Similar Documents at Fermi |
---|
Category:TECHNICAL SPECIFICATIONS
MONTHYEARML20212H2861999-09-24024 September 1999 Proposed Tech Specs 3/4.6.1.8,allowing Continued Operation Until Next Plant Shutdown at Which Time Valve T4803F601 Will Be Repaired ML20212H4351999-09-24024 September 1999 Proposed Tech Specs Re Util Request for Enforcement Discretion with Respect to TS 3/4.6.1.8 Re Drywell & Suppression Chamber Purge Sys ML20211Q1841999-09-10010 September 1999 Proposed Tech Specs Revising SRs & Bases for Div I Battery Sys to Agree with Design of New Battery Replacement ML20211Q7351999-09-0303 September 1999 Proposed Its,Rev 15 ML20211G0921999-08-25025 August 1999 Rev 14 Proposed ITS Pages,Providing Update for Remaining Open Issues Associated with NRC Review of ITS Submittal ML20211B9991999-08-0606 August 1999 Proposed Its,Rev 13 ML20210N0231999-08-0404 August 1999 Rev 12 to 980403 ITS Submittal,Providing Update to Submittal for ITS Sction 3.3,including Changes Associated with NRC Review of Rev 6 to ITS Submittal ML20210J1641999-07-30030 July 1999 Draft Proposed Tech Spec Pages Re Amend to License NPF-43 to Include Provisions for Enabling Oscillation Power Range Monitor (OPRM) Upscale Function in Average Power Range Monitor (APRM) ML20216D6091999-07-26026 July 1999 Rev 11 to ITS Submittal,Dtd 980403,providing Update to ITS Sections 3.5,3.6 & 3.8 ML20209H0331999-07-13013 July 1999 Rev 10 to ITS Submittal,Dtd 980403,providing Update to ITS Submittal for ITS Section 3.4,RCS ML20209D4001999-07-0707 July 1999 Rev 9 to Fermi 2 ITS Submittal Dtd 980403,providing Update for Sections 3.0,4.0 & 5.0 ML20196K1681999-07-0101 July 1999 Rev 8 to ITS Submittal Dtd 980403,providing Update to ITS Submittal for ITS Section 3.7 ML20196F4681999-06-24024 June 1999 Rev 7 to ITS Submittal of 980403 to Provide Remaining Responses to NRC RAIs Re ITS Sections 3.5 & 3.8 ML20212H5041999-06-0202 June 1999 Proposed Tech Specs Pages to Rev 6 of Fermi Unit 2 ITS ML20206M1121999-05-0707 May 1999 Proposed Tech Specs Section 3.6,converting to ITS ML20206H5521999-04-30030 April 1999 Proposed Rev 5 to Improved TS Pages ML20205T5361999-04-20020 April 1999 Marked-up & Typed Up Revised TS Pages Eliminating TS SR for Nitrogen Cover Gas on Nearly Empty Primary Sodium Storage Tanks in Sodium Bldg Complex ML20196K6621999-04-0202 April 1999 Proposed Tech Specs Re Rev 4 to Fermi 2 ITS Submittal ML20205A3201999-03-23023 March 1999 Proposed Tech Specs SR 4.4.1.1.1,requiring Each Recirculation Pump Discharge Valve Be Demonstrated Operable at Least Every 18 Months & Deleting Footnote That Applies to TS 4.4.1.1.1 & Stating *Not Used ML20202D9551999-01-26026 January 1999 Rev 2 to Fermi 2 Its,Incorporating Operating License Amends 119,122,128 & 129,issued Since Initial ITS Submittal Was Finalized ML20155A7111998-10-22022 October 1998 Proposed Replacement TS Sections F.1.a & F.2.b Pages, Utilizing Terminology of TEDE Instead of Whole Body & Organ Dose ML20154E5621998-09-28028 September 1998 Revised Proposed Tech Specs Pages Re 980403 Application for Amend to License NPF-43 for Conversion of TS to Improved Standard TS ML20237E8981998-08-26026 August 1998 Proposed Tech Specs Implementing Provisions of 1996 Decommissioning Rule,Including Requirements for Control of Effluents,Dose Limits,& Annual Reporting of 10CFR50.36a ML20236W4701998-07-31031 July 1998 Proposed Tech Specs 3.5.1 & 3.5.2 Re Footnote for Limiting Condition for Operation ML20236U4601998-07-23023 July 1998 Proposed Tech Specs Revising Table 4.0.2-1 to Include Two Functional Units for TS 4.3.1.3 (RPS Response Time Testing) & Allowing one-time Extension of Respective Surveillance