|
---|
Category:TECHNICAL SPECIFICATIONS
MONTHYEARML20209H5051999-07-14014 July 1999 Proposed Tech Specs Pages 3.1-15 & 3.1-17 of Table 3.1.1 ML20209E0951999-07-0707 July 1999 Proposed Tech Specs,Changing Component Surveillance Frequencies to Indicate Frequency of Once Per Three Months ML20212H5441999-06-18018 June 1999 Proposed Tech Specs Reflecting Installation of Addl SFP Storage Racks That Will Accommodate Increase in Spent Fuel Assemblies Beyond Existing Storage Capacity of SFP as Described in Licensing Rept ML20195D0761999-06-0303 June 1999 Proposed Tech Specs,Permitting Plant Operation with Three Operable Recirculation Loops ML20205P8531999-04-15015 April 1999 Proposed Tech Specs,Modifying Number of Items in Sections 2 & 3 of Tss,Expanding Two Definitions in Section 1 & Modifying Bases Statements in Sections 2,3 & 4 ML20198K0671998-12-23023 December 1998 Proposed Tech Specs Pages 3.8-2 & 4.8-1,changed to Specify Surveillance Frequency of Once Per Three Months ML20195C6561998-11-10010 November 1998 Proposed Tech Specs Section 5.1.A,removing Restriction on Sale or Lease of Property within Exclusion Area ML20155J7501998-11-0505 November 1998 Proposed Tech Specs,Modifying Safety Limits & Surveillances of LPRM & APRM Sys & Related Bases to Ensure APRM Channels Respond within Necessary Range & Accuracy & to Verify Channel Operability ML20151V5091998-09-0303 September 1998 Proposed Tech Specs 3.4.A.10.e & 3.5.A.2.e Re Condensate Storage Tank Level ML20237D9591998-08-21021 August 1998 Proposed Tech Specs Removing Requirement for ADS Function of EMRV to Be Operable During Rv Pressure Testing & Correcting Note H of Table 3.1.1 ML20237B2221998-08-0606 August 1998 Proposed Revised Tech Specs Pages for Change Request 205,dtd 961031,correcting Minor & Inadvertent Editorial Changes in Locations Where Changes Have Not Been Proposed ML20236T1211998-07-23023 July 1998 Proposed Tech Specs Pages for Amend to License DPR-16,to Establish That Existing SLMCPR Contained in TS 2.1.A Is Applicable for Next Operating Cycle (Cycle 17) ML20236T4981998-07-21021 July 1998 Proposed Tech Specs Re Reactivity Control ML20236T4811998-07-21021 July 1998 Proposed Tech Specs Re Changes to Administrative Controls ML20236J1431998-06-30030 June 1998 Proposed Tech Specs,Consisting of Revised Page 3-5 Re RPV Pressure/Temp Limits ML20236H2181998-06-29029 June 1998 Proposed Tech Specs,Modifying EDG Insp Requirement Previously Submitted in Entirety ML20248K2851998-05-28028 May 1998 Proposed Tech Specs Re That Such First Type a Test Required by Primary Containment Leakage Rate Testing Program Be Performed During Refueling Outage 18R ML20197G2771997-12-23023 December 1997 Proposed Tech Specs Reflecting Change in Trade Name of Owner & Operator of Oyster Creek Nuclear Generating Station ML20197J2561997-12-10010 December 1997 Proposed Tech Specs Changing 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 ML20210L3311997-08-15015 August 1997 Proposed Tech Specs,Incorporating Note Which Indicates That Proposed Change to SL Mcrp Applicable for Current Operating Cycle (Cycle 16) Only ML20135C2001996-11-27027 November 1996 Proposed Tech Specs Pages 4.7-1,4.7-2,4.7-3 & 4.7-4 Re Surveillances for Station Batteries ML20129K3401996-11-12012 November 1996 Proposed Tech Specs,Consisting of Change Request 224, Implementing Revised 10CFR20, Stds for Protection Against Radiation Effective 910620 ML20134H0541996-10-31031 October 1996 Proposed Tech Spec,Requesting Deletion of Table 3.5.2 ML20129C0691996-10-10010 October 1996 Proposed Tech Specs,Clarifying