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Category:SAFETY EVALUATION REPORT--LICENSING & RELATED ISSUES
MONTHYEARML20212J9251999-10-0101 October 1999 Safety Evaluation Accepting Licensee Relief Request IWE-3 for Second 10-year ISI for Plant ML20211N2611999-09-0808 September 1999 Safety Evaluation Concluding That Proposed Irradiation of Fuel Rods Beyond Current Lead Rod Burnup Limit & Clarification of Terminology with Respect to Reconstituted Fuel Assemblies Acceptable ML20211J2421999-08-31031 August 1999 Safety Evaluation Supporting Removal of Augmented Insp Program on RCS Bypass Lines from Licensing Basis of North Anna,Units 1 & 2 ML20211J2561999-08-31031 August 1999 Safety Evaluation Accepting Elimination of Augmented ISI Program for Pressurizer Spray Lines at North Anna Unit 2 ML18152B3831999-08-23023 August 1999 Safety Evaluation Granting Relief Request from ASME Section XI Requirements for Containment Insp ML20210T0791999-08-13013 August 1999 Safety Evaluation Concluding That Revised Withdrawal Schedules for North Anna Units 1 & 2 Satisfy Requirements of App H to 10CFR50 & Therefore Acceptable ML20206L4831999-05-10010 May 1999 SER Accepting Request to Delay Submitting Plant,Unit 1 Class 1 Piping ISI Program for Third Insp Interval Until 010430, to Permit Development of Risk Informed ISI Program for Class 1 Piping ML20206C0151999-04-22022 April 1999 Safety Evaluation Supporting Amends 219 & 200 to Licenses NPF-4 & NPF-7,respectively ML20205S0391999-04-21021 April 1999 SER Accepting Request for Relief IWE5,per 10CFR50.55a(a)(3) & Proposed Alternatives for IWE2,IWE4,IWE6 & IWL2 Authorized Per 10CFR50.55a(a)(3)(ii) ML20207H4451999-03-0202 March 1999 Safety Evaluation Supporting Amends 218 & 199 to Licenses NPF-4 & NPF-7,respectively ML20198H9541998-12-0303 December 1998 Safety Evaluation Authorizing Proposed Alternative for Remainder of Second 10-yr Insp Interval for Plant ML20196G1381998-11-0303 November 1998 Safety Evaluation Authorizing Rev to Relief Request NDE-32 for Remainder of Second 10-yr Insp Interval for Each Unit ML20155H0351998-10-30030 October 1998 Safety Evaluation Supporting Amends 215 & 196 to Licenses NPF-4 & NPF-7,respectively ML20237E1871998-08-26026 August 1998 Safety Evaluation Supporting Amends 214 & 195 to Licenses NPF-4 & NPF-7,respectively ML20236X3811998-08-0303 August 1998 Safety Evaluation Supporting Amends 213 & 194 to Licenses NPF-4 & NPF-7,respectively ML20236K5531998-07-0707 July 1998 SER Accepting Request for Change in ISI Commitment on Protection Against Pipe Breaks Outside Containment ML20249C1521998-06-23023 June 1998 Safety Evaluation Supporting Amends 212 & 193 to Licenses NPF-4 & NPF-7,respectively ML20248C8831998-05-29029 May 1998 SER Accepting Alternatives Proposed by Licensee for Use of Code Case N-535,pursuant to 10CFRa(a)(3)(i) in ASME Section XI Inservice Insp Program ML20217E7001998-04-22022 April 1998 Safety Evaluation Supporting Amends 211 & 192 to Licenses NPF-4 & NPF-7,respectively ML20217B5321998-04-20020 April 1998 Safety Evaluation Supporting Proposed Alternative to ASME Code for Surface Exam of Seal Welds on Threaded Caps for Plant Reactor Vessel Head Penetrations for part-length CRDMs ML20216G8741998-04-16016 April 1998 Safety Evaluation Supporting Amends 210 & 191 to Licenses NPF-4 & NPF-7,respectively ML20216F1251998-04-14014 April 1998 Safety Evaluation Supporting Amends 209 & 190 to Licenses NPF-4 & NPF-7,respectively ML20216E8801998-03-0606 March 1998 Safety Evaluation Authorizing Licensee Request for Relief from ASME Code Requirements,Paragraph IWA-2400(c) (Summer