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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
=. - . _ - . . _ . ..
( GPU Nuclear. loc.
( U.S. Route #9 South NUCLEAR Post Office Box 388 Forked River, NJ 087310388 Tel 609-9714000 October 31,1996 6730-96-2227
)
i, U. S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, DC 20555
Dear Sir:
Subject:
Oyster Creek Nuclear Generating Station (OCNGS)
Docket No. 50-219 Technical Specification Change Request No. 205 ;
1 1
in accordance with 10 CFR 50.4(b)(1), enclosed is Technical Specification Change Request t
(TSCR) No. 205.
l This TSCR requests deletion of Technical Specification Table 3.5.2 which lists automatic primary l containment isolation valves. This request is in accordance with Generic Letter 91-08 which permits licensees to delete component lists such as Table 3.5.2. In addition, this TSCR clarifies the applicability of an action statement which applies to several limiting conditions for operation in Section 3.5 and deletes closure time requirements for several automatic isolation valves in ,
Section 4.5.F. !
In accordance with 10 CFR 50.91 (b)(1), the designated oflicial of the State of New Jersey Bureau of Nuclear Engineering has been sent a copy of this TSCR.
)
130017 9611130501 961031 ._
PDR ADOCK 05000219
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_ _ . _ _ _ - - ._ . . _ _ _ _ _ _ _ . _ _ . _. _ _ .~ . .-_ _ _
6730-96-2227 Page 2 Pursuant to 10 CFR 50.91(a)(1), enclosed is an analysis applying the standards in 10 CFR 50.92 to make a determination of no significant hazards considerations. This license amendment application has undergone a safety review in accordance with Section 6.5 of the Oyster Creek l Technical Specifications and no unreviewed safety questions were identified.
Ifyou should have any questions concerning this license amendment application, please contact Mr. Paul F. Czaya at (201) 316-7975.
Very tmly yours, hY 0 ($ a Michael B. Roche Vice President and Director Oyster Creek PFC Attachments ;
i c: Administrator, USNRC Region I l USNRC Resident inspector l Oyster Creek USNRC Project Manager
)
i ;
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. -= _. . _ - - -_- -
i 4
GPU Nuclear, Inc.
Oyster Creek Nuclear Generating FL-tion Facility License No. DPR-16 Technical Specification Change Request No. 205 Docket No. 50 219 Applicant hereby submits changes to pages 1.02,3.5-1 through 3.5-4, 3.5-8 through 3.5 12,4.5 2,4.5 3,4.5-11 and 4.5 12 and deletes page 3.5-13. :
b By: Ltc Michael B. Roche l Vice President and Director Oyster Creek Sworn and Subscribed to before me this 3I day of October,1996.
EtruK LA -
A Notary Public of NJ -
GEMNE E. LEVIN 1 NOTARf PUBUC 0F MN gcommamanEM % *M ;
-.. _~. . - . _ _ ~ .. . _ . .. . _ - - - - - . - - . . = , _ . _ . - . _ . . _ .
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GPU Nuclear,Inc. l U $ Route r9 South r g
NUCLEAR [,,7,,$',8 "fo'e'73i.o3,8 y !
Tel 609 971-4000 6730-96-2227 October 31,1996 Mr. Kent Tosch, Director Bureau of Nuclear Engineering ,
Depanment of Environmental Protection ;
CN 411 Trenton, NJ 08625 f
t i
Dear Mr. Tosch:
l
Subject:
Oyster Creek Nuclear Generating Station :
Facility Operating License No. DPR-16 !
Technical Specification Change Request No. 205 i 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 October 31,1996.
i Very truly yours, lhEc h bb4_
Michael B. Roche Vice President and Director Oyster Creek l Attachment I
i
I
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1 1
l 1
GPU Nucleaf,inc.
l
' U S Route #9 South ,
'**'*"*** i NUCLEAR forked Rwer, NJ 087310388 '
Tel 609-9714000 ;
6730-96-2227 ;
i October 31,1996 ;
i The Honorable John Parker .