Functional Requirement to Provide Interlock Permissive Which Ensures Source of Cooling Water Available Via Core Spray Sys Prior to Depressurization ML20129A5731996-10-10010 October 1996 Proposed Tech Specs,Revising Addl Group of Surveillances Where Justification Completed Following Receipt of Amend 144 ML20134F4101996-10-0404 October 1996 Proposed Tech Specs 2.1.A & 3.10.C to Reflect Change in SLMCPR & Revise Operating CPR Limit for Stability, Respectively ML20117E7061996-08-23023 August 1996 Proposed Tech Specs,Proposing New pressure-temp Limits Up to 22,27 & 32 EFPY Based on Predicted Nilductility Adjusted Ref Temp for Corrresponding EFPY of Operation ML20115G2101996-07-17017 July 1996 Proposed Tech Specs,Allowing Implementation of 10CFR,App J, Option B ML20113A8641996-06-19019 June 1996 Proposed Tech Specs Table of Contents,1.24 Re Footnote to definition,1.25 Re Definition,Section 3.5.A.3b Re Containment,Section 4.5 Re Containment,Bases for Section 4.5 & Section 6.9.3.b Re Reporting Requirements ML20111A3841996-05-0707 May 1996 Proposed Tech Specs,Adopting Provisions of STS NUREG-1433, Rev 1,dtd 950407,Sections SR 3.0.1,3.0.3 & Associated Bases ML20107E7751996-04-15015 April 1996 Proposed Tech Specs 5.3.1 Re Handling Heavy Loads Over Irradiated Fuel ML20101J7681996-03-28028 March 1996 Proposed Tech Specs,Modifying Statements in TS & Bases to Correctly Reflect Ref Parameter for Anticipatory Scram Signal Bypass ML20101J6091996-03-25025 March 1996 Proposed Tech Specs,Deleting Spec Which Requires Thorough Insp of EDG Every 24 Months During Shutdown ML20100J9151996-02-23023 February 1996 Proposed Tech Specs Re Implementation of 10CFR50,App J, Option B ML20100H9971996-02-22022 February 1996 Proposed Tech Specs 3.7-1,3.7-2,4.7-1 & 4.7-2 Re Deletion of TS Requirement to bi-annually Inspect EDG & Mod of Spec Re AOT ML20095C1031995-12-0505 December 1995 Proposed Tech Specs Re Rev of Submittal Date for Annual Exposure Data Rept Bringing Plant Into Conformance w/10CFR20.2206 & Relaxing Overly Restrictive Administrative Requirement ML20086A7161995-06-26026 June 1995 Proposed Tech Specs Re Performance of Reactor Shutdown & Drywell to Inspect Snubbers in Svc for Only 12 Months ML20080P6501995-02-28028 February 1995 Proposed Tech Specs Change Request 225 Re Change to Page 6-4 of Tech Spec Section 6.5.1.12.Change Consistent w/NUREG-1433,STSs General Electric Plants,BWR/4,Rev 0,dtd 920928 ML20078N3791995-02-0808 February 1995 Proposed Tech Specs Re Oyster Creek Spent Fuel Pool Expansion ML20078Q6481994-12-15015 December 1994 Revised TS & Bases Pages to Section 3.1 of TS Change Request 191 ML20078M1431994-11-25025 November 1994 Proposed TS 5.3.1.E,allowing 2,645 Fuel Assemblies to Be Stored in Fuel Pool ML20072S2921994-09-0202 September 1994 Proposed Tech Specs Supporting Rev of APRM Channel Calibr Interval from Weekly to Quarterly ML20072L4741994-08-19019 August 1994 Proposed Tech Specs Control Rod Exercising & Standby Liquid Control Pump Operability Testing ML20070E3411994-07-0808 July 1994 Proposed Tech Specs Re Improved Protection to Safety Related Electrical Equipment from Loss of Capability ML20078A7731994-06-24024 June 1994 Proposed Tech Specs Reflecting Removal of Recirculation Flow Scram ML20069M8231994-06-15015 June 1994 Proposed Tech Spec 2.3.D, Reactor High Pressure,Relief Valve Initiation ML20070R5261994-05-12012 May 1994 Proposed TS Sections 3.1 & 4.1 for Protective Instrumentation ML20029E0451994-05-0606 May 1994 Proposed Tech Specs Clarifying Requirements for Demonstrating Shutdown Margin ML20065M9991994-04-19019 April 1994 Proposed Tech Specs 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 or Bypassed During Sys Pressure Testing ML20029C7571994-04-15015 April 1994 Proposed TS Change Request 215,deleting Audit Program Frequency Requirements from TS 6.5.3 & Utilize Operational QA Plan as Controlling Document 1999-07-07