Edition W/Summer 1983 Addenda),For Upcoming Naps,Unit 1 Outage,Per 10CFR50.55a(a)(3)(ii) ML20199J6431998-02-0202 February 1998 Safety Evaluation Approving Request for Approval to Repair Flaws in Accordance W/Gl 90-05 for ASME Code Class 3 SW Piping for North Anna,Unit 1,as Submitted in ISI Relief Request NDE-46 on 971218 ML20198S7571998-01-15015 January 1998 Safety Evaluation Accepting Licensee Request for Approval to Repair Flaws IAW GL-90-05 for ASME Code Class 3 Svc Water Piping ML20198H5541997-12-29029 December 1997 SER Accepting Request for Approval of ASME Case N-498,rev 1, as an Alternative to Required Hydrostatic Pressure Test for Plant,Unit 2 ML20197K1541997-12-18018 December 1997 SER Granting Request for Approval to Repair Flaws in Accordance W/Gl 90-05 for ASME Code Class 3 Service Water Piping for North Anna Power Station,Per Util 970919 Submittal ML20203C4191997-12-0404 December 1997 Safety Evaluation Supporting Amends 207 & 188 to Licenses NPF-4 & NPF-7,respectively ML20202B8751997-11-24024 November 1997 Safety Evaluation Denying Licensee Request for Exemption from Section III.G.2.f of App R to 10CFR50.Staff Concluded That Use of Combustible Radiant Energy Heat Shields Inside Containment at Surry & North Anna Unacceptable ML20199L0501997-11-24024 November 1997 SER Accepting Inservice Insp Program Relief Request NDE-32 ML20199E4971997-11-14014 November 1997 Safety Evaluation Authorizing Proposed Alternative of Licensee Relief Requests NDE-35 & NDE-37,for Plant,Units 1 & 2 During Second 10 Yr Interval ML20217E2411997-09-24024 September 1997 SER Accepting Request for Approval to Repair Flaws in Accordance W/Gl 90-05 for ASME Code Class 3 Service Water Piping,Virginia Electric & Power Co,North Anna Power Station,Unit 1 ML20217E1871997-09-24024 September 1997 SER Approving Request for Approval to Repair Flaws in Accordance W/Gl 90-05 for ASME Code Class 3 Service Water Piping,Virginia Electric & Power Co,North Anna Power Station,Units 1 & 2 ML20217E0701997-09-24024 September 1997 Safety Evaluation Granting Licensee ASME Section XI Relief Request NDE-33 at Plant,Unit 1 ML20149L2001997-07-29029 July 1997 SER Granting Requests for Relief NDE-33,34 & 35 Re ISI Program,Per 10CFR50.55a(g)(6)(i) ML20149F1321997-07-17017 July 1997 Safety Evaluation Supporting Amends 205 & 186 to Licenses NPF-4 & NPF-7,respectively ML20148H1971997-06-0404 June 1997 Safety Evaluation Granting Licensee Relief Request NDE-31 Related to Inservice Insp Program ML20140H8961997-05-0909 May 1997 Safety Evaluation Supporting Amends 204 & 185 to Licenses NPF-4 & NPF-7,respectively ML20140F4811997-04-30030 April 1997 Safety Evaluation Accepting Licensee 951207 Proposed Alternative in Request for Relief SPT-16 Re Second 10-yr Interval Inservice Insp Program for Unit 2 ML20133Q0661997-01-17017 January 1997 Safety Evaluation Supporting Amends 203 & 184 to Licenses NPF-4 & NPF-7,respectively ML20133G1561997-01-10010 January 1997 Safety Evaluation Accepting Second 10-year Relief Requests for Relief Numbers NDE-27,NDE-28 & NDE-29 ML20133G1911997-01-10010 January 1997 Safety Evaluation Accepting Second 10-year Interval Inservice Insp Plan Relief Request NDE-30 ML20138G1931996-10-16016 October 1996 SER Accepting Second 10-year Interval Inservice Insp Plan Request for Relief SPT-14,rev 1 Virginia Electric & Power Co North Anna Power Station,Unit 2 ML20128P1701996-10-10010 October 1996 Safety Evaluation Supporting Second 10-year Interval Inservice Insp Program Plan Requests for Relief NDE-23 Through NDE-30 for Plant Unit 2 ML20128F5981996-10-0101 October 1996 Safety