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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
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ATTACHMENT I to JPN-85-14 PROPOSED TECHNICAL SPECIFICATION CHANGES RELATED TO SAFETY REVIEW C0letITTEE ORGANIZATION CHANGES (JPTS-84-19)
NEW YORK POWER AUTHORITY JAhES A. FITZPATRICK NUCLEAR POWER PLANT DOCKET No. 50-333 DPR-59 February 22 , 1985 l
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'8502280343 850222 PDR ADOCK 05000333 p PDR
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s (B) Alternates Alternative members shall be appointed in writing by the PORC Chairman to serve on a temporary basis; however, no more than two alternates shall participate in PORC activities at any one time.
(C) Meeting Frequency Meetings will be called by the Chairman as the occasions for review or investigation arise. Meetings will be no less frequent than once a month.
(D) Quorum The Chairman or Vice Chairman and four members, including designated alternates, shall constitute a quorum.
(E) Responsibilities
- 1. Review plant procedures, and changes thereto, required by Specification 6.8.
- 2. Review proposed tests and experiments that affect nuclear safety.
- 3. Review proposed changes to the Operating License and Technical Specifications.
- 4. Review proposed changes or modifications to plant systems or equipment that affect nuclear safety.
- 5. Investigate violations of the Technical Specifications and prepare and forward a report covering evaluation and recommendations to prevent recurrence to the Resident Manager, who will forward the report to the Manager -
l Nuclear Operations and to the Chairman of the Safety Review Committee.
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l 6. Review plant operations to detect potential safety hazards.
- 7. Review the Security Plan (including the Safeguards Contingency Plan) and implementing procedures annually.
l 249 I- Amendment No. 22, 57 l
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- 8. Review the Emergency Plan and implementing procedures annually.
1 9. Perform special review and/or investigations at the request of the Resident Manager. i
- 10. Review of those reportable occurrences requiring 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> notification to the NRC, in accordance with Specification 6.9.
(F) Authority The PORC shall function to advise the Resident Manager on all matters related to nuclear safety and environmental operations.
The PORC shall recommend approval or disapproval to the Resident Manager of those items considered in 6.5 1E (1) through (4) and determina if items considered in 6.5 1E (1) through (5) constitute
- unreviewed s_fety questions, as defined in 10 CFR 50.59.
In the event of a disagreement between the PORC and the Resident Manager, the Chairman of the SRC and the Executive Vice President -
Nuclear Generation, or their designated alternates, shall be notified within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> and written notification provided on the next business day; however, the Resident Manager shall have responsibility for resolution of such disagreement pursuant to Section 6.1.
(G) Records i Minutes of all meetings of the PORC shall be recorded and numbered. _ Copies will be retained in file. Copies will be forwarded to the Chairman of th6 SRC and the Executive Vice President-Nuclear Generation.
(H) Procedures conduct of the PORC and the mechanism for implementation of its responsibilities and authority are defined in the pertinent Administrative Procedures, s 6.5.2 SAFETY REVIEW CORGIITTEE (SRC) i FUNCTION t
6.5.2.1 The SRC shall function to provide independent review and audit of designated activities in the creas of:
- a. Nuclear power plant operations
- b. Nuclear engineering
- c. Chemistry and radiochemistry
- d. Metallurgy
- e. Instrumentation and control Amendment No. 50, 78, 250
. _ _ _ _ , ~ - _ _ ._ _ ..,._._ _ ._ _ _,. _ _ __ _ ,,,,_,___ _ _ _._ _ __
e- -
- f. Radiological safety
- s. Mechanical engineering
. h. Electrical engineering
- 1. Administrative controls and quality assurance practices J. Environment
- k. Civil / Structural Engineering
- 1. Nuclear Licensing.
- m. Emergency Planning
- n. Other appropriate fields associated with the unique characteristics of a nuclear power plant MEMBERSHIP T 6.5.2.2 The SRC shall be composed of the followic5 voting members:
Chairman: Manager-Nuclear Safety Evaluation Vice-Chairman: Director-Quality Assurance !
