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Category:INTERNAL OR EXTERNAL MEMORANDUM
MONTHYEARML20217A8641999-10-0606 October 1999 Forwards NRC Approved Operator Licensing Exam (Facility Outline & Initial Exam Submittal & as-given Operating Exam) for Tests Administered on 990829-0903 ML20211H4441999-08-27027 August 1999 Notification of Significant Meeting with Util on 990916 & 17 in Arlington,Tx to Improve Utility & NRC Understanding of Industry & Regulatory Perspectives on Current Issues ML20138K0131997-05-0606 May 1997 Forwards NRC Approved Operator Licensing Exam (Facility Outline & Initial Exam Submittal) for Tests Administered on 970324-28 ML20138K0091997-05-0606 May 1997 Forwards NRC Approved Operator Licensing Exam (as-given Operating Exam) for Tests Administered on 970324-28 ML20137F2351997-03-24024 March 1997 Summary of 970207 Meeting W/Listed Attendees in Rockville,Md to Discuss Nuclear Energy Inst Concerns Re Graded Quality Assurance Activities W/Volunteer Plants ML20137C9201997-03-20020 March 1997 Forwards Documentation of Meeting Conducted in Region 4 Office on 970225 to Discuss NRC Enforcement Policy as Applied to Nonescalated Enforcement ML20135E7161997-03-0303 March 1997 Forwards NRC Approved Operator Licensing Exam (Facility Outline & Initial Exam Submittal & as-given Operating Exam) for Tests Administered on 961118-22 ML20134P2231997-02-20020 February 1997 Discusses Ti 2515/122 Evaluation or Rosemount Pressure Transmitter Performance & Licensee Enhanced Surveillance Programs multi-plant Action B-122 ML20134M2471997-02-14014 February 1997 Submits List of Plants Not Meeting Selection Criteria for Ti 2515/118 Insp on Basis of Factors Such as SWS Operating Experience,Contribution of SWS to Plant Risk Assessment, Licensee Programs in Response to GL-89-13 ML20236U9391995-12-20020 December 1995 Discusses Oi,Region IV Rept of Investigation,Dtd 940511, Case 5-93-023R,which Reported OI Investigative Efforts Re Alleged Employee Discrimination at Plant Units 1,2 & 3.Rept Was Sent to Us Attorney Office in Phoenix,Az in May 1994 IA-96-341, Discusses Allegation RV-94-A-0004,Songs Vendor Manuals. Licensee Reviewed Allegation,Concluded Unfounded & Notified NRC for Conclusion by 940228 Ltr1994-08-0303 August 1994 Discusses Allegation RV-94-A-0004,Songs Vendor Manuals. Licensee Reviewed Allegation,Concluded Unfounded & Notified NRC for Conclusion by 940228 Ltr ML20138F9871994-08-0303 August 1994 Discusses Allegation RV-94-A-0004,Songs Vendor Manuals. Licensee Reviewed Allegation,Concluded Unfounded & Notified NRC for Conclusion by ML20056E5141993-08-12012 August 1993 Submits SALP Schedule for FY94 Per Mgt Directive 8.6 ML20198E3271992-10-20020 October 1992 Notification of Significant Licensee Meeting W/Util on 921027 to Discuss Transfer of Fire Watch Responsibilities to Security Dept & Ongoing Programs within Security Dept ML20126L8441992-09-14014 September 1992 Provides Status Rept Concerning Actions Re Det Performed at Plant ML20127C2461992-03-0202 March 1992 Forwards AEOD SALP Input for Facilities in Support of Ongoing SALP Reviews.Two of Six Important Operating Events Involved Deficiencies of Reactor Power Cutback Sys Which Relies on Proper Functioning of Steam Bypass to Condenser IA-92-218, Forwards Updated Status Rept on Actions Re Diagnostic Evaluation Performed at Facility1990-12-31031 December 1990 Forwards Updated Status Rept on Actions Re Diagnostic Evaluation Performed at Facility ML20127B6281990-12-31031 December 1990 Forwards Updated Status Rept on Actions Re Diagnostic Evaluation Performed at Facility ML20127B5671990-12-12012 