Evaluation Authorizing Licensee Proposed Alternative to Examine Terminal End Welds on Lower Regenerative Heat Exchanger sub-vessels,per 10CFR50.55a(a)(3)(ii) ML20116B2361996-07-24024 July 1996 Safety Evaluation Supporting Amends 202 & 183 to Licenses NPF-4 & NPF-7,respectively ML20117K4221996-06-0505 June 1996 Safety Evaluation Supporting Amends 201 & 182 to Licenses NPF-4 & NPF-7,respectively ML20101L6861996-04-0101 April 1996 Safety Evaluation Supporting Amends 200 & 181 to Licenses NPF-4 & NPF-7,respectively ML20100L0031996-02-27027 February 1996 Safety Evaluation Supporting Amends 198 & 179 to Licenses NPF-4 & NPF-7,respectively ML20097D2491996-02-0808 February 1996 Safety Evaluation Supporting Amends 195 & 176 to Licenses NPF-4 & NPF-7,respectively 1999-09-08
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEAR05000339/LER-1999-002-03, :on 990922,containment Liner Through Wall Defect Was Noted.Caused by Corrosion.Pressure Test Was Performed.With1999-10-21021 October 1999
- on 990922,containment Liner Through Wall Defect Was Noted.Caused by Corrosion.Pressure Test Was Performed.With
ML20217N9281999-10-20020 October 1999 Special Rept:On 991003,PZR PORV Actuation Mitigated RCS low- Temp Overpressure Transient.Caused by a RCP Facilitating Sweeping of Entrained Air Out of RCS Loops.Operating Procedure 2-OP-5.1 Will Be Revised ML20217H3631999-10-14014 October 1999 Rev 0 to COLR for North Anna 2 Cycle 14 Pattern Su 05000339/LER-1999-001-03, :on 990915,failure to Lock Open Loop SV Breakers as Intended by TSs Was Noted.Caused by Failure to Update Operating Procedures.Procedure ARs Were Initiated & Approved for Maint Procedure 1/2-MOP-5.92.With1999-10-12012 October 1999
- on 990915,failure to Lock Open Loop SV Breakers as Intended by TSs Was Noted.Caused by Failure to Update Operating Procedures.Procedure ARs Were Initiated & Approved for Maint Procedure 1/2-MOP-5.92.With
ML18152A2811999-10-12012 October 1999 Technical Basis for Elimination of Nozzle Inner Radius Insps (for Nozzles Other than Reactor Vessel),Technical Basis for ASME Section XI Code Case N-619. ML20212J9251999-10-0101 October 1999 Safety Evaluation Accepting Licensee Relief Request IWE-3 for Second 10-year ISI for Plant ML20217D6851999-09-30030 September 1999 Monthly Operating Repts for Sept 1999 for North Anna Power Station,Units 1 & 2.With 05000338/LER-1999-006-01, :on 990904,potential for Safegurads Exhaust Flow to Bypass Charcoal Filter,Was Discovered.Caused by Degraded Damper.Plant Issue Rept Submitted for B Train of Savs Flow Rate.With1999-09-28028 September 1999
- on 990904,potential for Safegurads Exhaust Flow to Bypass Charcoal Filter,Was Discovered.Caused by Degraded Damper.Plant Issue Rept Submitted for B Train of Savs Flow Rate.With
05000338/LER-1999-002, :on 990213,unsecured Isolation Valve,Was Discovered.Caused by Valve Configuration.Unsecured Bit Manual Bypass Isolation Valve Was Verified Closed & Chain & Lock Secured Valve Tee Handle.With1999-09-17017 September 1999
- on 990213,unsecured Isolation Valve,Was Discovered.Caused by Valve Configuration.Unsecured Bit Manual Bypass Isolation Valve Was Verified Closed & Chain & Lock Secured Valve Tee Handle.With
