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Category:OPERATING LICENSES-APPLIATION TO AMEND-RENEW EXISTING
MONTHYEARML20209E0891999-07-0707 July 1999 TS Change Request 269 for License DPR-16,changing Component Surveillance Frequencies to Indicate Frequency of Once Per Three Months ML20212H5281999-06-18018 June 1999 Application for Amend to License DPR-16,modifying TSs to Reflect Installation of Addl SFP Storage Racks.Proprietary & non-proprietary Version of Rev 4 to HI-981983,encl. Proprietary Info Withheld,Per 10CFR2.790(b)(1) ML20195D0631999-06-0303 June 1999 TS Change Request 226 to License DPR-16,permitting Plant Operation with Three Operable Recirculation Loops ML20206H9541999-04-28028 April 1999 LAR 251 for License DPR-16,requesting Approval to Handle Loads Up to & Including 45 Tons in Reactor Bldg During Power Operations ML20205P8481999-04-15015 April 1999 TS Change Request 267 to License DPR-16,modifying Number of Items in Sections 2 & 3 of Ts,Expanding Two Definitions in Section 1 & Modifying Bases Statements in Sections 2,3 & 4 ML20198K0581998-12-23023 December 1998 Application for Amend to License DPR-16 Changing TS Pages 3.8.2 & 4.8-1 to Specify Surveillance Frequency of Once Per Three Months ML20195C6451998-11-10010 November 1998 TS Change Request 264 to License DPR-16,revising TS 5.1.A by Removing Restriction on Sale or Lease of Property within Exclusion Area ML20155J7141998-11-0505 November 1998 TS Change Request 266 to License DPR-16,modifying Safety Limits & Surveillances of LPRM & APRM Sys & Related Bases to Ensure APRM Channels Respond within Necessary Range & Accuracy & to Verify Channel Operability ML20153H1391998-09-19019 September 1998 LAR 263 to License DPR-16,revising TS Section 5.4.8 of Plant Ufsar,Incorporating Use of Freeze Seal as Temporary Part of Reactor Coolant Pressure Boundary ML20151V5051998-09-0303 September 1998 TS Change Request 259 to License DPR-16,requesting TS 3.4.A.10.e & 3.5.A.2.e,contained in App a of Facility License,Be Revised to Incorporate Condensate Storage Tank Level Limit of Greater than 35 Feet ML20237D9551998-08-21021 August 1998 TS Change Request 255 to License DPR-16,removing Requirement for ADS Function of EMRV to Be Operable During Rv Pressure Testing & Correcting Note H of Table 3.1.1 as Noted ML20236T1141998-07-23023 July 1998 Application for Amend to License DPR-16,changing TS Contained in App a to Establish That Existing SLMCPR Contained in TS 2.1.A Is Applicable for Next Operating Cycle (Cycle 17) ML20236T4951998-07-21021 July 1998 TS Change Request 256 to License DPR-16,permitting Alternative to Requirement to Perform Control Rod Drive Scram Time Testing W/Reactor Pressurized Prior to Resuming Power Operation.W/Certificate of Svc ML20236T4751998-07-21021 July 1998 TS Change Request 257 to License DPR-16,making Several Changes to Section 6 of Tech Specs & Make Other Changes of Administrative Nature ML20236H1981998-06-29029 June 1998 Rev 1 to TS Change Request 230 to License DPR-16,deleting Requirements That Biennial EDG Insp & Station Battery Capacity Tests Be Done While Plant Is Shutdown & Increasing Per Cent of Rated Power to Be Reached During Diesel Testing ML20248K2781998-05-28028 May 1998 Application for Amend to License DPR-16,requesting That TS 4.5.A.1 Be Revised Such That First Type a Test Required by Primary Containment Leakage Rate Testing Program Be Performed During Refueling Outage 18R ML20197G2691997-12-23023 December 1997 Rev 1 to TS Change Request 253 for License DPR-16,reflecting Change in Trade Name of Owner & Operator of Oyster Creek Nuclear Generating Station ML20197J2431997-12-10010 December 1997 Application for Amend to License DPR-16,consisting of TS Change Request 171,modifying TS Pages 2.3-6,2.3-7,3.1-11, 3.1-14,3.1-16,3.4-8,3.8-2,3.8-3,4.3-1,4.5-13 & 6-1 ML20198P3491997-10-30030 