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Category:TECHNICAL SPECIFICATIONS
MONTHYEARML20217G4341999-10-14014 October 1999 Rev C to Proposed TS Change Re Conversion to Improved Standard TSs ML20217G5121999-10-14014 October 1999 Revised Page 285 to TS Re Allowed Containment Leakage Rate, Changing Rev 0 to Rev 1 ML20216J3871999-09-29029 September 1999 Proposed Tech Specs Pages,Extending LCO Allowable Out of Service Time for RHRSW Sys from 7 Days to 11 Days with Special Conditions to Allow for Installation of Mod to Division a RHRSW Strainer ML20196F6071999-06-22022 June 1999 Proposed Tech Specs Re pressure-temp Limits ML20195B8831999-06-0101 June 1999 Proposed Tech Specs,Converting to Improved Std TS ML20206U1421999-05-19019 May 1999 Proposed Tech Specs Revising AOTs for Single Inoperable EDG ML20205K1091999-04-0505 April 1999 Proposed Tech Specs,Removing Position Title of General Manager from Sections & Will State That If Site Executive Officer Is Unavailable,Responsibilities Will Be Delegated to Another Staff Member,In Writing ML20199H3611999-01-15015 January 1999 Proposed Tech Specs Table 4.1-2 Re Local Power Range Monitor (LPRM) Signal Calibr ML20198M8321998-12-30030 December 1998 Proposed Tech Specs Page 258f Re Configuration Risk Mgt Program ML20197G6181998-12-0303 December 1998 Proposed Tech Specs Reducing Size of Spent Fuel Rack Assembly N3 from 8x13 Cells to 8x12 Cells & Deleting Proposed Inclusion of Fuel Pool Water Level Inadvertent Drainage Into Amend ML20154M7181998-10-16016 October 1998 Proposed Corrected Tech Specs Section 3/4.6.C,relocating Portions of Reactor Coolant Sys - Coolant Chemistry ML20236X8041998-08-0303 August 1998 Proposed Tech Specs Section 1.1.A Re SLMCPR to Be Applicable During Cycle 14 ML20236M6231998-07-10010 July 1998 Proposed Tech Specs Pages Re Amend to Relocate TS 3/4.6.C, RCS - Coolant Chemistry, from TS to UFSAR & Applicable Plant Procedures Controlled by 10CFR50.59 Process ML20249B1631998-06-16016 June 1998 Proposed Tech Specs Re Relocation of Safety Review Committee Review & Audit Requirements ML20236L2931998-06-0707 June 1998 Proposed Tech Specs Section 3.5.b.1 Re Main Condenser Steam Jet Air Ejector & Table 3.10-1 Re Radiation Monitoring Sys That Initiates &/Or Isolates Sys ML20217K0391998-03-30030 March 1998 Proposed Tech Specs Changing Interval of Selected LSFT from Semiannually to Once Per 24 Months & Revising Definition for LSFT to Be Consistent w/NUREG-1433 ML20247F7981998-02-26026 February 1998 Proposed Tech Specs Re Allowed Containment Leakage Rate ML20202G8841998-02-0606 February 1998 Revised Proposed TS Pages,Revising Allowed Outage Times for 4kV Emergency Bus Trip Functions & Replace Generic Actions for Inoperable Instrument Channels w/function-specific Actions ML20202D4021998-02-0606 February 1998 Proposed Tech Specs Revising RPS Normal Supply Electrical Protection Assembly Undervoltage Trip Setpoint as Result of Reanalysis Based on Most Limiting Min Voltage Requirements of Applied Loads ML20202D5621998-02-0606 February 1998 Proposed Tech Specs Allowing RCS Pressure Tests to Be Performed While Remaining in Cold Shutdown Mode ML20203J6971997-12-12012 December 1997 Proposed Tech Specs,Revising Administrative Controls for Normal Working Hours of Plant Staff Who Perform Safety Related Functions ML20217J0021997-10-14014 October 1997 Proposed TS Pages Re Changes to Design Features Section, Including Revised Limits for Fuel Storage ML20217G3071997-10-0808 October 1997 Proposed Tech Specs Re Distribution of Inoperable Control Rods ML20211H0801997-09-26026 September 1997 Revised Proposed TS Changes to ASME Section XI, Surveillance Testing ML20236N7061997-09-0909 September 1997 Proposed Tech Specs,Describing Licensee'S Configuration Risk Mgt Program Which Supports Rev of