Proposed TS 6.3.1.2, Unit Staff Qualifications, Covering Designation of Health Physics Mgt Personnel as Radiation Protection ManagerML20128B369 |
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Site: |
Callaway |
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Issue date: |
01/27/1993 |
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From: |
UNION ELECTRIC CO. |
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To: |
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Shared Package |
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ML20128B366 |
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References |
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ULNRC-2756, NUDOCS 9302030025 |
Download: ML20128B369 (10) |
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Category:TECHNICAL SPECIFICATIONS
MONTHYEARML20211Q5411999-09-0808 September 1999 Proposed Tech Specs Reflecting USQ Associated with Increases in Offsite Dose Consequences Reported in FSAR for SGTR & MSLB Accidents ML20195C5191999-05-28028 May 1999 Proposed Tech Specs Sections 3.9.1,revised to Maintain CTS Requirements on Refueling Pool Boron Concentration Limits & 5.6.5,revised to Delete Item 5.6.5.a ML20207F4801999-05-27027 May 1999 Proposed Improved TSs & ITS Bases ML20206G3621999-04-30030 April 1999 Proposed Conversion Tech Specs Section 1.0/ITS Section 1.0 ML20205S9141999-04-21021 April 1999 Proposed Tech Specs Sections 1.0,3.3,3.4,3.6,3.7 & 3.9, Converting to ITS ML20205L0901999-04-0707 April 1999 Proposed Tech Specs Section 3.3,3.4,3.5,3.6,3.7,3.8 & 4.0, Converting to ITS ML20207L1061999-03-0909 March 1999 Proposed Tech Specs Re Conversion to ITSs Sections 3.3,3.4, 3.6,3.7.3 8,3.9 & 5.0 ML20196G1731998-11-25025 November 1998 Proposed Tech Specs Section 3.3, Intstrumentation, Converting to Improved Tech Specs ML20196D0011998-11-23023 November 1998 Proposed Tech Specs Pages Re follow-up Items Related to 970515 Request for Amend to License NPF-30 ML20155B5791998-10-27027 October 1998 Proposed Tech Specs for Use of Electrosleeves on Two Cycle Basis ML20154S2371998-10-21021 October 1998 Proposed Tech Specs Sections 3.1,3.2,3.4,3.5 & 5.0 Re Reactivity Control Sys,Power Distribution Sys,Rcs,Eccs & Administrative Controls,Respectively ML20154F8311998-09-29029 September 1998 Proposed Tech Specs Revising ESFAS Functional Unit 6.f Re Loss of Offsite power-start turbine-driven Pump ML20154A2901998-09-24024 September 1998 Proposed Tech Specs Converting to Improved TS Re Section 3.4, RCS, Consistent w/NUREG-1431 ML20151U1031998-08-27027 August 1998 Proposed Tech Specs Sections 1.0,2.0 & 3.0,converting to Improved Tech Specs ML20236Y1721998-08-0404 August 1998 Proposed Tech Specs Re Conversion to Improved STS Sections 3.1,3.2,3.5,3.9 & 4.0 ML20236W3721998-07-30030 July 1998 Proposed Tech Specs Revising Table 4.3-2 by Adding Table Notation to Clarify That Verification of Time Delays Associated W/Esfas Functional Units 8.a & 8.b Is Only Performed as Part of Channel Calibr ML20236J0821998-06-29029 June 1998 Proposed Tech Specs 3.7.1.7,4.7.1.7.1,4.7.1.7.2 & Bases 3/4.7.1.7 Revising to Address All Four Atmospheric Steam Dump Lines ML20236E9651998-06-26026 June 1998 Proposed Tech Specs Pages Re Conversion to Improved STS, Section 3.6 ML20216F3791998-03-0909 March 1998 Proposed Tech Specs SR 3/4.5.2b.1 Adding Clarification in Regard to Venting ECCS Pump Casings & Accessible Discharge Piping High Points ML20217P8161998-02-23023 February 1998 Proposed Tech Specs Replacement Page B 3.8-34 Re AC Sources Shutdown