|
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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
_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - - .
4 4 8 OPU Nuclear Corporattori
? Nuclear - v- - -
Peggeny, New Jerser 07054 201 310 7000 TELEX 136-482 Writere Direct Del Nurntier March 17, 1992 C321-92-2056 U. S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, DC 20555 Gentlemen:
Subject:
Oyster Creek Nuclear Generating Station c t bpra g License Amendment Request No. 207 Pursuant to 10 CFR 50.90, GPU Nuclear Corporation, operator of the Oyster Creek Nuclear Generating Station (OCNGS), facility Operating License No. DPR-16, requests a change to that license.
Technical Specifiestion (TS) 4.2.E.5 requires a D-10 enrichment surveillance of the Standby Liquid Control System at each refueling outage with analyses available within 30 days after startup. Since OCNGS procures the sodium pentaborate pre enriched (B-10) and the B 10 is very stable, this TS unduly restricts the perfomance of this surveillance to a plant shutdown. In order to allow flexibility in the master surveillance schedule, OCNGS proposes to change the surveillance interval to once every 24 months.
This change request has been reviewed in accordance with Section 6.5 of the OCNGS Technical Specifications, and using the standards in 10 CFR 50.92 we have concluded that this proposed change does not constitute a significant hazards consideration.
I S O b [' 2' 9203230328 920317 \
l PDR ADOCK 05000219 P ppg GPU Nuclear Corpmaton is a subsnay ca Genmi Pubut UN tes C c+mhan
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Page 2 C321 92-2056 Pursuant to 10 CFR 50.9)(b)(1), a copy of this change request has been sent to the State of New Jersey Department of Environmental Protection, ry u au s, ,
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< . J. Bi rton
( Jide Pr sident and Director V0ys er ' reek Attachments JJB/DGJ/ pip (OTSCR207.LET) cc: Administrator, Region I NRC Resident inspector Oyster Creek NRC Project Manager I
GPU Nuclear Corporation m
Nuclear - - - " -
Parts)pa,iv. New Je,sey 07054 701 316 7000 TELEX 136 482 W,itet a Dweet omi Number March 17, 1992 Mr. Kent Tosch, Director Dureau of Nuclear Engineering Department of Environmental Protection CN 411 Tranton, NJ 08625
Dear Mr. Tosch:
Subject:
Oyster Creek Nuclear Generating Station Facility Operating License No. DPR-16 Facility Operating License Amendment Request No. 207 Pursuant to 10 CFR 50.91(b)(1), please find enclosed a copy of the subject document which was filed with the United States Nuclear Regulatory Commission on March 17,1992.
ery truly yours,
- - f &O J. Barton President and Director Oyster Creek JJB/DGJ/ pip L
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QPU Nuclear Corporation NUCI88r 1
o- u- e- a-Parswany, New Jersey 01054 201 316 7000 TELEX 130 482 Wnter's Direct Dal Nurrber March 17,1992 1he Honorable Russell C. Palumbo Mayor of Lacey Township .
818 West Lacey Road forked River, NJ 08731
Dear Mayor Palumbo:
Enclosed herewith is one copy of facility Operating License Amendment Request No.
207 for the Oyster Creek Nuclear Generating Station Operating License.
This document was filed with the United States Nuclear Regulatory Comission on March 17, 1992.
Very truly yours, f -
/
. . Bar on Vi >
e' dent and Director ster eek Attachment JJB/DGJ/ pip GPU Nuclear Corporation is a subscary of General Public Utihtien Corporation V
GPU i;UCLEAR CORPORATION OYSTER CREEK NUCLEAR GE!1LRATING STA110f1 facility Operating License No. DPR-16 Facility Operating License Amendment Request No. 207 Docket No. 50-219 Applicant submits, by this f acility Operating License Amendment Request No. 207 to the Oyster Creek Nuclear Generating Station Operating License, a change to pages 4.2-2 and 4.2-4.
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BY 1
[J. RB/rton VMe Vresident and Director Oyster Creek SwornandSubscribedtobeforemethis/ day o h d 1992.
uh? , ) h.
Notary Public of NJ ft<&
JUDTT}l M. Cn0WE Notary Putdic of New Jerqcy My Commission Erpires 'N C/ 9 f'
i e
o UN11ED STATES OF AMERICA NUCLEAR REGULA10RY COMMISSION ;
1 In the Matter of '
Docket No. 50 219 GPU Nuclear Corporation CERTlflCATE Of SERVICE This is to certify that a copy of facility Operating License Amendment Request No. 207 for Dyster Creek Nuclear Generating Station Operating L1censo, filed with the U.S. Nuclear Regulatory Commission on March 17, 1992 has this day of March 171992, been served on the Mayor of Lacey Township, Ocean County, New Jersey by deposit in the United States mail, addressed as follows:
The lionorable Russell C. Palumbo Mayor of Lacey Township 818 West Lacey Road forked River, NJ 08731
- y
,, ( J . a ton ic r sident and Director ty er Creek l
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I
l OYSTER CREEK NUCLEAR GENERATING STATION ,
OPERATING LICENSE NO. DPR-16 DOCKET NO. 50 219 LACIllTY OPERATING LICENSE AMENDMENT REQUEST NO. 207 Applicant hereby reouests the Commission to change Facility Operating tii 't-DPR-16 as discussed below, and pursuant to 10 CFR 50.91, an
, n2 mcerning the determination of no significent *azards car also presented:
, . .i0 BE CHANGED 1 Basis 2.0 (U M (,J CHANGE 3ange the surveillance for Boron-10 enrichment to reflect the use of sodium pentaborate preformulated and pre enriched at the vendor's facility.
