|
|
| Line 18: |
Line 18: |
| | Title = Forwards LER 97-001-00,providing Details Concerning Reactor Scram from 100 Percent Power Resulting from Personnel Error During Surveillance Testing | | | Title = Forwards LER 97-001-00,providing Details Concerning Reactor Scram from 100 Percent Power Resulting from Personnel Error During Surveillance Testing |
| | Plant = | | | Plant = |
| | Reporting criterion = | | | Reporting criterion = 10 CFR 50.73(a)(2)(iv) |
| | Power level = | | | Power level = |
| | Mode = | | | Mode = |
| | Docket = 05000260 | | | Docket = 05000260 |
| | LER year = 2097 | | | LER year = 1997 |
| | LER number = 1 | | | LER number = 1 |
| | LER revision = | | | LER revision = 0 |
| | Event date = | | | Event date = |
| | Report date = | | | Report date = |
| Line 32: |
Line 32: |
|
| |
|
| =text= | | =text= |
| {{#Wiki_filter:- , _. _ . _ ~_, _ _ . _ _ _ - . _ - .- . - . _ . | | {{#Wiki_filter:- |
| . .' i 4 -
| | ~_, |
| Tennessee Valley Authority, Post Office Box 2000, Decatur, Alabama 35609-2000 i Christopher M. (Chris) Crane ' | | i 4 |
| Vice President, Browns Ferry Nuclear Plant May 23, 1997 i | | Tennessee Valley Authority, Post Office Box 2000, Decatur, Alabama 35609-2000 i |
| U.S. Nuclear Regulatory Commission 10 CFR 50.73 - | | Christopher M. (Chris) Crane Vice President, Browns Ferry Nuclear Plant May 23, 1997 i |
| ATTN: Document Control Desk Washington, D.C. 20555 | | U.S. Nuclear Regulatory Commission 10 CFR 50.73 ATTN: |
| | Document Control Desk Washington, D.C. |
| | 20555 |
|
| |
|
| ==Dear Sir:== | | ==Dear Sir:== |
|
| |
| BROWNS FERRY NUCLEAR PLANT (BFN) - UNIT 2, DOCKET NO. 50- 260 | | BROWNS FERRY NUCLEAR PLANT (BFN) - UNIT 2, DOCKET NO. 50- 260 |
| - FACILITY OPERATING LICENSE DPR LICENSEE EVENT REPORT ,
| | :- FACILITY OPERATING LICENSE DPR LICENSEE EVENT REPORT 50-260/97001 The enclosed report provides details concerning a reactor scram from 100 percent power. |
| 50-260/97001 The enclosed report provides details concerning a reactor scram from 100 percent power. This event resulted from a personnel error during surveillance testing. This report is i submitted in accordance with 10 CFR 50.73 (a) (2) (iv) as a ' | | This event resulted from a personnel error during surveillance testing. |
| condition that resulted in an automatic actuation of an engineered safety feature, including the reactor protection system. | | This report is i |
| | submitted in accordance with 10 CFR 50.73 (a) (2) (iv) as a condition that resulted in an automatic actuation of an engineered safety feature, including the reactor protection system. |
| Sincerely, M | | Sincerely, M |
| C. M Crane ; | | C. M Crane cc: |
| cc: See page 2 1 l | | See page 2 1 |
| -(/ &/? $4
| | -( &/? $4 |
| , \
| | \\ |
| i l | | / |
| 040001 9706040257 970523 l PDR ADOCK 05000260 g PDR llEllllllllllRillll,ll4lllli e 4 4 3 6 A | | i 040001 9706040257 970523 PDR ADOCK 05000260 g |