ML20198T3521998-01-16016 January 1998 Proposed Tech Specs 3/4.3,revising Ms & Feedwater Isolation Sys Slave Relay Surveillance from Quarterly Actuation Logic Test to Monthly Actuation Logic Test on Staggered Test Basis ML20197D6461997-12-16016 December 1997 Proposed Tech Specs Table Revising Lift Setting Tolerance for Main Steam Line Safety Valves ML20199B4261997-11-10010 November 1997 Proposed Tech Specs Re Page 5 of 8 for FW Isolation Changes ML20198P3361997-10-31031 October 1997 Proposed Tech Specs Reducing Repeated Alarms,Rod Blocks & Partial Reactor Trips That Continue to Manifest,During Beginning of Cycle Operation Following Refueling Outages ML20198P4141997-10-31031 October 1997 Proposed Tech Specs,Revising ESFAS Functional Unit 6.f, Loss of Offsite Power-Start Turbine-Driven Pump, in Tables 3.3-3,3.3-4 & 4.3-2 ULNRC-03664, Proposed Tech Specs 3/4.4.9 Re Pressure/Temp Limits1997-10-17017 October 1997 Proposed Tech Specs 3/4.4.9 Re Pressure/Temp Limits ML20198F3911997-08-0808 August 1997 Proposed Tech Specs Changes,Revising Feedwater Isolation ESFAS Functions in TS Tables 3.3-3,3.3-4 & 4.3-2 ML20198F3411997-08-0808 August 1997 Proposed Tech Specs,Revising Table 3-7.2 to Specify That Lift Setting Tolerance for Main Steam Line Safety Valves Is +3/-1% as-found & +1% as-left.Table 2.2-1 Revised by Reducing Sensor Error for Pressurizer pressure-high Trip ML20210H2151997-08-0808 August 1997 Proposed TS Revising SRs 3/4.7.4, Essential Svc Water Sys by Removing Requirement to Perform SRs 4.7.4.b.1, 4.7.4.b.2 & 4.7.4.c During Shutdown ML20217H8031997-08-0808 August 1997 Proposed Tech Specs 3/4.3 Re Instrumentation ML20198J7301997-05-15015 May 1997 Proposed Conversion to ITS Sections 1.0,3.1,3.2,3.3,3.4,3.7, 3.9 & 5.0 for Plant ML20154Q1191997-05-15015 May 1997 Proposed Improved TS Section 3.7, Plant Sys ML20138B7421997-04-24024 April 1997 Proposed Tech Specs 6.0 Revising Title Senior Vice President,Nuclear to Vice President & Chief Nuclear Officer ML20137N6111997-04-0101 April 1997 Proposed Tech Specs Table 3.3-3 Re Engineered Safety Features Actuation Sys Instrumentation ML20117K6431996-09-0505 September 1996 Proposed Tech Specs,Revising TS 3/4.4 Re RCS ML20115J0181996-07-18018 July 1996 Proposed Tech Specs 3/4.7.7,3/4.9.13 & Corresponding Bases Re Charcoal Test Methodology for Emergency Exhaust Sys ML20107H3931996-04-17017 April 1996 Proposed Tech Specs 3/4.3 Re Adding Ms & FW Isolation Sys Actuation Logic & Relays to Functional Units 4.b & 5.a of Tables 3.3-3,3.3-4 & 4.3-2 & Revising Table 3.3-3 by Adding Action Statements 27a & 34a ML20107F0791996-04-12012 April 1996 Proposed Tech Specs 3/4.4 Re Changing TS, RCS & Associated Bases to Address Installation of Electrosleeves in Callaway Plant SGs ML20107E3251996-04-12012 April 1996 Proposed Tech Specs 3/4.4.5, SGs & 3.4.6.2, Operational Leakage & Associated Bases,Addressing Installation of Laser Welded Tube Sleeves in Plant SGs ML20101R4211996-04-0909 April 1996 Revised TS Pages That Adhere to Testing Methods of ASTM Std D2276-78,Method a for Diesel Fuel Oil Particulate Concentration ML20101J0381996-03-22022 March 1996 Proposed Tech Specs,Implementing Containment Integrated Leakage Rate Program That Would Allow Ilrt,Presently Scheduled for Refuel 8,to Be Rescheduled ML20106G4351996-02-28028 February 1996 Proposed TS 3/4.8.1,ac Sources ML20106G4131996-02-23023 February 1996 Proposed Tech Specs Paragraph 1.A. Re Operating License Change to Reflect Union Electric as wholly-owned Subsidiary of Ameren Corp ML20097D5801996-02-0909 February 1996 Proposed Tech Specs