trip Sys & ESF Sys Instrumentation ML20236S2881998-07-13013 July 1998 Proposed Tech Specs Revising BVPS-1 UFSAR Pages 9.7-7 & 8 & BVPS-2 UFSAR Pages 3.6-11 & 12 Re Potential Flooding of Intake Structure Pump Cubicles ML20236P8051998-07-0909 July 1998 Proposed Tech Specs Revising TS 3.7.1.1, Svs, Incorporating Improved STS Guidance of NUREG-1431 & Recommendations of W Nuclear Safety Advisory 94-01,dtd 940120 ML20236P7761998-07-0909 July 1998 Proposed Tech Specs 3/4 3-2,3/4 3-11 & B 3/4 3-1b,modifying Source Range Neutron Flux Requirements to Allow Use of Alternate Detectors ML20249C4531998-06-23023 June 1998 Final Tech Specs Pages for LARs 256/126 ML20249C3161998-06-19019 June 1998 Proposed Tech Specs Modifying Channel Calibr Definition to Exclude RTDs & Thermocouples from TS Channel Calibr Requirements ML20248M1901998-05-19019 May 1998 Proposed Rev 2F to Bvps,Unit 2 Inservice Testing (IST) Program for Pumps & Valves ML20247L3071998-05-14014 May 1998 Proposed Tech Specs,Final Pages for License Amend Requests 249/118 & 254/123,as Amends A-249,A-118,A-254 & A-123, Respectively ML20247J2851998-04-20020 April 1998 Alternative Request BV1-RV-AUG-1,Rev 1 for Reactor Vessel Lower Circumferential Weld (RC-R-1-C-8) ML20247J6761998-04-20020 April 1998 Alternative Request BV2-RV-AUG-1,Rev 1 for Reactor Vessel Lower Circumferential Weld (2RCS-REV21-C-4) ML20216J9771998-04-13013 April 1998 BVPS Unit 1,Cycle 13 Startup Physics Test Rept ML20248K3061998-03-20020 March 1998 Rev 1,Issue 3 to Inservice Testing Program for Pumps & Valves ML20237B9721998-03-19019 March 1998 Rev 1 to Procedure Npdap 2.14, Fitness-For-Duty for Duquesne Light Employees ML20216G7011998-03-17017 March 1998 Proposed Tech Specs,Revising Engineered Safety Feature Actuation Sys Instrumentation Table 3.3-3,action 34 & Associated Bases Section ML20216G1011998-03-16016 March 1998 Proposed Tech Specs Adding New LCO 3.0.6 to Section 3/4.0, Applicability ML20216G0801998-03-16016 March 1998 Proposed Tech Specs,Exempting Neutron Flux Detectors from Channel Calibr Requirements 1999-09-22
[Table view] |
Text
7 t l TABt.E 3.2 1 ,
ONB PARAMETERS 3 Loops in PARAMETER Operation Reactor Coolant System T,yg 1 580.3*F
' Pressurizer Pressure > 2220 psia" Reactor Coolant System > 2 '
Total Flow Rate ~ 8 ,000 gpm**
0;$ EO F
- Limit not applicable during either e. THERMAL POWER ramp increase in excess of-5 percent RATED THERMAL POWER per minute or a THERMAL POWER step increase in excess of 10% RATED THERMAL-POWER.
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- Includes pa~ flow measurement uncertainty.
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BEAVER VALLEY:- UNIT 2 3/4 2-12 3.$f sob!$ k (8ropsed WordM
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ATTACHMENT A Beaver Valley Power Station, Unit No. 2 Proposed Technical Specification Change Nc, 62 s . _
Revise the Techrical Specification as follows:
Remove Paca Insert Page 3/4 2-12 3/4 2-12 i
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ATTACIU4ENT B Beaver Valley Power Station, Unit No. 2 Proposed Technical Specification Change No. 62 REVISION OF TABLE 3.2-1 OF SPECIFICATION 3.2.5
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r A. DESCRIPTION OF AMENDMENT REQUEST The proposed amendment would revise Tablu 3.2-1 of Technical Specification 3.2.5 titled "DNB PARAMETERS". The revision includes the lowering of the value for the reactor coolant system (RCS) total flow rate from 2 274,800 gpm to 2 270,850 gpm and the lowering of the 3.5% flow measurement uncertainty value, specified in the table footnote, to 2.0%.