| * Perdad rm astvDd psier
| | PDR llEllllllllllRillll,ll4lllli e |
| | 4 4 |
| | 3 6 |
| | A Perdad rm astvDd psier |
|
| |
|
| . l 1
| | 1 U.S. Nuclear Regulatory Commission Page 2 May 23, 1997 1 |
| I U.S. Nuclear Regulatory Commission Page 2 May 23, 1997 '
| | 1 Enclosure cc Enclosure): |
| 1 1 | | Mr. Mark S. Lesser, Branch Chief U.S. Nuclear Regulatory Commission Region II |
| Enclosure ' | | ] |
| cc Enclosure): | | 61 Forsyth Street, S. W. |
| Mr. Mark S. Lesser, Branch Chief U.S. Nuclear Regulatory Commission Region II 61 Forsyth Street, S. W. ] | | Suite 23T85 f |
| ! Suite 23T85 f Atlanta, Georgia 30303 l NRC Resident Inspector l
| | Atlanta, Georgia 30303 l |
| Browns Ferry Nuclear Plant 10833 Shaw Road Athens, Alabama 35611 Mr. J. F. Williams, Project Manager I U.S. Nuclear Regulatory Commission i One White Flint, North i l | | NRC Resident Inspector l |
| 11555 Rockville Pike Rockville, Maryland 20852 l . | | Browns Ferry Nuclear Plant 10833 Shaw Road Athens, Alabama 35611 Mr. J. |
| ,
| | F. Williams, Project Manager U.S. Nuclear Regulatory Commission i |
| | One White Flint, North i |
| | l 11555 Rockville Pike Rockville, Maryland 20852 l |
| }} | | }} |
|
| |
|
| {{LER-Nav}} | | {{LER-Nav}} |
LER-1997-001, Forwards LER 97-001-00,providing Details Concerning Reactor Scram from 100 Percent Power Resulting from Personnel Error During Surveillance Testing |
| Event date: |
|
|---|
| Report date: |
|
|---|
| Reporting criterion: |
10 CFR 50.73(a)(2)(iv), System Actuation |
|---|
| 2601997001R00 - NRC Website |
|
text
-
~_,
i 4
Tennessee Valley Authority, Post Office Box 2000, Decatur, Alabama 35609-2000 i
Christopher M. (Chris) Crane Vice President, Browns Ferry Nuclear Plant May 23, 1997 i
U.S. Nuclear Regulatory Commission 10 CFR 50.73 ATTN:
Document Control Desk Washington, D.C.
20555
Dear Sir:
BROWNS FERRY NUCLEAR PLANT (BFN) - UNIT 2, DOCKET NO. 50- 260
- - FACILITY OPERATING LICENSE DPR LICENSEE EVENT REPORT 50-260/97001 The enclosed report provides details concerning a reactor scram from 100 percent power.
This event resulted from a personnel error during surveillance testing.
This report is i
submitted in accordance with 10 CFR 50.73 (a) (2) (iv) as a condition that resulted in an automatic actuation of an engineered safety feature, including the reactor protection system.
Sincerely, M
C. M Crane cc:
See page 2 1
-( &/? $4
\\
/
i 040001 9706040257 970523 PDR ADOCK 05000260 g
PDR llEllllllllllRillll,ll4lllli e
4 4
3 6
A Perdad rm astvDd psier
1 U.S. Nuclear Regulatory Commission Page 2 May 23, 1997 1
1 Enclosure cc Enclosure):
Mr. Mark S. Lesser, Branch Chief U.S. Nuclear Regulatory Commission Region II
]
61 Forsyth Street, S. W.
Suite 23T85 f
Atlanta, Georgia 30303 l
NRC Resident Inspector l
Browns Ferry Nuclear Plant 10833 Shaw Road Athens, Alabama 35611 Mr. J.