[Table view] Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML20212B5741999-09-0505 September 1999 Rev 11 to 2000-ADM-4532.04, Oyster Creek Emergency Offsite Dose Calculation Manual ML20209H5051999-07-14014 July 1999 Proposed Tech Specs Pages 3.1-15 & 3.1-17 of Table 3.1.1 ML20209E0951999-07-0707 July 1999 Proposed Tech Specs,Changing Component Surveillance Frequencies to Indicate Frequency of Once Per Three Months ML20212H5441999-06-18018 June 1999 Proposed Tech Specs Reflecting Installation of Addl SFP Storage Racks That Will Accommodate Increase in Spent Fuel Assemblies Beyond Existing Storage Capacity of SFP as Described in Licensing Rept ML20195D0761999-06-0303 June 1999 Proposed Tech Specs,Permitting Plant Operation with Three Operable Recirculation Loops ML20205P8531999-04-15015 April 1999 Proposed Tech Specs,Modifying Number of Items in Sections 2 & 3 of Tss,Expanding Two Definitions in Section 1 & Modifying Bases Statements in Sections 2,3 & 4 ML20198K0671998-12-23023 December 1998 Proposed Tech Specs Pages 3.8-2 & 4.8-1,changed to Specify Surveillance Frequency of Once Per Three Months ML20195C6561998-11-10010 November 1998 Proposed Tech Specs Section 5.1.A,removing Restriction on Sale or Lease of Property within Exclusion Area ML20155J7501998-11-0505 November 1998 Proposed Tech Specs,Modifying Safety Limits & Surveillances of LPRM & APRM Sys & Related Bases to Ensure APRM Channels Respond within Necessary Range & Accuracy & to Verify Channel Operability ML20151V5091998-09-0303 September 1998 Proposed Tech Specs 3.4.A.10.e & 3.5.A.2.e Re Condensate Storage Tank Level ML20237D9591998-08-21021 August 1998 Proposed Tech Specs Removing Requirement for ADS Function of EMRV to Be Operable During Rv Pressure Testing & Correcting Note H of Table 3.1.1 ML20237B2221998-08-0606 August 1998 Proposed Revised Tech Specs Pages for Change Request 205,dtd 961031,correcting Minor & Inadvertent Editorial Changes in Locations Where Changes Have Not Been Proposed ML20236T1211998-07-23023 July 1998 Proposed Tech Specs Pages for Amend to License DPR-16,to Establish That Existing SLMCPR Contained in TS 2.1.A Is Applicable for Next Operating Cycle (Cycle 17) ML20236T4811998-07-21021 July 1998 Proposed Tech Specs Re Changes to Administrative Controls ML20236T4981998-07-21021 July 1998 Proposed Tech Specs Re Reactivity Control ML20236J1431998-06-30030 June 1998 Proposed Tech Specs,Consisting of Revised Page 3-5 Re RPV Pressure/Temp Limits ML20236H2181998-06-29029 June 1998 Proposed Tech Specs,Modifying EDG Insp Requirement Previously Submitted in Entirety ML20248K2851998-05-28028 May 1998 Proposed Tech Specs Re That Such First Type a Test Required by Primary Containment Leakage Rate Testing Program Be Performed During Refueling Outage 18R ML20197G2771997-12-23023 December 1997 Proposed Tech Specs Reflecting Change in Trade Name of Owner & Operator of Oyster Creek Nuclear Generating Station ML20197J2561997-12-10010 December 1997 Proposed Tech Specs Changing 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 ML20210L3311997-08-15015 August 1997 Proposed Tech Specs,Incorporating Note Which Indicates That Proposed Change to SL Mcrp Applicable for Current Operating