|
---|
Category:OPERATING LICENSE (SEE LIBRARIANS FOR MORE INFORMATION)
MONTHYEARML20081L9471991-07-0202 July 1991 Full-term License DPR-16 Issued to Gpu & Jersey Central Power & Light Co 1991-07-02
[Table view] Category:OPERATING LICENSES & AMENDMENTS
MONTHYEARML20216H4981999-09-24024 September 1999 Amend 209 to License PDR-16,revising Surveillance Frequency for Verifying Operability of Motor Operated Isolation Valves & Condensate Makeup Valves in IC TS 4.8.A.1 & Bases Page from Once Per Month to Once Per Three Months ML20195C8051999-06-0202 June 1999 Amend 208 to License DPR-16,modifying Safety Limits & Surveillances of LPRM & APRM Systems & Related Bases Pages to Ensure APRM Channels Respond within Necessary Range & Accuracy & to Verify Channel Operability ML20206U9451999-05-18018 May 1999 Amend 207 to License DPR-16,deleting Organizational Chart & Related Refs from App B Environ TS & Revises Appearance of Format of Environ TS ML20206P0731999-05-12012 May 1999 Amend 205 to License DPR-16,removing Restriction on Sale or Lease of Property within Exclusion Area & Replaces Restriction with Requirement to Retain Complete Authority to Determine & Maintain Sufficient Control of Activities ML20205A7241999-03-17017 March 1999 Amend 204 to License DPR-16,revising TS 3.4.A.10.e & 3.5.a.2.e to Incorporate Condensate Storage Tank Level of Greater than 35 Feet ML20196E2571998-11-30030 November 1998 Amend 203 to License DPR-16,modifying Spec 6.2.2(a) to Provide Some Flexibility to Accomodate Unexpected Absense of on-duty Shift Crew Members ML20155G9841998-11-0505 November 1998 Amend 202 to License DPR-16,establishing That Existing Safety Limit Min Critical Power Ratio Contained in TS 2.1.A, Applicable for Next Operating Cycle,(Cycle 17) ML20154M6081998-10-15015 October 1998 Amend 200 to License DPR-16,revising TS 4.5.A.1 Such That First Type a Test Required by Primary Containment Leakage Rate Testing Program Will Be Performed During Refueling Outage 18 Rather than Refueling Outage 17 ML20154L3151998-10-14014 October 1998 Amend 199 to License DPR-16,removing Requirements for ADS Function of Emvr to Be Operable During Reactor Vessel Pressure Testing ML20154B4261998-10-0101 October 1998 Amend 198 to License DPR-16,deleting Table 3.5.2 Which Lists Automatic Primary Containment Isolation Valves.In Addition, Amend Clarifies Applicability of Action Statement Which Applies to Several Limiting Conditions for Operation ML20151U8371998-09-0808 September 1998 Amend 197 to License DPR-16,reducing Scope of Previous Amend Request Dtd 960222.Amend Retains Provision to Delete Requirement That Biennial EDG Insp Be Performed During Shutdown & Permits Skipping Diesel Starting Battery Test ML20237B7291998-08-13013 August 1998 Amend 196 to License DPR-16,deleting Table 3.5.2 Which Lists Automatic Primary Ci Valves & Clarifying Applicability of Action Statement Which Applies to Several Limiting Conditions for Operation in Section 3.5 ML20236K7221998-07-0707 July 1998 Errata to Pp 2-3.7 of Amend 195 to License DPR-16.Footnote Correction 871130 Was Omitted ML20248L1551998-06-0404 June 1998 Amend 195 to License DPR-16,clarifies Sections of TSs Which Have Demonstrated to Be Unclear or Conflicting as Result of Licensee Review ML20197B0081998-02-11011 February 1998 Errata to Amend 194 to License DPR-16.Date of Issuance 980211 Was Inadvertently Omitted from Page 2 of Amend. License Amend Number 194 Was Inadvertently Omitted from Page 3 of Revised Operating License,In Paragraph 2.C.