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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 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 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 ML20073F9241994-09-26026 September 1994 LAR 246 to License DPR-50,revising License Condition 2.C.9 Re Long Range Planning Program ML20073F9341994-09-26026 September 1994 LAR 223 to License DPR-16,revising License Condition 2.C.(6) 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
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 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 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 ML20073F9241994-09-26026 September 1994 LAR 246 to License DPR-50,revising License Condition 2.C.9 Re Long Range Planning Program ML20073F9341994-09-26026 September 1994 LAR 223 to License DPR-16,revising License Condition 2.C.(6) 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] |
Text
i
{ GPU Nuclear,Inc.
( U.S. Route #9 South NUCLEAR '**'*"'c'*****
Forked River, NJ 087310388 Tel 609 9714000 August 23, 1996 6730-96-2151 U. S. Nuclear Regulatory Commission Att: Document Control Desk Washington, D.C. 20555 Gentlemen
Subject:
Oyster Creek Nuclear Generating Station (OCNGS)
Docket No. 50-219
. Technical Specification Change Request (TSCR) No. 245 -
In accordance with 10 CFR 50.4(b)(1), enclosed is a Technical Specification Change Request (TSCR) No.
245. Also enclosed is a Certificate of Service for this request certifying service to the chief executive of the township in which the facility is located, as well as the designated official of the State of New Jersey Bureau of Nuclear Engineering.
In accordance with the requirement of the Oyster Creek Technical Specifications GPU Nuclar submitted pressure-temperature (P-T) limits for operation up to seventeen (17) effective full power years (EFPY) on January 11,1991 (TSCR No.194). Subsequently, on April 11,1991 the Commission issued Amendment No.
151 in response to our application. It is projected that OCNGS will reach 17 EFPY ofoperation in April, 1997 The current P-T limits were developed in accordance with 10 CFR 50, Appendix G to assure that brittle fracture of the reactor _ vessel is prevented. Part of the analysis involved in developing the P-T curve is to account for irradiation embrittlement effects in the core region or beltline. The results of the surveillance capsule test and the method described in Regulatory Guide 1.99, Revision 2 were used to account for irradiation embrittlement.
This TSCR proposes new pressure-temperature limits up to 22,27 and 32 EFPY based upon the predicted nil-ductility adjusted reference temperature (ARTmr) for corresponding EFPY ofoperation. These new sets cf curves will be used beyond 17 EFPY in the future as the corresponding EFPY ofoperation is completed. The new sets of the P-T limits were also developed based on the surveillance capsule test results, and in accordance with requirements of10 CFR 50, Apperxlix G and Regulatory Guide 1,99, Revision 2.
I 9609030041 960823 PDR ADOCK 05000219
!I p PDR
Page 2 Detailed discussions on methodology c.nd results of the analyses for generating the P-T limits are provided in !
the attached report, GENE-B13-01769, " Pressure-Temperature Curves per Regulatory Guide 1.99, Revision 2 for the Oyster Creek Nuclear Generating Station" Pursuant to 10 CFR 50.9)(a)(1), enclosed is an analysis applying the stanosds of 10 CFR 50.92 to make a '
determination ofno significant hazards consideration.
Very truly yours, 7dA%
Michael B. Roche Vice President and Director Oyster Creek
. YN/ pip c: Administrator, Region I NRC Resident Inspector (OC)
Oyster Creek NRC Project Manager i
i l
1
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l i
GPU NUCLEAR CORPORATION !
OYSTER CREEK NUCLEAR GENERATING STATION Provisional Operating License No. DPR-16 .
Technical Specification Change Request No. 245 Docket No. 50-219 I
Applicant submits, by this Technical Specification Change Request No. 245, to the Oyster Creek Nuclear i Generating Station Technical Specifications, a change to pages 3.3-1,3.3-5,3.3-8a,3.3-9,4.3-1, and 4.3-2.
l
~~ M'ichael B. Roche Vice President and Director !
Oyster Creek l Sworn and Subscribed to before me this23 day of 89,1996. ;
M /b A Notary Public ofNJ l
gpE E.LEVW8
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, em y % go
T g GPU Nucleer, Inc.
U.S. Route #9 South NUCLEAR ' " U 8
- 88 forked River, NJ 087310388 Tel 609-9714000 i
August 23, 1996 6730-96-2151 The Honorable John C. Parker MayorofLacey Township 818 West Lacey Road Forked River, NJ 08731
DearMayor Parker:
Enclosed herewith is one copy of Technical Specification Change Request N Nuclear Generating Station Operating License.
This document was filed with the United States Nuclear Regulatory Commission on Aueust 23 .1996.
Sincerely, b
Michael B. Roche Vice President and Director Oyster Creek
. YN/ pip Attachment -
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1
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[
GPU Nuclear,Inc.
(
U.S. Route #9 South NUCLEAR '**'******
Forked River. NJ 08731-0388 Tel 609-971-4000
- August 23, 1996 6730-96-2151 Mr. Kent Tosch, Director Bureau ofNuclear Engmeenng 4
Department ofEnvironmental Protection CN 411
-l Trenton,NJ 08625
Dear Mr. Tosch:
Subject:
Oyster Creek Nuclear Generating Station Provisional Operating License No. DPR-16 Technical Specification Change Request No. 245 Pursuant to 10 CFR 50.91(b)(1), please find enclosed a copy of the subject document w United States Nuclear Regulatory Commission on August 23, 1996.