Member: - Vice President Nuclear Support-BWR Member: Vice President Nuclear Support-PWR Member: Vice President-Generic Nuclear Support Member: Vice President-Design and Analysis Member:. Resident Manager-IP3 Member: Resident Manager-JAF Member: Consultant
, ALTERNATES 6.5.2.3 All alternate members shall be appointed in writing by the ,
SRC Chairman; however, no more than two alternates shall participate as voting members in SEC activities at any one time, s
CONSULTANTS 6.5.2.4 Consultants shall be utilized as determined by the SRC
_ Chairman to provide expert advice to the SRC.
MEETING FREQUENCY _, ,
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6.5.2.5 The SRC shall meet at least once per calendar quarter
! during the initial year of facility operation following initial fuel loading and at least once per six months, thereafter.
Amendment No. 50, 60, 65, 78, L
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- c. The results of actions taken to correct deficiencies occurring in facility equipment, structures, systems or method of operation that affect nuclear safety at least 3 '.- once per 6 months.
- d. The performance of activities required by the Operational Quality Assurance Program to meet the criteria of Appendix "B", 10 CFR 50, at least once per 24 months,
- e. The Facility Emergency Plan and implementing procedures at least once per 12 months.
- f. The Facility Security Plan (including Safeguard Contingency Plan) and implementing procedures'at'least oncc per 12 months.
- g. Any other area of facility operation considered appropriate by the SRC or the Executive Vice President-Nuclear Generation.
- h. The Facility Fire Protection Program and implementing procedures at least once per two years.
- i. An independent fire protection and loss prevention inspection and audit shall be performed sanually utilizing either qualified offsite licensee personnel or an outside g l fire protection firm.
I j. An inspection and audit of the fire protection and loss prevention program shall be perfoceed by an outside qualified fire consultant at intervals no greater than 3 i _
years, i AUTHORITY l
6.5.2.9 The SRC shall report to and advise the Executive Vice President-Nuclear Generation on those areas of responsibility specified in Section 6.5.2.7 and 6.5.2.8 s
RECORDS l 6.5.2.10 Records will be maintained in accordance with ANSI 18.7-1972. The following shall be prepared, approved and distributed as indicated below:
l-I a. Minutes of each SEC meeting shall be prepared, approved and i forwarded to the Executive Vice President-Nuclear I Generation within 14 days after the date of the meeting.
l b. Reports of review encompassed by Section 6.5.2.7 above l shall be prepared, approved and forwarded to the Executive Vice President-Nuclear Generation within 14 days following completion of the review.
l
- c. Audit reports encompassed by Section 6.5.2.8 above, shall be forwarded to the Executive Vice President-Nuclear Generation and to the management positions responsible for
~ the areas audited within 30 days after completion of the audit.
. Amendment No. 50, 60, 65, j 252a
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%- ATTACHMENT II to JPN-85-14 SAFETY EVALUATION RELATED TO SAFETY REVIEW COMMITTEE ORGANIZATION CHANGES (JPTS-84-19)
February 22 , 1985 NEW YORK POWER AUTHORITY JAMES A FITZPATRICK NUCLEAR POWER PLANT DOCKET NO. 50-333 DPR-59 i
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- Section I - Description of the Proposed Channes This safety evaluation considers the effects of the reorganization
- of the Authority's Safety Review Committee (SRC) as described below. I The Committee membership will be changed to include the next-to-highest level management in the Nuclear Generation, ,
Engineering and Quality Assurance and Reliability Departments. The l Directors of Mechanical, Electrical Nuclear, Civil / Structural, and l Piping and Process in the Design and Analysis Section of the !
Engineering Department will be replaced by the Vice President-Design and Analysis. The Managers of Radiological Health !
and Chemistry and Operational Analysis and Training in the Nuclear Generation Department will be replaced by the Vice President-Generic Nuclear Support. The Director of Environmental Programs in the Engineering Department will no longer be a member l of the Committee.
The Resident Managers for the Indian Point 3 and James A.
FitzPatrick facilities will be included as voting members of the Safety Review Committee. Previously, these individuals were non-voting members. Also, the consultant to the Safety Review Committee will be included as a voting member of the Committee.
Previously, this individual was an alternate voting member.