Allowed out-of-svc Times for Single Inoperable EDGs to Accommodate on-line Maint of EDGs ML20140D8131997-04-14014 April 1997 Proposed Tech Specs Re SRC Audit Requirements & Mgt Title Change ML20135B1921996-11-26026 November 1996 Proposed Tech Specs,Requesting That Snubber Operability, Surveillance & Records Requirements in TS Be Relocated to Plant Controlled Documents ML20134M1751996-11-20020 November 1996 Proposed Tech Specs Reflecting Interposed Amend That Was Issued,Updating References to Repts on TS Pp & Changing Rev Bars on Previously Submitted Update Pp Which Were Erroneously Positioned on Pp ML20149L7191996-11-0808 November 1996 Proposed Tech Specs Re Min Critical Power Ratio Safety Limit ML20129G0091996-10-23023 October 1996 Proposed Tech Specs Re Page 134 Deleted Under Amend 236 & Remain Deleted ML20128Q7441996-10-11011 October 1996 Proposed Tech Specs Re Extension of Instrumentation & Miscellanous Surveillance Test to Accommodate 24 Month Cycles ML20115G0641996-07-12012 July 1996 Proposed Tech Specs Re Cycle 12 Min Critical Power Ratio Safety Limit ML20113B6511996-06-20020 June 1996 Proposed Tech Specs Re Option B to 10CFR50,App J for Primary Containment Leakage Rate Testing Program ML20112D1531996-05-30030 May 1996 Proposed Tech Specs,Revising Minimum Critical Power Ratio Safety Limit & Associated Basis ML20112D5711996-05-30030 May 1996 Proposed Tech Specs,Eliminating Selected Response Time Testing Requirements ML20112D2721996-05-30030 May 1996 Proposed Tech Specs Re ATWS Recirculation Pump Trip Instrumentation Requirements JPN-96-023, Proposed Tech Specs Re Deletion of Requirement for PORC to Review Fire Protection Program & Implementing Procedures. Addl Deletion of Insp & Audit Requirements of Specs 6.14.A & 6.14.B1996-05-16016 May 1996 Proposed Tech Specs Re Deletion of Requirement for PORC to Review Fire Protection Program & Implementing Procedures. Addl Deletion of Insp & Audit Requirements of Specs 6.14.A & 6.14.B ML20108D1171996-04-24024 April 1996 Proposed Tech Specs,Supporting Adoption of Primary Containment Lrt Requirements of Option B to 10CFR50,App J & Clarifying Numerical Value of Allowable Containment Leakage Rate as 1.5% Per Day ML20107M4511996-04-24024 April 1996 Proposed Tech Specs 3.11.B/4.11.B Re Crescent Area Ventilation ML20101H6741996-03-27027 March 1996 Proposed Tech Specs,Supporting Adoption of Primary Containment Lrt Requirements of Option B to 10CFR50,App J at Plant & Clarifies Numerical Value of Allowable Containment Lrt as 1.5% Per Day ML20101H3821996-03-22022 March 1996 Proposed TS Table 3.2-2 Re Core & Containment Cooling Sys Initiation & Control Instrumentation Operability Requirements ML20101F8411996-03-22022 March 1996 Proposed Tech Specs,Implementing BWROG Option I-D long-term Solution for Thermal Hydraulic Stability ML20097A2271996-02-0101 February 1996 Proposed Tech Specs,Allowing RCS Pressure Tests to Be Performed While Remaining in Cold Shutdown Mode ML20100C2991996-01-25025 January 1996 Proposed Tech Specs Re EDGs Surveillance Testing ML20097J6691996-01-25025 January 1996 Proposed Tech Specs Re Extension of Instrumentation & Miscellaneous Surveillance Test Intervals to Accommodate 24- Month Operating Cycles ML20095F7091995-12-14014 December 1995 Proposed Tech Specs,Incorporating IST Requirements of Section XI of ASME Boiler & Pressure Vessel Code ML20094R6981995-11-30030 November 1995 Proposed Tech Specs,Extending Surveillance Test Intervals for SLC Sys to Support 24 Month Operating Cycles ML20094B6641995-10-25025 October 1995 Proposed Tech Specs Extending Containment Sys Surveillance Test Intervals to Accommodate 24 Month Operating Cycles ML20092H5401995-09-15015 September 1995 Proposed Tech Specs Extending Surveillance Test Intervals for Auxiliary Electrical Sys to Support 24 Month Operating Cycles ML20086P6561995-07-21021 July 1995 Proposed Tech Specs Re Replacement of title-specific List of PORC Members W/More General Statement of Membership Requirements 1999-09-29