October 1997 Proposed Amended Page 4 for LAR 252,reflecting Latest Rev Levels of Plant Security Contingency Plan & Security Training & Qualification Plan ML20217H8741997-10-10010 October 1997 TS Change Request 253 to License DPR-16,changing Trade Name of Owner & Operator of Plant ML20135C1911996-11-27027 November 1996 TS Change Request 232 to License DPR-16,changing Pages 4.7-1,4.7-2,4.7-3 & 4.7-4 Re Surveillances for Station Batteries ML20135C1521996-11-27027 November 1996 TS Change Request 224 to License DPR-61,inserting Page 8 of No Significant Hazards Determination Inadvertently Omitted ML20129K3371996-11-12012 November 1996 Application for Amend to License DPR-16,consisting of Change Request 224,implementing Revised 10CFR20, Stds for Protection Against Radiation Effective 910620 ML20134H0391996-10-31031 October 1996 Application for Amend to License DPR-16,requesting Deletion of Tech Spec Table 3.5.2 Which Lists Automatic Primary Containment Isolation Valves ML20129A5501996-10-10010 October 1996 Application for Amend to License DPR-16,revising Addl Group of Surveillances Where Justification Completed Following Receipt of Amend 144 ML20129C0611996-10-10010 October 1996 Application for Amend to License DPR-16,clarifying Functional Requirement to Provide Interlock Permissive Which Ensures Source of Cooling Water Available Via Core Spray Sys Prior to Depressurization ML20134F4061996-10-0404 October 1996 Application for Amend to License DPR-16,revising TS 2.1.A to Reflect Change in SLMCPR & TS 3.10.C Revising Operating CPR Limit for Stability ML20117E6951996-08-23023 August 1996 Application for Amend to License DPR-16,consisting of TS Change Request,Proposing New pressure-temp Limits Up to 22, 27 & 32 EFPY Based on Predicted Nilductility Adjusted Ref Temp for Corresponding EFPY of Operation ML20115G2011996-07-17017 July 1996 Application for Amend to License DPR-16,allowing Implementation of 10CFR50,App J,Option B ML20113A8521996-06-19019 June 1996 Application for Amend to License DPR-16,Tech Spec Change Request Change Request 242,Rev 1 Re Implementation of 10CFR50,App J,Option B ML20111A3701996-05-0707 May 1996 TS Change Request 247 to License DPR-16,adopting Provisions of STS NUREG-1433,Rev 1,dtd 950407 Which Clarify SR Applicability & Allow Max Period of 24 H to Complete SR Upon Discovery That Surveillance Missed ML20107E7601996-04-15015 April 1996 Application for Amend to License DPR-16,revising Spec 5.3.1 Re Handling Heavy Loads Over Irradiated Fuel ML20101J7621996-03-28028 March 1996 Application for Amend to License DPR-16,modifying Statements in TS & Bases to Correctly Reflect Ref Parameter for Anticipatory Scram Signal Bypass ML20101J5991996-03-25025 March 1996 Application for Amend to License DPR-16,deleting Spec Which Requires Thorough Insp of EDG Every 24 Months During Shutdown ML20100J8981996-02-23023 February 1996 Application for Amend to License DPR-16,allowing Implementation of 10CFR50,App J,Option B ML20100H9331996-02-22022 February 1996 Application for Amend to License DPR-16,deleting EDG Insp Requirement & Mod of Spec Re AOT ML20095C0921995-12-0505 December 1995 Application for Amend to License DPR-16,consisting of Change Request 231 Re Rev of Submittal Date for Annual Exposure Data Rept Bringing Plant Into Conformance w/10CFR20.2206 & Relaxing Overly Restrictive Administrative Requirement ML20094D1341995-10-26026 October 1995 TS Change Request 229,modifying License Condition 2.C.(5) to Eliminate Process Associated W/Obtaining Separate NRC Approvals for Reviewing Insp Results & Obtaining Restart Authorization Prior to End of Each Refueling Outage ML20086A7051995-06-26026 June 1995 Application for Amend to License DPR-16.Amend Would Eliminate Requirement to Perform Reactor Shutdown & Drywell Solely for Purpose of Inspecting Snubbers in Svc for Only 12 Months ML20078M1381994-11-25025 November 1994 Application for Amend to License DPR-16,consisting of TS Change Request 222,allowing 2,645 Fuel Assemblies to Be Stored in Fuel Pool ML20073F9341994-09-26026 September 1994 LAR 223 to License DPR-16,revising License Condition 2.C.