Intervals ML20236U0421998-07-16016 July 1998 TS Insert Page & Associated Index Page Reflecting Withdrawal of Request for Extension of Surveillance Interval for TS 4.0.5,as Contained in Enclosure 20 of & Administrative Change ML20236F0671998-06-26026 June 1998 Proposed Tech Specs Allowing one-time Extension of Surveillance Intervals to Delay Shutdown for Upcoming Sixth Refueling Outage (RFO6) Until 980904 ML20248L8021998-06-0505 June 1998 Proposed Tech Specs Section 2.1.2,re Thermal Pressure,High Pressure & High Flow ML20248E4151998-05-28028 May 1998 Proposed Tech Specs Page 3/4 5-1,revised to Include Remaining Proposed Changes W/Applicability Restored to Reflect Original Notation Re Realignment of LPCI Sys ML20247Q1191998-05-20020 May 1998 Proposed Tech Specs Pages Revising TS 3.1.3.1,Action D to Apply to Valves Inoperable for Any Reason & Increase Time Allowed for Restoring SDV Vent or Drain Line W/One Valve Inoperable from Current 24 Hours to 7 Days ML20247A7401998-04-27027 April 1998 Proposed Tech Specs Pages,Adding Configuration Risk Mgt Program to TS Section 6.8.5 ML20216F6971998-04-0909 April 1998 Proposed Tech Specs,Withdrawing Previously Submitted Response Time Testing Requirement Clarification Re Neutron Monitoring Sys ML20216J7581998-04-0909 April 1998 Proposed Tech Specs 3.3.7.5,3.7.1.2 & 3.8.1.1 Re Alignment of Shutdown Action Statements for Primary Containment Oxygen Monitoring Instrumentation ML20216B3311998-04-0303 April 1998 Proposed Tech Specs,Extending EDG Allowed Times at Plant ML20217P0631998-04-0202 April 1998 Proposed Tech Specs Re Mod of Drywell Oxygen Monitoring Instrumentation Action Requirements to Be Consistent W/Those Contained in NUREG-1433 Rev 1, Std Tech Specs GE Plants BWR/4 ML20217P5691998-04-0202 April 1998 Proposed Tech Specs Changing Requirements Associated W/ Containment Oxygen & Hydrogen Monitors ML20217J5441998-03-27027 March 1998 Proposed Tech Specs Eliminating Incorrect Descriptive Info Re Water Inventory in CST Reserved for Hpci/Rcic & Raising CST Min Water Level for Core Spray ML20217J5841998-03-27027 March 1998 Proposed Tech Specs Revising Footnote Specifying Conditions Where Isolation Valves Associated W/Lpci Sys Operation Are Repositioned ML20199H9371998-01-28028 January 1998 Proposed Tech Specs Re thermal-hydraulic Stability,Idle Recirculation Loop Startup & Post Accident Monitoring ML20199H2611998-01-28028 January 1998 Proposed Tech Specs Re Access Control to Provide Flexibility While Maintaining Similar Control Over Access ML20199H2561998-01-28028 January 1998 Proposed Tech Specs,Modifying Sections F & I of Plant TS to Include Requirements for Control of Effluents,Dose Limits & Annual Requirements Per 10CFR50.36a ML20199H2501998-01-28028 January 1998 Proposed Tech Specs 4.4.3.2.2.a,changing Surveillance Interval in TS 4.4.3.2.2.a by Extending It from Current 18 Month Testing Interval to 24 Month Testing Interval to Be Consistent W/Asme Code Requirements ML20199H2411998-01-28028 January 1998 Proposed Tech Specs,Revising Footnotes Specifying Conditions Under Which SRs Associated W/Ts 3/4.9.1, Reactor Mode Switch Can Be Performed ML20199H2141998-01-28028 January 1998 Proposed Tech Specs,Revising SRs for Div II Battery Sys to Agree W/Design of New Battery Replacement ML20199H2281998-01-28028 January 1998 Proposed Marked Up & Retyped TS of Sheet 2,Table 3.3.6-2, Deleting RCS Recirculation Flow Trip Functions ML20203F1941997-12-10010 December 1997 Proposed Tech Specs Revising TS to Be Consistent W/Planned Replacement of Current Power Range Monitoring Portion of Existing Nms ML20202A7961997-11-26026 November 1997 Proposed Tech Specs Reflecting