[Table view] Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML20217G5121999-10-14014 October 1999 Revised Page 285 to TS Re Allowed Containment Leakage Rate, Changing Rev 0 to Rev 1 ML20217G4341999-10-14014 October 1999 Rev C to Proposed TS Change Re Conversion to Improved Standard TSs ML20217D9961999-10-13013 October 1999 Risk-Informed ISI Program Plan for Ja Fitzpatrick ML20216J3871999-09-29029 September 1999 Proposed Tech Specs Pages,Extending LCO Allowable Out of Service Time for RHRSW Sys from 7 Days to 11 Days with Special Conditions to Allow for Installation of Mod to Division a RHRSW Strainer ML20196F6071999-06-22022 June 1999 Proposed Tech Specs Re pressure-temp Limits ML20195B8831999-06-0101 June 1999 Proposed Tech Specs,Converting to Improved Std TS ML20206U1421999-05-19019 May 1999 Proposed Tech Specs Revising AOTs for Single Inoperable EDG ML20205K1091999-04-0505 April 1999 Proposed Tech Specs,Removing Position Title of General Manager from Sections & Will State That If Site Executive Officer Is Unavailable,Responsibilities Will Be Delegated to Another Staff Member,In Writing ML20204B6321999-03-21021 March 1999 Plant Referenced Simulation Facility Four Year Performance Testing Rept ML20199H3611999-01-15015 January 1999 Proposed Tech Specs Table 4.1-2 Re Local Power Range Monitor (LPRM) Signal Calibr ML20206P0541998-12-31031 December 1998 Rev 3.2 to EDAMS/RADDOSE-V ML20198M8321998-12-30030 December 1998 Proposed Tech Specs Page 258f Re Configuration Risk Mgt Program ML20197G6181998-12-0303 December 1998 Proposed Tech Specs Reducing Size of Spent Fuel Rack Assembly N3 from 8x13 Cells to 8x12 Cells & Deleting Proposed Inclusion of Fuel Pool Water Level Inadvertent Drainage Into Amend ML20154M7181998-10-16016 October 1998 Proposed Corrected Tech Specs Section 3/4.6.C,relocating Portions of Reactor Coolant Sys - Coolant Chemistry ML20155E7831998-09-15015 September 1998 Rev 2 to Ja FitzPatrick NPP IST Program for Pumps & Valves Third Interval Plan ML20236X8041998-08-0303 August 1998 Proposed Tech Specs Section 1.1.A Re SLMCPR to Be Applicable During Cycle 14 ML20236M6231998-07-10010 July 1998 Proposed Tech Specs Pages Re Amend to Relocate TS 3/4.6.C, RCS - Coolant Chemistry, from TS to UFSAR & Applicable Plant Procedures Controlled by 10CFR50.59 Process ML20249B1631998-06-16016 June 1998 Proposed Tech Specs Re Relocation of Safety Review Committee Review & Audit Requirements ML20236L2931998-06-0707 June 1998 Proposed Tech Specs Section 3.5.b.1 Re Main Condenser Steam Jet Air Ejector & Table 3.10-1 Re Radiation Monitoring Sys That Initiates &/Or Isolates Sys ML20217K0391998-03-30030 March 1998 Proposed Tech Specs Changing Interval of Selected LSFT from Semiannually to Once Per 24 Months & Revising Definition for LSFT to Be Consistent w/NUREG-1433 B110073, Rev 1 to GE-NE-B1100732-01, FitzPatrick Reactor Pressure Vessel Surveillance Matls Testing & Analysis Rept of 120 Degree Capsule at 13.4 Efpy1998-02-28028 February 1998 Rev 1 to GE-NE-B1100732-01, FitzPatrick Reactor Pressure Vessel Surveillance Matls Testing & Analysis Rept of 120 Degree Capsule at 13.4 Efpy ML20247F7981998-02-26026 February 1998 Proposed Tech Specs Re Allowed Containment Leakage Rate ML20202G8841998-02-0606 February 1998 Revised Proposed TS Pages,Revising Allowed Outage Times for 4kV Emergency Bus Trip Functions & Replace Generic Actions for Inoperable Instrument Channels w/function-specific Actions ML20202D4021998-02-0606 February 1998 Proposed Tech Specs Revising RPS Normal Supply Electrical Protection Assembly Undervoltage Trip Setpoint as Result of