(2) ML20198Q4251998-01-14014 January 1998 Amend 194 to License DPR-16,revising Plant Operating License & TS to Reflect Registered Trade Name of Gpu Energy from Gpu Nuclear Corp to Gpu Nuclear,Inc ML20202B7401997-11-26026 November 1997 Amend 193 to License DPR-16,extending Instrumentation Surveillances for Condenser Low Vacuum,High Temp Main Steamline Tunnel,Recirculation Flow & Reactor Coolant Leakage ML20140H7641997-05-0808 May 1997 Amend 191 to License DPR-16,updating TSs to Reflect Implementation of Revised 10CFR20, Stds for Protection Against Radiation ML20137X0981997-04-14014 April 1997 Amend 190 to License DPR-16,modifying TS by Replacing Description of Existing Permissive Interlock from AC Voltage to Core Spray Booster Pump Differential Pressure Permissive Greater than 21.2 Psid ML20137D5861997-03-24024 March 1997 Amend 189 to License DPR-16 Changing TSs to Delete Surveillance 4.7.B.4.d & Adds Clarifying Phrase While on a Float Charge... Where Appropriate ML20136D5911997-03-0606 March 1997 Amend 188 to License DPR-16,updating pressure-temperature Limits Up to 22,27 & 32 Effective Full Power Years ML20117G8051996-09-0303 September 1996 Amend 186 to License DPR-16,changing TS to Allow Implementation of 10CFR50,App J,Option B ML20115F4091996-07-15015 July 1996 Amend 185 to License DPR-16,adding TS 4.0.1 & 4.0.2 & Associated Bases to Clarify SR Applicability & Allow Max Period of 24 H to Complete SR ML20117K5311996-06-0404 June 1996 Amend 184 to License DPR-16,changing TS 3.1-5 & 3.1-16 to Indicate 40 Percent of Rated Reactor Thermal Power as Anticipatory Reactor Scram Bypass Setpoint on Turbine Trip or Generator Load Rejection ML20100Q3971996-03-0404 March 1996 Amend 183 to License DPR-16,revising Submittal Date for Annual Exposure Data Rept Bringing Oyster Creek Into Conformance w/10CFR20.2206 & Relaxing Overly Restrictive Administrative Requirement ML20092A2931995-09-0606 September 1995 Amend 182 to License DPR-16,revising Snubber Visual Insp Interval to Match Schedule Developed by NRC Staff for Use w/24-month Refueling Interval.Schedule Documented in GL 90-09 ML20087D0441995-08-0707 August 1995 Amend 181 to License DPR-16,revises TS Section 6.5.3, Audits, by Removing Specified Frequency for Interval Audits ML20087J2741995-05-0101 May 1995 Amend 180 to License DPR-16,revising TS Section 6.5.1.12 to Delete Requirement to Render Determinations in Writing W/ Regard to Whether or Not Activities Listed in TS 6.5.1.2 & 6.5.1.5 Constitute Unreviewed Safety Question ML20081G9661995-03-21021 March 1995 Amend 178 to License DPR-16,changing TS Section 1.6,3.2.A, 3.9.f.5 & 4.2.A ML20078S8361995-02-21021 February 1995 Amend 177 to License DPR-16,revising TS 2.3.D to Change Setpoints Reactor High Pressure,Relief Valve Initiation by Increasing Setpoint Value for Each of Electromatic Relief Valves in ADS ML20078M9421994-12-0101 December 1994 Amend 175 to License DPR-16,deleting TS Section 2.3.0 & Associated Bases & Thereby Removing Limiting Safety Sys Setting for High Recirculation Flow Reactor Scram Based on Max Attainable Recirculation Flow Analysis ML20078L8141994-11-28028 November 1994 Amend 173 to License DPR-16,revising License Condition Re Plan for Long Range Planning Program ML20076H7261994-10-19019 October 1994 Amend 172 to License DPR-16,updating & Clarifying Surveillance Requirements for Control Rod Exercising & Standby Liquid Control Pump Operability Testing,In Line W/Gl 93-05 ML20076G4871994-10-11011 October 1994 Amend 171 to License DPR-16,revising TSs 3.1 & 4.1 for Protective Instrumentation,Associated Bases & Tables to Increase Test Intervals & Add Allowable out-of Svc Times ML20073G0921994-09-27027 September 1994 Amend 170 to License DPR-16,revising TS 3.4.B.1 to Be Consistent W/Tss 1.39 & 4.3.D ML20065B2951994-03-28028 March 1994 Corrected Amend 168 to License DPR-16,clarifying Requirements for Maintaning Secondary Containment Integrity ML20063M2231994-03-0707 