Allowing Use of Alternate Zirconium Based Fuel Cladding Material ML20097D6151996-02-0909 February 1996 Proposed Tech Specs & Bases Re Containment Systems ML20097D6341996-02-0909 February 1996 Proposed Tech Specs Re AFW Sys ML20097F8991996-02-0404 February 1996 Proposed Tech Specs 4.6.1.2.a Re Containment Sys ML20097C2791996-02-0202 February 1996 Proposed Tech Spec 3/4.6.3, Containment Isolation Valves ML20096B1891996-01-0202 January 1996 Proposed Tech Specs 3.9.4, Containment Bldg Penetrations & Associated Bases Section to Allow Containment Personnel Airlock Doors to Be Open During Core Alterations ML20094A1721995-10-23023 October 1995 Proposed Tech Specs,Relocating Audit Frequencies in Former TS 6.5.2.9 to Operational QA Manual 1999-09-08
[Table view] Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML20211Q5411999-09-0808 September 1999 Proposed Tech Specs Reflecting USQ Associated with Increases in Offsite Dose Consequences Reported in FSAR for SGTR & MSLB Accidents ML20195C5191999-05-28028 May 1999 Proposed Tech Specs Sections 3.9.1,revised to Maintain CTS Requirements on Refueling Pool Boron Concentration Limits & 5.6.5,revised to Delete Item 5.6.5.a ML20207F4801999-05-27027 May 1999 Proposed Improved TSs & ITS Bases ML20206G3621999-04-30030 April 1999 Proposed Conversion Tech Specs Section 1.0/ITS Section 1.0 ML20205S9141999-04-21021 April 1999 Proposed Tech Specs Sections 1.0,3.3,3.4,3.6,3.7 & 3.9, Converting to ITS ML20205L0901999-04-0707 April 1999 Proposed Tech Specs Section 3.3,3.4,3.5,3.6,3.7,3.8 & 4.0, Converting to ITS ML20207L1061999-03-0909 March 1999 Proposed Tech Specs Re Conversion to ITSs Sections 3.3,3.4, 3.6,3.7.3 8,3.9 & 5.0 ML20196G1731998-11-25025 November 1998 Proposed Tech Specs Section 3.3, Intstrumentation, Converting to Improved Tech Specs ML20196D0011998-11-23023 November 1998 Proposed Tech Specs Pages Re follow-up Items Related to 970515 Request for Amend to License NPF-30 ML20155B5791998-10-27027 October 1998 Proposed Tech Specs for Use of Electrosleeves on Two Cycle Basis ML20154S2371998-10-21021 October 1998 Proposed Tech Specs Sections 3.1,3.2,3.4,3.5 & 5.0 Re Reactivity Control Sys,Power Distribution Sys,Rcs,Eccs & Administrative Controls,Respectively ML20154F8311998-09-29029 September 1998 Proposed Tech Specs Revising ESFAS Functional Unit 6.f Re Loss of Offsite power-start turbine-driven Pump ML20154A2901998-09-24024 September 1998 Proposed Tech Specs Converting to Improved TS Re Section 3.4, RCS, Consistent w/NUREG-1431 ML20151U1031998-08-27027 August 1998 Proposed Tech Specs Sections 1.0,2.0 & 3.0,converting to Improved Tech Specs ML20236Y1721998-08-0404 August 1998 Proposed Tech Specs Re Conversion to Improved STS Sections 3.1,3.2,3.5,3.9 & 4.0 ML20198D3201998-07-31031 July 1998 Rev 20 to Inservice Testing Program at Callaway Nuclear Plant ML20236W3721998-07-30030 July 1998 Proposed Tech Specs Revising Table 4.3-2 by Adding Table Notation to Clarify That Verification of Time Delays Associated W/Esfas Functional Units 8.a & 8.b Is Only Performed as Part of Channel Calibr ML20236J0821998-06-29029 June 1998 Proposed Tech Specs 3.7.1.7,4.7.1.7.1,4.7.1.7.2 & Bases 3/4.7.1.7 Revising to Address All Four Atmospheric Steam Dump Lines ML20236E9651998-06-26026 June 1998 Proposed Tech Specs Pages Re Conversion to Improved STS, Section 3.6 ML20216F3791998-03-0909 March 1998 Proposed Tech Specs SR 3/4.5.2b.1 Adding Clarification in Regard to Venting ECCS Pump Casings & Accessible Discharge Piping High Points ML20195B5651998-03-0202 March 1998 Rev 22 to QC Procedure