(6) Re Long Range Planning Program ML20073F9241994-09-26026 September 1994 LAR 246 to License DPR-50,revising License Condition 2.C.9 Re Long Range Planning Program ML20072L4701994-08-19019 August 1994 TS Change Request 220 to License DPR-16,updating & Clarifying SRs for Control Rod Exercising & Standby Liquid Control Pump Operability Testing to Be Consistent W/Generic Ltr 93-05 ML20070E3381994-07-0808 July 1994 Application for Amend to License DPR-16,revising TS to Provide Improved Protection to Safety Related Electrical Equipment from Loss of Capability in Event of Sustained Degraded Voltage Condition on Electrical Grid ML20078A7691994-06-24024 June 1994 TS Change Request 221 to License DPR-16,deleting TS 2.3.0 & Associated Bases,Reflecting Removal of Recirculation Flow Scram ML20069Q6751994-06-22022 June 1994 Application for Amend to License DPR-16,consisting of TS Change Request 217,rev 1,clarifying Requirements for Demonstrating Shutdown Margins ML20069M8031994-06-15015 June 1994 TS Change Request 216,revising Setpoints of TS 2.3.D, Reactor High Pressure,Relief Valve Initiation, by Increasing Setpoint Value by 15 Psig for Each Electromatic Relief Valve in ADS ML20070R5101994-05-12012 May 1994 TS Change Request 218 to License DPR-16,revising TS Sections 3.1 & 4.1 for Protective Instrumentation,Associated Bases & Tables to Increase Surveillance Test Intervals & Add Allowable out-of-svc Times ML20029E0431994-05-0606 May 1994 TS Change Request 217 to License DPR-16,clarifying Requirements for Demonstrating Shutdown Margin ML20065M9971994-04-19019 April 1994 TS Change Request 213 to License DPR-16,updating & Clarifying TS 3.4.B.1 to Be Consistent W/Existing TS 1.39 & 4.3.D Re Five Electromatic Relief Valves Pressure Relief Function Inoperable During Pressure Testing 1999-07-07
[Table view] Category:TEXT-LICENSE APPLICATIONS & PERMITS
MONTHYEARML20216H4981999-09-24024 September 1999 Amend 209 to License PDR-16,revising Surveillance Frequency for Verifying Operability of Motor Operated Isolation Valves & Condensate Makeup Valves in IC TS 4.8.A.1 & Bases Page from Once Per Month to Once Per Three Months ML20209E0891999-07-0707 July 1999 TS Change Request 269 for License DPR-16,changing Component Surveillance Frequencies to Indicate Frequency of Once Per Three Months ML20212H5281999-06-18018 June 1999 Application for Amend to License DPR-16,modifying TSs to Reflect Installation of Addl SFP Storage Racks.Proprietary & non-proprietary Version of Rev 4 to HI-981983,encl. Proprietary Info Withheld,Per 10CFR2.790(b)(1) ML20195D0631999-06-0303 June 1999 TS Change Request 226 to License DPR-16,permitting Plant Operation with Three Operable Recirculation Loops ML20195C8051999-06-0202 June 1999 Amend 208 to License DPR-16,modifying Safety Limits & Surveillances of LPRM & APRM Systems & Related Bases Pages to Ensure APRM Channels Respond within Necessary Range & Accuracy & to Verify Channel Operability ML20206U9451999-05-18018 May 1999 Amend 207 to License DPR-16,deleting Organizational Chart & Related Refs from App B Environ TS & Revises Appearance of Format of Environ TS ML20206P0731999-05-12012 May 1999 Amend 205 to License DPR-16,removing Restriction on Sale or Lease of Property within Exclusion Area & Replaces Restriction with Requirement to Retain Complete Authority to Determine & Maintain Sufficient Control of Activities ML20206H9541999-04-28028 April 1999 LAR 251 for License DPR-16,requesting Approval to Handle Loads Up to & Including 45 Tons in Reactor Bldg During Power Operations ML20205P8481999-04-15015 April 1999 