Alternative Wording for Surveillance Which Address Only Clarification to Situational Testing Requirement NRC-97-0089, Proposed Tech Specs,Relocating Selected Requirements & Bases from TS to Ufsar.Rev of TS Index & List of Tables to Reflect Relocation Requested1997-09-29029 September 1997 Proposed Tech Specs,Relocating Selected Requirements & Bases from TS to Ufsar.Rev of TS Index & List of Tables to Reflect Relocation Requested ML20216F3581997-09-0505 September 1997 Proposed Tech Specs,Adding Special Test Exception to Allow Unit to Remain in Operational Condition 4 W/Reactor Coolant Temps Greater than 200 F,But Less than 212 F,When Performing Inservice Leak & Hydrostatic Testing ML20141B8881997-06-20020 June 1997 Proposed Tech Specs Re Relocation of Reactor Recirculation Sys MG Set Scoop Tube Stop Setting Surveillance 1999-09-03
[Table view] Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML20212H4351999-09-24024 September 1999 Proposed Tech Specs Re Util Request for Enforcement Discretion with Respect to TS 3/4.6.1.8 Re Drywell & Suppression Chamber Purge Sys ML20212H2861999-09-24024 September 1999 Proposed Tech Specs 3/4.6.1.8,allowing Continued Operation Until Next Plant Shutdown at Which Time Valve T4803F601 Will Be Repaired ML20211Q1841999-09-10010 September 1999 Proposed Tech Specs Revising SRs & Bases for Div I Battery Sys to Agree with Design of New Battery Replacement ML20211Q7351999-09-0303 September 1999 Proposed Its,Rev 15 ML20211G0921999-08-25025 August 1999 Rev 14 Proposed ITS Pages,Providing Update for Remaining Open Issues Associated with NRC Review of ITS Submittal ML20211B9861999-08-13013 August 1999 Rev 5 to Inservice Testing Program for Pumps & Valves for Fermi 2 Second 10-Year Interval ML20211C2631999-08-13013 August 1999 Rev 2,change 0 to ISI-Nondestructive Exam (ISE-NDE) Program (Plan) for Fermi 2 Power Plant, for Second ten-year Interval ML20211B9991999-08-0606 August 1999 Proposed Its,Rev 13 ML20210N0231999-08-0404 August 1999 Rev 12 to 980403 ITS Submittal,Providing Update to Submittal for ITS Sction 3.3,including Changes Associated with NRC Review of Rev 6 to ITS Submittal ML20210J1641999-07-30030 July 1999 Draft Proposed Tech Spec Pages Re Amend to License NPF-43 to Include Provisions for Enabling Oscillation Power Range Monitor (OPRM) Upscale Function in Average Power Range Monitor (APRM) ML20216D6091999-07-26026 July 1999 Rev 11 to ITS Submittal,Dtd 980403,providing Update to ITS Sections 3.5,3.6 & 3.8 ML20209H0331999-07-13013 July 1999 Rev 10 to ITS Submittal,Dtd 980403,providing Update to ITS Submittal for ITS Section 3.4,RCS ML20209D4001999-07-0707 July 1999 Rev 9 to Fermi 2 ITS Submittal Dtd 980403,providing Update for Sections 3.0,4.0 & 5.0 ML20196K1681999-07-0101 July 1999 Rev 8 to ITS Submittal Dtd 980403,providing Update to ITS Submittal for ITS Section 3.7 ML20210A3031999-06-30030 June 1999 Rev 14 to Fermi 2 Security Personnel Training & Qualification Plan ML20196F4681999-06-24024 June 1999 Rev 7 to ITS Submittal of 980403 to Provide Remaining Responses to NRC RAIs Re ITS Sections 3.5 & 3.8 ML20212H5041999-06-0202 June 1999 Proposed Tech Specs Pages to Rev 6 of Fermi Unit 2 ITS ML20206M1121999-05-0707 May 1999 Proposed Tech Specs Section 3.6,converting to ITS ML20206M8651999-05-0606 May 1999 Rev 30,Vol I to Technical Requirements Manual ML20206H5521999-04-30030 April 1999 Proposed Rev 5 to Improved TS Pages ML20205T5361999-04-20020 April 1999 Marked-up & Typed Up Revised TS Pages Eliminating TS SR for Nitrogen Cover Gas on Nearly Empty Primary Sodium Storage Tanks in Sodium Bldg Complex ML20196K6621999-04-0202 April 1999 Proposed Tech Specs Re Rev 