ML20211N2611999-09-0808 September 1999 Safety Evaluation Concluding That Proposed Irradiation of Fuel Rods Beyond Current Lead Rod Burnup Limit & Clarification of Terminology with Respect to Reconstituted Fuel Assemblies Acceptable ML20216E5011999-08-31031 August 1999 Monthly Operating Repts for Aug 1999 for Naps,Units 1 & 2. with ML20211J2421999-08-31031 August 1999 Safety Evaluation Supporting Removal of Augmented Insp Program on RCS Bypass Lines from Licensing Basis of North Anna,Units 1 & 2 ML20211J2561999-08-31031 August 1999 Safety Evaluation Accepting Elimination of Augmented ISI Program for Pressurizer Spray Lines at North Anna Unit 2 ML18152B3831999-08-23023 August 1999 Safety Evaluation Granting Relief Request from ASME Section XI Requirements for Containment Insp ML20210T0791999-08-13013 August 1999 Safety Evaluation Concluding That Revised Withdrawal Schedules for North Anna Units 1 & 2 Satisfy Requirements of App H to 10CFR50 & Therefore Acceptable ML20210Q9931999-07-31031 July 1999 Rev 1 to COLR for North Anna Power Station,Unit 2 Cycle 13 Pattern Ud ML20210S1411999-07-31031 July 1999 Monthly Operating Repts for July 1999 for North Anna Power Station.With ML20209E5641999-06-30030 June 1999 Monthly Operating Repts for June 1999 for North Anna Power Stations,Units 1 & 2.With ML20195G1901999-05-31031 May 1999 Monthly Operating Rept for May 1999 for NAPS Units 1 & 2. with 05000338/LER-1999-004, :on 990413,position Switch for Suction Supply Dampers to CR Emergency Fan Was Discovered Out of Position. Cause Could Not Be Determined.Station Entered Action Statement for TS 3.7.7.1.With1999-05-11011 May 1999
- on 990413,position Switch for Suction Supply Dampers to CR Emergency Fan Was Discovered Out of Position. Cause Could Not Be Determined.Station Entered Action Statement for TS 3.7.7.1.With
ML20206L4831999-05-10010 May 1999 SER Accepting Request to Delay Submitting Plant,Unit 1 Class 1 Piping ISI Program for Third Insp Interval Until 010430, to Permit Development of Risk Informed ISI Program for Class 1 Piping ML20206Q6671999-04-30030 April 1999 Monthly Operating Repts for Apr 1999 for North Anna Power Station,Units 1 & 2.With 05000338/LER-1999-003, :on 990331,potential Loss of HHSI Pumps, Occurred Due to Postulated Main CR Fire.Caused by Incomplete Understanding of Time Sensitivity of Actions Required to Avoid Potential Loss.Procedure Revised.With1999-04-27027 April 1999
- on 990331,potential Loss of HHSI Pumps, Occurred Due to Postulated Main CR Fire.Caused by Incomplete Understanding of Time Sensitivity of Actions Required to Avoid Potential Loss.Procedure Revised.With
ML20206C0151999-04-22022 April 1999 Safety Evaluation Supporting Amends 219 & 200 to Licenses NPF-4 & NPF-7,respectively ML20205S0391999-04-21021 April 1999 SER Accepting Request for Relief IWE5,per 10CFR50.55a(a)(3) & Proposed Alternatives for IWE2,IWE4,IWE6 & IWL2 Authorized Per 10CFR50.55a(a)(3)(ii) ML20205K3041999-03-31031 March 1999 Monthly Operating Repts for Mar 1999 for North Anna Power Station,Units 1 & 2.With 05000338/LER-1999-002, :on 990213,isolation Valve Was Unsecured. Caused by Valve Configuration.Unsecured Valve Verified to Be Closed & Chain & Lock Placed in Manner That Would Secure Valve Tee Handle.With1999-03-11011 March 1999
- on 990213,isolation Valve Was Unsecured. Caused by Valve Configuration.Unsecured Valve Verified to Be Closed & Chain & Lock Placed in Manner That Would Secure Valve Tee Handle.With
ML20207H4451999-03-0202 March 1999 Safety Evaluation Supporting Amends 218 & 199 to Licenses NPF-4 & NPF-7,respectively ML20207K5921999-02-28028 February 1999 Monthly Operating Repts for Feb 1999 for North Anna Power Station,Units 1 & 2.With ML20207E1731999-02-18018 February 1999 Informs Commission of Status of Preparations of IAEA Osart Mission to North Anna Nuclear Power Plant Early Next Year 05000338/LER-1999-001-01, :on 990106,RCS Leak Rate Missed Surveillance Was Noted.Caused by Computer Malfunction.Computer Malfunction Affecting VCT & Pzr Level Inputs Was Corrected. with1999-01-22022 January 1999