TS Change Request 267 to License DPR-16,modifying Number of Items in Sections 2 & 3 of Ts,Expanding Two Definitions in Section 1 & Modifying Bases Statements in Sections 2,3 & 4 ML20205A7241999-03-17017 March 1999 Amend 204 to License DPR-16,revising TS 3.4.A.10.e & 3.5.a.2.e to Incorporate Condensate Storage Tank Level of Greater than 35 Feet ML20198K0581998-12-23023 December 1998 Application for Amend to License DPR-16 Changing TS Pages 3.8.2 & 4.8-1 to Specify Surveillance Frequency of Once Per Three Months ML20196E2571998-11-30030 November 1998 Amend 203 to License DPR-16,modifying Spec 6.2.2(a) to Provide Some Flexibility to Accomodate Unexpected Absense of on-duty Shift Crew Members ML20195C6451998-11-10010 November 1998 TS Change Request 264 to License DPR-16,revising TS 5.1.A by Removing Restriction on Sale or Lease of Property within Exclusion Area ML20155J7141998-11-0505 November 1998 TS Change Request 266 to License DPR-16,modifying Safety Limits & Surveillances of LPRM & APRM Sys & Related Bases to Ensure APRM Channels Respond within Necessary Range & Accuracy & to Verify Channel Operability ML20155G9841998-11-0505 November 1998 Amend 202 to License DPR-16,establishing That Existing Safety Limit Min Critical Power Ratio Contained in TS 2.1.A, Applicable for Next Operating Cycle,(Cycle 17) ML20154M6081998-10-15015 October 1998 Amend 200 to License DPR-16,revising TS 4.5.A.1 Such That First Type a Test Required by Primary Containment Leakage Rate Testing Program Will Be Performed During Refueling Outage 18 Rather than Refueling Outage 17 ML20154L3151998-10-14014 October 1998 Amend 199 to License DPR-16,removing Requirements for ADS Function of Emvr to Be Operable During Reactor Vessel Pressure Testing ML20154B4261998-10-0101 October 1998 Amend 198 to License DPR-16,deleting Table 3.5.2 Which Lists Automatic Primary Containment Isolation Valves.In Addition, Amend Clarifies Applicability of Action Statement Which Applies to Several Limiting Conditions for Operation ML20153H1391998-09-19019 September 1998 LAR 263 to License DPR-16,revising TS Section 5.4.8 of Plant Ufsar,Incorporating Use of Freeze Seal as Temporary Part of Reactor Coolant Pressure Boundary ML20151U8371998-09-0808 September 1998 Amend 197 to License DPR-16,reducing Scope of Previous Amend Request Dtd 960222.Amend Retains Provision to Delete Requirement That Biennial EDG Insp Be Performed During Shutdown & Permits Skipping Diesel Starting Battery Test ML20151V5051998-09-0303 September 1998 TS Change Request 259 to License DPR-16,requesting TS 3.4.A.10.e & 3.5.A.2.e,contained in App a of Facility License,Be Revised to Incorporate Condensate Storage Tank Level Limit of Greater than 35 Feet ML20237D9551998-08-21021 August 1998 TS Change Request 255 to License DPR-16,removing Requirement for ADS Function of EMRV to Be Operable During Rv Pressure Testing & Correcting Note H of Table 3.1.1 as Noted ML20237B7291998-08-13013 August 1998 Amend 196 to License DPR-16,deleting Table 3.5.2 Which Lists Automatic Primary Ci Valves & Clarifying Applicability of Action Statement Which Applies to Several Limiting Conditions for Operation in Section 3.5 ML20236T1141998-07-23023 July 1998 Application for Amend to License DPR-16,changing TS Contained in App a to Establish That Existing SLMCPR Contained in TS 2.1.A Is Applicable for Next Operating Cycle (Cycle 17) ML20236T4751998-07-21021 July 1998 TS Change Request 257 to License DPR-16,making Several Changes to Section 6 of Tech Specs & Make Other Changes of Administrative Nature ML20236T4951998-07-21021 July 1998 TS Change Request 256 to License DPR-16,permitting Alternative to Requirement to Perform Control Rod Drive Scram Time Testing W/Reactor Pressurized Prior to Resuming Power Operation.W/Certificate of Svc ML20236K7221998-07-0707 July 1998 Errata to Pp 2-3.7 of