March 1994 Amend 168 to License DPR-16,revising TSs to Clarify Requirements for Maint Secondary Containment Integrity When One or More Reactor Bldg Ventilation Supply & Exhaust Valves Declared Inoperable ML20062M2761993-12-21021 December 1993 Amend 167 to License DPR-16,deleting Requirements to Demonstrate by Testing,That Redundant Sys/Component Operable When Sys/Component Declared Inoperable ML20058L7231993-12-13013 December 1993 Amend 166 to License DPR-16,deleting Portions of Oyster Creek Nuclear Generating Station Radiological Effluent Tss & Relocates to Controlled Programs in Accordance w/890131 NRC GL 89-01 ML20057A9201993-09-16016 September 1993 Amend 165 to License DPR-16,revising TS 5.2.A & Bases to Change Current Containment Drywell Design Pressure ML20045A4361993-06-0707 June 1993 Amend 164 to License DPR-16,reducing Setpoint on Ninth (Highest) Safety Valve from 1230 to 1221 Psig ML20097H1021992-06-15015 June 1992 Corrected Amend 158 to License DPR-16,correcting Pages 3.13-3 & 3.13-4 to Incorporate Previously Issued Changes ML20096G6791992-05-12012 May 1992 Amend 158 to License DPR-16,revising TS to Permit No Limitation on Number of Inoperable Position Indicators for Nine ASME Code Safety Valves During Power Operation ML20086U2321991-12-27027 December 1991 Amend 156 to License DPR-16,revising TS 4.2.A & 4.2.C.1 to Delete Restriction That Refueling Outage Interval Not to Exceed 20 Months ML20083D8271991-09-18018 September 1991 Amend 155 to License DPR-16,revising Tech Specs,Table 4.15.2,items 2.a & 3.a Re Channel Functional Test Requirements for Main Stack & Turbine Bldg Vent Radioactive Gaseous Effluent Monitoring Sys ML20082U3141991-09-12012 September 1991 Amend 154 to License DPR-16,adding TS 4.3.I Which Requires Inservice Insp Program for Piping to Be Performed,Per Generic Ltr 88-01 ML20082Q4781991-09-0505 September 1991 Amend 153 to License DPR-16,revising Tech Specs 3.4.A.3, 3.4.A.4,3.4.D.2 & Associated Bases to Incorporate 10CFR50.46 LOCA Analysis ML20081M6271991-07-0202 July 1991 Corrected Amend 152 to License DPR-16,consisting of Tech Spec Page 3.1-4 Re High Drywell Pressure Trip Setting ML20081L9471991-07-0202 July 1991 Full-term License DPR-16 Issued to Gpu & Jersey Central Power & Light Co ML20066K5971991-02-21021 February 1991 Amend 148 to License DPR-16,allowing Draining of Emergency Diesel Generator Fuel Oil Storage Tank for Purpose of Internal Insp During Periods of Cold Shutdown or Refueling 1999-09-24
[Table view] Category:TEXT-LICENSE APPLICATIONS & PERMITS
MONTHYEARML20216H4981999-09-24024 September 1999 Amend 209 to License PDR-16,revising Surveillance Frequency for Verifying Operability of Motor Operated Isolation Valves & Condensate Makeup Valves in IC TS 4.8.A.1 & Bases Page from Once Per Month to Once Per Three Months ML20209E0891999-07-0707 July 1999 TS Change Request 269 for License DPR-16,changing Component Surveillance Frequencies to Indicate Frequency of Once Per Three Months ML20212H5281999-06-18018 June 1999 Application for Amend to License DPR-16,modifying TSs to Reflect Installation of Addl SFP Storage Racks.Proprietary & non-proprietary Version of Rev 4 to HI-981983,encl. Proprietary Info Withheld,Per 10CFR2.790(b)(1) ML20195D0631999-06-0303 June 1999 TS Change Request 226 to License DPR-16,permitting Plant Operation with Three Operable Recirculation Loops ML20195C8051999-06-0202 June 1999 Amend 208 to License DPR-16,modifying Safety Limits & Surveillances of LPRM & APRM Systems & Related Bases Pages to Ensure APRM Channels Respond within Necessary Range & Accuracy & to Verify Channel Operability ML20206U9451999-05-18018 May 1999 Amend 207 to License DPR-16,deleting Organizational Chart & Related