3.0 CHANGES REQESJfD As delineated on the attached revised Technical Specification pages 4,2-2 and 4.2 '.
4.0 QISfdS$1QRS Paragraph (c)(4) of 10 CFR 50.62, " Requirements for reduction of risk from Anticipated Transients Without Scram (ATWS) events for light-water-cooled nuclear power plants", reqitires that each boiling water reactor must have a Staridby Liquid Control System (SLCS) with a minimum flow capacity -and boron content equivalent in control capacity to 86 gallons per minute of 13 weight percent sodium pentaborate solution. OCNGS meets the equivalency requirements based on a minimum solution concentration of- 15.0 wt. percent, a Boron-10 enrichment of 35 atom percent and a-30 gpm pump flow rate-The approach taken by OCNGS was one of three options approved by the NRC staff as -an acceptable response to the ATWS Rule (Referene.e:
Safety Evaluation of Topical Report NEDE-31096-p, " Anticipated Transient Without Scram; Response to ATWE Rule 10 CFR 50.62,"
trcnsmitted by letter, G. Lainas, NRC, -to T. Pickens, BWR 0wners Group, dated October 21,1986). Associated with this option was a
.equiremert .for surveillance and positive verification of the ct rect Boron-10 enrichment. These surveillances were discussed with the NRC staff during a BWR Owners' Group meeting on April 3, 1987.
o ec
.+
4.0- ElSCUSSIOfLS (Continued)
OCNGS purchases sodium pentaborate preformulated and pr9-enriched at the . vendor's facil:ty. The B-10 enriched sodium pentaborate is procured in accordance with the vendor's quality assurance plan as approved by GPU Nuclear. Samples of batches to be shipped are analyzed prior to shipment by an independent laboratory contracted by GPU Nuclear. Once verification is completed it is only then that
, these batches are shipped to the plant site. The chemical, while in storage or in the SLCS tank, cannot change its B-10 enrichment, l because B-10 is very stable. Since chemicals used in making up the i solution in the SLCS tank are only from these batches, there is no reason why the resulting solution will be below the minimum B-10 l enrichment. Water addition to the tank can change the weight '
percent of the sodium pentaborate solution but cannot change the B-10 enrichment.
ihe current Technical Specification 4.2.E.5 requires the performance of the B-10 enrichment surveillance at each refueling outage with the receipt of the analysis no later than 30 days after startup.
The intent of this surveillance is to provide a periodic ,
verification, at least once per operating cycle, of the B-10 cnrichment as found in the SLCS tank.
Since the samples for the enrichment analysis can be taken from tht.
SLCS tank at any time (power operation, refueling, etc), the current Technical Specification unduly restricts the perfcrmance of this surveillance to plant shutdowns. Further, the B-10 is very stable which precludes a change while in the SLCS tank. Since the intent is to verify the B-10 enrichment once per operating cycle, there is no specific need to restrict this surveillance to only a refueling outage when the surveillance can be performed at any time. Based on these facts, OCNGS proposes to change the surveillance to once every 24 months. This change will retain a defined schedule for the surveillance, but the' change will allow flexibility in performing the sur. veillan. ce._
5.0- DETERMINATION GPU Nuclear has determined that operation of the Oyster Creek Nuclear Generati_ng Station in accordance with the proposed Technical
' Specifications does not involve a significant-hazard. The changes
-do not:
- 1. Involve a-JJgnificant increase in the probability or the conseauence of an accident orevicusly evaluated.
The proposed changes reflect the use of preformulated and pre-enriche1 sodium pentaborate in the SLCS. .Since the sodium
--pentaborate is independently ve fled for the B-10 enrichment prior-to shipment, an enrichmeat analysis of the SLCS tank once every twenty-four months is deemed adequate to ensure that the reactor can-be brought to-a cold shutdown condition from full power steady state operating conditions at any time
in core life independent- nf control rod system capabilities.
The probability or the consequences of an accident previously
- evaluated are unaltered by-the proposed change.
- 2. Create the possibjlity of a new or diff_qtenLkind of accident from any previous 1v evaluatqq.
The proposed changes do not modify the system design for the SLCS nor the manner in which the SLCS would be operated.
Since the SLCS retains-the capability to shutdown the reactor, this change does not create the possibility of a new or diiforent kind of accident from any previously evaluated.
- 3. Ir,volve_A sianificant reduction in a maroin of safety.
The proposed changes allows the performance of the 0-10 enrichment surveillance during power operation. or plant shutdown. Since the frequency of the surveillance stays the same, once per twenty-four months, there is no significant reduction in' the margin of safety. The SLCS retains - the canability to bring the reactor to a cold shutdown condition from full power steady state operating conditions at any time in core life independent of control rod system capabilities.
6.0 IMPLEMENTATION
- It is requested that the amendment authorizing this change become effective 60 days after issuance.
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