F. Williams, Project Manager U.S. Nuclear Regulatory Commission i
One White Flint, North i
l 11555 Rockville Pike Rockville, Maryland 20852 l
|
|---|
|
|
| | | Reporting criterion |
|---|
| 05000260/LER-1997-001-05, :on 970424,reactor Scram Occurred During Surveillance Testing.Caused by Personnel Error.Affected Sys Were Restored to pre-event Conditions,Administered Personnel Corrective Actions & Briefed Maintenance |
- on 970424,reactor Scram Occurred During Surveillance Testing.Caused by Personnel Error.Affected Sys Were Restored to pre-event Conditions,Administered Personnel Corrective Actions & Briefed Maintenance
| 10 CFR 50.73(a)(2) | | 05000260/LER-1997-001, Forwards LER 97-001-00,providing Details Concerning Reactor Scram from 100 Percent Power Resulting from Personnel Error During Surveillance Testing | Forwards LER 97-001-00,providing Details Concerning Reactor Scram from 100 Percent Power Resulting from Personnel Error During Surveillance Testing | 10 CFR 50.73(a)(2)(iv), System Actuation | | 05000259/LER-1997-001-03, :on 970203,potential Overpressurization Containment Penetration Pipe Occurred Due to Thermal Expansion of Entrapped Water Was Identified.Plant Procedures Will Be Revised |
- on 970203,potential Overpressurization Containment Penetration Pipe Occurred Due to Thermal Expansion of Entrapped Water Was Identified.Plant Procedures Will Be Revised
| 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition
10 CFR 50.73(a)(2)(v), Loss of Safety Function
10 CFR 50.73(a)(2)(iv), System Actuation
10 CFR 50.73(a)(2)(i)
10 CFR 50.73(a)(2) | | 05000296/LER-1997-001-04, :on 970305,loss of Offsite Power on Unit 3 During Refueling Outage Resulted from Shorted Component. Replaced Relays Involved in Event W/Less Sensitive Relays |
- on 970305,loss of Offsite Power on Unit 3 During Refueling Outage Resulted from Shorted Component. Replaced Relays Involved in Event W/Less Sensitive Relays
| 10 CFR 50.73(a)(2)(v), Loss of Safety Function
10 CFR 50.73(a)(2)(vii), Common Cause Inoperability
10 CFR 50.73(a)(2)(iv), System Actuation
10 CFR 50.73(a)(2)(x)
10 CFR 50.73(a)(2)(viii)
10 CFR 50.73(a)(2) | | 05000296/LER-1997-001, Forwards LER 97-001-00 Re Loss of Offsite Power to Unit During Scheduled Refueling Outage Which Resulted in Auto Start of EDGs A,C & D | Forwards LER 97-001-00 Re Loss of Offsite Power to Unit During Scheduled Refueling Outage Which Resulted in Auto Start of EDGs A,C & D | 10 CFR 50.73(a)(2)(iv), System Actuation | | 05000296/LER-1997-002-03, :on 970410,HPCI Declared Inoperable.Caused by Personnel Error.Operations Personnel Stopped Instrument Mechanics Testing & Returned HPCI to Standby Readiness |
- on 970410,HPCI Declared Inoperable.Caused by Personnel Error.Operations Personnel Stopped Instrument Mechanics Testing & Returned HPCI to Standby Readiness
| 10 CFR 50.73(a)(2)(v), Loss of Safety Function
10 CFR 50.73(a)(2)(vii), Common Cause Inoperability
10 CFR 50.73(a)(2)(iv), System Actuation
10 CFR 50.73(a)(2)(i)
10 CFR 50.73(a)(2)(x)
10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition
10 CFR 50.73(a)(2)(viii)
10 CFR 50.73(a)(2) | | 05000259/LER-1997-002-02, :on 970314,inadequate CREVS Surveillance Instruction Was Identified During GL 96-01 Review.Caused by Deficient Procedure.Rev to O-SI-4.2.G-2 Was Made & SI Section Was Successfully Completed |
- on 970314,inadequate CREVS Surveillance Instruction Was Identified During GL 96-01 Review.Caused by Deficient Procedure.Rev to O-SI-4.2.G-2 Was Made & SI Section Was Successfully Completed
| 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications
10 CFR 50.73(a)(2)(1) | | 05000260/LER-1997-002-04, :on 970626,discovered That Four Surveillance Instructions (Sis) Did Not Fully Test All Relay Logic Combinations.Caused by Personnel Error.Verified Relay Contacts Operable & Revised Applicable SIs |
- on 970626,discovered That Four Surveillance Instructions (Sis) Did Not Fully Test All Relay Logic Combinations.Caused by Personnel Error.Verified Relay Contacts Operable & Revised Applicable SIs
| 10 CFR 50.73(a)(2)(v), Loss of Safety Function
10 CFR 50.73(a)(2)(vii), Common Cause Inoperability
10 CFR 50.73(a)(2)(iv), System Actuation
10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications
10 CFR 50.73(a)(2)(iii)
10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition
10 CFR 50.73(a)(2) | | 05000260/LER-1997-003, Forwards LER 97-003-00 Re Failure of HPCI Surveillance Instruction | Forwards LER 97-003-00 Re Failure of HPCI Surveillance Instruction | 10 CFR 50.73(a)(2)(v), Loss of Safety Function | | 05000259/LER-1997-003-01, Forwards LER 97-003-01,providing Assessment of Safety Consequences Which Was Inadvertently Omitted from Initial Rept | Forwards LER 97-003-01,providing Assessment of Safety Consequences Which Was Inadvertently Omitted from Initial Rept | 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition | | 05000296/LER-1997-003-01, :on 970314,Unit 3 Main Steam SRVs Pilot Cartridges Failed Setpoint Tolerance Bench Tests.Caused by Corrosion Bonding of SRV Pilot Disc/Seat Interface Resulting in Drifting.Main Steam SRV Pilot Replaced |
- on 970314,Unit 3 Main Steam SRVs Pilot Cartridges Failed Setpoint Tolerance Bench Tests.Caused by Corrosion Bonding of SRV Pilot Disc/Seat Interface Resulting in Drifting.Main Steam SRV Pilot Replaced
| 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability
10 CFR 50.73(a)(2)(iv), System Actuation
10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications
10 CFR 50.73(a)(2)(x)
10 CFR 50.73(a)(2)(iii)
10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition
10 CFR 50.73(a)(2)(viii)
10 CFR 50.73(a)(2)
10 CFR 50.73(a)(2)(i)(8) | | 05000260/LER-1997-003-03, :on 970711,determined That HPCI Turbine Speed Lower than Indicated.Caused by Improper Evaluation of Valve Leak.Work Orders to Troubleshoot HPCI Initiated |
- on 970711,determined That HPCI Turbine Speed Lower than Indicated.Caused by Improper Evaluation of Valve Leak.Work Orders to Troubleshoot HPCI Initiated
| 10 CFR 50.73(a)(2)(v), Loss of Safety Function
10 CFR 50.73(a)(2)(vii), Common Cause Inoperability
10 CFR 50.73(a)(2)(iv), System Actuation
10 CFR 50.73(a)(2) | | 05000259/LER-1997-003-04, :on 970812,potential for Containment Pressure to Exceed Design During Purging or Inerting If LOCA Occurred Due to Unanalyzed Suppression Pool Bypass Path Was Noted. Caused by Design Error.Revised Sys Operating Instructions |
- on 970812,potential for Containment Pressure to Exceed Design During Purging or Inerting If LOCA Occurred Due to Unanalyzed Suppression Pool Bypass Path Was Noted. Caused by Design Error.Revised Sys Operating Instructions
| 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition | | 05000260/LER-1997-004-03, :on 970909,TS Surveillances Were Not Performed During Refueling Outage Timeframe.Caused by Personnel Error. Incorporated Missed Snubber & Vacuum Breaker Surveillances Into Refueling Outage Schedule |
- on 970909,TS Surveillances Were Not Performed During Refueling Outage Timeframe.Caused by Personnel Error. Incorporated Missed Snubber & Vacuum Breaker Surveillances Into Refueling Outage Schedule
| 10 CFR 50.73(a)(2)(v), Loss of Safety Function
10 CFR 50.73(a)(2)(vii), Common Cause Inoperability
10 CFR 50.73(a)(2)(iv), System Actuation