Cycle (Cycle 16) Only ML20135C2001996-11-27027 November 1996 Proposed Tech Specs Pages 4.7-1,4.7-2,4.7-3 & 4.7-4 Re Surveillances for Station Batteries ML20129K3401996-11-12012 November 1996 Proposed Tech Specs,Consisting of Change Request 224, Implementing Revised 10CFR20, Stds for Protection Against Radiation Effective 910620 ML20134H0541996-10-31031 October 1996 Proposed Tech Spec,Requesting Deletion of Table 3.5.2 ML20129C0691996-10-10010 October 1996 Proposed Tech Specs,Clarifying Functional Requirement to Provide Interlock Permissive Which Ensures Source of Cooling Water Available Via Core Spray Sys Prior to Depressurization ML20129A5731996-10-10010 October 1996 Proposed Tech Specs,Revising Addl Group of Surveillances Where Justification Completed Following Receipt of Amend 144 ML20134F4101996-10-0404 October 1996 Proposed Tech Specs 2.1.A & 3.10.C to Reflect Change in SLMCPR & Revise Operating CPR Limit for Stability, Respectively ML20117E7061996-08-23023 August 1996 Proposed Tech Specs,Proposing New pressure-temp Limits Up to 22,27 & 32 EFPY Based on Predicted Nilductility Adjusted Ref Temp for Corrresponding EFPY of Operation ML20115G2101996-07-17017 July 1996 Proposed Tech Specs,Allowing Implementation of 10CFR,App J, Option B ML20113A8641996-06-19019 June 1996 Proposed Tech Specs Table of Contents,1.24 Re Footnote to definition,1.25 Re Definition,Section 3.5.A.3b Re Containment,Section 4.5 Re Containment,Bases for Section 4.5 & Section 6.9.3.b Re Reporting Requirements ML20111A3841996-05-0707 May 1996 Proposed Tech Specs,Adopting Provisions of STS NUREG-1433, Rev 1,dtd 950407,Sections SR 3.0.1,3.0.3 & Associated Bases ML20107E7751996-04-15015 April 1996 Proposed Tech Specs 5.3.1 Re Handling Heavy Loads Over Irradiated Fuel ML20101P1561996-03-31031 March 1996 Rev 9 to Oyster Creek Nuclear Generating Station Pump & Valve IST Program ML20101J7681996-03-28028 March 1996 Proposed Tech Specs,Modifying Statements in TS & Bases to Correctly Reflect Ref Parameter for Anticipatory Scram Signal Bypass ML20101J6091996-03-25025 March 1996 Proposed Tech Specs,Deleting Spec Which Requires Thorough Insp of EDG Every 24 Months During Shutdown ML20100J9151996-02-23023 February 1996 Proposed Tech Specs Re Implementation of 10CFR50,App J, Option B ML20100H9971996-02-22022 February 1996 Proposed Tech Specs 3.7-1,3.7-2,4.7-1 & 4.7-2 Re Deletion of TS Requirement to bi-annually Inspect EDG & Mod of Spec Re AOT ML20095C1031995-12-0505 December 1995 Proposed Tech Specs Re Rev of Submittal Date for Annual Exposure Data Rept Bringing Plant Into Conformance w/10CFR20.2206 & Relaxing Overly Restrictive Administrative Requirement ML20086A7161995-06-26026 June 1995 Proposed Tech Specs Re Performance of Reactor Shutdown & Drywell to Inspect Snubbers in Svc for Only 12 Months ML20080P6501995-02-28028 February 1995 Proposed Tech Specs Change Request 225 Re Change to Page 6-4 of Tech Spec Section 6.5.1.12.Change Consistent w/NUREG-1433,STSs General Electric Plants,BWR/4,Rev 0,dtd 920928 ML20078N3791995-02-0808 February 1995 Proposed Tech Specs Re Oyster Creek Spent Fuel Pool Expansion ML20078Q6481994-12-15015 December 1994 Revised TS & Bases Pages to Section 3.1 of TS Change Request 191 ML20078M1431994-11-25025 November 1994 Proposed TS 5.3.1.E,allowing 2,645 Fuel Assemblies to Be Stored in Fuel Pool ML20073F9501994-09-26026 September 1994 Revised Plan for Long Range Planning Program for Oyster Creek Nuclear Generating Station ML20073F9411994-09-26026 September 1994 Revised Plan for Long Range Planning Program for