QCP-ZZ-03003, Matl Receipt Insp ML20217P8161998-02-23023 February 1998 Proposed Tech Specs Replacement Page B 3.8-34 Re AC Sources Shutdown ML20198T3521998-01-16016 January 1998 Proposed Tech Specs 3/4.3,revising Ms & Feedwater Isolation Sys Slave Relay Surveillance from Quarterly Actuation Logic Test to Monthly Actuation Logic Test on Staggered Test Basis ML20197D6461997-12-16016 December 1997 Proposed Tech Specs Table Revising Lift Setting Tolerance for Main Steam Line Safety Valves ML20199B4261997-11-10010 November 1997 Proposed Tech Specs Re Page 5 of 8 for FW Isolation Changes ML20198P3361997-10-31031 October 1997 Proposed Tech Specs Reducing Repeated Alarms,Rod Blocks & Partial Reactor Trips That Continue to Manifest,During Beginning of Cycle Operation Following Refueling Outages ML20198P4141997-10-31031 October 1997 Proposed Tech Specs,Revising ESFAS Functional Unit 6.f, Loss of Offsite Power-Start Turbine-Driven Pump, in Tables 3.3-3,3.3-4 & 4.3-2 ML20217B3261997-10-22022 October 1997 Procedure MPE-ZZ-QY128, Operational Test Sequence of 4.16KV Diesel Generator NE02 Air Circuit Breaker 152NB0211 ULNRC-03664, Proposed Tech Specs 3/4.4.9 Re Pressure/Temp Limits1997-10-17017 October 1997 Proposed Tech Specs 3/4.4.9 Re Pressure/Temp Limits ML20217B3001997-09-14014 September 1997 Procedure ETP-NF-00001, MDAFW Pump (DPAL01A) Start Inhibit Circuit Test,Lsels Relay K1102 ML20217B3081997-09-0404 September 1997 Procedure ETP-BF-00002, Mdaew Pump (DPAL01B) Start Inhibit Circuit Test,Lsels Relay K4102 ML20217H8031997-08-0808 August 1997 Proposed Tech Specs 3/4.3 Re Instrumentation ML20210H2151997-08-0808 August 1997 Proposed TS Revising SRs 3/4.7.4, Essential Svc Water Sys by Removing Requirement to Perform SRs 4.7.4.b.1, 4.7.4.b.2 & 4.7.4.c During Shutdown ML20198F3411997-08-0808 August 1997 Proposed Tech Specs,Revising Table 3-7.2 to Specify That Lift Setting Tolerance for Main Steam Line Safety Valves Is +3/-1% as-found & +1% as-left.Table 2.2-1 Revised by Reducing Sensor Error for Pressurizer pressure-high Trip ML20198F3911997-08-0808 August 1997 Proposed Tech Specs Changes,Revising Feedwater Isolation ESFAS Functions in TS Tables 3.3-3,3.3-4 & 4.3-2 ML20195B5261997-05-20020 May 1997 Rev 6 to EDP-ZZ-03000, Containment Building Coatings ML20154Q1191997-05-15015 May 1997 Proposed Improved TS Section 3.7, Plant Sys ML20198J7301997-05-15015 May 1997 Proposed Conversion to ITS Sections 1.0,3.1,3.2,3.3,3.4,3.7, 3.9 & 5.0 for Plant ML20138B7421997-04-24024 April 1997 Proposed Tech Specs 6.0 Revising Title Senior Vice President,Nuclear to Vice President & Chief Nuclear Officer ML20141D9331997-04-14014 April 1997 Rev 18 to Inservice Testing Program for Callaway Nuclear Plant ML20141C3401997-04-14014 April 1997 Rev 18 to CNP IST Program ML20137N6111997-04-0101 April 1997 Proposed Tech Specs Table 3.3-3 Re Engineered Safety Features Actuation Sys Instrumentation ML20195B5581997-03-11011 March 1997 Rev 12 to Matls Engineering Procedure WEP-ZZ-00015, Preparation of Procurement Documents ML20195B5491997-01-31031 January 1997 Rev 22 to Administrative Procedure APA-ZZ-00400, Procurement of Parts,Supplies,Matls & Svcs ML20135E7351996-12-11011 December 1996 Tests to Determine Ampacity Derating Factors for Electrical Conductors Installed in 1 & 4 Diameter Rigid Steel Conduits Encapsulated by KM1 Darmatt One H Replacement Matl ML20135E7391996-12-11011 December 1996 Tests to Determine Ampacity Derating Factors for Electrical Conductors Installed in 1 & 4 Diameter Rigid Steel Conduits Encapsulated by KM1 Darmatt Three H Replacement Matl ML20135E7431996-12-11011 December 1996 Test to Determine Ampacity Derating Factor for Electrical Conductors Installed in 600mm X 101mm X 3650mm Long Cable Tray Encapsulated by KM1 Darmatt Three H Replacement Matl ML20140G2331996-10-31031 October 1996 Rev 6 to Callaway Plant Offsite Dose Calculation Manual ML20217B2951996-10-0303 October 1996 Procedure ISP-SA-2413A, Diesel Generator & Sequencer Testing (Train a) ML20117K6431996-09-0505 September 1996 Proposed Tech Specs,Revising TS 3/4.4 Re RCS 1999-09-08