Sincerely, b
Michael B. Roche Vice President and Director Oyster Creek YN/ pip .
Attachment
UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION
! l i
l l
In the Matter of )
) Docket No. 50-219 GPU Nuclear Corporation )
CERTIFICATE OF SERVICE I
This is to certify that a copy of Technical Specification Change Request No. 245, for Oyster Creek Nuclear l Generating Station Technical Specifications, filed with the U.S. Nuclear Regulatory Commission on August 23, !
1996 has this day of 8/2Vl996, been served on the Mayor of Lacey Township, Ocean County, New Jersey by j deposit in the United States mail, addressed as follows:
l The Honorable John Parker Mayor ofLacey Township 818 West Lacey Road Forked River, NJ 08731 i
By Michael B. Roche !
Vice President and Director i Oyster Creek l
1
)
I l
OYSTER CREEK NUCLEAR GENERATING STATION PROVISIONAL OPERATING LICENSE NO. DPR-16 DOCKET NO. 50-219 TECHNICAL SPECIFICATION CHANGE REQUEST NO. 245 l
i Applicam hereby requests the Commission to change Appendix A to the above captioned license as below, and pursuant to 10 CFR 50.91, an analysis concerning the determination of no significant hazards consideration is presented below:
i l
1.0 SECTIONS TO BE CHANGED )
l Section 3.3. A (i), (ii), (iii) and (iv) and Bases References Curves (a), (b) and (c) in Figure 3.3.1 (
Section 4.3.A and Bases i l
2.0 EXTENT OF CHANGli l l
i) Section 3.3.A (i), (ii), (iii) and (iv), and curves (a), (b) and (c) in Figure 3.3.1 are revised to provide i new pressure-temperature (P-T) operating curves for operations up to 22,27 and 32 effective full - ;
power years (EFPY) and, J
ii) The current Oyster Creek Technical Specifications provide P-T operating curves for operation up to 17 EFPY in Figure 3.3.1. Technical Specification Change Request No. 245_ proposes to provide P-T operating curves for operations up to 22,27 and 32 EFPY (Figures 3.3.1,3.3.2 and 3.3.3 respectively). To reflect this arrangement, editorial changes are made in Section 3.3. A and its Bases and Section 4.3.A and its Bases.
3.0 CHANGES REOUESTED The changes are shown on the attached Technical Specification pages 3.3-1,3.3-5, 3.3-8a, 3.3-9a, 3.3-9b,3.3-9c,4.3-1, and 4.3-2.
4.0 DISCUSSION The purpose of the Technical Specification Change Request is to revise the Technical Specification to l incorporate new pressure-temperature (P-T) limits. Following discussion supports these proposed !
Technical Specification changes:
. 1 t
Section 3.3.A(iv) of Oyster Creek Technical Specifications requires appropriate new pressure temperature limits be approved when the reactor system has reached 17 effective full power years (EFPY) ofreactor operation. ;
l Neutron irradiation results in the embrittlement of pressure vessel steels. The primary materials of concern are those surrounding the active core. To monitor the effects ofirradiation on these materials, test specimens fabricated from the materials used to fabricate the reactor vessel are installed on the !
reactor vessel wall at the core mid-plane. Dosimetry wires are included which provide an estimate of the fluence to which the specimens were exposed. The specimens and wires are periodically removed, tested, analyzed and the results evaluated to determine the extent ofembiittlement as a function offluence.
The property of concern is the reference nil-ductility temperature (RTun) which increases as a function of fluence and material chemistry. Once the RTun, fluence and material chemistry are known, ;
predictions of RTmn in the future can be made. P-T curves are developed based upon the adjusted i RTmn at the end of the operating period.
After Cycle 9, GPUN removed Reactor Vessel Materials Surveillance Program (RVMSP) Capsule No.
- 2. Its contents were tested and analyzed; the results were evaluated and predictions of RTun for various ;
periods ofoperation were prepared.
I The new P-T limits were developed through 22,27 and 32 EFPY based upon the Reg. Guide 1.99, Rev.
2, methodology for predicting adjusted RTmn. j We have determined that this change request with respect to P-T limits involves no significant hazards !
considerations in that operation of the Oyster Creek Plant in accordance with the proposed amendment, will not:
- 1. Involve a significant increase in the probability of an accident because the new limits account for the .
increase in RTun, including statistical uncertainty, due to neutron irradiation of the reactor vessel as j well as establishing initial RTun on the basis ofcurrent Code requirements, also including statistical uncertainty, in accordance with Reg. Guide 1.99, Rev.2. The new P-T curves will assure that brittle l fracture of the reactor vessel is prevented. i
- 2. Create the probability of a new or different kind of accident from any accident previously evaluated.
These new limits are the result of the calculation methodology in Reg. Guide 1.99, Rev. 2, as required !
by Generic Letter 88-11. Primary system configuration and function remain unchanged.
- 3. Involve a significant reduction in margin of safety because the bases for the margin of safety remain the same as current limits, i.e., ASME, Sect. XI, App. G for available fracture toughness and applied stress intensity, Reg. Guide 1.99, Rev. 2 for calculating applied stress intensity, Reg. Guide 1.99, Rev.
2 for calculating adjusted RTun and 10 CFR 50, App. G, for criticality conditions.
1 5.0 IMPLEMENTATION 1
It is requested that the amendment authorizing this change become effective prior to restart ofOyster !
Creek for the Cycle 16 operation.
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