December 1990 Forwards NRR Input for SALP Rept,Per NRC Ofc Ltr 907,Rev 1 ,NRC Manual Chapter 0516 & 901120 Memo ML20059M2041990-09-27027 September 1990 Notification of Significant Licensee Meeting W/Util on 901003 to Discuss Licensee Response to Diagnostic Evaluation Team Findings & Overall Status of Programs. Addl NRC Attendees Should Be Made Known by 901002 ML20059L6531990-09-20020 September 1990 Notification of 900921 Meeting W/Util in Walnut Creek,Ca to Discuss Licensee Initiatives & Status in Area of QA ML20059D6361990-08-27027 August 1990 Notification of 900831 Enforcement Conference W/Util in Walnut Creek,Ca to Discuss Medical Qualifications & Exams of Licensed Operators ML20127B4571990-08-24024 August 1990 Comments on Response to Facility Diagnostic Evaluation Team Rept.Suggests That Region V Followup & Closely Monitor Development & Implementation of Specific Tasks Which Will Address Team Findings ML20058M3441990-08-0606 August 1990 Forwards List of Open Items in Sims for Plant.Documented Basis Exists for Closure of TMI Related Items at Plant ML20126L8271990-06-14014 June 1990 Provides Summary of Schedule & Status of Items Re Det of Plant Performed by Aeod,In Response to 900314 Memo ML20055C3521990-02-26026 February 1990 Notification of 900305 Meeting W/Util in Rockville,Md to Discuss Status of Licensing Activities for Facility ML20127B2171990-01-18018 January 1990 Forwards AEOD Input for Commissioner Curtiss Visit to Plant on 900201,consisting of Summary of Operating Experience from Oct 1988 to Dec 1989 ML20127B1681989-11-0909 November 1989 Forwards NRR Input to SALP for Facilities.Category 2 Rating Assigned in Functional Areas of Plant Operations, Radiological Controls,Emergency Preparedness,Security & Safety Assessment/Quality Verification ML20248E9391989-09-29029 September 1989 Forwards AEOD Technical Review Rept on Debris in Containment Recirculation Pumps.No Occurrences Found to Involve Actual Accumulation of Debris in Containment Sumps.Immediate Corrective Actions Completed ML20248C8311989-09-20020 September 1989 Request for Hearing by Alchemie.* Forwards Response & Request for Hearing,In Response to NRC 890818 Order Modifying License & Order to Show Cause Why Licenses Should Not Be Revoked,For Appropriate Action ML20247H9261989-09-0909 September 1989 Advises That SALP Meeting for Facilities Scheduled for 891115.Assessment Input Should Be Submitted by 891016 ML20246N7371989-08-29029 August 1989 Notification of Maint Team Insp Meeting on 890901 W/Util in Phoenix,Az to Discuss Status of Licensee Commitments from 890605 Mgt Meeting in Consideration of Unit 3 Restart ML20127B1401989-08-0707 August 1989 Forwards for Info & Consideration for Info Notice,Lers Describing Potter & Brumfield Relay Problems & Atmospheric Dump Valve Deficiencies.Info Provided as Part of AEOD Function to Identify Potential Adverse Events ML20245E8501989-08-0707 August 1989 Advises of Reassignments in Project Mgt Duties Due to Recent Reorganization of Standardization & Life Extension Project Directorate ML20245H6451989-08-0404 August 1989 Requests Closure of Outstanding Action Item 87-0198,per 870617 Request Re Review & Evaluation of Acceptability of Fairbanks-Morse Diesel Generator Bearings.Action Completed W/Submittal of Transfer of Lead Responsibility to NRR ML20248D1431989-07-27027 July 1989 Forwards Proposed Generic Ltr Requesting Voluntary Licensee Participation in ERDS & Requests That Proposed Generic Ltr Be Sent to All Licensees of Power Reactors,Except for Participants & Licensees of Listed Plants ML20247B7541989-07-19019 July 1989 Confirms That