Reanalysis Based on Most Limiting Min Voltage Requirements of Applied Loads ML20202D5621998-02-0606 February 1998 Proposed Tech Specs Allowing RCS Pressure Tests to Be Performed While Remaining in Cold Shutdown Mode ML20199G5921998-01-0707 January 1998 Rev 0 to JAF-ISI-0003, Third ISI Interval,Ten-Yr ISI Plan ML20199G5661998-01-0606 January 1998 Rev 0 to JAF-ISI-0002, Third ISI Interval,Isi Program. W/28 Oversize Drawings ML20203J6971997-12-12012 December 1997 Proposed Tech Specs,Revising Administrative Controls for Normal Working Hours of Plant Staff Who Perform Safety Related Functions ML20217J0021997-10-14014 October 1997 Proposed TS Pages Re Changes to Design Features Section, Including Revised Limits for Fuel Storage ML20217G3071997-10-0808 October 1997 Proposed Tech Specs Re Distribution of Inoperable Control Rods ML20217K5841997-09-30030 September 1997 Rev 1 to Ja FitzPatrick Nuclear Power Plant IST Program for Pumps & Valves,Third Interval ML20211H0801997-09-26026 September 1997 Revised Proposed TS Changes to ASME Section XI, Surveillance Testing ML20236N7061997-09-0909 September 1997 Proposed Tech Specs,Describing Licensee'S Configuration Risk Mgt Program Which Supports Rev of Allowed out-of-svc Times for Single Inoperable EDGs to Accommodate on-line Maint of EDGs ML20149G2571997-07-14014 July 1997 JAFNPP ISI Program Relief Requests for 2nd Ten-Yr Interval Closeout ML20140D8131997-04-14014 April 1997 Proposed Tech Specs Re SRC Audit Requirements & Mgt Title Change ML20198G7211997-04-0303 April 1997 Hot Rolled XM-19 Stainless Steel Core Shroud Tie-Rod Matl - Crevice Corrosion Investigation ML20136H3771997-03-11011 March 1997 Rev 0 to Power Uprate Startup Test Rept for Cycle 13 ML20135B1921996-11-26026 November 1996 Proposed Tech Specs,Requesting That Snubber Operability, Surveillance & Records Requirements in TS Be Relocated to Plant Controlled Documents ML20134M1751996-11-20020 November 1996 Proposed Tech Specs Reflecting Interposed Amend That Was Issued,Updating References to Repts on TS Pp & Changing Rev Bars on Previously Submitted Update Pp Which Were Erroneously Positioned on Pp ML20149L7191996-11-0808 November 1996 Proposed Tech Specs Re Min Critical Power Ratio Safety Limit ML20129G0091996-10-23023 October 1996 Proposed Tech Specs Re Page 134 Deleted Under Amend 236 & Remain Deleted ML20128Q7441996-10-11011 October 1996 Proposed Tech Specs Re Extension of Instrumentation & Miscellanous Surveillance Test to Accommodate 24 Month Cycles ML20135D0311996-07-31031 July 1996 Rev 4 to Radiological Effluent Controls & Offsite Dose Calculation Manual ML20115G0641996-07-12012 July 1996 Proposed Tech Specs Re Cycle 12 Min Critical Power Ratio Safety Limit ML20113B6511996-06-20020 June 1996 Proposed Tech Specs Re Option B to 10CFR50,App J for Primary Containment Leakage Rate Testing Program ML20112D1531996-05-30030 May 1996 Proposed Tech Specs,Revising Minimum Critical Power Ratio Safety Limit & Associated Basis ML20112D2721996-05-30030 May 1996 Proposed Tech Specs Re ATWS Recirculation Pump Trip Instrumentation Requirements ML20112D5711996-05-30030 May 1996 Proposed Tech Specs,Eliminating Selected Response Time Testing Requirements JPN-96-023, Proposed Tech Specs Re Deletion of Requirement for PORC to Review Fire Protection Program & Implementing Procedures. Addl Deletion of Insp & Audit Requirements of Specs 6.14.A & 6.14.B1996-05-16016 May 1996 Proposed Tech Specs Re Deletion of Requirement for PORC to Review Fire Protection Program & Implementing Procedures. Addl Deletion of Insp & Audit Requirements of Specs 6.14.A & 6.14.B ML20108D1171996-04-24024 April 1996 Proposed Tech Specs,Supporting Adoption of Primary Containment Lrt Requirements of Option B to 10CFR50,App J & Clarifying Numerical Value of Allowable Containment Leakage Rate as 1.5% Per Day 1999-09-29