10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications
10 CFR 50.73(a)(2)(iii)
10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition
10 CFR 50.73(a)(2) | | 05000260/LER-1997-004, Forwards LER 97-004-00,providing Details Re Failure to Perform Required Surveillances During Refueling Outage Time Frames as Required by TS | Forwards LER 97-004-00,providing Details Re Failure to Perform Required Surveillances During Refueling Outage Time Frames as Required by TS | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | | 05000296/LER-1997-004-02, :on 970414,unplanned Manual Start of EDG During Scheduled Redundant Start Test Occurred.Caused by Personnel Error.Edg 3D Shutdown & Returned to pre-event Configuration |
- on 970414,unplanned Manual Start of EDG During Scheduled Redundant Start Test Occurred.Caused by Personnel Error.Edg 3D Shutdown & Returned to pre-event Configuration
| 10 CFR 50.73(a)(2)(iv), System Actuation
10 CFR 50.73(a)(2)(i)
10 CFR 50.73(a)(2)(x)
10 CFR 50.73(a)(2)(iii)
10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition
10 CFR 50.73(a)(2)(viii)
10 CFR 50.73(o)(2)(vii) | | 05000259/LER-1997-004, Forwards LER 97-004-00 Re Discovery of non-conservative TS Lco.Will Submit TS Change Request to NRC to Remove non- Conservatism | Forwards LER 97-004-00 Re Discovery of non-conservative TS Lco.Will Submit TS Change Request to NRC to Remove non- Conservatism | 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition | | 05000259/LER-1997-004-04, :on 971010,discovered That RHR Swp LCO Is non- Conservative.Caused by Error in Preparation & Approval of Original TS 3.5.C.Will Submit TS Change to NRC to Remove non-conservatism from TS 3.5.C |
- on 971010,discovered That RHR Swp LCO Is non- Conservative.Caused by Error in Preparation & Approval of Original TS 3.5.C.Will Submit TS Change to NRC to Remove non-conservatism from TS 3.5.C
| 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition
10 CFR 50.73(a)(2) | | 05000260/LER-1997-005, Forwards LER 97-005-00,providing Details Concerning auto- Start of Engineered Safety Features.Event Resulted from Inadequate Procedure in That Procedure for Developing Post Mod Tests Did Not Require Task Risk Review | Forwards LER 97-005-00,providing Details Concerning auto- Start of Engineered Safety Features.Event Resulted from Inadequate Procedure in That Procedure for Developing Post Mod Tests Did Not Require Task Risk Review | 10 CFR 50.73(a)(2)(iv), System Actuation | | 05000260/LER-1997-005-03, :on 971012,ESF Components Were Actuated.Caused by Inadequate Procedure.Cs Pumps Were Secured & Injection Valves Were Closed & Refueling Floor Activities Were Stopped |
- on 971012,ESF Components Were Actuated.Caused by Inadequate Procedure.Cs Pumps Were Secured & Injection Valves Were Closed & Refueling Floor Activities Were Stopped
| 10 CFR 50.73(a)(2)(v), Loss of Safety Function
10 CFR 50.73(a)(2)(vii), Common Cause Inoperability
10 CFR 50.73(a)(2)(iv), System Actuation
10 CFR 50.73(a)(2)(i)
10 CFR 50.73(a)(2)(x)
10 CFR 50.73(a)(2)(iii)
10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition
10 CFR 50.73(a)(2)(viii) | | 05000296/LER-1997-005, Forwards LER 97-005-00,providing Details Concerning Failure to Enter LCO When Unit 3 Primary Containment Isolation Flow Control Valve Was Declared Inoperable Due to Sticking Solenoid Valve.Rsos Developed Mindset Re Failure Mech | Forwards LER 97-005-00,providing Details Concerning Failure to Enter LCO When Unit 3 Primary Containment Isolation Flow Control Valve Was Declared Inoperable Due to Sticking Solenoid Valve.Rsos Developed Mindset Re Failure Mechanism | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | | 05000296/LER-1997-005-02, :on 970824,LCO Was Not Entered When Valve Was Malfunctioning.Caused by Lack of Questioning Attitude by Operations Crew.Involved SROs Were Counseled & Problem Evaluation Rept Will Be Discussed |