[Table view] |
Text
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4 ULNRC-2756 ,
6 ATTACHMENT 1 TECHNICAL SPECIFICATION CHANGES 9302030025 930127
. hDR ADOCK 05000483 PDR
.. g ADMINISTRATIVE CDC ROLS 6.2.3 INDEPENDENT SAFETY ENS!NEERING GROUP (ISEG}.
FUNCTION 6.2.3.1 The ISEG shall function to examine plant operating characteristics, NRC issuances, industry advisories, REPORTABLE EVENTS and other sources of plant design and operating experience infomation, including plants of similar design, which may indicate areas for improving plant safety. The ISEG shall make detailed recomendations for revised procedures, equipment modifications, maintenance activities, operations activities or other means of improving plant safety to the Manager, Nuclear Safety and Emergency Preparedness and the Manager, Callaway Plant.
COMPOSITION 6.2.3.2 The ISEG shall be composed of at least five, dedicated, full-time engineers located on site. Each shall have a bachelor's degree in engineering or related science and at least 2 years professional level experience in his field.
RESPONSIBILITIES 6.2.3.3 The ISEG shall be responsible for maintaining surveillance of plant activities to provide independent verification
- that these activities are performed correctly and that human errors are reduced as much as practical. .
RECORDS 6.2.3.4 Records of activities performed by the ISEG shall be prepared, maintained, and forwarded each calendar month to the Manager Nuclear Safety and Emergency
) Preparedness and the Manager, Callaway Plant.
6.2.4 SHIFT TECHNICAL ADVISOR The Shift Technical Advisor (STA)** shall provide technical support to the Shif t Supervisor in the areas of thermal hydraulics, reactor engineering and plant analysis with regard to the safe operation of the unit.
6.3 UNIT STAFF OUALIFICATIONS
- d 6.3.1 Each member of the unit staff shall meet or exceed the minimum qualifica.
tions of ANSI /ANS 3.1-1978 with the following exceptions:
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w 6.3.1.1 Shift Supervisors, Operating Supervisors Reactor Operators, and Shift S Technical Advisors shall meet or exceed the qualifications of ANSI /ANS 3.1-1981
~K.T .o as endorsed by Reg. Guide 1.8, Revision 2, with the same exceptions as contained g ~$ in the current revision to the Operator Licensing Examiner Standarcs NUREG-1021, i
ES-202.
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! Q c;# icction. vi h%uie;ury Ga de i.a. 3r.g e w er H75, im c Rcd e:icn Pro v __
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'Not respons1 Die f or sign-of f function.
! "The STA position shall be manned in MDDES 1, 2, 3 and 4 unless the Shif t Supervisor or the individual with a Senior Operator license meets the qualifi-cations for the SIA as required by the NRC.
j I
CALLAWAY - UNIT 1 6-6 Amendment No. 60 i
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., ULNRC 2756 : I I
i Insert A i G.3.1.2 The Superintendent, Health Physics, the Suoerviso n :
liealth Physics, Technical Support. or the Supervisor. Health !
