Letter Sequence Approval |
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MONTHYEARML20211N9981986-07-0303 July 1986
Safety Evaluation Supporting Actions Required by Generic Ltr 83-28,Item 4.5.1, Generic Implications of Salem ATWS Events
Project stage: Approval
ML20211N9931986-07-0303 July 1986
Forwards SER for Generic Ltr 83-28,Item 4.5.1, Generic Implications of Salem ATWS Event. TAC 59172 Closed.Salp Input Also Encl
Project stage: Approval
1986-07-03
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Category:SAFETY EVALUATION REPORT--LICENSING & RELATED ISSUES
MONTHYEARML17313A7791999-02-0505 February 1999
Safety Evaluation Accepting Licensee Rev to Emergency Plan That Would Result in Two Less Radiation Protection Positions Immediatelu Available During Emergencies
ML20210B5491986-09-0909 September 1986
Rev 1 to Staff Evaluation of Operator Performance,Emergency Operating Procedures & Relationship to CEN-152 Re 860712 Event at Facility.Diagnostic Aids Section of CEN-152 Should Be Revised to Eliminate Vagueness
ML20206U9481986-07-0303 July 1986
Safety Evaluation Accepting Util Response to Generic Ltr 83-28,Items 3.2.1 & 3.2.2 Re post-maint Testing of safety- Related Components Unrelated to Reactor Trip Sys
ML20211N9981986-07-0303 July 1986
Safety Evaluation Supporting Actions Required by Generic Ltr 83-28,Item 4.5.1, Generic Implications of Salem ATWS Events
ML20199F3641986-06-18018 June 1986
Safety Evaluation Supporting Licensee Response to Generic Ltr 83-28,Items 3.1.1 & 3.1.2 Re post-maint Testing of Reactor Trip Sys Components
ML20199F2731986-06-18018 June 1986
SER Supporting Util Responses to Generic Ltr 83-28,Item 4.1 Concerning Generic Implications of Salem ATWS Event.Item Closed
ML20129H7931984-12-14014 December 1984
Sser Re Fire Protection Program.Proposed License Condition for Fire Protection Program & SALP Input Encl
1999-02-05
[Table view]
Category:TEXT-SAFETY REPORT
MONTHYEARML17300B3811999-09-30030 September 1999
Monthly Operating Repts for Sept 1999 for Pvngs,Units 1,2 & 3.With 991007 Ltr
ML17300B3271999-08-31031 August 1999
Monthly Operating Rept for Aug 1999 for Pvngs,Units 1,2 & 3
ML17313B0751999-08-27027 August 1999
LER 99-002-00:on 990730,test Mode Trip Bypass for EDG Output Breakers Not Surveilled.Cause Under Investigation.Operations Personnel Conservatively Invoked SR 3.0.3 for SR 3.8.1.13. with 990827 Ltr
ML17313B0611999-07-31031 July 1999
Monthly Operating Repts for July 1999 for Pvngs,Units 1,2 & 3.With 990810 Ltr
ML17313B0191999-07-16016 July 1999
LER 99-005-00:on 990618,RT on Low DNBR Was Noted.Caused by Hardware Induced Calculation Error.Cr Operator Was Taken to Place Reactor in Stable Condition IAW Appropriate Operating Procedure
ML17300B3151999-06-30030 June 1999
Monthly Operating Repts for June 1999 for Pvngs,Units 1,2 & 3.With 990714 Ltr
ML17313A9921999-06-21021 June 1999
Special Rept:On 990525,RMS mini-computer Was Removed from Service to Implement Yr 2000 Mod & Was OOS Longer than 72 H Allowed.Caused by Planned Y2K Mods.Preplanned Alternate Sampling Program Was Initiated
ML17313A9911999-06-18018 June 1999