TMI Nuclear Station Unit 1 ML20072S2921994-09-0202 September 1994 Proposed Tech Specs Supporting Rev of APRM Channel Calibr Interval from Weekly to Quarterly ML20072Q4251994-08-20020 August 1994 Rev 0 to Oyster Creek Nuclear Generating Station Sea Turtle Surveillance,Handling & Reporting Instructions for Operations Personnel ML20072L4741994-08-19019 August 1994 Proposed Tech Specs Control Rod Exercising & Standby Liquid Control Pump Operability Testing ML20070J7971994-07-31031 July 1994 Rev 8 to Oyster Creek Nuclear Generating Station Pump & Valve Inservice Testing Program ML20070E3411994-07-0808 July 1994 Proposed Tech Specs Re Improved Protection to Safety Related Electrical Equipment from Loss of Capability 1999-09-05
[Table view] |
Text
. . .. _ _
Dockel No. 50 219 October 1,1986
- APPENDIX A TO PROVISIONAL OPERATING LICENSE DPR 16*
TECHNICAL SPECIFICATIONS AND BASES FOR OYSTER CREEK NUCLEAR POWER PLANT UNIT NO.1 OCEAN COUNTY, NEW JERSEY Jersey Central Power & Light Company d/b/a GPU Energy GPU Nuclear,Inc.
t OPer Errata Sheet date:14 6-0 9710170109 971010 PDR P
ADOCK 05000219-PDR
. ADf4INISTRATIVE CONTROLS 6.1 RESPONSIBILITY 6.1.1 The Vice President & Director Oyster Creek shall be responsible for overall fccility operation. Those responsibilities delegated to the Vice president &
Director as stated in the Oyster Creek Technical specifications may also be fulfilled by the Deputy Director. The Vice President & Director shall delegate in writing the succession to this responsibility during his and/or the Deputy Directors cbs:nce.
6.2 ORGANI"ATION 6.2.1 gpruerate 6.2.1.1 An oneite and offsite organization shall be established for unit operation end corporate '4gement. The onsite and of f aite organization shall include the positions for acsivities affecting the safety of the nuclear power plant.
6.2.1.2 Lines of authority, responsibility and communication shall be established cnd defined f rom the highest ranagement levels through intermediate levels to and including operating organization positions. These relationships shall be documented end updated as appropriate, in the form of organizational charts. These organizational charts will be documented in the Updated FSAR and updr.ted in cccordance with 10 CFR 50.71e.
6.2.1.3 The President - GPU Nuclear shall have corporate responsibility for overall l plent nuclear safety and shall take measures needed to ensure acceptable performance of the staff in operating, maintaining, and providing technical support in the plant co that continued nuclear safety is assured.
6.2.2 FACILITY STAFF 6.2.2.1 The Vice President & Director Oyster Creek shall be responsible for overall unit safe operation and shall have control over those onsite activities necessary for safe operation and maintenance of the plant.
6.2.2.2 The facility organization shall meet the following
- a. Each on duty shift shall include at least the following shift staffing:
One (1) group shift supervisor Two (2) control room operators Three (3) equipment operators - one may be a Radwaste operator
- b. At all timen when there is fuel in the vessel, at least one licenrad senior reactor operator shall be on site and one licensed reactor operator should be at the controls,
- c. At all times when there is fuel in the vessel, except when the reactor la in COLD SHUTDOWN or REFUEL modes, two licensed senior reactor operators and two licensed reactor operators shall be on site, with at least one licensed senior reactor operator in the control room and one licensed reactor operator at the controls.