EhyEics. Operations (who) shall meet or exceed the qualificetions of USNRC Regulatory Guide 1.8, Septerrber 1975, for a' Radiation Protection Manager. The Radiation Protection Manaaer will b_e ;
desionated by the Plant Manauer. .
i (Note: Additions are underlined;. deletions are bracketed.) -
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ADMINISTRATIVE CONTROLS 0.2.3 INDEPENpjNT SAFETY ENGINEERING GROUP (ISEG)
ERNCTION 6.2.3.1 The ISEG shall function to examino plant operating characteristics, NRC issuancos, industry advisorios, REPORTABLE EVENTS and other sourcos of plant design and operating experienco information, including plants of similar design, which may indicato areas for improving plant safety. The ISEG shall make detailed recommendations for revised procedures, equipment modifications, maintenanco activities, operations activities or other means of improving plant safety to the Manager, ,
Nuclear Safety and Emergency Preparednoss and the Manager, Callaway Plant.
COMERS 11LQfi 0.2.3.2 The ISEG shall be composed of at least five, dedicated, full-timo ongincors located on sito, Each shall have a bachelor's degreo in engineering or related selonco and at least 2 years professional lovel experience in his field.
1 RESPONSIBILLI[ES G.2.3.3 The ISEG shall be responsible for maintaining survoillance of plant activities to ;
provido indopondent verification' that those activities are performed correctly and that human orrors are reduce as much as practical, HECORDS 6.2.3.4 Records of activities porformed by the ISEG shall be prepared, rnaintainod, and forwarded each calendar month to the Managor, Nuclear Safety and Emergoncy '
Preparodnoss and the Manager, Callaway Plant.
D.2.4 SHIFT TECHNICAL ADVISOR The Shif t Technical Advisor (STA) shall provido technical support to the Shif t Supervisor in the areas of thermal hydraulics, reactor engineering and plant analysis with regard to the safe operation of the unit.
L3 QNIT STAFF QUALIFICATIONS . _ _
6.3.1 Each member of the unit staff shall meet or exceed the minirnum qualifications of ANSI /ANS 3.1 1978 with the following exceptions:
0.3.1,1 Shif t Supervisors, Operating Supervisors, Reactor Operators, and Shif t Technical Advisors shall moet or exceed the qualifications of ANSI /ANS 3,1 1981 as ondorsed by Reg. Guido 1.8, Revision 2, with the same exceptions as contained in the current revision to the Operator Licensing Examiner Standards, NUREG-1021, ES 202.
6.3.1.2 The Superintendent, Health Physics, the Supervisor, Health Physics, Technical Support, or the Suporvisor, Health Physics, Operations shall meet or excoed tho qualifications of USNRC Regulatory Guido 1.8, September 197S, for a Radiation Protection Manager. The Radiation Protection Manager will be designated by the Plant Manager.
'Not responsibio for sign-off function.
- 'The STA position shall be manned in MODES 1,2,3 and 4 unless the Shift Supervisor or the individual with a Senior Operator license moots the qualifications for tho STA as required by the NRC.
CALLAWAY - UNIT 1. 6-6 Amendment No. 60
. . = _
4
- ULNRC- 27$6 I
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ATTACIIMENT 2 I l
SAFETY EVALUATION i i
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. ULNRC 2756
. Attachment 2
- Page 1 of 1 SAFETY RyhLUJ1TlDJ{
This amendment application requesto a revision to Technical specification 6.3.1.2 to allow any one of three nanagement personnel within the llealth Physics department, i.e., the Superintendent, llealth Physics, the Supervisor, Health Physics, Technical Support, or the Supervisor, Health Physics, Operations, to be designated as the Radiation Protection Manager as long as that person meets or exceeds the qualifications of USNRC Regulatory Guide 1.8, September 1975, for a Radiation Protection Manager ao clarified in NUREG/CR-5569, " Health Physics Positions Data Base," May 1992. The Radiation Protection Manager will be designated by the Plant Manager.
The proposed change to the Technical Specifications does not --
involve an unreviewed safety question because operation of the Callaway Plant with this change would not:
- 1. Increase the probability of occurrence or consequences of an accident or malfunction of equipment important to safety previously evaluated in the safety analysis report.
The proposed change does not affect accident initietors or assumptions. The radiological consequences of any accident previously evaluated remain uncnanged.
- 2. Create the possibility for an accident or malfunction of a different type than any previously evaluated in the safety analysis report.
The proposed change does not create any new accident initiators nor involve any modifications or changes in the plant.
- 3. Reduce the margin of safety as defined in the basis for any technical specification.