Refs from App B Environ TS & Revises Appearance of Format of Environ TS ML20206P0731999-05-12012 May 1999 Amend 205 to License DPR-16,removing Restriction on Sale or Lease of Property within Exclusion Area & Replaces Restriction with Requirement to Retain Complete Authority to Determine & Maintain Sufficient Control of Activities ML20206H9541999-04-28028 April 1999 LAR 251 for License DPR-16,requesting Approval to Handle Loads Up to & Including 45 Tons in Reactor Bldg During Power Operations ML20205P8481999-04-15015 April 1999 TS Change Request 267 to License DPR-16,modifying Number of Items in Sections 2 & 3 of Ts,Expanding Two Definitions in Section 1 & Modifying Bases Statements in Sections 2,3 & 4 ML20205A7241999-03-17017 March 1999 Amend 204 to License DPR-16,revising TS 3.4.A.10.e & 3.5.a.2.e to Incorporate Condensate Storage Tank Level of Greater than 35 Feet ML20198K0581998-12-23023 December 1998 Application for Amend to License DPR-16 Changing TS Pages 3.8.2 & 4.8-1 to Specify Surveillance Frequency of Once Per Three Months ML20196E2571998-11-30030 November 1998 Amend 203 to License DPR-16,modifying Spec 6.2.2(a) to Provide Some Flexibility to Accomodate Unexpected Absense of on-duty Shift Crew Members ML20195C6451998-11-10010 November 1998 TS Change Request 264 to License DPR-16,revising TS 5.1.A by Removing Restriction on Sale or Lease of Property within Exclusion Area ML20155J7141998-11-0505 November 1998 TS Change Request 266 to License DPR-16,modifying Safety Limits & Surveillances of LPRM & APRM Sys & Related Bases to Ensure APRM Channels Respond within Necessary Range & Accuracy & to Verify Channel Operability ML20155G9841998-11-0505 November 1998 Amend 202 to License DPR-16,establishing That Existing Safety Limit Min Critical Power Ratio Contained in TS 2.1.A, Applicable for Next Operating Cycle,(Cycle 17) ML20154M6081998-10-15015 October 1998 Amend 200 to License DPR-16,revising TS 4.5.A.1 Such That First Type a Test Required by Primary Containment Leakage Rate Testing Program Will Be Performed During Refueling Outage 18 Rather than Refueling Outage 17 ML20154L3151998-10-14014 October 1998 Amend 199 to License DPR-16,removing Requirements for ADS Function of Emvr to Be Operable During Reactor Vessel Pressure Testing ML20154B4261998-10-0101 October 1998 Amend 198 to License DPR-16,deleting Table 3.5.2 Which Lists Automatic Primary Containment Isolation Valves.In Addition, Amend Clarifies Applicability of Action Statement Which Applies to Several Limiting Conditions for Operation ML20153H1391998-09-19019 September 1998 LAR 263 to License DPR-16,revising TS Section 5.4.8 of Plant Ufsar,Incorporating Use of Freeze Seal as Temporary Part of Reactor Coolant Pressure Boundary ML20151U8371998-09-0808 September 1998 Amend 197 to License DPR-16,reducing Scope of Previous Amend Request Dtd 960222.Amend Retains Provision to Delete Requirement That Biennial EDG Insp Be Performed During Shutdown & Permits Skipping Diesel Starting Battery Test ML20151V5051998-09-0303 September 1998 TS Change Request 259 to License DPR-16,requesting TS 3.4.A.10.e & 3.5.A.2.e,contained in App a of Facility License,Be Revised to Incorporate Condensate Storage Tank Level Limit of Greater than 35 Feet ML20237D9551998-08-21021 August 1998 TS Change Request 255 to License DPR-16,removing Requirement for ADS Function of EMRV to Be Operable During Rv Pressure Testing & Correcting Note H of Table 3.1.1 as Noted ML20237B7291998-08-13013 August 1998 Amend 196 to License DPR-16,deleting Table 3.5.2 Which Lists Automatic Primary Ci Valves & Clarifying Applicability of Action Statement Which Applies to Several Limiting Conditions for Operation in Section 3.5 ML20236T1141998-07-23023 