Mayor of Lacey Township i
818 West Lacey Road Forked River, NJ 08731
Dear Mayor Parker:
r 2
Enclosed herewith is one copy of Technical Specification Change Request No. 205 for the Oyster Creek Nuclear Generating Station Operating License. i This document was filed with the United States Nucicar Regulatory Commission on October 31 i l
1996.
Very truly yours, h #h Michael B. Roche Vice President and Director Oyster Creek Attachment i
l i
i
l .
I United States of America Nuclear Regulatory Commission i In the Matter of )
) Docket No. 50-219 j GPU Nuclear, Inc. )
CertificJte of Service !
This is to certify that a copy of Technical Specification Change Request No. 205 for the Oyster .
Creek Nuclear Generating Station Operating License, filed with the U.S. Nuclear Regulatory Commission on October ,1996 has this day of October ,1996, been served on the Mayor of Lacey Township, Ocean County, New Jersey by deposit in the United States mail, addressed as follows:
The Honorable John Parker Mayor of Lacey Township 818 West Lacey Road Forked River, NJ 08731 i l
By: bbb Michael B. Roche '
Vice President and Director Oyster Creek 5
l l
1
l i
l Technical Specification Chance Reauest (TSCR) No. 205 1
I. Channes Reauested I GPU Nuclear requests that Appendix A Technical Specification pages be replaced as !
follows:
Delete existing pages 1.0-2, 3.5-1 through 3.5-4,3.5-8 through 3.5-13,4.5-2,4.5-3,4.5- l 11 and 4.5-12 and replace them with attached revised pages 1.9-2, 3.5-1 through 3.5-4, l 3.5-8 through 3.5-12,4.5-2, 4.5-3,4.5-11 and 4.5-12.
II. Reasons for Channe Technical Specification Table 3.5.2 is a list of valves which receive automatic primary 1 containment isolation signals. Generic Letter (GL) 91-08 permits licensees to delete component lists such as Table 3.5.2 provided that cenain conditions are met.
Maximum stroke times for several automatic isolation valves are given in Specification l 4.5.F. As provided in GL 91-08 and the Improved Standard Technical Specifications (STS) NUREG-1433, stroke times for all but four of these valves can be deleted. The allowable closure time for the four main steam isolation valves is retained consistent with the STS An administrative change to an existing action statement is proposed. Specification 3.5.A.7 is several pages removed frcm the condition statements to which it applies. To enhance clarity, the action statement is being inserted into each of those condition statements and deleted as a stand alone specification.
III. Safety Evaluation Justifyinn Channe i Oyster Creek Technical Specifications describe conditions under which primary l containment shall be maintained and specific steps to be taken if one or more automatic primary containment isolation valves is inoperable. In addition, the Technical Specifications require testing for automatic closure by isolation signal, post-maintenance ;
operability testing, leak rate testing and specific closure times for particular valves.
1 Technical Specification Table 3.5.2 lists automatic primary containment isolation valves and describes the primary containment isolation signals they receive. The proposed deletion of Table 3.5.2 does not alter or reduce Technical Specification requirements but shifts identification of automatic primary containment isolation valves from Technical Specifications to controlled plant procedures. In addition, references to Table 3.5.2 have l been deleted from the text and replaced by a description of the subject valves in l
l 1
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Specifications 3.5.A.3.a. 4.5.F.1,4.5.F.2 and in Defmition 1.13. These changes conform to the guidance contained in GL 91-08.
Valve stroke times are given in Specification 4.5.F.1 for main steam line, isolation condenser, cleanup, cleanup auxiliary pumps and shutdown cooling isolation valves. The proposed deletion of closure times for automatic primary containment isolation valves (except main steam line isolation valves) in Specification 4.5.F.1 does not remove the closure time test requirement which is retained in Specification 4.5.F.2. The isolation condenser isolation valves do not receive a primary containment isolation signal (the isolation condenser vent valves do, however). The isolation condenser isolation valves close on line break signals and are required to be tested in accordance with Specifications 4.8. A.1 and 2 which are not changed. Closure time limits are incorporated in controlled plant procedures. These time limits ensure design basis performance objectives are met as described in Technical Specification bases. The deletion of automatic primary containment isolation valve closure times is consistent with the guidance in GL 91-08 in !
that the closure time testing requirement remains in Specification 4.5.F.2 for automatic primary containment isolation valves and the inservice testing program required by Specification 4.3.C covers stroke time verification testing for these valves.