OYSTER CREEK 6-1 Amendment No.: 54, 59,65, 69, 102, 134 i
6.4 TfAINING 6.4.1 A retaining program for operators shall be maintained under the direction of the Manager responsible for plant training and shall
. a meet the requirements and recommendation of 10 CFR Part 55.
Replacement training programs, the content of which shall meet the requirements of 10 CFR Part 55, shall be conducted under the direction of the Manager responsible for plant training for licensed operators and Senior Reactor Operators.
- 6. 5 REVIEW AT,D /.'JDIT 6.5.1 TECHNICAL PEVIEW AND CONTROL The Vice President of each division within GPU Nuclear, Inc. shall be responsible l
for ensuring the preparation, review, and approval of documents required by the cetivities described in 6.5.1.1 through 6.5.1.5 within his functional area of responsibility as assigned in the GPU Nuclear Review and Approval Matrix.
Implementing approvals shall be performed at the cognizant manager level or above.
ACTIVITIES
-6.5.1.1 Each procedure required by Technical Specification 6.8 and other procedures which affect nuclear safety, and substantive changes thereto, shall be
-prepared by a designated individual (s)/ group knowledgeable in the area affected by tha procedure. Each such procedure, and substantive change thereto, shall be reviewed for adequacy by-an individual (s)/ group other than the preparer, but who may be from the same division as the individual who prepared tho' procedure or change.
OYSTER CREEK 6-3 Amendment No.: 69, ~18 , 125, 134, 161
____ 4
PECORDS 4.5.1.13 Uritten records of cetivities performsd undar specifications 6.5.1.1 through 6.5.1.11 shall be maintained.
QUALIFICATIONS 6.5.1.14 Responsible Technical Reviewers shall meet or exceed the qualifications of ANSI /ANS 3.1 1970 Section 4.6 or 4.4 for applicable dtsciplines or have 7 years of cppropriate experience in the field of his specialty. Credit towards exp3rience will be given for advanced degrees on a one-for-one basis up to a maximum of two years. These Reviewers shall be designated in writing.
6.5.2 JJfDEPENDENT SAFETY P.EVIEW FUNCTION 6.5.2.1 The Vico President of each division within GPU Nuclear, Inc shall be l rosponsible for ensuring the periodic independent safety review of the subjects dsscribed in G.5.2.5 within his assigned area of safety review respor.isibility, as casigned in the GPUN Review and Approval Matrix.
6.5.2.2 Independent safety review shall be completed by an individual / group not having direct responsibility for the performance of the activities under review, but who may be from the same functicnally cognatant organization au tne individual / group performing the original work.
6.5.2.3 GPU Nuclear, Inc. shall collectively have or have access to the l experience and competence required to independently review subjects in the following areas:
- a. Nuclear power plant operations
- b. Nuclest engineering
- c. Chemistry and radiochemistry
- d. hetallurgy
- e. Nondestructive testing
- f. Instrumentation and control
- g. Radiological safety
- h. Mechanical engineering
- i. Electrical engineering
- j. Administrative controls and quality casurance practices
- k. Emergency plans and related organization, procudures and equipment
- 1. 0ther appropriate fields associated with the unique characteristics of Oyster Creek 6.5.2.4 Consultants may be utilized as determined by the cognizant Vice President to provide expert advice.
OYSTER CREEK 6-5 Amendment No.: 69, 134, 181
6.5.3 ' AUDITS 6.5.3.1 Audits of facility activities shall be performed in accordance with the Oyster Creek Operational Quality Ass'urarne Plan. These audits shall encompass:
- a. The confonnance of facility operations to provisions contained within the Technical d
Specifications and applicable license conditions,
- b. The performance, training and qualifications of the facility staff.