B. BACKGROUND Technical Specification 3.2.5 requires that the RCS flow be maintained within a limit of greater than or equal to 274,800 gpm, and contains a footnote stating that this flow limit includes a 3.5% flow measurement uncertainty. This limit placed on- RCS flow along with RCS coolant temperature, and pressurizer pressure ensures that the minimum departure from nucleate boiling ratio (DNBR) will be met for each of the transients analyzed la the safety analyses. The current e=fety analyses assumes a total
-RCS thermal desigt. flow rate of 2 265,500 gpm.
The RCS total flow rate is measured on an 18 Taonth freqlency, as specified by Surveillance Requirement (SR) 4.2,5.2, to ensure that the plant remains within the assumptions of the safety analyses. This flow measurement is performed by conducting a heat balance using RCS heat input and steam generator seconrary side heat output. The typical measurement uncertainty assigned to Westinghouse plants is 3.5%. Given this uncertainty-factor, the value specified in Table 3.2-1 for RCS total flow rate is increased by 3.S% over the valuc assumed in the safety analyses (ie, 265,500 gpm plus 3.5% approximately equals 274,800 gpm).
C. JUSTIFICATION The proposed reduction of the RCS flow measurement uncertainty from 3.5% to 2.0% and the resulting lowering of the required RCS total flow rate from 2 274,800 gpm to 2 270,850 gpm is based on a plant specific annlysis for Beaver Valley Power Station (BVPS)
Unit No. 2. This plant specific analysis was performed by Westinghouse Electric Corpordtion using the same methodology as provided in WCAP 12478 and WCAP 11366 Revision 2, titled "RTD Bypass Elimination Licensing Report For BVPS Unit No.'2" and
" Westinghouse Setpoint Mathodology for Protection Systems For BVdS Unit No. 2" respectively. A review of in-plant procedures used to calibrate the various instruments used when determining RCS total flow rate was performed. The test procedure used to conduct the heat balance which-determines the RCS total flow rate
' ATTA'HMENT C B, continued
' Proposed Technical Specification Change No. 62 Page 2 using thermodynamic equations was also reviewed. The information obtained by these reviews was then used in the determination of a flow measure.nent uncertainti value for BVPS Unit No. 2. The result of this analysis resulted in RCS flow measurement uncertainty of 1.9%. A value of 0.1% was then added to account for undetected feedwater venturi fouling. Potential fouling of the feedwater venturi which might not be detected could bias the results from the heat balance in a non-conservative manner.
Therefore, a penalty of 0.1% was added to account for this factor.- It should be noted- that BVPS Unit No. 2 has not exhibited any evidence of feedwater venturi fouling as shown by our secondary side performance monitoring program. The addition of the 0.1% is strictly to add additional conservatism to the measured RCS total flow rate.
Therefore, the proposed value of 2.0% for RCS flow measurement uncertainty was derived from a plant specific analysis, using Westinghouse methodology, and contains an additional allowance for u. detected feedwater venturi fouling.
D. SAFETY ANALYSIS The- proposed change to the RCS flow uncertainty does not affect the safety analyses which model RCS flow. A value of 265,500 gpm RCS tatal flow is used as an initial condition in the safety analyses. This proposed change will not hiter this assumption.
The flow uncertainty value provides an allowance for the various instrument inaccuracies that are introduced into the measured data when performing the RCS total flow measurement. The uncertainty _value ensures that when a total RCS flow rate is measured, the actual r.cs flow is greater than or equal to the minimum required flow rate of 265,500 gpm. The proposed lowering of the uncertainty factor will not affect the ability to demonstrate that che RCS total flow limit will continue to be met based on the BVPS Unit No. 2 plant specific review. Therefore, this proposed changa. is considered safe based on the plant specific evaluation which was performed to determine the proposei
. uncertainty factor of 2.0%. The proposed uncertainty factor will l' continue to ensure that actual RCS total flow rate is above the l value assumed in the safety analyses for normal operatite conditions and anticipated operational occurrences. The rese.' .
of ensuring RCS total flow is above analyses limits proves that the minimum DNBR will be met for each of the transients analyzed and that the plant will remain within the limits which are prescribed for continued safe operation.