- on 990106,RCS Leak Rate Missed Surveillance Was Noted.Caused by Computer Malfunction.Computer Malfunction Affecting VCT & Pzr Level Inputs Was Corrected. with
ML20205A0241998-12-31031 December 1998 Summary of Facility Changes,Tests & Experiments,Including Summary of SEs Implemented at Plant During 1998,per 10CFR50.59(b)(2).With ML20199C8781998-12-31031 December 1998 Monthly Operating Repts for Dec 1998 for North Anna Power Station,Units 1 & 2.With ML20198H9541998-12-0303 December 1998 Safety Evaluation Authorizing Proposed Alternative for Remainder of Second 10-yr Insp Interval for Plant ML20198J5561998-12-0303 December 1998 ISI Summary Rept for North Anna Power Station,Unit 1 1998 Refueling Outage Owner Rept for Inservice Insps ML20197G8551998-11-30030 November 1998 Monthly Operating Repts for Nov 1998 for North Anna Power Station,Units 1 & 2.With 05000338/LER-1998-007-01, :on 981015,3B Casing Cooling Pump Failed to Develop Discharge Pressure & Recirculation.Caused by Air Binding.Subject Pump Was Vented of Air,Started & Tested Satisfactorily.With1998-11-12012 November 1998
- on 981015,3B Casing Cooling Pump Failed to Develop Discharge Pressure & Recirculation.Caused by Air Binding.Subject Pump Was Vented of Air,Started & Tested Satisfactorily.With
ML20196G1381998-11-0303 November 1998 Safety Evaluation Authorizing Rev to Relief Request NDE-32 for Remainder of Second 10-yr Insp Interval for Each Unit ML20195D0571998-10-31031 October 1998 Monthly Operating Repts for Oct 1998 for North Anna Power Station,Units 1 & 2.With ML20155H0351998-10-30030 October 1998 Safety Evaluation Supporting Amends 215 & 196 to Licenses NPF-4 & NPF-7,respectively ML20154L0691998-10-14014 October 1998 COLR for North Anna Power Station Unit 1 Cycle 14 Pattern Xy ML20155J6911998-10-0909 October 1998 Staff Response to Tasking Memorandum & Stakeholder Concerns 05000338/LER-1998-005-01, :on 980921,safety Valve Setpoints Were Noted Out of Tolerance.Caused by Setpoint Variance.Valves Were Disassembled,Inspected,Repaired as necessary,re-assembled & Tested Satisfactory.With1998-10-0707 October 1998
- on 980921,safety Valve Setpoints Were Noted Out of Tolerance.Caused by Setpoint Variance.Valves Were Disassembled,Inspected,Repaired as necessary,re-assembled & Tested Satisfactory.With
05000338/LER-1998-006-01, :on 980922,ESFA Occurred.Caused by Human Error. Safety Injection Signal Was Reset & Equipment Was Restored to Normal1998-10-0707 October 1998
- on 980922,ESFA Occurred.Caused by Human Error. Safety Injection Signal Was Reset & Equipment Was Restored to Normal
05000339/LER-1998-004-02, :on 980917,reactor Trip Was Noted.Caused by Lightning Strike.Operations Emergency Procedure 2-E-0, RT or SI Was Entered1998-10-0606 October 1998
- on 980917,reactor Trip Was Noted.Caused by Lightning Strike.Operations Emergency Procedure 2-E-0, RT or SI Was Entered
05000339/LER-1998-003-01, :on 980424,multiple Failures Occurred During Functional Testing of RCS Large Bore Snubbers.Cause Unknown. Large Bore Snubbers Replaced.With1998-10-0505 October 1998
- on 980424,multiple Failures Occurred During Functional Testing of RCS Large Bore Snubbers.Cause Unknown. Large Bore Snubbers Replaced.With
ML20154H4001998-09-30030 September 1998 Monthly Operating Repts for Sept 1998 for North Anna Power Station,Units 1 & 2.With 05000338/LER-1998-004-01, :on 980902,motor Operated Valve Surveillance Was Missed.Caused by Personnel Error.Station Entered 24 H Action of TS 4.0.3 & Station Deviation Rept Was Initiated to Document Condition.With1998-09-22022 September 1998