- c. The results of actions taken to correct deficiencies occurring in facility equipment, structures, system, or method of operation that affect nuclear safety.
J i d. The Facility Emergency Plan and implementing procedures.
- c. The Facility Security Plan and implementing procedures.
l f. The Fire Protection Program and implementing procedures.
]
- g. The performance of activities required by the Operational Quality Assurance Plan to meet the criteria of Appendix 'B',10 CFR 50.
- h. The radiological environmental monitoring program and the results thereof.
- i. The OFFSITE DOSE CALCULATION MANUAL and implementing procedures. ;
, l J. The PROCESS CONTROL PROGRAM and implementing procedures for radioactive wastes. I
- k. Any other area of facility operation considered appropriate by the 10SRG or the Office of the
. President GPU Nuclear. l 6.5.3.2 Audits of the following shall be performed under the cognizance of the Vice President - .
' l responsible for technical support,
- a. An independent fire protection and loss prevention program inspection and audit shall be
, performed utilizing cither qualified licensee personnel or an outside flic protection firm.
- b. An inspection and audit of the fire protection and loss prevention program, by an outside qualified fire consultant.
i a
OYSTER CREEK 6-7 Amendment No.:
69,89,108,117,134,161,181
--,----.v, , .- ye .~s -
--m - - ,,--- -,- - - --. ~ ..qw,,,,
6.17 POST ACCIDENT SAhiPI,1NG
. The following program shall be established, implemented, and maints3ned, t -
A program has been established w hich will ensure the capability to obtain and analyze reactor coolant, radioactive lodines and particulates in plant gaseous emuents, and containment atmosphere samples under accident conditions. The program shall include the following:
- a. Training of personnel in sampling and analysis.
- b. Procedures for sampling and analysis,
- c. Provisions for verifying operability of the System.
6.18 PROCESS CONTROL Pl. AN -
- a. GPU Nuclear,Inc. Initiated changer to the PCP:
- 1. Shall be submitted to the NRC in the Annual Radioactive tiffluent Release Report for the period in which the changes w re made. This submittal shall contain:
- a. sufficiently detailed information tojustify the changes without benefit of additional or supplementalinformation;
- b. a determination that the changes did not reduce the overall conformance of the solidified waste product to existing criteria for solid wastes; and
- c. documentation that the changes have been reviewed and approved pursuant to Section 6.8.2.
- 2. Shall become effective upon review and approval by GPU Nuclear hianagement.
)
6.19 OFFSITE DOSE cal.CUI.ATlON h1 ANUAl.
- a. The ODChi shall be approved by the Commission prior to implementation.
- b. GPU Nuclear, Inc. initiated changes to the ODChi shall be submittcd to the NRC in the Annual Radioactive Effluent Release Report for the period in which the changes were made. This submittal shall contain:
- 1. sufficiently detailed information tojustify the changes without benefit of additional or
- upplementalinfumation;
- 2. a determination that the changes did not reduce the accuracy or reliability of dose calculations I or setpoint determination; and, 3, documentation that the changes have been reviev ed and approved pursuant to Section 6.8.2.
- c. Change (s) shall become effective upon review and approval by GPU Nucleai hiana;ement.
OYSTER CREEK 6 20 Amendment No.:69,98,108,134,166 1
6.20 h1610R CilANGES TO RADIOACTIVE WASTE TREATMENT SYSTEMS
.DELETsC.
OYSTERCREEK 6-21 Amendment No.: 166
APPENDlX B TO PROVISIONAL OPERATING LICENSE NO. DPR 16 IE JRONMENTAL TECIINICAL SPECIFICATIONS FOR OYSTER CREEK NUCLEAR GENERATING STATION DOCKET NO,50-219 OCEAN COUNTY, NEW JERSEY J
JERSEY CENTRAL POWER & LIGHT COMPANY d/b/a GPU ENEROY GPU NUCLEAR,INC.
NOVEMBER 197.9' Olssued to the ASLB on this date; issued by License Amendment No. 37, June 6,1979.
Amendment No.: 59,_66,-107
- _ _ _ _ - _ - _ _ _ - - - .