Special Rept:On 990510,loose-part Detection Sys Channel 2 Was Declared Inoperable.Caused by Malfunction of Mineral Cable Connector to Accelerometer.Licensee Will Implement Modifications Which Will Enhance loose-part Detection Sys
ML17313A9731999-05-31031 May 1999
Monthly Operating Repts for May 1999 for Pvngs,Units 1,2 & 3.With 990608 Ltr
ML17313A9281999-05-0707 May 1999
LER 99-004-00:on 990408,PSV Lift Pressures Were Outside of TS Limits.Caused by Lift Pressure Setpoint Drift.Psvs Have Been Tested,Disassembled,Inspected,Reassembled & Certified at Wyle Labs
ML17313A9201999-04-30030 April 1999
Monthly Operating Repts for Apr 1999 for Pvngs,Units 1,2 & 3.With 990512 Ltr
ML17313A8951999-04-14014 April 1999
LER 99-003-00:on 990317,required Surveillance Requirement Not Completed Due to Deficient Procedure,Was Determined. Caused by Cognitive Personnel Error.St Procedures Revised to Require Chiller to Be Operating & Oil Temperature Checked
ML17313A8921999-04-13013 April 1999
LER 98-003-01:on 980902,discovered That MSSV as-found Lift Pressures Were Outside TS Limits.Caused by Bonding of Valve Disc to Nozzle Seat.Affected Valves Were Adjusted,Retested & Returned to Svc
ML17313A8891999-04-0909 April 1999
LER 99-001-00:on 990310,RT on High Pressurizer Pressure Was Noted.Caused by Loss of Heat Removal.Cr Supervisor Was Removed from Shift Duties for Diagnostics Skills Training. with 990409 Ltr
ML17300B3071999-03-31031 March 1999
Seismic Portion of Submittal-Only Screening Review of Palo Verde Nuclear Generating Station Units Ipeee.
ML17313A8801999-03-31031 March 1999
Monthly Operating Repts for Mar 1999 for Pvngs,Units 1,2 & 3.With 990412 Ltr
ML20207M9231999-03-12012 March 1999
Amended Part 21 Rept Re Cooper-Bessemer Ksv EDG Power Piston Failure.Total of 198 or More Pistons Have Been Measured at Seven Different Sites.All Potentially Defective Pistons Have Been Removed from Svc Based on Encl Results
ML20207H7471999-03-10010 March 1999
1999 Emergency Preparedness Exercise 99-E-AEV-03003
ML17313A8361999-03-0101 March 1999
LER 99-001-00:on 990103,TS Violation for Power Dependent Insertion Limit Alarm Being Inoperable.Caused by Personnel Error.Revised Procedure to Clarify How Computer Point Is to Be Returned to Scan Mode.With 990302 Ltr
ML17313A8501999-02-28028 February 1999
Monthly Operating Repts for Feb 1999 for Palo Verde Nuclear Generating Station.With 990311 Ltr
ML17313A7791999-02-0505 February 1999
Safety Evaluation Accepting Licensee Rev to Emergency Plan That Would Result in Two Less Radiation Protection Positions Immediatelu Available During Emergencies
ML17313A8061999-01-31031 January 1999
Monthly Operating Repts for Jan 1999 for Pvngs,Units 1,2 & 3.With 990218 Ltr
ML17313A7701999-01-15015 January 1999
LER 96-008-00:on 960507,inadequate Procedure Results in Nuclear Power Channels Not Calibrated During Power Ascension Tests Occurred.Caused by Deficient Procedure.Procedure Revised
ML17313A7381998-12-31031 December 1998
Monthly Operating Repts for Dec 1998 for Palo Verde Nuclear Generating Station,Units 1,2 & 3.With 990113 Ltr
ML20206H2101998-12-31031 December 1998
SCE 1998 Annual Rept
ML17313A7031998-11-30030 November 1998
Monthly Operating Repts for Nov 1998 for Pvngs,Unit 1,2 & 3. with 981209 Ltr
ML17313A6701998-11-0404 November 1998
Rev 2 to PVNGS Unit 2 Colr.