Amend 195 to License DPR-16.Footnote Correction 871130 Was Omitted ML20236H1981998-06-29029 June 1998 Rev 1 to TS Change Request 230 to License DPR-16,deleting Requirements That Biennial EDG Insp & Station Battery Capacity Tests Be Done While Plant Is Shutdown & Increasing Per Cent of Rated Power to Be Reached During Diesel Testing ML20248L1551998-06-0404 June 1998 Amend 195 to License DPR-16,clarifies Sections of TSs Which Have Demonstrated to Be Unclear or Conflicting as Result of Licensee Review ML20248K2781998-05-28028 May 1998 Application for Amend to License DPR-16,requesting That TS 4.5.A.1 Be Revised Such That First Type a Test Required by Primary Containment Leakage Rate Testing Program Be Performed During Refueling Outage 18R ML20197B0081998-02-11011 February 1998 Errata to Amend 194 to License DPR-16.Date of Issuance 980211 Was Inadvertently Omitted from Page 2 of Amend. License Amend Number 194 Was Inadvertently Omitted from Page 3 of Revised Operating License,In Paragraph 2.C.(2) ML20198Q4251998-01-14014 January 1998 Amend 194 to License DPR-16,revising Plant Operating License & TS to Reflect Registered Trade Name of Gpu Energy from Gpu Nuclear Corp to Gpu Nuclear,Inc ML20197G2691997-12-23023 December 1997 Rev 1 to TS Change Request 253 for License DPR-16,reflecting Change in Trade Name of Owner & Operator of Oyster Creek Nuclear Generating Station ML20197J2431997-12-10010 December 1997 Application for Amend to License DPR-16,consisting of TS Change Request 171,modifying TS Pages 2.3-6,2.3-7,3.1-11, 3.1-14,3.1-16,3.4-8,3.8-2,3.8-3,4.3-1,4.5-13 & 6-1 ML20202B7401997-11-26026 November 1997 Amend 193 to License DPR-16,extending Instrumentation Surveillances for Condenser Low Vacuum,High Temp Main Steamline Tunnel,Recirculation Flow & Reactor Coolant Leakage ML20198P3491997-10-30030 October 1997 Proposed Amended Page 4 for LAR 252,reflecting Latest Rev Levels of Plant Security Contingency Plan & Security Training & Qualification Plan ML20217H8741997-10-10010 October 1997 TS Change Request 253 to License DPR-16,changing Trade Name of Owner & Operator of Plant ML20140H7641997-05-0808 May 1997 Amend 191 to License DPR-16,updating TSs to Reflect Implementation of Revised 10CFR20, Stds for Protection Against Radiation ML20137X0981997-04-14014 April 1997 Amend 190 to License DPR-16,modifying TS by Replacing Description of Existing Permissive Interlock from AC Voltage to Core Spray Booster Pump Differential Pressure Permissive Greater than 21.2 Psid ML20137D5861997-03-24024 March 1997 Amend 189 to License DPR-16 Changing TSs to Delete Surveillance 4.7.B.4.d & Adds Clarifying Phrase While on a Float Charge... Where Appropriate ML20136D5911997-03-0606 March 1997 Amend 188 to License DPR-16,updating pressure-temperature Limits Up to 22,27 & 32 Effective Full Power Years ML20135C1521996-11-27027 November 1996 TS Change Request 224 to License DPR-61,inserting Page 8 of No Significant Hazards Determination Inadvertently Omitted ML20135C1911996-11-27027 November 1996 TS Change Request 232 to License DPR-16,changing Pages 4.7-1,4.7-2,4.7-3 & 4.7-4 Re Surveillances for Station Batteries ML20129K3371996-11-12012 November 1996 Application for Amend to License DPR-16,consisting of Change Request 224,implementing Revised 10CFR20, Stds for Protection Against Radiation Effective 910620 ML20134H0391996-10-31031 October 1996 Application for Amend to License DPR-16,requesting Deletion of Tech Spec Table 3.5.2 Which Lists Automatic Primary Containment Isolation Valves ML20129A5501996-10-10010 October 1996 Application for Amend to License DPR-16,revising Addl Group of Surveillances Where Justification Completed Following Receipt of Amend 144 ML20129C0611996-10-10010 October 1996 Application for Amend to License DPR-16,clarifying Functional Requirement to Provide Interlock Permissive Which Ensures