Licensee 880711,890221 & 0630 Responses to NRC Bulletin 88-004, Potential Safety-Related Pump Loss, Acceptable.Licensing Action for TACs 69886,69887,69893 & 69894 Considered Complete ML20247E6721989-07-17017 July 1989 Proposes Closeout of Plant Correspondence Control Ticket Re Environ Conservation Organization Request for Notification Whenever License Amend Requests Result in Impairment of Plant Operability.Intervenor Will Be Placed on Svc List ML20246K5991989-07-12012 July 1989 Notification of 890725 Meeting W/Util in Birmingham,Al to Discuss Status of Current Licensing Activities & Corporate Initiatives for Plants.Meeting Agenda Encl ML20246L6801989-07-10010 July 1989 Notification of Significant Licensee Meeting 89-101 W/Util on 890718 in King of Prussia,Pa to Discuss Util Engineering Reorganization ML20247A9561989-07-0606 July 1989 Notification of 890717 Meeting W/Lead Plant Utils in Rockville,Md to Discuss Implementation of Revised STS ML20246H3771989-05-12012 May 1989 ALAB-913.* Advises That Time Provided within Which Commission May Act to Review Aslab Decision ALAB-913 Expired.Commission Declined Review.Decision Became Final on 890501.W/Certificate of Svc.Served on 890512 ML20246P9601989-05-10010 May 1989 Discusses 890413 Meeting W/Rosemount & Industry Re Malfunctions of Rosemount Transmitters.List of Attendess, Agenda,Nrc Info Notice 89-042 & Viewgraphs Encl ML20245E9781989-04-17017 April 1989 Forwards Regulatory History AC83-2 Re Licensee Action During Natl Security emergency,10CFR50 (54FR7178) ML20245B7501989-04-15015 April 1989 Forwards Engineering Evaluation Rept on BWR Overfill Events Resulting in Flooding of Steam Lines.Potential for Equipment Damage Believed to Exist & Any Damage Occurring Should Be Fixed Prior to Restart ML20245B6531989-04-15015 April 1989 Forwards Evaluation Rept on BWR Overfill Events Resulting in Flooding of Steam Lines.Events Determined to Involve Deficiencies in Control Sys ML20245B6421989-04-15015 April 1989 Forwards Engineering Evaluation Rept on BWR Overfill Events Resulting in Steam Line Flooding.Though Little Actual Damage Experienced,Potential for Equipment Damage Believed to Exist & Any Damage Occurring Should Be Fixed Prior to Restart ML20245B6191989-04-15015 April 1989 Forwards Evaluation Rept Re BWR Overfill Events Resulting in Steam Line Flooding.All Events Included Reactor Depressurization Followed by Uncontrolled Condensate or Condensate Booster Pumps Injection or Both ML20244E2681989-04-12012 April 1989 Summary of Operating Reactors Events Meeting 89-015 on 890412.Discussion of Events,List of Attendees & Three Significant Items Identified for Input Into NRC Performance Indicator Program & Summary of Reactor Scrams Also Encl ML20244A5571989-04-10010 April 1989 Notification of 890502 Meeting W/Util in Rockville,Md to Discuss Nonlinear Piping Analysis to Remove Snubbers & Pipe Supports 1999-08-27
[Table view] Category:MEMORANDUMS-CORRESPONDENCE
MONTHYEARML20217A8641999-10-0606 October 1999 Forwards NRC Approved Operator Licensing Exam (Facility Outline & Initial Exam Submittal & as-given Operating Exam) for Tests Administered on 990829-0903 ML20211H4441999-08-27027 August 1999 Notification of Significant Meeting with Util on 990916 & 17 in Arlington,Tx to Improve Utility & NRC Understanding of Industry & Regulatory Perspectives on Current Issues ML20138K0091997-05-0606 May 1997 Forwards NRC Approved Operator Licensing Exam (as-given Operating Exam) for Tests Administered on 970324-28 ML20138K0131997-05-0606 May 1997 Forwards NRC Approved Operator Licensing Exam (Facility Outline & Initial Exam