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. ATTACHMENT B, continued Proposed Technical Specification Change No. 62 Page 3 E. NO SIGNIFICANT HAZARDS EVALUATION The no significant hazard considerations involved with the proposed amendment have been evaluated, focusing on the three standards set forth in 10 CFR 50.92(c) as quoted below:
The Commission may make a final determination, pursuant to the procedures in paragraph 50.91, that a proposed amendment to an operating license for a facility licensed -under paragraph 50.21(b) or paragraph 50.22 or for a testing facility involves no significant hazards consideration, if operation of the- facility in accordance with the proposed.
amendment would not:
(1)- Invol" a significant increase in the probability or consequences of an accident previously evaluated; or (2) Create the possibility of a new or different kind of accident from any accident previously evaluatea;.or (3) Involve a significant reduction in a margin of safety.
The following evaluation is provided for the no significant hazards consideration standards.
- 1. Does the change involve a significant increase in the probability or cc :weguences of an accident previously evaluated?
The proposed change to the RCS flow uncertainty does not involve a significant . increase in the probability or consequences of an accident previously evaluated. The RCS flow will continue to be monitored once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> in accordance with . surveillance requirement 4.2.5.1.1. No new performance requirements. are being imposed on the RCS in order. to satisfy the revised flow ' uncertainty value of 2.0%. No new requirements must be considered by the safety analyses which model RCS flow since the thermal oesign'value of 265,500 gpm remains unchanged. RCS flow is.an assumed initial condition in the safety analyses and does not act as an . initiator for any transjent. The accident analyses-are not affected by 'chis , proposed change and therefore no additionnl fuel failures or mass releases vill result.
Therefore, the proposed change does not involve a significant increase 'in the probability or consequences of an accident previously evaluated.
. ATTACHMENT B, continued Prdposed Technical Specification Change No. 62 Page 4'
- 2. Does the change create the possibility of a new or different ,
kind of accident from any accident pecviously evaluated?
There would be no change to system configurations, plant equipment or analysis as a result of this proposed amendment.
Therefore, the proposed change doet not create the possibility of a new or different kind of accident from any accident previously evaluated.
- 3. Does the change involve a significant reduction in a margin of safety?
The proposed change to the RCS flow uncertainty does not involve a significant reduction in the margin of safety.
The unccrtainty value is being reduced from 3.5% to 2.0%
based on a BVPS Unit No. 2 plant specific evaluation which includes a review of calibration procedures and in-plant equipment based on the same methodology used in WCAP 12478 and WCAP 11366 Rev. 2 and provides a value which accounts
-for an appropriate naryin of safety. Accident analyses are performed at a flow value cf 265,500 gpm without the addition of the uncertainty factor and have shown acceptable results in all cases.
Therefore, the proposed chance does not involve a significant reduction in the margin of safety.
F. NO SIGNIFICANT HAZARDS CONSIDERATION DETERMINATION Based on the considerations expressed above, it is concluded that tha activities associated with this license amendment request satisfies the no significant hazards consideration standards of i 10 CFR 50.92(c) and, accordingly, a no significant hazards consideration finding is justified.
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ATTACHMENT C Beaver Valley Power Station, Unit No. 2 Proposed Technical Specification change No. 62 Typed Page: 3/4 2-12 4
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- TABLE 3,2-1 DNB PARAMETERS 3 Loops in PARAMETEE OperatiQD Reactor Coolant System T avg $ 580.3*F Pressurizer Pressure 1 2220 psia
Total Flow Rate l Limit not- applicable during either a THERMAL POWER ramp increase in' excess of 5 percent. RATED THERMAL POWER- per minute or a THERMAL POWER step increast in excess of.10% RATED THERMAL POWER.
Includes a 2.0% flow measurement uncertainty.
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4 BEAVER VALLEY.- UNIT 2 3/4 2-12 Amendment ho. l (Proposed Wording)