4 to Fermi 2 ITS Submittal ML20205A3201999-03-23023 March 1999 Proposed Tech Specs SR 4.4.1.1.1,requiring Each Recirculation Pump Discharge Valve Be Demonstrated Operable at Least Every 18 Months & Deleting Footnote That Applies to TS 4.4.1.1.1 & Stating *Not Used ML20202D9551999-01-26026 January 1999 Rev 2 to Fermi 2 Its,Incorporating Operating License Amends 119,122,128 & 129,issued Since Initial ITS Submittal Was Finalized ML20198D1391998-12-14014 December 1998 Rev 28 to Vol 1 of Technical Requirements Manual ML20198B8121998-12-10010 December 1998 Rev 27 to Fermi 2 Technical Requirements Manual,Vol I ML20155A7111998-10-22022 October 1998 Proposed Replacement TS Sections F.1.a & F.2.b Pages, Utilizing Terminology of TEDE Instead of Whole Body & Organ Dose ML20154Q0771998-10-15015 October 1998 6 to Fermi 2, Technical Requirements Manual, Vol I ML20154M4611998-10-0909 October 1998 5 to Vol 1 of Fermi 2 Technical Requirements Manual ML20154H8931998-10-0808 October 1998 Rev 24 to Fermi 2 Technical Requirements Manual,Vol I ML20154E5621998-09-28028 September 1998 Revised Proposed Tech Specs Pages Re 980403 Application for Amend to License NPF-43 for Conversion of TS to Improved Standard TS ML20153F3931998-09-23023 September 1998 Rev 23 to Fermi 2 Technical Requirements Manual,Vol 1 ML20237E8981998-08-26026 August 1998 Proposed Tech Specs Implementing Provisions of 1996 Decommissioning Rule,Including Requirements for Control of Effluents,Dose Limits,& Annual Reporting of 10CFR50.36a ML20237D6311998-08-18018 August 1998 Rev 22 to Fermi 2 Technical Requirements Manual,Vol 1 ML20236W4701998-07-31031 July 1998 Proposed Tech Specs 3.5.1 & 3.5.2 Re Footnote for Limiting Condition for Operation ML20236U4601998-07-23023 July 1998 Proposed Tech Specs Revising Table 4.0.2-1 to Include Two Functional Units for TS 4.3.1.3 (RPS Response Time Testing) & Allowing one-time Extension of Respective Surveillance Intervals ML20236U0421998-07-16016 July 1998 TS Insert Page & Associated Index Page Reflecting Withdrawal of Request for Extension of Surveillance Interval for TS 4.0.5,as Contained in Enclosure 20 of & Administrative Change ML20236F0671998-06-26026 June 1998 Proposed Tech Specs Allowing one-time Extension of Surveillance Intervals to Delay Shutdown for Upcoming Sixth Refueling Outage (RFO6) Until 980904 ML20236P9241998-06-10010 June 1998 Rev 20 to Fermi 2 Technical Requirements Manual, Vol 1 ML20248L8021998-06-0505 June 1998 Proposed Tech Specs Section 2.1.2,re Thermal Pressure,High Pressure & High Flow ML20248H0901998-05-31031 May 1998 Vol 1,Rev 19 to Technical Requirements Manual for Fermi 2 ML20248E4151998-05-28028 May 1998 Proposed Tech Specs Page 3/4 5-1,revised to Include Remaining Proposed Changes W/Applicability Restored to Reflect Original Notation Re Realignment of LPCI Sys ML20247Q1191998-05-20020 May 1998 Proposed Tech Specs Pages Revising TS 3.1.3.1,Action D to Apply to Valves Inoperable for Any Reason & Increase Time Allowed for Restoring SDV Vent or Drain Line W/One Valve Inoperable from Current 24 Hours to 7 Days ML20247A7401998-04-27027 April 1998 Proposed Tech Specs Pages,Adding Configuration Risk Mgt Program to TS Section 6.8.5 ML20216F6971998-04-0909 April 1998 Proposed Tech Specs,Withdrawing Previously Submitted Response Time Testing Requirement Clarification Re Neutron Monitoring Sys ML20216J7581998-04-0909 April 1998 Proposed Tech Specs 3.3.7.5,3.7.1.2 & 3.8.1.1 Re Alignment of Shutdown Action Statements for Primary Containment Oxygen Monitoring Instrumentation ML20216B3311998-04-0303 April 1998 Proposed Tech Specs,Extending EDG Allowed Times at Plant ML20217P5691998-04-0202 April 1998 Proposed Tech Specs Changing Requirements Associated W/ Containment Oxygen & Hydrogen Monitors ML20217P0631998-04-0202 April 1998 Proposed Tech Specs Re Mod of Drywell Oxygen Monitoring Instrumentation Action Requirements to Be Consistent W/Those Contained in NUREG-1433 Rev 1, Std Tech Specs GE Plants BWR/4 ML20217J5841998-03-27027 March 1998 Proposed Tech Specs Revising Footnote Specifying Conditions Where Isolation Valves Associated W/Lpci Sys Operation Are Repositioned 1999-09-03