Specification 3.5. A.7 is an action statement which requires that a shutdown be initia:ed and the plant be in the cold shutdown condition within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> if Specifications 3.5.A.l.a, b, c(1) and 3.5.A.? through 3.5.A.5 cannot be met. The action required by Specification 3.5.A.7 has been inserted into Specifications 3.5.A.1 (as 3.5.A. l .d), 3.5. A.3
[as 3.5.A.3.a(2)] and 3.5.A.5 (as 3.5.A.5.d). Specification 3.5.A.2 establishes conditions to be satisfied before pressure suppression system maintenance and repair work can be performed. 'liese conditions require the plant to be in the same condition as Specification ;
3.5.A.7 (cold sbutdown). Therefore, the requirements of Specification 3.5.A.7 are i redundant and it is unnecessary to insert the action statement into Specification 3.5.A.2. ;
A previous license amendment had inserted the action statement into Specification 3.5. A.4 (as 3.5. A.4.c) and additional change is not required. This change does not modify the !
limiting conditions for operation nor the required action to be taken if those conditions are not met.
Technical Specification Definitions on pages associated with this TSCR are capitalized consistent with STS. Page 3.5-13 which contains Table 3.5.2 should be deleted as well as the existing page which contains Table 3.5.1. Table 3.5.1 was deleted by a previous license amendment.
Technical Specification bases have been revised to provide greater clarity regarding primary containment isolation valve design bases. The changes appear on pages 3.5-9, 4.5-11 and 4.5-12. For pagination purposes all Section 3.5 bases pages should be reissued. Amendment numbers at the bottom of each bases page have been revised to 2
4 1 reflect repagination and to reflect amendments which revised bases and not simply denoted previous repagination.
IV. No Sinnificant Hazards Consideration GPU Nuclear has determined that this TSCR poses no significant hazards as defined by the NRC in 10 CFR 50.92. <
- l. The proposed deletion of the automatic primary containment isolation valve Table 3.5.2 and closure times for several valves in Specification 4.5.F.1 are administrative in nature and do not afreet the purpose, function, operability and testing requirements of the automatic primary containment isolation valves or the isolation condenser isolation valves. The required action contained in Specification 3.5.A.7 has been moved to the associated specifications and has not changed. Capitalizing definitions and deleting unneeded pages are also administrative changes which enhance the usability of the Technical Specifications. i Therefore, the proposed changes do not increase the probability of occurrence or consequence of an accident previously evaluated.
- 2. The proposed changes are administrative and do not involve a physical change to plant configuration nor do they affect the performance of any equipment. Existing limiting conditions for operation and surveillance requirements are retained, i Therefore, the possibility of a new or different kind of accident from any accident I previously evaluated is not created. l
- 3. Deleting the list of valves in Table 3.5.2 and valve closure times in Specification l
4.5.F.1 are administrative changes which do not affect the purpose or function of the automatic primary containment isolation valves. The listing of the automatic primary containment isolation valves and stroke time requirements will be in controlled plant procedures. Changes to the list or closure times can be made in accordance with review procedures required by Section 6.5 of the Technical Specifications and 10 CFR 50.59. Similarly, inserting the statement of required action in Specification 3.5 A.7 into the Specifications to which it applies does not modify the condition or the action to be taken and is an administrative change which clarifies the Technical Specifications. Therefore, the margin of safety is not !
reduced.
V. Imolementation It is requested that the license amendment authorizing the proposed changes be effective j
- 60 days after issuance to permit required procedure changes to be implemented.
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