Submittal) for Tests Administered on 970324-28 ML20137F2351997-03-24024 March 1997 Summary of 970207 Meeting W/Listed Attendees in Rockville,Md to Discuss Nuclear Energy Inst Concerns Re Graded Quality Assurance Activities W/Volunteer Plants ML20137C9201997-03-20020 March 1997 Forwards Documentation of Meeting Conducted in Region 4 Office on 970225 to Discuss NRC Enforcement Policy as Applied to Nonescalated Enforcement ML20135E7161997-03-0303 March 1997 Forwards NRC Approved Operator Licensing Exam (Facility Outline & Initial Exam Submittal & as-given Operating Exam) for Tests Administered on 961118-22 ML20134P2231997-02-20020 February 1997 Discusses Ti 2515/122 Evaluation or Rosemount Pressure Transmitter Performance & Licensee Enhanced Surveillance Programs multi-plant Action B-122 ML20134M2471997-02-14014 February 1997 Submits List of Plants Not Meeting Selection Criteria for Ti 2515/118 Insp on Basis of Factors Such as SWS Operating Experience,Contribution of SWS to Plant Risk Assessment, Licensee Programs in Response to GL-89-13 ML20236U9391995-12-20020 December 1995 Discusses Oi,Region IV Rept of Investigation,Dtd 940511, Case 5-93-023R,which Reported OI Investigative Efforts Re Alleged Employee Discrimination at Plant Units 1,2 & 3.Rept Was Sent to Us Attorney Office in Phoenix,Az in May 1994 IA-96-341, Discusses Allegation RV-94-A-0004,Songs Vendor Manuals. Licensee Reviewed Allegation,Concluded Unfounded & Notified NRC for Conclusion by 940228 Ltr1994-08-0303 August 1994 Discusses Allegation RV-94-A-0004,Songs Vendor Manuals. Licensee Reviewed Allegation,Concluded Unfounded & Notified NRC for Conclusion by 940228 Ltr ML20138F9871994-08-0303 August 1994 Discusses Allegation RV-94-A-0004,Songs Vendor Manuals. Licensee Reviewed Allegation,Concluded Unfounded & Notified NRC for Conclusion by ML20056E5141993-08-12012 August 1993 Submits SALP Schedule for FY94 Per Mgt Directive 8.6 ML20198E3271992-10-20020 October 1992 Notification of Significant Licensee Meeting W/Util on 921027 to Discuss Transfer of Fire Watch Responsibilities to Security Dept & Ongoing Programs within Security Dept ML20126L8441992-09-14014 September 1992 Provides Status Rept Concerning Actions Re Det Performed at Plant ML20127C2461992-03-0202 March 1992 Forwards AEOD SALP Input for Facilities in Support of Ongoing SALP Reviews.Two of Six Important Operating Events Involved Deficiencies of Reactor Power Cutback Sys Which Relies on Proper Functioning of Steam Bypass to Condenser IA-92-218, Forwards Updated Status Rept on Actions Re Diagnostic Evaluation Performed at Facility1990-12-31031 December 1990 Forwards Updated Status Rept on Actions Re Diagnostic Evaluation Performed at Facility ML20127B6281990-12-31031 December 1990 Forwards Updated Status Rept on Actions Re Diagnostic Evaluation Performed at Facility ML20127B5671990-12-12012 December 1990 Forwards NRR Input for SALP Rept,Per NRC Ofc Ltr 907,Rev 1 ,NRC Manual Chapter 0516 & 901120 Memo ML20059M2041990-09-27027 September 1990 Notification of Significant Licensee Meeting W/Util on 901003 to Discuss Licensee Response to Diagnostic Evaluation Team Findings & Overall Status of Programs. Addl NRC Attendees Should Be Made Known by 901002 ML20059L6531990-09-20020 September 1990 Notification of 900921 Meeting W/Util in Walnut Creek,Ca to Discuss Licensee Initiatives & Status in Area of QA ML20059D6361990-08-27027 August 1990 Notification of 900831 Enforcement Conference W/Util in Walnut Creek,Ca to Discuss Medical Qualifications & Exams of Licensed Operators ML20127B4571990-08-24024 August 1990 Comments on Response to Facility Diagnostic Evaluation Team Rept.Suggests That Region V Followup & Closely Monitor Development & Implementation of Specific Tasks Which Will Address Team Findings ML20058M3441990-08-0606 August 1990 Forwards List of Open Items in Sims for Plant.Documented Basis Exists for Closure of TMI Related Items at Plant ML20126L8271990-06-14014 June 1990 Provides Summary of Schedule & Status of Items Re Det of Plant Performed by Aeod,In Response to 900314 Memo ML20055C3521990-02-26026 February 1990 Notification of 900305 Meeting W/Util in Rockville,Md to Discuss Status of Licensing Activities for Facility ML20127B2171990-01-18018 January 1990 Forwards AEOD Input for Commissioner Curtiss Visit to Plant on 900201,consisting of Summary of Operating Experience from Oct 1988 to Dec 1989 ML20127B1681989-11-0909 November 1989 Forwards NRR Input to SALP for Facilities.Category 2 Rating Assigned in Functional Areas of Plant Operations, Radiological Controls,Emergency Preparedness,Security & Safety Assessment/Quality Verification ML20248E9391989-09-29029 September 1989 Forwards AEOD Technical Review Rept on Debris in Containment Recirculation Pumps.No Occurrences Found to Involve Actual Accumulation of Debris in Containment Sumps.Immediate Corrective Actions Completed ML20248C8311989-09-20020 September 1989 Request for Hearing by Alchemie.* Forwards Response & Request for Hearing,In Response to NRC 890818 Order Modifying License & Order to Show Cause Why Licenses Should Not Be Revoked,For Appropriate Action ML20247H9261989-09-0909 September 1989 Advises That SALP Meeting for Facilities Scheduled for 891115.Assessment Input Should Be Submitted by 891016 ML20246N7371989-08-29029 August 1989 Notification of Maint Team Insp Meeting on 890901 W/Util in Phoenix,Az to Discuss Status of Licensee Commitments from 890605 Mgt Meeting in Consideration of Unit 3 Restart ML20245E8501989-08-0707 August 1989 Advises of Reassignments in Project Mgt Duties Due to Recent Reorganization of Standardization & Life Extension Project Directorate ML20127B1401989-08-0707 August 1989 Forwards for Info & Consideration for Info Notice,Lers Describing Potter & Brumfield Relay Problems & Atmospheric Dump Valve Deficiencies.Info Provided as Part of AEOD Function to Identify Potential Adverse Events ML20245H6451989-08-0404 August 1989 Requests Closure of Outstanding Action Item 87-0198,per 870617 Request Re Review & Evaluation of Acceptability of Fairbanks-Morse Diesel Generator Bearings.Action Completed W/Submittal of Transfer of Lead Responsibility to NRR ML20248D1431989-07-27027 July 1989 Forwards Proposed Generic Ltr Requesting Voluntary Licensee Participation in ERDS & Requests That Proposed Generic Ltr Be Sent to All Licensees of Power Reactors,Except for Participants & Licensees of Listed Plants ML20247B7541989-07-19019 July 1989 Confirms That Licensee 880711,890221 & 0630 Responses to NRC Bulletin 88-004, Potential Safety-Related Pump Loss, Acceptable.Licensing Action for TACs 69886,69887,69893 & 69894 Considered Complete ML20247E6721989-07-17017 July 1989 Proposes Closeout of Plant Correspondence Control Ticket Re Environ Conservation Organization Request for Notification Whenever License Amend Requests Result in Impairment of Plant Operability.Intervenor Will Be Placed on Svc List ML20246K5991989-07-12012 July 1989 Notification of 890725 Meeting W/Util in Birmingham,Al to Discuss Status of Current Licensing Activities & Corporate Initiatives for Plants.Meeting Agenda Encl ML20246L6801989-07-10010 July 1989 Notification of Significant Licensee Meeting 89-101 W/Util on 890718 in King of Prussia,Pa to Discuss Util Engineering Reorganization ML20247A9561989-07-0606 July 1989 Notification of 890717 Meeting W/Lead Plant Utils in Rockville,Md to Discuss Implementation of Revised STS ML20246D8841989-06-19019 June 1989 Staff Requirements Memo Re 890601 Briefing on Operating Reactors & Fuel Facilities in Rockville,Md.Commission Expressed Disappointment in Long Term Operating Performance of Turkey Point Nuclear Power Plant ML20246H3771989-05-12012 May 1989 ALAB-913.