[Table view] |
Text
_ -__ ____ -__ _ __
ADMINISTRATIVE CONTROLS $
, UNIT STAFF (Continued)
- c. A Health Physics Technician
- shs11 be on site when fuel is in the
, reactor; ")
- d. All CORE ALTERATIONS shall bd observed and directly supervised by either a licensed Senior Operator or licensed Senior Operator Limited to Fuel Handlin during this operation; g who has no other concurrent responsibilities
- e. A site fire brigadt of at least five members shall be m3intained on site at all times". The fire brigade shall not include the Nuclear Shift Supervisor, the Shift Technical Advisor, nor the two other members of the minimum shift crew necessary for safe shutdown of the unit and any personnel required for other essential functions during a fire emergency; and
- f. Adelnistrative procedures shall be developed and implemer.ted to limit the workin functions (e.g.,g licensed hours ofSenior unit staff who perfom Operators, safety-related licensed Operators, health physics personnel, auxiliary operctors, and key maintenance personnel).
Adequate shift coverage shall be maintained without routine heavy use of overtime. The objective shall be to have operating personnel horninst[7 work a%oma' 9-br d:ys 40-hour week while the unit is operating.
However, in the event that unforeseen problems require substantial l amounts of overtime to be used, or during extended periods of shut-down for refueling, major maintenance, or major unit modifications, on a temporary basis the following guidelines shall be followed:
- 1. An individual should r,ot be permitted to work more than 16 hours1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br /> straight, excluding shift turnovar time. O
- 2. An individual should not be permitted to work more than 16 hours1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br /> in any 24-hour period, nor wrt than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> in any 48-hour period, nor more than 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> in any 7 day period, all exclud-ing shift turnover time.
l 3. A break of at least E hours should be allowed between work periods, including shift turnover time.
. 4. Except during extended shutdown periods, the use of overtime should be considered on an individual basis and not for the er, tire staff on a shift.
. Any deviation from the above guidelines shall be authorized by the Plant Manager or a Section Superintendent or higher levels of _
, management in accordance with established procedures and with ~'
! documentation of the basis for granting the deviation. Controls shell be included in the procedures such that individual overtime shall be reviewed monthly by the Plant Manager or a Section Super-intendent to assure that excessive hours have not'been assigned.
Routine deviation from the above guidelines is not authorizwd.
'l "Ihe Health Physics Technician and fire brigade composition may be less than i the minimum requirements for a period of time not to exceed 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />, in order to accommodate unexpected absence, provided immediate action is taken to fill the required positions.