Source of Cooling Water Available Via Core Spray Sys Prior to Depressurization ML20134F4061996-10-0404 October 1996 Application for Amend to License DPR-16,revising TS 2.1.A to Reflect Change in SLMCPR & TS 3.10.C Revising Operating CPR Limit for Stability ML20117G8051996-09-0303 September 1996 Amend 186 to License DPR-16,changing TS to Allow Implementation of 10CFR50,App J,Option B ML20117E6951996-08-23023 August 1996 Application for Amend to License DPR-16,consisting of TS Change Request,Proposing New pressure-temp Limits Up to 22, 27 & 32 EFPY Based on Predicted Nilductility Adjusted Ref Temp for Corresponding EFPY of Operation 1999-09-24
[Table view] |
Text
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GPU NUCLEAR CORPORATION OYSTER CREEK NUCLEAR GENENATING &YATION s
PROVISIONAL OPERATING l
LICENSE NO. DPR.
Technical specification Change Request No.'188 Docket No. 50-219 Applicant submits, by this Technical specification Change. Request No. 188, i
to the Oyster Creek Nuclear Generating Station Technical specifications, a change to pages 3.1-4, 3.1-5 and 3.1-8.
By:
E. E. Fitzpadrick
(
Vice President and Director Oyster Creek Sworn and subscribed to before me this day o
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1990.
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NOTARY PUBLIC NEW-JERSEY l
DIANA M. DeBLASIO -
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, u,, g JER g r NOTARY PUBLIC OF N r
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l UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION IN THE MASTER OF
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DOCKET No. 50-219 GPU NUCLEAR CORPORATION )
]
A CERTIFICATE OF SERVICE i
i This is to certify that a copy of Technical Specification Change. Request No. 188 l
for the Oyster Creek Nuclear Generating Station Technical Specifications, filedL with the United States Nuclear Regulatory Commission on. ' July.10 1990, has this i
day of July 10 1990, been served on the Mayor of I:acey Township, Ocean County, New Jersey by deposit in the United States mail, addressed as follows:
The Honorable Debra Madensky Mayor of Lacey Township 818 West Lacey Road Forked River, NJ 08731 By:
E. E.'Fitzpatrick l
Vice President and Director Oyster Creek r
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1 OYSTER CREEK NUCLEAR CENERATING STATION PROVISIONAL OPERATING LICENSE NO. DPR-16 DOCKET NO. 50-219 TECHNICAL SPECIFICATION CHANGE REQUEST NO. 188 Applicant hereby requests the Commission to change Appendix A to the above captioned license as indicated below.
Pursuant to 10CFR$0.91, an analysis concerning the determination of no significant haaards considerations is alsi presented:
1.0 Section to be Chanced Sees!on 3.1 entitled " Protective Instrumentation".
I 2.0 Extent of Chanos This change request proposes to reduce the low condenser vacuum scram setpoint in Table 3.1.1 from 23 inches Hg to 20 inches Hg and revises the bases to support the new setpoint.
3.0 chanaes Reauggj;pj The requested change is shown on the attacned Technical Specification pages 3.1-4, 3.1-5 and 3.1-8.
4.0 Discussion The OCNGS Technical Specifications currently require a reactor scram on low condenser vacuum with a trip setting equal to or greater than 23 inches Hg.
Restrictive requirements are placed upon the actual setpoint to ensure that the Tech Spec is not exceeded. During the summer months l
when condenser cooling water is at its highest temperature, the margin between the operational vacuum and the scram setpoint is minimal. As a normal procedure, the condenser must be backwashed which further reduces j
the margin. Under these conditions, it becomes difficult to maintain full power operation while backwashing a condenser section. The possibility of a spurious reactor scram is increased greatly during this period.