[Table view] |
Text
_ ~
ATTACHMENT-I TO JPN-86-30 l
s I
PROPOSED TECHNICAL SPECIFICATION CHANGES
! RELATED TO SEPARATE SHIFT TECHNICAL I
ADVISOR POSITION 4
l NEW YORK POWER AUTHORITY JAMES A. FITZPATRICK NUCLEAR POWER PLANT DOCKET NO. 50-333 DPR-59 8607210243 860711 PDR ADOCK 05000333 P PDR
JAFNPP TABLE OF CONTENTS (cont'd)
Page D. Emergency Service Water System 240 E. Intake Deicing Heaters 242 3.12 Fire Protection Systems 244a 5.0 Design Features 245 5.1 Site 245 5.2 Reactor 245 5.3 Reactor Pressure Vessel 245 5.4 Containment 245 l
5.5 Fuel Storage 245 5.6 Seismic Design 246 6.0 Administrative Controls 247 6.1 Responsibility 247 6.2 Plant Staff Organization 247 6.3 Plant Staff Qualifications 248 6.4 Retraining and Replacecent Training 243a l
6.5 Review and kadit 248a l
6.5.1 Plant Operating Review Committee (PORC) 24Sa 1
6.5.2 Safety Review Committee (SRC) 250 6.6 Reportable Event Action 253 6.7 Safety Limit Action 253 6.8 Procedures 253 6.9 Reporting Requirements 254a 6.10 Record Retention 254g 6.11 Radiation Protection Program 255 6.12 Industrial Security Program 258 6.13 Emergency Plan 258 6.14 Fire Protection Program 258 6.15 Environmental Qualification 258a Amendment No. /, g , 3[, [ , }[, g 111
- 6. In addition to items 1, 2 and 3 above, two additional operators 4 shall be readily available on site whenever the reactor is in other than cold shutdown. During cold shutdown, an additional operator shall be readily available on site.
- 7. An individual qualified in radiation protection procedures shall be on site when fuel is in the reactor.
- 8. In the event of illness or absenteeism up to two (2) hours is
' allowed to restore the shift crew or fire brigade to normal' complement.
I
! 9. A fire brigade of five (5) or more members shall be maintained l on site at all times. This excludes two (2) members of the minimum shift crew necessary for safe shutdown and any personnel
, required for other essential functions during a fire emergency.
- 10. A Shift Technical Advisor shall be on site and readily available to the control room except during the cold shutdown or refuel j mode.
j 6.3 PLANT STAFF QUALIFICATIONS i 6.3.1 The minimum qualifications with regard to educational background and i experience for plant staff positions shown in Fig 6.2-1 shall meet or
- exceed the minimum qualifications specified in ANSI N18.1-1971 for l
.! comparable positions except for the Radiological and Environmental j Services Superintendent, who shall meet or exceed the qualifications specified in Regulatory Guide 1.8, September, 1975.
} 6.3.2 The Shift Technical Advisor (STA) shall meet or exceed the minimum 4
requirements of either Option 1 (Combined SRO/STA Position) or
! Option 2 (Continued use of STA Position), as defined in the 2
Commission Policy Statement on Engineering Expertise on Shift, i
published in the October 28, 1985 Federal Register (50 FR 43621).
~
When invoking Option 1, the STA role may be filled by the Shift !
Supervisor or Assistant Shift Supervisor. (1) 1 6.3.3 Any deviations will be justified to the NRC prior to an individual's j
! filling of one of these positions.
) NOTE:
i (1) The 13 individuals who hold SRO licenses, and have completed the FitzPatrick Advanced Technical Training Program prior to I the issuance of this license amendment, shall be considered STA
- qualified under Option 1 of the Policy Statement.
t l
1 AmendmentNo.y[,%,7[,[
248 e
6.4 RETRAINING AND REPLACEMENT TRAINING A training program shall be maintained under the direction of the Training Coordinator to assure overall proficiency of the plant staff organization. It shall consist of both retraining and replacement training and shall meet or exceed the minimum requirements of Section 5.5 of ANSI N18.1-1971.