- on 980902,motor Operated Valve Surveillance Was Missed.Caused by Personnel Error.Station Entered 24 H Action of TS 4.0.3 & Station Deviation Rept Was Initiated to Document Condition.With
05000338/LER-1998-003, :on 980804,service Water Supports Surveillance Was Missed.Caused by Personnel Error.Component Supports Were Examined & Found to Be Acceptable.With1998-09-17017 September 1998
- on 980804,service Water Supports Surveillance Was Missed.Caused by Personnel Error.Component Supports Were Examined & Found to Be Acceptable.With
ML20151X8011998-09-10010 September 1998 Special Rept:On 980622,groundwater Level at Piezometer P-22 Was Again Noted to Be Above Max Water Level by 0.71 Feet. Increased Frequency of Piezometer Monitoring & Installed Addl Piezometers at Toe of Slope Along Southwest Section 1999-09-08
[Table view] |
Text
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UNITED STATES h
NUCLEAR REGULATORY COMMISSION 5
j WASHINGTON, D. C. 20555
\\...../
SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NOS. 85 AND 72 TO FACILITY OPERATING LICENSE NOS. NPF-4 AND NPF-7 VIRGINIA ELECTRIC AND POWER COMPANY OLD DOMINION ELECTRIC COOPERATIVE NORTH ANNA POWEP STATION, UNITS NO. 1 AND NO. 2 DOCKET NOS. 50-338 AND 50-339
==
Introduction:==
By letter dated January 3,1986, the Virginia Electric and Power Company (the licensee), requested a change to the Technical Specifications (TS) for the North Anna Power Station, Units No. I and No. 2 (NA-182). Specifically, the proposed changes would revise the negative end-of-cycle (EOC) modegator temperature coefficient (QC) limit from a current value of -4.0 x 10~
delta k/k/*F to -4.4 x 10 delta k/k/'F, and would also revise the corresponding 300partpermillion(ppm)equijibriumboronconcentrationvaluefrom-3.1x 10-4 delta k/k/*F to -3.3 x 10 delta k/k/*F.
In addition, the proposed changes would update the EOC MTC limits to reflect current plant operating conditions. The above changes have been proposed in order to provide greater flexibility during the reload design process. The staff's discussion and evaluation of the proposed changes are provided below.
Discussion:
The current NA-182 TS require that the MTC be confimed as the fuel cycle approaches the O ppm boron concentration end ggint of EOC conditions. The negative EOC MTC limit is currently -4.0 x 10 delta k/k/*F in the NA-1A?
TS Gection 3.1.1.4.b).
The value of the EOC MTC is measured upon reaching anequilibriumboronconcentrationo{deltak/k/'F(Section4.1.1.4.b).
300 ppm. The current TS value for this measurement point is -3.1 x 10' If the measured MTC is within this value, no further checks of MTC against the EOC negative MTC limit are necessary.
If the measured MTC at the 300 ppm boron check point violates the NA-1 A2 TS value, operation of the unit may continueifMTCmeasurementsaretakenatjeastevery14effectivefullpower days and found to be within the -4.0 x 10' delta k/k/*F EOC limit.
Bases Section 3/4.1.1.4 of the TS identifies the source for the MTC limit and the conversions used to derive the value for measurement comparison at the 300 ppm ecuilibrium boron concentration point. The most negative MTC value is basec on the limiting moderator density coefficient, (MDC), used in the Chapter 15 of the Final Safety Analysis Report (FSAR) analyses:
OhbOhcS ObObu r
m
-2 O
This MDC value is first incrementally adjusted to allow for changing the core from the all-rods-inserted condition, upon which the safety analysis is based, to an all-rods-withdrawn condition consistent with actual measurement conditions.