The proposed change does not affect any safety limits or boundary or tystem perf ormance.
This change does not reduce management control of the Callaway Plant radiation protection program nor affect the potential for exposures vf persons to radiation. The proposed change does not reduce the overall base of experience at the Callaway Plant nor the commitment to minimum qualifications. Callaway Plant personnel will continue to have the training, experience, and expertise necessary to recognize, analyze, assess, evaluate, and effectively respond to plant transients or other abnormal events.
Given the above discussions, as well as those presented in the Significant Hazards Consideration, the proposed cr.ange does not adversely affect or endanger the health or safety of the general public or involve a significant safety hazard.
1
. - ULNRC- 2756 ATTACHMENT 3 '
SIGNIFICANT HAZARDS EVALUATION W.
m_ __--_.__-__ _____________._._______ ___m _.m___________.______-_______..______________m. _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _
? :-.-- ULNRC- 2756
... -Attachment 3- -
E Page 1 of 11 l I
-SIGNIFICANT'HAZARDSfEV.1LUATION This amendment application requestsLa-revision--to? Technical 1
[
Specification'6.3,1~.2Lto allow any one of three_ management ;
personnelLwithin the' Health' Physics department, i.e., _the Superintendent, Health: Physics, the= Supervisor,L Health-Physics,:
j
-Technical' Support,-or the Supervisor,JHealth Physics, 0perations; to be designated as the' Radiation Protection Manager as long:as that person meets or exceeds the qualifications ofLUSNRCL '
Regulatory Guide 1.8,_ September:1975, for-a-Radiation ~ Protection Manager. _The Radiation Protection Manager will be designated by the Plant Manager.
The proposed change to Technical Specifications--does not-involve a significant hazards consideration because operationLof the Callaway Plant with this change would not:
1.- Involve a significant increase in the probability 'ori coneequences of an accident previously evaluated.
The change does not affect accident initiators or assumptions. The radiological' consequences of any-accident previously evaluated remain unchanged.
- 2. Create _the possibility-of a new or different kind.of accident from any previously evaluated.
The proposed change does not create any new accident initiators nor involve any modifications or changes-in-the 4 plant.
- 3. Involve a significant reduction in a margin of safety.
The proposed change will not affect any safety limits.or boundary or system performance.
This change does not reduce management: control of the1Callaway -
Plant radiation protection program nor affect'the_ potential _for exposures of persons to radiation. The-proposed change does not reduce the overall base of experience at the _Callaway Plant. nor: ,
the commitment to minimum qualifications. ~Callaway PlantL personnel will continue to have'the training,iexperience,fand expertise necessary to. recognize, analyze,- assess,_ evaluate, and effectively respond.to plant transients or other abnormal events.
, As discussed above, the proposed change does not involve a:
significant increase in.the probability or consequences of an accident-previously evaluated, create the possibility-of a new'or -
different kind of accident:from any previously evaluated, or:
result in a-significant reduction in a margin of safety.
Therefore, it has been determined that the proposed change does not involve a significant hazards consideration.
a
- ULNRC-2756 ATTACHMENT 4 EtNIRONMENTAL CONSIDERATION I
. ULNRC- 2756
. Attachment 4 Page 1 of 1 ENVIRONMENTAla CONSIDERATION This amendment application requests a revision to Technical Specification 6,3.1.2 to allow any one of three management personnel within the Health Physics department, i.e., the Superintendent, Health Physics, the Supervisor, Health Physics, Technical Support, or the Supervisor, Health Physics, Operations, to be designated as the Radiation Protection Manager as long as that person meets or exceeds the qualifications of USNRC Regulatory Guide 1.8, September 1975, for a Radiation Protection Manager. The Radiation Protection Manager will be designated by the Plant Manager.
The proposed amendment involves a change to the administrative controls on plant personnel located within the restricted area as defined in 10CFR20. Union Electric has determined that the proposed amendment does not involve:
- 1) A significant hazard consideration, as discussed in Attachment 3 of this amendment application;
- 2) A significant change in the types or significant increase in the amounts of any effluents that may be released offsite;
- 3) A significant increase in individual or cumulative occupational radiation exposure.
Accordingly, the proposed amendment meets the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22 (c) (9) . Pursuant to 10 CFR 51.22 (b) no environmental impact statement or environmental assessment need be prepared in connection with the issuance of this amendment.
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