July 1998 Application for Amend to License DPR-16,changing TS Contained in App a to Establish That Existing SLMCPR Contained in TS 2.1.A Is Applicable for Next Operating Cycle (Cycle 17) ML20236T4751998-07-21021 July 1998 TS Change Request 257 to License DPR-16,making Several Changes to Section 6 of Tech Specs & Make Other Changes of Administrative Nature ML20236T4951998-07-21021 July 1998 TS Change Request 256 to License DPR-16,permitting Alternative to Requirement to Perform Control Rod Drive Scram Time Testing W/Reactor Pressurized Prior to Resuming Power Operation.W/Certificate of Svc ML20236K7221998-07-0707 July 1998 Errata to Pp 2-3.7 of Amend 195 to License DPR-16.Footnote Correction 871130 Was Omitted ML20236H1981998-06-29029 June 1998 Rev 1 to TS Change Request 230 to License DPR-16,deleting Requirements That Biennial EDG Insp & Station Battery Capacity Tests Be Done While Plant Is Shutdown & Increasing Per Cent of Rated Power to Be Reached During Diesel Testing ML20248L1551998-06-0404 June 1998 Amend 195 to License DPR-16,clarifies Sections of TSs Which Have Demonstrated to Be Unclear or Conflicting as Result of Licensee Review ML20248K2781998-05-28028 May 1998 Application for Amend to License DPR-16,requesting That TS 4.5.A.1 Be Revised Such That First Type a Test Required by Primary Containment Leakage Rate Testing Program Be Performed During Refueling Outage 18R ML20197B0081998-02-11011 February 1998 Errata to Amend 194 to License DPR-16.Date of Issuance 980211 Was Inadvertently Omitted from Page 2 of Amend. License Amend Number 194 Was Inadvertently Omitted from Page 3 of Revised Operating License,In Paragraph 2.C.(2) ML20198Q4251998-01-14014 January 1998 Amend 194 to License DPR-16,revising Plant Operating License & TS to Reflect Registered Trade Name of Gpu Energy from Gpu Nuclear Corp to Gpu Nuclear,Inc ML20197G2691997-12-23023 December 1997 Rev 1 to TS Change Request 253 for License DPR-16,reflecting Change in Trade Name of Owner & Operator of Oyster Creek Nuclear Generating Station ML20197J2431997-12-10010 December 1997 Application for Amend to License DPR-16,consisting of TS Change Request 171,modifying TS Pages 2.3-6,2.3-7,3.1-11, 3.1-14,3.1-16,3.4-8,3.8-2,3.8-3,4.3-1,4.5-13 & 6-1 ML20202B7401997-11-26026 November 1997 Amend 193 to License DPR-16,extending Instrumentation Surveillances for Condenser Low Vacuum,High Temp Main Steamline Tunnel,Recirculation Flow & Reactor Coolant Leakage ML20198P3491997-10-30030 October 1997 Proposed Amended Page 4 for LAR 252,reflecting Latest Rev Levels of Plant Security Contingency Plan & Security Training & Qualification Plan ML20217H8741997-10-10010 October 1997 TS Change Request 253 to License DPR-16,changing Trade Name of Owner & Operator of Plant ML20140H7641997-05-0808 May 1997 Amend 191 to License DPR-16,updating TSs to Reflect Implementation of Revised 10CFR20, Stds for Protection Against Radiation ML20137X0981997-04-14014 April 1997 Amend 190 to License DPR-16,modifying TS by Replacing Description of Existing Permissive Interlock from AC Voltage to Core Spray Booster Pump Differential Pressure Permissive Greater than 21.2 Psid ML20137D5861997-03-24024 March 1997 Amend 189 to License DPR-16 Changing TSs to Delete Surveillance 4.7.B.4.d & Adds Clarifying Phrase While on a Float Charge... Where Appropriate ML20136D5911997-03-0606 March 1997 Amend 188 to License DPR-16,updating pressure-temperature Limits Up to 22,27 & 32 Effective Full Power Years ML20135C1521996-11-27027 November 1996 TS Change Request 224 to License DPR-61,inserting Page 8 of No Significant Hazards Determination Inadvertently Omitted ML20135C1911996-11-27027 November 1996 TS Change Request 232 to License DPR-16,changing