ML17313A6741998-10-31031 October 1998
Monthly Operating Repts for Oct 1998 for Pvngs,Units 1,2 & 3.With 981109 Ltr
ML17313A6611998-10-24024 October 1998
LER 98-008-00:on 980729,EQ of Electrical Connectors Were Not Adequately Demonstrated.Caused Because Test Was Conducted with Only Single Lv Connector & Without Fully Ranged Inputs. Revised EQ Requirements
ML17313A6561998-09-30030 September 1998
Monthly Operating Rept for Sept 1998 for PVNGS Units 1,2 & 3.With 981007 Ltr
ML17313A5961998-09-14014 September 1998
LER 98-002-00:on 980814,B Train H Recombiner Was Noted Inoperable Due to cross-wired Power Receptacle.Cause of Event Is Under investigation.Cross-wired Power Supply Receptacle for B Train H Recombiner Was re-wired
ML17313A5761998-09-0808 September 1998
LER 98-003-01:on 980113,discovered That One Channel of RWT Level Sys Had Failed High.Caused by Water Intrusion Into Electrical Termination Pull Box.Weep Holes Were Drilled Into Bottoms of Pull Boxes Nearest Level Transmitters
ML17313A5591998-08-28028 August 1998
LER 98-001-00:on 980730,entered TS 3.0.3 Due to Safety Injection Flow Instruments Being Removed from Svc.Caused by Personnel Error.Transmitters Were Unisolated & Returned to svc.W/980828 Ltr
ML20151S0941998-08-21021 August 1998
Rev 6 to COLR for PVNGS Unit 3
ML20151S0861998-08-21021 August 1998
Rev 4 to COLR for PVNGS Unit 1
ML20151S0901998-08-21021 August 1998
Rev 1 to COLR for PVNGS Unit 2
ML18066A2771998-08-13013 August 1998
Part 21 Rept Re Deficiency in CE Current Screening Methodology for Determining Limiting Fuel Assembly for Detailed PWR thermal-hydraulic Sa.Evaluations Were Performed for Affected Plants to Determine Effect of Deficiency
ML17313A5401998-08-13013 August 1998
Special Rept:On 980715,declared PASS Inoperable.Caused by Failure of Offgas Flush/Purge Control Handswitch HS0101. Handswitch Replaced & Post Maintenance Retesting Was Initiated
ML17313A5301998-07-31031 July 1998
Monthly Operating Repts for July 1998 for Pvgns,Units 1,2 & 3.W/980812 Ltr
ML17313A5201998-07-30030 July 1998
LER 98-004-00:on 980630,personnel Discovered That Pressure Safety Valve Had Not Received Periodic Set Pressure Test for ASME Class 1 Pressure Safety Valve.Caused by Personnel Error.Pressure Safety Valve reviewed.W/980730 Ltr
ML17313A5791998-07-0707 July 1998
to PVNGS SG Tube ISI Results for Seventh Refueling Outage Mar & Apr 1998.
ML17313A5001998-06-30030 June 1998
Monthly Operating Repts for June 1998 for Palo Verde Nuclear Generating Station,Units 1,2 & 3.W/980710 Ltr
ML17313A4671998-06-19019 June 1998
LER 98-007-00:on 980520,CR Personnel Observed Flow & Pressure Perturbations on Chemical & Vol Control Sys Letdown Sys.Caused by Cyclic Fatigue Due to Dynamic Pressure Transients.Unit Letdown Piping Replaced
ML17313A4521998-06-19019 June 1998
Rev 5 to COLR for Pvngs,Unit 3.
ML17313A4501998-06-19019 June 1998
Rev 4 to COLR for Pvngs,Unit 3.
ML17313A4131998-06-0505 June 1998
LER 98-006-00:on 980507,determined That Plant Was Outside Design Basis Due to SI Discharge Check Valve Reverse Flow. Check Valve Was Disassembled,Examined & Reassembled, Whereupon Valve Met Acceptance Criteria
ML17313A4211998-05-31031 May 1998
Monthly Operating Repts for May 1998 for Pvngs,Units 1,2 & 3.W/980609 Ltr
ML17313A3951998-05-26026 May 1998
LER 98-005-00:on 980428,noted That Required Response Time Testing Had Not Been Performed.Caused by Personnel Error. Coached I&C Personnel Responsible for Reviewing Work Authorization Documentation
ML17313A3691998-04-30030 April 1998
Monthly Operating Repts for Apr 1998 for PVNGS.W/980412 Ltr
ML17313A3251998-04-0101 April 1998
LER 98-004-00:on 980304,safety Valves as-found Pressures Out of Tolerance.Cause of Event Is Under Investigation.Three Mssv'S & Psv Will Be Replaced W/Refurbished & Recertified Valves During Refueling Outage U1R7
1999-09-30
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Text
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SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION GENERIC IMPLICATIONS OF SALEM ATWS EVENT GENERIC LETTER 83-28, ITEM 4.5.1 ARIZONA PUBLIG SERVICE COMPANY, ET AL.