- on 970824,LCO Was Not Entered When Valve Was Malfunctioning.Caused by Lack of Questioning Attitude by Operations Crew.Involved SROs Were Counseled & Problem Evaluation Rept Will Be Discussed
| 10 CFR 50.73(a)(2)(v), Loss of Safety Function
10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications
10 CFR 50.73(a)(2)(vi)
10 CFR 50.73(a)(2)(iii)
10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition
10 CFR 50.73(a)(2) | | 05000260/LER-1997-006-02, :on 971019,declared Unit 2 Hpcis Inoperable. Caused by High Condensate Level in HPCI Turbine Inlet Steam Line Drain Pot.Work Request Initiated |
- on 971019,declared Unit 2 Hpcis Inoperable. Caused by High Condensate Level in HPCI Turbine Inlet Steam Line Drain Pot.Work Request Initiated
| 10 CFR 50.73(a)(2)(v), Loss of Safety Function
10 CFR 50.73(a)(2)(vii), Common Cause Inoperability
10 CFR 50.73(a)(2)(iv), System Actuation
10 CFR 50.73(a)(2)(i)
10 CFR 50.73(a)(2)(x)
10 CFR 50.73(a)(2)(iii)
10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition
10 CFR 50.73(a)(2)(viii) | | 05000260/LER-1997-006, Forwards LER 97-006-00 Re Inoperable Unit 2 Hpcis Discovered During Power Ascension from Unit 2 Cycle 9 Refueling Outage. Rept Submitted in Accordance w/10CFR50.73(a)(2)(v) | Forwards LER 97-006-00 Re Inoperable Unit 2 Hpcis Discovered During Power Ascension from Unit 2 Cycle 9 Refueling Outage. Rept Submitted in Accordance w/10CFR50.73(a)(2)(v) | 10 CFR 50.73(a)(2)(v), Loss of Safety Function | | 05000260/LER-1997-007-02, :on 971028,Unit 2 Automatically Scrammed.Caused by Momentary Pressure Drop in electro-hydraulic Control Sys at Turbine Control Valves.Scram Contactor Replaced |
- on 971028,Unit 2 Automatically Scrammed.Caused by Momentary Pressure Drop in electro-hydraulic Control Sys at Turbine Control Valves.Scram Contactor Replaced
| 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability
10 CFR 50.73(a)(2)(iv), System Actuation
10 CFR 50.73(a)(2)(i)
10 CFR 50.73(a)(2)(x)
10 CFR 50.73(a)(2)(iii)
10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition
10 CFR 50.73(a)(2)(viii) | | 05000260/LER-1997-007, Forwards LER 97-007-00 Re Reactor Scram from 70 Percent Power.Event Resulted from Pressure Perturbation in electro- Hydraulic Control Sys at Turbine Control Valves | Forwards LER 97-007-00 Re Reactor Scram from 70 Percent Power.Event Resulted from Pressure Perturbation in electro- Hydraulic Control Sys at Turbine Control Valves | 10 CFR 50.73(a)(2)(iv), System Actuation | | 05000260/LER-1997-008, Forwards LER 97-008-00,which Provides Details Re Main Steam Safety/Relief Valves That Exceeded TS Setpoint Limit During Surveillance Tests | Forwards LER 97-008-00,which Provides Details Re Main Steam Safety/Relief Valves That Exceeded TS Setpoint Limit During Surveillance Tests | | | 05000260/LER-1997-008-02, :on 971104,main Steam Safety/Relief Valves Exceeded TS Setpoint Limit.Caused by Pilot Valve Disc/Seat Bonding.Replaced All 13 Unit 2 Main Steam SRV Pilot Cartridges |
- on 971104,main Steam Safety/Relief Valves Exceeded TS Setpoint Limit.Caused by Pilot Valve Disc/Seat Bonding.Replaced All 13 Unit 2 Main Steam SRV Pilot Cartridges
| 10 CFR 50.73(a)(2)(v), Loss of Safety Function
10 CFR 50.73(a)(2)(iv), System Actuation
10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications
10 CFR 50.73(a)(2)(x)
10 CFR 50.73(a)(2)(viii)
10 CFR 50.73(a)(2) |
|