Pages 4.7-1,4.7-2,4.7-3 & 4.7-4 Re Surveillances for Station Batteries ML20129K3371996-11-12012 November 1996 Application for Amend to License DPR-16,consisting of Change Request 224,implementing Revised 10CFR20, Stds for Protection Against Radiation Effective 910620 ML20134H0391996-10-31031 October 1996 Application for Amend to License DPR-16,requesting Deletion of Tech Spec Table 3.5.2 Which Lists Automatic Primary Containment Isolation Valves ML20129A5501996-10-10010 October 1996 Application for Amend to License DPR-16,revising Addl Group of Surveillances Where Justification Completed Following Receipt of Amend 144 ML20129C0611996-10-10010 October 1996 Application for Amend to License DPR-16,clarifying Functional Requirement to Provide Interlock Permissive Which Ensures Source of Cooling Water Available Via Core Spray Sys Prior to Depressurization ML20134F4061996-10-0404 October 1996 Application for Amend to License DPR-16,revising TS 2.1.A to Reflect Change in SLMCPR & TS 3.10.C Revising Operating CPR Limit for Stability ML20117G8051996-09-0303 September 1996 Amend 186 to License DPR-16,changing TS to Allow Implementation of 10CFR50,App J,Option B ML20117E6951996-08-23023 August 1996 Application for Amend to License DPR-16,consisting of TS Change Request,Proposing New pressure-temp Limits Up to 22, 27 & 32 EFPY Based on Predicted Nilductility Adjusted Ref Temp for Corresponding EFPY of Operation 1999-09-24
[Table view] |
Text
_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _
p* M c%'c, i
d
!i-UNITED STATES h'%g n
i NUCLEAR REGULATORY COMMISSION I
W
~f WASHINGTON. D C. 20666 gv j
....+
GPU NUCLEAR CORPORATION AJ JERSEY CENTRAL POWER & LIGIIT COMPANY DOCKET NO. 50-219 OYSTER CREEK NUCLEAR GENERATING STATION TACILITY OPERATING LICENSE License No. DPR-16 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The applicatign for a license filed by Jersey Central Power &
Light Company complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission s rules and regulations set forth in 10 CFR Chapter I, and all required notifications to other agencies or bodies have been duly made; B.
Construction of the Oyster Creek Nuclear Generating Station (the facility) has been completed in conformity with Provisional Construction Permit No. CPPR-15; the application, as amended; the provisions of the Act; and the rules and regulations of the Commission, and has been operating under a provisional license since April 9, 1969; C.
The facility will operate in conformity with the application, as amended; the provisions of the Act; and the rules and regulations of the Commission (except as exempted from compliance in Section 2.D.
below);
D.
There is reasonable assurance (i) that the activities authorized by this operating license can be conducted without endangering the health and safety of the public and (ii) that such activities will be conducted in compliance with the Commission's rules and regulations set forth in 10 CFR Chapter 1 (except as exempted from compliance in Section 2.D. below);
- / Subsequent to the filing of this application, on December 29, 1981, the NRC issued Amendment No. 59 to POL DPR-16 for this facility, per uant to which GPU Nuclear Corporation was added as a licensee, authorn J to possess, use and operate the facility, and Jersey Central Power &
Light Company remained as a licensee, authorized to possess the facility. All subsequent applications for amendments to the license were filed jointly by the two licensees.
91070eo20s 9 o7o2 FF;DR ALOCK 0500C219 ppy
1 2-E.
GPU Nuclear Corporation is technically qualified to engage in the activities authorized by this license in accordance with the rules and regulations of the Coannission; F.