The retraining program shall not exceed periods two years in length with a curriculum designed to meet or exceed the requalification requirements of 10 CFR 55, Appendix A. In addition fire brigade training shall meet or exceed the requirements of NFPA 27-1975, except for fire brigade training sessions which shall be held at least quarterly. The effective date for implementation of fire brigade training is March 17, 1978.
6.5 REVIEW AND AUDIT Two seperate review groups for plant operations have been constituted. One of these, the plant Operating Review Committee (PORC), is an onsite review group. The other is an independent review and audit group, the offsite Safety Review Committee (SRC).
6.5.1 PLANT OPEFATING REVIEW COMMITTEE (PORC)
(A) Membership The PORC is comprised of the Resident Manager (Chairman),
Superintendent of Power (Vice Chairman), Operations Superintendent, Maintenance Superintendent. Technical Services Superintendent, Instrument and Control Superintendent, Radiological and Environmental Services Superintendent and Reactor Analyst. Special consultant to provide expert advice may be utilized when the nature of a particular problem dictates.
Amendment No. ;VI, 74, FI, M 248a
j FIGURE 6.2-1 i POWER AUTHORITY OF THE STATE OF NEW YORK d JAMES A. FITZPATRICK NUCLEAR POWER PLANT j
-?
= VICE PRESIDENT 3 RESIDENT MANAGER QUALITY ASSURANCE AND STAFF
'n PLANT OPERATING h REVIEW COMMITTEE .
SUPERINTENDENT OF POWER 1 AND STAFF l
l i i i i l MAINTENANCE OPERATIONS INST. & CONT. TECHNICAL TRAINING SUPT. QA SUPT.
SUPT. & STAFF SUPT. (SRO) SUPT. & STAFF SERVICES AND STAFF & STAFF L
AND STAFF SUPT. & STAFF REACTOR # SECURITY / SAFETY ANALYST RADIOLOGICAL & OFFICE FIRE PROTECTION SHIFT ENVIRONMENTAL MANAGER SUPT. & STAFF j SUPERVISOR (SRO) SERVICES SUPT.
a SHIFT AND STAFF TECHNICAL ----
ADVISOR
- Shift Technical Advisor (STA) role may be NUCLEAR CONTROL fulfilled by any individual meeting the OPERATOR (RO) qualification requirements of Section 6.3.2 1
I 3 (SRO) - Senior Reactor Operator AUXILIARY OPERATOR NUCLEAR OPERATOR (RO) - Reactor Operator i
j ATTACHMENT II TO JPN-86-30 1
1 ,
4 PROPOSED TECHNICAL SPECIFICATION CHANGES RELATED TO SEPARATE SHIFT TECHNICAL ADVISOR POSITION SAFETY EVALUATION f
l ll i
l NEli YORK POWER AUTHORITY j
, JAMES A. FITZPATRICK NUCLEAR POWER PLANT
! DOCKET NO. 50-333 DPR-59
\
l 4
?
}
I. Description of the Proposed Chances The proposed changes to the FitzPatrick Technical Specifications relate to the position of the Shift Technical Advisor (STA) in the operating shitt organization.
Specifically, on page 248, Section 6.3 is split into three paragraphs to read as follows:
"6.3 PLANT STAFF OUALIFICATIONS 6.3.1 The minimum qualifications with regard to educational background and experience for plant staff positions shown in Figure 6.2-1 shall meet or exceed the minimum
< qualifications specified in ANSI N18.1-1971 for comparable positions; except for the Radiological and Environmental Services Superintendent, who shall meet or exceed the qualifications specified in Regulatory Guide 1.8, September, 1975.
6.3.2 The Shift Technical Advisor (STA) shall meet or exceed the minimum requirements of either Option 1 (Combined SRO/STA Position) or Option 2, (Continued use of STA position) as defined in the Commission Policy Statement on Engineering Expertise on Shift, published in the October 28, 1985 Federal Register (50 FR 43621). When invoking Option 1, the STA role may be filled by the Shift Supervisor or Assistant Shift Supervisor. (1) 6.3.3 Any deviations will be justified to the NRC prior to an individual's filling of one of these positions.
Note:
(1) The 13 individuals who hold SRO licenses, and have completed the FitzPatrick Advanced Technical Training Program prior to the issuance of this license amendment, shall be considered STA qualified under Option 1 of the Policy Statement." '
The wording in Sections 6.3.1 and 6.3.3 is unchanged except that in two places ANSI NI8.1-1971 are replaced with ANSI N18.1-1971 to correct the typographical error. Section 6.4 and 6.5 are unchanged but are moved to a new page 248a. The Table of Contents is revised to show Sections 6.4 and 6.5 on page 248a. Section 6.3.2 and Note (1) are entirely new.