PALO VERDE NUCLEAR GENERATING STATION, UNITS 1, 2 AhT 3 DOCKET NOS. STN 50-528, 50-529 AND 50-530 I. INTRODUCTION On February 25, 1983, during startup of the Salem Unit 1 Nuclear Plant, both circuit breakers in the Reactor Trip System failed to open automatically upon receipt of a valid trip signal. As a result of that event, the NRC's Office of Inspection and Enforcement issued IE Bulletin 83-01 which described the event and requested specified prompt corrective and preventive actions by licensees. As the cause and ramifications of the event were more clearly developed, the NRC's Office of Nuclear Reactor Regulation issued on July 8, 1983, Generic Letter 83-28, " Required Actions Based on Generic Implications of Salem ATWS Events." This letter addressed issues related to reactor trip systen reliability and general management capability. The letter was sent to all licensees of operating reactors, applicants for operating licenses and holders of construction permits.
One of the areas of reactor trip system reliability considered in Generic Letter 83-28 (GL 83-28), is that of system functional testing.
This is identified in GL 83-28 as Item 4.5.1. This evaluation addresses the acceptability of the response to this item provided by Arizona Public Service Company, et al. (APS) for the Palo Verde Nuclear Generating Station, Units 1, 2 and 3 (PVNGS).
II. EVALUATION Item 4.5.1. of GL 83-28 states "On-line functional testing of therreactor trip system, including independent testing of the diverse trip features, shall be performed on all plants.
"1. The diverse trip features to be tested include the breaker undervoltage and shunt trip features on ... CE Plants."
By letter dated November 3, 1983, APS responded to a number of GL 83-28 items, including Item 4.5.1.
Regarding Item 4.5.1, this letter stated testing of undervoltage and shunt trip features would be covered by station procedures in accordance with the requirements of the PVNGS Technical Specifications. APS added that the design of the system permitted and the applicable procedures would require that such testing be performed while the plant was on-line, and thac the procedures should be approved by January 1, 1984.
kP
1 In reviewing this matter, the staff noted facility technical specification 4.3.1.1, Table 4.3-1, requires a functional test of the reactor trip breakers both monthly and every 18 months. However, although the specification requires independent testing of both the undervoltage and shunt trips "At least once per 18 months and following maintenance or adjustment of the reactor trip breakers...", there is no explicit requirement this be done while the plant is on-line.
Therefore, because 18 months is a typical interval between refueling outages, it would be possible (within the wording of the technical specifications and if breaker maintenance was infrequent) for all independent testing of the redundant trip features to be performed when the plant was shutdown for refueling, i.e. not "on-line".
In addition to the 18 month test requirement, the other factor controlling the frequency of testing the diverse trip features is the performance of maintenance on the reactor trip breakers. This maintenance is the i subject of Item 4.2.1 of Generic Letter 83-28. In Attachment 2 to the 1 APS letter of April 19, 1985, APS addresses this item and commits to perform preventive maintenance on each reactor trip breaker each six months. APS also states in response to this item that a surveillance test will be performed following any maintenance on the reactor trip breakers, and that the surveillance will verify the independent trip functions of the undervoltage and shunt trip coils. Inasmuch as the six month maintenance interval will frequently occur while the plant is operating, we conclude independent testing of the undervoltage and 4
shunt trip features will occur both when the plant is "on-line" and when it is shutdown.
Note: The acceptability of the six month test interval, as implicitly defined by the preventive maintenance program for the reactor trip breakers, is addressed by item 4.5.3 of Generic Letter 83-28.
III. CONCLUSION e-
! Based on the surveillance requirements of facility technical
- specification 4.3.1.1, and the commitment by APS to perform preventive maintenance and post-maintenance surveillance on the reactor trip breakers at six month intervals, we conclude APS will acceptably perform for PVNGS, the actions requested by Item 4.5.1 of Generic Letter 83-28.
- Accordingly, this item is closed.
1 l
3 Date:
, Principal Contributor:
G. Zwetzig l
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