Jersey Central Power & Light Company has satisfied the applicable provisions of 10 CFR Part 140, " Financial Protection Requirements and Indemnity Agreements," of the Commission's regulations; G.
The issuatce of this license will not be inimical to the common defense and security or to the health and safety of the public; H.
The receipt, possession and use of source, byproduct, and special nuclear materials as authorized by this license will be in accordance with the Commission's regulations in 10 CFR Parts 30, 40, and 70; and I.
The issuance of this license is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
2.
Provisional Operating License No. DPR-16, dated April 9, 1969, as amended, is superseded in its entirety by Facility Operating License No. DPR-16, hereby issued to GPU Nuclear Corporation and Jersey Central Power & Light Company to read as follows:
A.
This license applies to the Oyster Creek Nuclear Generating Station, a boiling-water reactor and associated equipment (the facility). The facility is located in Ocean County, New Jersey, and is described in the licensee's Updated Final Safety Analysis Report, as-supplemented and amended, and in the licensee's Environmental Report, as supplemented and amended.
B.
Subject to the conditions and requirements incorporated herein, the Commission hereby licenses GPU Nuclear Corporation:
(1) Pursuant to1Section 104b of the Act and 10 CFR Part 50, to possess, use, and operate Oyster Creek Nuclear Generating i
Station, and Jersey Central Power & Light Company to possess the Oyster Creek Nuclear Generating Station, at the designated
. location on the Oyster Creek site in Ocean County, New Jersey, in accordance with the procedures and limitations set forth in this license; (2)- Pursuant to the Act and 10 CFR Part 70, to receive, possess, and use at any time special nuclear material as reactor fuel, in accordance with the limitations for storage and amounts required for reactor operation, as described in the Updated Final Safety Analysis Report, as supplemented and amended;
' sj
i (3) Pursuant to the Act and 10 CFR Parts 30, 40, and 70, to receive possess, and use at any time any byproduct, source, orspecIa1nuclearmaterialsassealedneutronsourcesfor reactor startup, sealed sources for reactor instrumentation and radiation monitoring equ;pment calibration, and as fission detectors in amounts as required; (4) Pursuant to the Act and 10 CFR Parts 30, 40, and 70, to receive, possess, and use in amounts as required any byproduct, source, or special materials without restriction to chemical or physical form, for sample analysis or instrument calibration or associated with radioactive apparatus or components; and (5) Pursuant to the Act and 10 CFR Parts 30, 40, and 70, to possess, but not separate, such byproduct, source, or special nuclear materials as may be produced by the operation of the facility.
C.
This license shall be decired to contain and is subject to the conditions specified in the Commission's regulations set forth in 10 CFR Chapter 1 and is subject to all applicable provisions of the Act and to the-rules, regulations, and orders of the Commission now or hereafter in effect and is subject to the additional conditions specified or incorporated below:
(1) Maximum Powe,r,1.ev,e1 GPU Nuclear Corporation is authorized to operate the f acility at steady-state power levels not in excess of 1930 megawatts (thermal) (100 percent rated power) in accordance with the conditions specified herein.
(2) Technical Sp,ecifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.152, are hereby incorporated I
in the license. GPU Nuclear Corporation shall operate the facility in accordance with the Technical Specifications.
(3) Fire Protect _i,on GPU Nuclear Corporation shall implement and maintain in effect l
all provisions of the approved fire protection program as
-described in the Updated Final Safety Analysis Report for the l
facility and as approved in the Safety Evaluation Report dated March 3, 1978, and supplements thereto, subject to the following provision:
The licensee may make changes to the approved fire protection program without prior approval of the Commission only if those changes would not adversely affect the ability to achieve and n.aintain safe shutdown in the event of a fire.
(4) The licensee shall fully implement and maintain in effect all provisions of the Comission-approved physical security, guard training and qualification, and safeguards contingency plans, including amendments made pursuant to provisions of the IMscellaneous Amendments and Search Requirements revisions to 10 CFR 73.55 (51 FR 27817 and 27022) and to the authority of 10 CFR 50.90 and 10 CFR 50.54(p). The piens, which contain Safeguards information protected under 10 Cf R 73.21, are entitled:
"0yster Creak fluclear Generating Station Physical Security Plan," with revisions submitted through July 6,1928; "0yster Creek tluclear Generating Station Training and Qualification Plan," with revis'ons subm'tted through June 24,198E; and "0yster Creek I'uclear Generating Station Safeguards Contingency Plan," with revisions submitted through June 24, 1986 Changes made in accordance with 10 CFR 73.55 shall be impico'ented in accordance with the schedule set forth therein.