Reducing the scram setpoint to 20 inches Hg will'better accommodate backwashing operations. As discussed below, GPUN has determined that this change has no effect on reactor safety, e.g.,
the low vacuum scram has no safety function. The scram function is being retained in the Tech specs because it does provide a reliable backup scram for turbine and condenser protection and this benefit is preserved with a setpoint of 20 inches Hg.
The Tech Spec bases on page 3.1-4 state the low condenser vacuum scram trip of 23 inches Hg has been provided to protect the main condenser in the event that vacuum is lost. A decrease in condenser vacuum (22 inches Hg) will cause the turbine stop valves to close resulting in a turbine l
trip. The closure of the stop valves will cause a reactor scram signal l
independent of the low vacuum scram. Currently the low vacuum scram anticipates this transient and trips the reactor protection system at 23 inches Hg.
4
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,1 An cn31ysio cf the condenser rO:ponto to leco of v2 suum cv:nto w 0
~
performed using a computer model (RELAPS Mo02).- The model was used to
' evaluate several degraded Sondenser cooling and increased air inleakage events. The evaluation of these events showed that a setpoint of 20 inches Hg had little or no impact upon condenser protection as compared I
with 23 inches Hg.
In the analysis of the loss of condenser vacuum event'in Chapter 15 of the FSAR, no credit is taken for the reactor scram trip on low condenser vacuum. This event is bounded by the turbine trip without bypass transient.
Further, no cradit is taken for this trip in any other l
transient analysed in the FSAR.
An analysis was also performed to evaluate the impact of the low vacuum 1
scram upon the reactor pressure vessel (RPV) using a computer model j
(RETRAN).
The results showed that the RPV response was acceptable l
regardless of the setpoint and does not impact the licensing reload analysis. With a scram setpoint below the turbine trip for a rapid loss of condenser vacuum (2 inches Hg/sec), the event is bounded by a normal j
turbine trip.
For an instantaneous loss of vacuum, the event is bounded by a turbine trip without bypass. operating limits of the plant are conservatively astablished by the turbine trip without bypass.
Therefore, the low vacuum scram satpoint does not impact those limits.
From a turbine protection point of view, the low vacuum scram should be set in the proximity of the low vacuum-turbine trip.
This will insure that, if there is no turbine trip _on low vacuum, the turbine will not
-operate under excessively low vacuum conditions for an extended period of time.
A scram setpoint of 20 inches Hg provides sufficient margin between the scram and the condef.aa.r bypass valve closure (7 inches Hg). This margin-is critical to avoid a potential condenser isolation prior to the scram.
At 23 inches Hg, the scram occurred prior to the turbine trip (22 inches Hg). With a 20 inch Hg setpoint, the scram will occur after the turbine trip.
Since the turbine trip also produces a scram, the low vacuum scram would provide a scram backup.
In the event that the turbine trip on low vacuum does not occur, the low vacuum scram will initiats the load l
reduction required to protect the condenser.
l i,
i 5.0 Determination GPUN has determinod that this Technical Specificattan Change Request involves no significant hasards consideration as defined in 10CFR50.92.
5.1 operation of the f acility in accordance with the proposed amendment would not involve a significant increase in the probability of occurrence or the consequences of an accident previously evaluated. No credit is taken for the. low cendenser vacuum scram in any of the transients analyzed in the FSAR. The turbine trip without bypass transient bounds the loss of condensor vacuum 1
scenario.
5.2 operation of the facility in accordance with the proposed amendment would not creats the possibilit.y of a new or different kind of L
accident from any accident previouoly evaluated. The scram L
function on low vacuum is still being preserved, and an evaluation p
has demonstrated that the lower setpoint provides an acceptable l
response to loco of vacuum scenarios.
i 0-5.3 Operation of the facility in accordance with the proposed amendment would not involve a significant reduction in a margin of safety.
operating limits for the plant are conservatively established with the more bounding turbine trip without bypass transient.
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6.0 Implement 4 tion j
It is requested that the amendment authorising this change become effective upon issuance.
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