FERMI - UNIT 2 6-2 Amendment No. II, 30
}
8908070297 890724 ,
PDR ADOCK 05000341 P puu
_ _ _ _ _ _ _ _ - - - - _ _ _ - - __ - - - - - . - - - - - _ . .- )
v- . . ,
' ADMINISTRATIVE CONTROL 5' 6.2.3 ! @ EPENDENT SAFETY ENGINEERING GROUP (ISEG)
FUNCTION -
6.2.3.1 The ISEG shall function to examine unit operating characteristics, NRC issuances, industry advisories, Licensee Event Reports, and other sources of plant design and operating esperience infomation, including plants of similar design, which may indicate areas for improving unit safety.
COMPOSITION 6.2.3.2 The ISEG shall be composed of at least five dedicated, full-time engineers located onsite, each with a bachelor's degree in engineering or related science and at least two years professional level experience in his field, at least one year of which experience shall be in the nuclear fie 4.
RESPONSIBILITIES o 6.2.3.3 The ISEG shall be responsible for maintaining surveillance of unit activities to provide independent verification
- that these activities are perfomed correctly and that human errors are reduced as much as practical.
l AUTHORITY 6.2.3.4 The ISEG shall make detailed recommendations for revised procedures, equipment modifications, maintenance activities, operations activities or other means of improving unit safety to the N :i r ., ":: h r u tt; 5 : S; ',
Cr:;. Vice PresWent Nuclear E"Encedm3 *"d S<rvices.
6.2.4 SHIFT TECHNICAL ADVISOR 6.2.4.1 The Shift Technical Advisor shall provide advisory technical support to the Nuclear Shift Supervisor in the areas of thermal hydraulics, reactor l
I engineering, and plant analysis with regard to safe operation of the unit.
The Shift Technical Advisor shall have a bachelor's degree or equivalent in a scientific or engineering discipline and shall have received specific training i
in the response and analysis of the unit for transients and accidents, and in unit design and layout, including the capabilities of instrumentation and controls in the control room.
i
- Not responsible for sign-off function.
6-6 Amendment No. ZZ, 30 FERMI - UNIT 2
~
ADMINISTRATIVE CONTROLS k 6.3 UNITSTAFFQUALIFICATI0f3 1 .
l 6.3.1 Each member of the unit etaff shall meet or exceed the minimum qualifi-cations of ANSI N18.1-1971 for comparable positions, excapt for the j Superintendent - Radiation Prrstection or his designee who sha!1 meet or exceen d
! the qualifications of Regulatory Guide 1.8, September 1975. The licensed Operators and Senior Operators shals also meet or exceed the minimum qualifica-tions of the supplemental requirements specified in Sections A and C of En:losure 1 of the March 29, 1980 NRC letter to all licensees.
6.4 TRAINING 6.4.1 A retraining and replacement training program for the unit staff shall be maintained under the direction of the Director (s), Nuclear Training, shall meet or exceed the requirements and recommendations of Section 5 of ANSI N18.1-1971 and Appendix A of 10 CFR Part 55 and the supplemental requirements specified in Sections A and C of Enclosure 1 of the March 29, 1980 NRC letter to all licensees, and shall include familiarization with relevant industry operational experience.
6.5 REVIEW AND AUDIT 6.5.1 ONSITE REVIEW ORGANIZATION (05RO)
FUNCTION 6.5.1.1 The 05RO shall function to advise the Plant Manager on all matters related to nuclear safety as described in Specification 6.5.1.6 COMPOSITION 6.5.1.2 The 05RO shall be composed of the:
Chairman Plant Manager Vice-Chairman / Member
- Director, Plant Safety Vice-Chairman / Member
- Superintendent-Operations /
Member Operations Engineer Superintendent-Technical 9 Member Member Superintendent-Radiation Protection Member Superintendent-Maintenance :nd ":di't :ti:n:
Member Reactor Engineer
(
- May not act as Chairsan and member at the same time. .
FERMI - UNIT 2 6-7 Amendment No. II,30
N .
ADMINISTRATIVE CONTROLS
{' RESPONSIBILITIES (Continued)
- 1. Review of. every unplanned onsite release of radioactive material to the environs including the preparation and forwarding of reports covering evaluation, recommendations and disposition of the correc-tive action to prevent recurrence to the Vice Prasident-Nuclear Operations and to the Nuclear Safety Review Group; and
- m. Review of changes to the PROCESS CONTROL PROGRAM, the DFFSITE DDSE CALCULATION MANUAL, and major modifications to the Radwaste Treatment Systems.