(5)
Inspections by a nethod acceptable to the flRC, cf all accessible surfaces and welds of both core spray sparger' and repair assemblies at least once per 24 months, will be performed so that meaningful comparisons of any indications with previous inspections can be made.
Results of the inspections, along with an evaluatior. of the safety significance of any new or 4
progressing indications, will te provided to the Comission's staff for review. Authorization wi'1 be obtained from the Comission's staff before the plant is restarted from each refueling outage. Shouisi the staff aetermine that new cracks or further progression of existing cracks has occurred, resulting in unacceptable degradation of saftty margins, the sparger will be replaced before restart.
(6) popg,R,apg,e, P,1, app,ing Program The " Plan for the Long-Range Planning Program for the Oyster Creek fluclear Generating Station" (the Plan) submitted by GPU Nuclear Corporation letter C 311-88-2030 dated March 16, 1988, is approved, a.
The Plan shall be followed by the licenste from and after May 27, 1988.
6
s b.
The Category A schedule shall not be changed without priot approval from the NRC.
The schedules for Categories B and C may be changed without prior approval by the NRC.
D.
The facility has been granted certain exemptions from the requirements of Section III.G of tppendix R to 10 CFR Part 50, " Fire Protection Program for Nuclear Power Facilities Operating Prior to January 1,1979."
This section relates to fire protection features for ensuring the I
systems and associated circuits used to achieve and maintain safe shutdown are free of f f re damage.
These exemptions were granted and sent to the licensee in letters dated March 24, 1986 and June 25, 1990.
The facility has also been granted certain exemptions from the
. requirements of Section III.J of Appendix R to 10 CFR Part 50, " Fire Protection Program for Nuclear Power Facilities operating Prior to January 1, 1979." This section relates to emergency lighting that shall be provided in all areas needed for operation of safe shutdown equipment and in access and egress routes thereto. This exemption v
was granted and sent to the licensee in a letter dated February 12, 1990.
In addition, the facility has been granted certain exemptions from Section 55.45(b)(2)(iii) and (iv) of 10 CFR Part 55, " Operators' Licenses." These sections contain requirements related to site-specific simulator certification and require that operating tests will not be administered on other than a certified or an approved simulation facility after May 26, 1991. These exemptions were granted and sent to the licensee in a letter dated March 25, 1991.
These exemptions granted pursuant to 10 CFR 50.12 are authorized by law, will-not present an undue risk to the public health and safety, and are consistent with the common defense and security.
{
With these exemptions, the facility will operate, to the extent authorized herein, in conformity with the application, as amended,-
the provisions of the Act, and the rules and regulations of the
-Conaission.
('
E.
Except as otherwise provided in the Technical Specifications, the licensee shall report any violations of the requirements contained in l
l Section 2.0 of this license in the following manners initial i
notification shall be made within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> to the NRC Operations Center via the Emergency Notification System with written follow-up within 30 days in accordance with the procedures described in 10 CFR 50.73(b), (c), and (e).
,,-.-~,,,,n--,,,,.,.
r.w.,,...-
-,,r-,,
,-.,y
.._y, wm
,,,,m,.,...n.,
._,,,-,,,r--....
__,.m,.,
I
.e.
F.
The licensee shall have and maintain financial protection of such type and in such amounts as the Commission shall require in accordance with Section 170 of the Atomic Energy Act of 1954, as amended, to cover public liability claims.
3.
This license is effective as of the date of issuance and shall expire at i
midnight on December 15, 2004.
FOR THE NUCLEAR REGULATORY C0 fir!!SS10N Thomas E. Hurley, Director Office of Nuclear Reactor Regulation
Attachment:
Appendices A and D -
Technical Specifications Date of Is6uance:
- -.