The Consultant may be either an individual under contract to NYPA or a regular, full-time employee of NYPA assigned by the SRC chairman. At a meeting, a regular, full-time employee may serve as a Consultant, even though a different individual is under contract as a Consultant to the SRC at that time.
These changes in the committee membership reduce the Committee to nine (9) voting members.
In addition references to the Senior Vice President are changed to Executive Vice President, and typographical corrections are made on page 252a.
The change on page 249 is editorial in nature.
Section II - Purpose of the Proposed Channes The Executive Vice President-Nuclear Generation has decided to increase senior management involvement and attention to the safe operation of the FitzPatrick plant. These proposed changes to the SRC membership serve to accomplish this objective.
Section III - Impact Of The Proposed Channes The SRC's responsibility for independent review and audit of the FitzPatrick plant to assure safe operation of the FitzPatrick plant remains unchanged by the proposed membership changes.
The duties and responsibilities of the Chairman of the SRC are not affected by this reorganization of the Committee. The Chairman shall continue to report directly to the Executive Vice President-Nuclear Generation, j I
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The 8RC Program as described in the FitzPatrick FSAR and Technical 1 Specifications is similar to that described in the NRC's Standard
- Technical Specifications (STS) (see Reference 3). The basic difference is the Authority's commitment that the Committee membership "shall collectively have the competence required to review problems in the following areas." [ Emphasis added) The STS allow the Committee "to provide independent review and audit of designated activities in the areas." (Baphasis added) The changes proposed are consistent with the intent of the STS. Moreover, the
- Committee members replaced from the Engineering and Nuclear l
Generation Departments will be the alternates to the new voting members from the same Departments.
The inclusion of the Resident Managers as voting members is 4
consistent with the FitzPatrick Plant's current Technical i S,(ecifications (and the STS) which state that "No more than a minority of the quorum shall have a direct line responsibility for the operation of the plant." The sentence in the FSAR that "The acabers of this committee do not have direct line responsibility for the operation of the plant" is merely a statement of fact of the present Committee membership, rather than a commitment.
The inclusion of the Consultant as a voting member is consistent
! with the current practice of the Chairman to consider that
, individual as one of the two alternates allowed "as voting members in SRC activities at any one time" under the current Technical Specifications (and the STS).
f The Director of Environmental Programs will no longer be a member i of the Committee; however, that individual shall provide expert advice to the SRC in matters relating to the environment as allowed under the current Technical Specifications (and the STS).
These proposed changes to the Technical Specifications can be classified as not likely to involve significant safety hazard considerations since they constitute pucely administrative changes as cited in (i) of " Examples of Amendments that are considered not likely to Involve Significant Hazards Considerations...," Federal Register, Vol 48, No. 67, April 6, 1983.
l Additionally, these proposed changes do not involve significant
! hazards considerations since they would not:
! (1) Involve a significant increase in the probability or consequences of an accident previously evaluated; or (2) Create the possibility of a new or different kind of accident from any accident previously evaluated; or (3) Involve a significant reduction in a margin of safety.
Section IV - Implementation of the Proposed Channes The char.ges, as proposed, do not adversely impact the ALARA.
Security or Fire Protection programs at FitzPatrick, nor do they impact the environment.
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e Section V - Conclusion The incorporation of these proposed changes:
(1) will not increase the probability nor the consequences of an accident or malfunction of equipment important to safety as previously evaluated in the Safety Analysis Report; (2) will not increase the probability of an accident or malfunction of any type different from those evaluated previously in the Safety Analysis Report; (3) will not reduce the margin of safety as defined in the basis for any Technical Specification; (4) does not constitute an unreviewed safety question as defined in 10 CFR 50.59; and (5) involves no significant hazards considerations as defined in 10 CFR 50.92.
Section V - References
- 1. James A. FitzPatrick FSAR, Section 13.10.1.3 (Safety Review Committee)
- 2. James A. FitzPatrick Facility Operating License, Appendix A (Technical Specifications), Section 6.5.2 Safety Review Committee
- 3. NUREG-0123, Revision 3, Standard Technical Specifications for General Electric Boiling Water Reactors, Section 6.5.2 Company Nuclear Review and Audit Group (CNRAG) l 4
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