3 The second conversion translates the MDC value in delta k/k/(g/cm ) to MTC in delta k/k/*F. A derivative of water density with respect to temperature at core operating conditions is used to make this conversion.
The result is the Technical Specification EOC negative MTC limit.
The final conversion translates the EOC negative MTC limit into a TS value at the 300 ppm equilibrium boron concentration measurement point, i
Conservative corrections for MTC change due to burnup and soluble boron concentration are used.
The resulting E0C negative MTC limit and negative MTC value at tge 300 ppm equilibrium bogon concentration measurement point are -4.4 x 10~ delta k/k/*F and -3.3 x 10- delta k/k/*F, respectively. The differences between these values and the current NA-182 TS limits are primarily due to a difference in the derivative of water density with respect to temperature at the current core operating conditions.
Once the equilibrium baron concentration falls below about 60 ppm, dilution operations take an extended amount of time due to the large required volume of dilution water. For example, dilution of the RCS from 50 ppm to 40 ppm requires charging of about 17,000 gallon of primary grade water and would require over 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />. These extended oilotion times make re?iable MTC measurements difficult to obtain due to any of a variety of fluctuations in the system conditions which could take place over this time interval.
As a result of this difficulty, t!.e licensec has proposed a change to TS 4.1.1.4.b to eliminate further MTC measurements provided a measurement of 60 ppm equili-brium boron (ay rods withdrawn, rated themal power conditions) is less negative delta k/k/*F. Calculations have shown that for this condition than -4.0 x 10, delta k/k/*F limit will always be met at the licensed end of the -4.4 x 10" cycle, conservatively accounting fca the effects of control rods, burnup, boren concentration and end of cycle coastdown.
The proposed TS continue to ensure that the acceptance criterf a for the NA UFSAR accident analyses are met. The limiting value used in the UFSAR safety analysis is the positive MDC limit value, and this value is not changed by the proposed Technical Specifications. Thus, the current analyses remain bounding.
Fvaluation:
The changes in EOC negative MTC limit and the valut at 300 ppm nre primtfily the result of an increase of 7.52F in Tave which was aporoved by the Commission in March 1984 This temperature change results in a difference in the derative of the water density with respect to tempeyture an( thss allows a sjightly more negative MTC botn at EOC W.3 x 10 delta k/k/'F vs.
-4.0 x 10~4 deltak/k/*F)andat300 ppm (-3.3x10" delta k/k/'F vs.
-3.1 x 10" delta k/k/*F1.
(
o a
To support elimination of measurements below 60 ppm, the licensee has shown by calculatignthatthemaximumchangeinMTCfrom60ppmtoEOCislesstgan 0.4 x 10- delta k/k/*F. Thus a measurement of greater than -4.0 x 10-delta k/k/jF at 60 ppm will insure that the MTC will not be less than
-4.4 x 10' delta k/k/*F at EOC.
Thus the changes to the MTC limit at EOC and at 300 gpm are acceptable. Also if the 60 ppm measurement is greater tnan -4.0 x 10- delta k/k/'F further measurements are not necessary.
Environmental Consideration These amendments involve a change in the installation or use of a facility component located within the restricted area as defined in 10 CFR Part 20.
The staff has detennined that the amendments involve no significant increase in the amounts, and no significant change in the types, of any effluents that may be released offsite, and that there is no significant increase in individual or cumulative occupational radiation exposure. The Comission has previously published a proposed finding that these amendments involve no significant hazards consideration and there has been no public comen+ on such finding. Accordingly, these amendments meet the eligibility criteria for categorical exclusion set forth in 10 CFR 651.22(c)(9). Pursuant to 10 CFR 651.22(b), no environmental impact statement or environmental assessment need be prepared in connection with the issuance of these amendments.
Conclusion We have concluded, based on the considerations discussed above, that (1) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner, and (2) such activities will be conducted in compliance with the Comission's regulations, and the issuance of the amendments will not be inimical to the comon defense and security or to the health and safety of the public.
Date: September 8,1986 Prir.cipal Contributors:
M. Chatterton L. Engle