On page 260, Figure 6.2-1 is revised to show a pound sign and a note added to allow the STA role to be filled by any individual meeting the qualification requirements of Section 6.3.2.
II. Purpose of the Proposed Chances The pound sign and the note provide clarification concerning the qualification of personnel fulfilling the STA function and the use of dual role SRO/STA. .
1 l
l
III. Impact of the Proposed Chances In Reference 2, the Commission presented guidance for engineering and accident assessment expertihe on shift. This Policy Statement stated that the NRC "... prefers a combined SRO/STA position (Option 1)." The proposed changes to the FitzPatrick Technical in Specifications provide for the dual-role SRO/STA on shift accordance with the Commission Policy Statement. This change will enhance the operation of the plant by improving the level of knowledge and training of the shift complement. This amendment does not affect STA training program, but more definitively prescribes it by reference to the NUREG-0737 STA training criteria. "he policy statement will also assure a higher level of educational background for the STA requiring a bachelor's degree or more stringent means of demonstrating equivalency to the bachelor's degree. The use of dual role SRO/STA's does not reduce the margin of safety since engineering and accident assessment expertise on shift is maintained at its current level.
A footnote to Section 6.3.2 of the Technical Specifications, identifies licenses and thehave fact completed that thirteen the individuals who hold Technical FitzPatrick Advanced current SRO Training Program prior to the issuance of this amendment are considered qualified as STA's. Individuals are considered to have completed this training program upon completion of the classroom training and successful performance in all final examinations.
Receipt of a formal certificate for STA qualification is not This program necessary prior to the issuance of thisThe amendment.
Authority will maintain is described in References 3 and 4.
the option of using a separate degreed STA described in the Commission Policy Statement as Option 2.
IV. Implementation of the Proposed Chances The changes, as proposed, do not adversely impact the ALARA, Security or Fire Protection programs at FitzPatrick, nor do they impact the environment.
V. Evaluation of Hazards Considerations The proposed changes to the FitzPatrick Technical Specifications do not involve hardware or procedural changes to the plant.
Operation of the FitzPatrick plant in accordance with the proposed amendment would not involve a significant hazards concideration as defined in 10 CFR 50.92 since it would not:
(1) involve a significant increase in the probability or consequences of an accident previously evaluated because the change will not result in a decrease of expertise on shift.
The operations staff will be better prepared to mitigate the consequences of abnormal operating events for the following reasons:
The STA will meet a more stringent educational requirement by eliminating the option of demonstrating equivalency to a bachelor's degree.
1
. The training program for the STA is more definitively described in the revised Specification by the addition of a reference to NUREG 0737 training criteria.
. No change is made to the minimum shift complement.
The dual role SRO/STA is preferred by the Commission and does not result in a reduction in safety.
(2) create the possibility of a new or different kind of accident from any accident previously evaluated because the change has no impact on shift manning or required expertise on shift. Refer to (1) above. No new or different kind of accident can be created by more clearly describing the qualification of an STA or by combining the SRO and STA into a dual role.
(3) involve a significant reduction in margin of safety since the current level of engineering expertise on shift is maintained, and there is not change in shift manning requirements.
VI. Conclusion The changes, as proposed, do not constitute and unreviewed safety question as defined in 10 CFR 50.59, that is, they (a) will not increace the probability or the consequences of an accident or malfunction of equipment important to safety as evaluated previously in the Safety Analysis Report (SAR): (b) will not increase the possibility of an accident or malfunction of a type other than that evaluated previously in the SAR: (c) will not reduce ;he margin of safety as defined in the basis for any technical Specification: (d) does not constitute an unreviewed safety question; and (e) involves no significant hazards considerations, as defined in 10 CFR 50.92.
VII. References
- 1. James A. FitzPatrick FSAR
- 2. NRC Generic letter 86-04 " Policy Statement on Engineering Expertise on Shift" dated February 13, 1986.
- 3. NYPA letter. J. P. Bayne to D. B. Vassallo, dated September 7, 1984 (JPN-84-59).
- 4. NYPA letter, J. C. Brons to D. R. Muller, dated May 15, 1986 (JPN-86-23).