6.5.1.7- The 0$R0 shall:
~
- a. Recommend in writing to the Plant Manager approval or disapproval of items considered under Specific.ation 6.5.1.5a. through d. prior to their implementation. *
- b. Render determinations in writing to the Nuclear Safety Review Group with regard to whether or not each item considered under Specifica-o tion 6.5.1.6ayttn ;;5 f. constitutes an unreviewed safety question.
l
[c. Providewrittennotificationwithin24hourstotheVicePresident-
' b> d"le Nuclear Operations and the Nuclear Safety Review Group of disagree-ment between the OSR0 and the Plant Manager; however, the Plant Manager shall have responsibility for resolution of such disagree-ments pursuant to Specification 6.1.1.
.( RECORDS 6.5.1.8 The DSR0 shall maintain written minutes of each 0$R0 meeting that, at a minimum, document the results of all OSRO activities performed under the responsibility provisions of these Technical Specifications. Copies shall be provided to the Vice President-Nuclear Operations and the Nuclear Safety Review Group.
6.5.2 NUCLEAR SAFETY REVIEW GROUP (NSRG)
FUNCTION -
6.5.2.1 The NSRG r. hall function to provide independent review and audit of designated activities in the areas of:
- a. Nuclear power plant operations,
- b. Nuclear engineering,
- c. Chemistry and radiochemistry,
- d. Metallurgy,
- e. Instrumentation cod control, I
- f. Radiological controls;
- g. Mechanical and electrical engineering, and
- h. Quality assurance practices.
I The NSRG shall report to and advise the Senior Vice President on those areas of responsibility in Specifications 6.5.2.7 and 6.5.2.8.
d'
. FERMI - UNIT 2 6-9 Amendment No. IIJO
e , ,
- ADMINISTRATIVE CONTROLS COMPOSITION 6.5.2.2 The Senior Vice President shall appoint at least nine members to the .vf I NSRG and shall designate from this membership a Chairman and at least one Vice i Chairman. The membership shall collectively possess experience and competence to provide independent review and audit in the areas listed in Section 6.5.2.1.
The Chairman and Vice Chaiman shall have nuclear background in engineering or operations and shall be capable of determining when to call in experts to assist the NSRG review of complex problems. All members shall have at least a bache-lor's degree in engineering or related sciences. The Chairman shall have at least 10 years of professional level management experience in the power field and each of the other members shall have at least 5 years of cumulative profes-sional level experience in one or more of the fields listed in Section 6.5.2.1.
ALTERNATES 6.5.2.3 All alternate members stia11 be appointed in writing by the NSRG Chairman to serve on a temporary basis; however, no more than two alternates shall participate as voting sienbers in NSRG activities at any one time.
CONSULTANTS 6.5.2.4 Consultant, shall be utilized as detemined by the NSRG Chairman to provide expert advice to the NSRG.
MEETING FREQUENCY 6.5.2.5 The MSRG shall meet et le :t :::: per ::1:ne r = -t- i rin; th:
4Mhl-year f :.; nit ;pr;tien f;11e.;ing fwl le; ding :.;d at least once per 6 months.t':re:fteev QUORUM 6.5.2.6 The quorum of the NSRG necessary for the performance of the NSRG review and audit functions of these Technical Specifications shall consist of the Chairman or his designated alternate and at least one half of the remain-ing NSRG members 4ns-itding :ltern:te:. No more than a minority of the quorum shall have lin responsibility for operation of the unit.
REVIW
' f whd fwo my le aSrnaic5.
6.5.2.7 The NSRG shall be responsible for the review of 6.5.2.7.a and shall review 6.5.2.7.b through 1:
- a. The safety evaluations for (1) changes to procedures, equipment, facilities or systems and (2) tests or experiments completed under the provision of 10 CFR 50.E.. to verify that such actions did not constitute an unreviewed safety question;
- b. Proposed changes to procedures, equipment, or systems which involve an unreviewed safety question as defined in 10 CFR 50.59; 6-10 Amendment No. II,30 FERMI - UNIT 2
.__ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _