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Category:TECHNICAL SPECIFICATIONS
MONTHYEARML20210H2901999-07-30030 July 1999 Proposed Tech Specs Pages,Extending Operation of RBS from Current Licensed Power Level of 2894 Mwt to Uprated Power Level 3039 Mwt ML20205P8701999-04-15015 April 1999 Proposed Tech Specs,Implementing Bwrog/Ge Enhanced Option I-A (EI-A) Reactor Stability long-term Solution ML20205L7321999-04-0808 April 1999 Proposed Tech Specs,Removing Notes That Refer to Specific Cycles,Per LAR 1998-15 Re Change to TS 2.1.1.2, Reactor Core Safety Limits ML20206R9351999-01-12012 January 1999 Proposed Tech Specs Re Refueling Equipment Interlocks Required Actions ML20198E8091998-12-16016 December 1998 Proposed Tech Specs Pages Re Change to TS Safety Limit 2.1.1.2,changing Two Recirculation Loop MCPR Limit from 1.13 to 1.12 & Single Recirculation Loop MCPR Limit from 1.14 to 1.13 ML20196A1401998-11-20020 November 1998 Proposed Tech Specs Adding 3.10.9, Control Rod Pattern - Cycle 8, to Support Startup from Outage Planned for Early Dec 1998 ML20154H3691998-10-0808 October 1998 Proposed Tech Specs Implementing BWROG Enhanced Option I-A Reactor Stability Long Term Solution as Documented in NEDO-32339,Rev 1, Reactor Stability Long-Term Solution, Enhanced Option I-A ML20153H0311998-09-23023 September 1998 Proposed Tech Specs Changing Specific Gravity Acceptance Criteria for Div III Battery ML20153E8111998-09-22022 September 1998 Proposed Tech Specs Deleting License Conditions Associated with Transamerica Delaval,Inc EDGs ML20217J0951998-04-21021 April 1998 Proposed Tech Specs Bases Update Package for Revs Implemented Since Last Submittal Through Refuel Outage 7 ML20216F1941998-04-0909 April 1998 Proposed Tech Specs License Condition 2.C(13) Re Partial Feedwater Heating & Final Feedwater Temp Reduction ML20216E4861997-09-0505 September 1997 Proposed Tech Specs Re APRM Setpoints,Reactivity Anomalies & RPS Instrumentation ML20210K2131997-08-15015 August 1997 Proposed Administrative Changes to TS 2.1.1.2 W/Note to Indicate Operating Cycle for Which SLMCPR Value Has Been Approved & TS 5.6.5 W/Note Providing Link to Specific GE Documents Used in Approving SLMCPR Changes for Given Cycle ML20217J0481997-08-0505 August 1997 Proposed Tech Specs 2.1.1.2, Reactor Core (Safety Limits), Increasing Two Recirculation Loop MCPR Limit to 1.13 & Single Recirculation Loop MCPR Limit to 1.14 ML20151L6041997-07-31031 July 1997 Proposed Tech Specs,Requesting Approval of Change to TS 3.6.1.8, Penetration Valve Leakage Control Sys, for Upcoming Outage ML20196J7741997-07-30030 July 1997 Proposed Tech Specs Clarifying Surveillance Requirements 3.6.4.2.1 & 3.6.4.2.2 to Match Corresponding Changes to NUREG-1434 ML20134A7021997-01-20020 January 1997 Proposed Tech Specs to License NPF-47,enhancing Operation of Plant to Allow Operation at 100% Power W/Lower Core Flows & Use of Flow Control Spectral Shift Strategies to Increase Cycle Energy ML20133M0451997-01-10010 January 1997 Proposed Tech Specs 3.4.11 Re RCS Pressure & Temp Limits ML20134M2271996-11-15015 November 1996 Proposed Tech Specs,Changing TS SL 2.1.1.2, Reactor Core (Sl), Which Increases Two Recirculation Loop MCPR Limit from 1.07 to 1.10 & Single Recirculation Loop MCPR from 1.08 to 1.12 ML20134M0151996-11-15015 November 1996 Proposed Tech Specs 3.8.1 Re AC Sources Operating ML20134M2061996-11-0606 November 1996 Proposed Tech Specs,Permitting Increase in Allowable Leak Rate for MSIVs & Deleting Penetration Valve Leakage Control Sys & Ms Positive Leakage Control Sys Requirements ML20129J4231996-10-24024 October 1996 Proposed Tech Specs 3.8.1 Re A.C. Sources - Operating ML20117K1071996-08-29029 August 1996 Proposed Tech Specs Re Reactor Vessel Matl Surveillance Program Capsule Withdrawal Schedule ML20117G7401996-08-29029 August 1996 Proposed Tech Specs 3.1 Re Reactivity Control Systems ML20116J3151996-08-0707 August 1996 Proposed Tech Specs,Submitting TS Bases Pages for Revs Performed Since 951001 Approval of TS Bases ML20116L6321996-08-0101 August 1996 Proposed Tech Specs Re Primary Containment/Drywell Hydrogen Mixing Sys & Drywell Isolation Valves ML20117L2581996-06-0404 June 1996 Proposed Tech Specs Re Replacement Page for Ltr RBG-42764, Proposed Tech Specs 3.9.1 Re Refueling Equipment Interlocks1996-05-31031 May 1996 Proposed Tech Specs 3.9.1 Re Refueling Equipment Interlocks ML20112E7831996-05-30030 May 1996 Proposed Tech Spec 3.8.3 Re Incorporation of 5-start Air Pressure Design Criterion for Div III DG ML20117H3271996-05-20020 May 1996 Proposed Tech Specs Re Change in Co Name from Gulf States Utils Co to Entergy Gulf States,Inc ML20107E4681996-04-18018 April 1996 Proposed Tech Specs Re Fuel Loading W/Control Rods Withdrawn or Removed from Defueled Core Cells ML20094N7741995-11-22022 November 1995 Proposed Tech Specs,Clarifying Info Contained in License Amend Request (LAR) 95-21 ML20094M8001995-11-20020 November 1995 Proposed Tech Specs Re Drywell Leak Rate Testing Requirements ML20094N0091995-11-20020 November 1995 Proposed Tech Specs Eliminating Selected Response Time Testing Requirements ML20094B0001995-10-26026 October 1995 Proposed Tech Specs,Consisting of Change Request 95-10, Deleting TS 5.5.12, Biofouling Prevention & Detection, & Various Editorial Corrections ML20093L7361995-10-24024 October 1995 Proposed Tech Specs 3.6.1.1 Through 3.6.1.3 Re Containment Sys ML20087J5451995-08-17017 August 1995 Proposed Tech Specs Re Engineered Safety Sys Which Responds to Fuel Handling Accident Conditions ML20084L4541995-05-30030 May 1995 Proposed Tech Specs Re Request for Exemption from App J, Primary Reactor Containment Leakage Testing for Water- Cooled Power Reactors ML20084L5001995-05-30030 May 1995 Proposed Tech Specs,Allowing TS 3/4.6.2.2, Drywell Bypass Leakage, Tests to Be Performed at Intervals as Long as Five Yrs Based on Demonstrated Performance of Drywell Structure ML20078M1171995-02-0808 February 1995 Proposed Tech Specs Page Re Secondary Containment Automatic Isolation Dampers ML20077S4401995-01-18018 January 1995 Revised Pages of Proposed Tech Specs Re Conversion to TS Based on NUREG-1434, Improved TS Rev 0 ML20078H0881994-11-10010 November 1994 Proposed Tech Specs Reflecting Clarifications to LAR 91-11 ML20024J3341994-10-0404 October 1994 Proposed Tech Spec Removing one-hour Requirement for Completing Noble Gas & Tritium Sampling & Analysis ML20073B2381994-09-12012 September 1994 Proposed TS 3/4.2.2, APRM Setpoints ML20072U7901994-09-0808 September 1994 Proposed Tech Spec 3.10.2, Special Test Exceptions - Rod Pattern Control Sys ML20064L6481994-03-15015 March 1994 Proposed Tech Specs,Reflecting Removal of Turbine Overspeed Protection Sys Requirements ML20064C0961994-03-0303 March 1994 Proposed Tech Specs,Reflecting Relocation of Response Time Limits to Usar,Per GL 93-08 ML20063K3721994-02-22022 February 1994 Proposed Tech Specs 3.6.1.8 & 3.6.1.9 Re Penetration Valve Leakage Control Sys Air Compressor ML20063A6301994-01-14014 January 1994 Proposed Tech Specs Reflecting Removal of Component Lists ML20059G8181994-01-14014 January 1994 Proposed Tech Specs Re Surveillance Test Interval & Allowed Outage Time Extension Request 1999-07-30
[Table view] Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML20210H2901999-07-30030 July 1999 Proposed Tech Specs Pages,Extending Operation of RBS from Current Licensed Power Level of 2894 Mwt to Uprated Power Level 3039 Mwt ML20205P8701999-04-15015 April 1999 Proposed Tech Specs,Implementing Bwrog/Ge Enhanced Option I-A (EI-A) Reactor Stability long-term Solution ML20205L7321999-04-0808 April 1999 Proposed Tech Specs,Removing Notes That Refer to Specific Cycles,Per LAR 1998-15 Re Change to TS 2.1.1.2, Reactor Core Safety Limits ML20206R9351999-01-12012 January 1999 Proposed Tech Specs Re Refueling Equipment Interlocks Required Actions ML20199C1881999-01-0808 January 1999 Revised Page 7 to Rev 13 of RBS Security Training & Qualification Plan ML20198E8091998-12-16016 December 1998 Proposed Tech Specs Pages Re Change to TS Safety Limit 2.1.1.2,changing Two Recirculation Loop MCPR Limit from 1.13 to 1.12 & Single Recirculation Loop MCPR Limit from 1.14 to 1.13 ML20196A1401998-11-20020 November 1998 Proposed Tech Specs Adding 3.10.9, Control Rod Pattern - Cycle 8, to Support Startup from Outage Planned for Early Dec 1998 ML20154H3691998-10-0808 October 1998 Proposed Tech Specs Implementing BWROG Enhanced Option I-A Reactor Stability Long Term Solution as Documented in NEDO-32339,Rev 1, Reactor Stability Long-Term Solution, Enhanced Option I-A ML20153H0311998-09-23023 September 1998 Proposed Tech Specs Changing Specific Gravity Acceptance Criteria for Div III Battery ML20153E8111998-09-22022 September 1998 Proposed Tech Specs Deleting License Conditions Associated with Transamerica Delaval,Inc EDGs ML20217J0951998-04-21021 April 1998 Proposed Tech Specs Bases Update Package for Revs Implemented Since Last Submittal Through Refuel Outage 7 ML20216F1941998-04-0909 April 1998 Proposed Tech Specs License Condition 2.C(13) Re Partial Feedwater Heating & Final Feedwater Temp Reduction RBG-44355, Cycle 8 Startup Physics Test Summary1998-01-19019 January 1998 Cycle 8 Startup Physics Test Summary ML20202F0361997-11-26026 November 1997 Rev 0 to IST Plan for Pumps & Valves Second Ten-Yr Interval ML20216E4861997-09-0505 September 1997 Proposed Tech Specs Re APRM Setpoints,Reactivity Anomalies & RPS Instrumentation ML20210K2131997-08-15015 August 1997 Proposed Administrative Changes to TS 2.1.1.2 W/Note to Indicate Operating Cycle for Which SLMCPR Value Has Been Approved & TS 5.6.5 W/Note Providing Link to Specific GE Documents Used in Approving SLMCPR Changes for Given Cycle ML20217J0481997-08-0505 August 1997 Proposed Tech Specs 2.1.1.2, Reactor Core (Safety Limits), Increasing Two Recirculation Loop MCPR Limit to 1.13 & Single Recirculation Loop MCPR Limit to 1.14 ML20151L6041997-07-31031 July 1997 Proposed Tech Specs,Requesting Approval of Change to TS 3.6.1.8, Penetration Valve Leakage Control Sys, for Upcoming Outage ML20196J7741997-07-30030 July 1997 Proposed Tech Specs Clarifying Surveillance Requirements 3.6.4.2.1 & 3.6.4.2.2 to Match Corresponding Changes to NUREG-1434 ML20134A7021997-01-20020 January 1997 Proposed Tech Specs to License NPF-47,enhancing Operation of Plant to Allow Operation at 100% Power W/Lower Core Flows & Use of Flow Control Spectral Shift Strategies to Increase Cycle Energy ML20133M0451997-01-10010 January 1997 Proposed Tech Specs 3.4.11 Re RCS Pressure & Temp Limits ML20140F0151996-12-26026 December 1996 Rev 6 to RSP-0008, ODCM Procedure ML20134M2271996-11-15015 November 1996 Proposed Tech Specs,Changing TS SL 2.1.1.2, Reactor Core (Sl), Which Increases Two Recirculation Loop MCPR Limit from 1.07 to 1.10 & Single Recirculation Loop MCPR from 1.08 to 1.12 ML20134M0151996-11-15015 November 1996 Proposed Tech Specs 3.8.1 Re AC Sources Operating ML20134M2061996-11-0606 November 1996 Proposed Tech Specs,Permitting Increase in Allowable Leak Rate for MSIVs & Deleting Penetration Valve Leakage Control Sys & Ms Positive Leakage Control Sys Requirements ML20129J4231996-10-24024 October 1996 Proposed Tech Specs 3.8.1 Re A.C. Sources - Operating ML20117K1071996-08-29029 August 1996 Proposed Tech Specs Re Reactor Vessel Matl Surveillance Program Capsule Withdrawal Schedule ML20117G7401996-08-29029 August 1996 Proposed Tech Specs 3.1 Re Reactivity Control Systems ML20116P1341996-08-0808 August 1996 Technical Requirements Manual ML20116J3151996-08-0707 August 1996 Proposed Tech Specs,Submitting TS Bases Pages for Revs Performed Since 951001 Approval of TS Bases ML20116L6321996-08-0101 August 1996 Proposed Tech Specs Re Primary Containment/Drywell Hydrogen Mixing Sys & Drywell Isolation Valves ML20113F2271996-06-12012 June 1996 Rev 0 to Calculation PI-0103-00203.002-101, Ampacity Derating Evaluation ML20117L2581996-06-0404 June 1996 Proposed Tech Specs Re Replacement Page for Ltr RBG-42764, Proposed Tech Specs 3.9.1 Re Refueling Equipment Interlocks1996-05-31031 May 1996 Proposed Tech Specs 3.9.1 Re Refueling Equipment Interlocks ML20112E7831996-05-30030 May 1996 Proposed Tech Spec 3.8.3 Re Incorporation of 5-start Air Pressure Design Criterion for Div III DG ML20117H3271996-05-20020 May 1996 Proposed Tech Specs Re Change in Co Name from Gulf States Utils Co to Entergy Gulf States,Inc B130180, Surveillance Specimen Program Evaluation for River Bend Station1996-04-30030 April 1996 Surveillance Specimen Program Evaluation for River Bend Station ML20107E4681996-04-18018 April 1996 Proposed Tech Specs Re Fuel Loading W/Control Rods Withdrawn or Removed from Defueled Core Cells ML20094N7741995-11-22022 November 1995 Proposed Tech Specs,Clarifying Info Contained in License Amend Request (LAR) 95-21 ML20094M8001995-11-20020 November 1995 Proposed Tech Specs Re Drywell Leak Rate Testing Requirements ML20094N0091995-11-20020 November 1995 Proposed Tech Specs Eliminating Selected Response Time Testing Requirements ML20094B0001995-10-26026 October 1995 Proposed Tech Specs,Consisting of Change Request 95-10, Deleting TS 5.5.12, Biofouling Prevention & Detection, & Various Editorial Corrections ML20093L7361995-10-24024 October 1995 Proposed Tech Specs 3.6.1.1 Through 3.6.1.3 Re Containment Sys ML20108B5941995-10-0101 October 1995 Rev 5A to River Bend Station Offsite Dose Calculation Manual Procedure ML20087J5451995-08-17017 August 1995 Proposed Tech Specs Re Engineered Safety Sys Which Responds to Fuel Handling Accident Conditions ML20084L5001995-05-30030 May 1995 Proposed Tech Specs,Allowing TS 3/4.6.2.2, Drywell Bypass Leakage, Tests to Be Performed at Intervals as Long as Five Yrs Based on Demonstrated Performance of Drywell Structure ML20084L4541995-05-30030 May 1995 Proposed Tech Specs Re Request for Exemption from App J, Primary Reactor Containment Leakage Testing for Water- Cooled Power Reactors ML20078M1171995-02-0808 February 1995 Proposed Tech Specs Page Re Secondary Containment Automatic Isolation Dampers ML20077S4401995-01-18018 January 1995 Revised Pages of Proposed Tech Specs Re Conversion to TS Based on NUREG-1434, Improved TS Rev 0 ML20078H0881994-11-10010 November 1994 Proposed Tech Specs Reflecting Clarifications to LAR 91-11 1999-07-30
[Table view] |
Text
RECEIVED i DEC 151987 l
ADMINISTRATIVE CONTROLS SOC l
6;? UNIT STAFF QUALIFICATIONS 6.3.1 Each member of the unit staff shall meet or exceed the minimum qualifica-tions of ANS!/ANS 3.1-1978 for comparable positions, except for the Director- l Radiological Programs who shall meet or exceed the qualifications of Regulatory Guide 1.8, September 1975. The licensed Operators and Senior Operators shall also meet or exceed the minimum qualifications of the supplemental requirements specified in Sections A and C of Enclosure 1 of the March 28, 1980 NRC letter to all licensees.
6.4 TRAINING 6.4.1 A retraining and replacement treining program for the unit staff shall be maintained under the direction of the Director - Nuclear Training and shall meet or exceed the requirements and recommendations of Section 5.5 of ANSI /
ANS 3.1-1978 and Appendix A of 10 CFR Part 55 and the su)plemental requirements specifled in Sections A and C of Enclosure 1 of the Marc 128,1980 NRC letter to all licensees, and shall include familiarization with relevant industry operational experience.
6.5 REVIEW AND AUDIT 6.5.1 FACILITY REVIEW COMMITTEE (F_RC) .
FUNCTION -
6.5.1.1 The FRC shall function to advise the Plant Manager on all matters related to nuclear safety.
COMP 0SITION 6.5.1.2 The TRO eheil L; cc p;;;d ;' the:
Phd -e a - Ant: tent olent %ge*Mhnte:1 Sersi:::
Memb . Assistant Plant Manager-Operations a asta Member: istant Plant Manager-Main -
Member: Oper g Superviso Member: Director-Radi al Program Member: Reac neering%9e.rvisor b Member: rol Systems Supervisc h N h .bI
. .b. . . . T.,,N. ...I[# N."[..a. . . .
g- ...r... ...
to ALTERNATES n InsrRP Cy 6.5.1.3 $"
alternate - -bers the. .: appointed !- - it! ; by the "C Chef ~ea h t: : rve en : t :p r:ry b;;ia; h; wever, n; ;;re4h;.n two ;1t rn:te:-:h:11 p:rtie g pt :: vetig ::: bare in TRC ectivtt4es-et ny One ti;t, oE b METINGFREQUENCY f Quirperson i 6.5.1.4 The FR l by the FRClh:1y::pa or 64+ designated alternate.shall meet at least once per cal RIVER BEND - UNIT 1 6-7 Amendment No. 17
. ADMINISTRATIVE CONTROLS QUORUM
- 6. 5.1. 5 The qt.wam of the FRC necessary for the performance of the FRC responsibility and authority provisions of these Technical Specifications shall consist of the Kh-i =p or Ms designated alternate and four members including no more than two alte na .
RESPONSIBILITIES '
- 6. 5.1. 6 The FRC shall be responsible for:
a.
Review of all plant general administrative procedures and changes thereto; b.
Review of all proposed tests and experiments that affect nuclear safety; c.
Review of all proposed changes to Appendix A Technical Specifications; d.
Review of all proposed changes or modifications to structures, compo-nents, systems or equipment that affect nuclear safety; e.
Investigation of all violations of the Technical Specifications, including the preparation and forwarding of reports covering evalua-tion and recommendations to prevent' recurrence, to the Senior Vice President - RBNG and the Nuclear Review Board;
- f. Review of all REPORTABLE EVENTS; *
Review of unit operations to detect potential hartNc to nuclear safety; items that may be included in this review are NU inspection reports that require written response, QA audits / surveil 16nce findings of operating and maintenance activities, NRB audit results, and Ameri-
' can Nuclear Insurer (ANI) inspection results; h.
Performance of special reviews, investigations, or analyses and reports thereon as requested by the Plant Manager or the Nuclear Review Board;
, i. Review ofand initial start-up testing phase start-up procedures and i revisions;
- j. Review of the Emergency Plan and implementation procedures at least once per 12 months and all proposed changes thereto.
- 6. 5.1. 7 The FRC shall:
a.
Recommend in writing to the Plant Manager approval or disapproval of a itonsimplementation.
their considered under Specification 6.5.1.6.a. through d. prior to b.
Render determinations in writing with regard to whether or not each item considered under Specification 6.5.1.6.a. through e. constitutes an unreviewed safety question.
c.
Provide written notification within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> to the Senior Vice l '
President - RBNG and the Nuclear Review Board of disagreement between the FRC and the Plant Manager; however, the Plant Manager shall have responsibility for resolution of such disagreements pursuant.to Speci-fication 6.1.1.
RIVER BEND - UNIT 1 6-8 Amendment No. 17
i ADMINISTRATIVE CONTROLS *
- l I
EUNCTION (Continued) gg are y
- a. Nuclear power plant operations.
t
- b. Nuclear engineering,
- c. Chemistry and radiochemistry.. . kc
+
%* g
- d. Metallurgy, c\g % n 0
- e. ./
f.
Instrumentation and control, Radiological safety, %7
\
h.
Mechanical and electrical engineering. g*trone*O Quality assurance practices,
- 1. Licensing and regulatory affairs,
- j. Training.
The NRB shall report to and advise the Senior Vice President --RBNG on those <
areas of responsibility in Specifications 6.5.3.7 and 6.5.3.8.
COMP 0$! TION 6.5.3.t the'MehD M 7 et-de'+H ng
- 4 =e - - "en;:r ? her S .d 5 :r.'
4embe d Vice Manager-Quality Assurance;5t -
Chairma 4 ember: Manager- Administration 4 ember: Manager-Design Engineer ,
Technical ces opar tomber: Manager- ering 4 ember: Pla nager ,
4embert sistant Plant ~ Man Operations and Radwaste 4 ember: Director-Design Engineer 4 ember: Director-Nuclear Licensing 4 ember: Outage Manager.
4e i '
Director-Joint Ownership Participation Si =trPhr.t 5:::';ht ALTERNATES
- 6. 5. A11 21**-a**= -
, n.
- 3. 3. . . . - - _ _ . . . . " . _j g n .g...., ;-s e M!! S .:- :!-ted . g. gS ge !ti .7....
- by th ".*.*
05:11 ;;rt'c';;t: = ntir.; d :r: i . ^:^^ ::thith: :t :../ := t'r.
i
, CONSULTANTS 6.5.3.4 Consultants shall be utilized 'as detemined by the NRS .to provide expert advice to the NRS.
cbsirperson
! RECEIVEO E f 919s RIVER BEND - UNIT 1 6-10 SDC- 4.end.ent no,:17;
i
.- i
. . . -. e i
i ADMINISTRATIVE CONTROLS i MEETING FREQUENCY I 6.5.3.5 The NR8 shall meet ft ' e t : : per e @ - er e:rt: 7 er y4 the 4-$ gag -
s ,
yter Akeess#ber.
? U-'t :;;retit: 1:11='y feel 1::dr4 =;" at least once per 6_ months.
QUORUM q .
6.5.3.6 e quor of the NRB necessary for the performance.of the NR8 review.
and au functions >
these Technical Specifications shal' ^1nsist of the
- 1 Lid or the Vice f_i-r and at leastWNR8 member 3 ..icluding no more than two alternates. No more than a minority of the quorum shall-have line .
responsibility for operation of the unit. =m #
a mjority of-the gg ~~ ,
6.5.3.7 The NR8 shall be responsible for the review ofi
- a. ?
i The safety evaluations for (1) changes to procedures,_ equipment, or systems; and (2)-tests or experiments completed under the proviston of 10 CFR 50.59-to verify that such actions did not constitute an '
l unreviewed safety question;
Proposed changes to procedures, equipment.-or systems which involve an unreviewed safety que'stion as defined in 10 CFR 50.59- *
- c. 1 Proposed tests or experiments which involve-an '
unreviewed safety.
- question as defined in 10 CFR 50.59;__
- d. ':
! Proposed changes to Technical Specifications-or this Operati_ng' License;- - ' ~
! e, ;
-Violations of codes,-regulations orders, Technical Specifications, license- requirements, or of internal < procedures ~ or: instructions, having nuclear safety significance; .
L f. Significant operating abnormalities or deviations from normal and--
l expected performance of unit equipment that' affect nuclear safety; j-. g. All REPORTA8LE EVENTS:
i h.
. All. recognized indications of at unanticipated deficiency-in(some j
aspect of design or operation of structures, systems,-or-components i that could affect nuclear. safety; and ~
- 1. )
Reports and meeting minutes'of the FRC. .
- AUDITS ' 1 y ~
3 6.5.3.8_ Audits of unit activities: shall be'perfoi t under the cognizance oft the NRB. These audits shall encompass:=
'f RIVER BEND' - UNIT 1 6-11l l
)