* Advises That Time Provided within Which Commission May Act to Review Aslab Decision ALAB-913 Expired.Commission Declined Review.Decision Became Final on 890501.W/Certificate of Svc.Served on 890512 ML20246P9601989-05-10010 May 1989 Discusses 890413 Meeting W/Rosemount & Industry Re Malfunctions of Rosemount Transmitters.List of Attendess, Agenda,Nrc Info Notice 89-042 & Viewgraphs Encl NUREG-1353, Board Notification 89-003:forwards Listed Documents Re Spent Fuel Pool Accidents for Resolution of Generic Issue 82, Beyond DBA in Spent Fuel Pools, Including NUREG-13531989-05-0202 May 1989 Board Notification 89-003:forwards Listed Documents Re Spent Fuel Pool Accidents for Resolution of Generic Issue 82, Beyond DBA in Spent Fuel Pools, Including NUREG-1353 ML20245E9781989-04-17017 April 1989 Forwards Regulatory History AC83-2 Re Licensee Action During Natl Security emergency,10CFR50 (54FR7178) ML20245B7501989-04-15015 April 1989 Forwards Engineering Evaluation Rept on BWR Overfill Events Resulting in Flooding of Steam Lines.Potential for Equipment Damage Believed to Exist & Any Damage Occurring Should Be Fixed Prior to Restart ML20245B6531989-04-15015 April 1989 Forwards Evaluation Rept on BWR Overfill Events Resulting in Flooding of Steam Lines.Events Determined to Involve Deficiencies in Control Sys ML20245B6421989-04-15015 April 1989 Forwards Engineering Evaluation Rept on BWR Overfill Events Resulting in Steam Line Flooding.Though Little Actual Damage Experienced,Potential for Equipment Damage Believed to Exist & Any Damage Occurring Should Be Fixed Prior to Restart ML20245B6191989-04-15015 April 1989 Forwards Evaluation Rept Re BWR Overfill Events Resulting in Steam Line Flooding.All Events Included Reactor Depressurization Followed by Uncontrolled Condensate or Condensate Booster Pumps Injection or Both 1999-08-27
[Table view] |
Text
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8
[ 'o,,
o UNITED STATES NUCLEAR REGULATORY COMMISSION 3 .I ADVISORY COMMITTEE ON REACTOR SAFEGUARDS
%...../ September 11, 1985 MEMORANDUM FOR: C. Wylie, Chairman, CE System 80 Subcormiittee o ACRS Members FROM:
G.A. Reed [
SUBJECT:
Attached Morning Report on Palo Verde Incident You are acquainted with my position that the Palo Verde (CE System 80) units had " lean" systems as far as assured core cooling was concerned and that my opinion favored the inclusion of a PORV system. (ACRS letters in
. the past have expressed concern about the noninclusion of PORVs in the i System 80 design.) The attached Morning Report of August 25, 1985 indi-cates to me that reliance by CE on Auxiliary Feed Pumps (in the configura-tion at Palo Verde) for the accidents of tube rupture and steam ifne breaks (wherein.the need for primary depressurization and assured core cooling becomes complicated) should be further reviewed on an urgent basis.
In my opinion, this Palo Verde incident may also be a precursor indicating a need for ACRS to reflect further on my proposed primary blowdown --
redundant in principle -- concepts for some PWRs.
Attachment:
as stated cc: J. Flack i
I l
l 8604030593 860311 PDR FOIA SCOTT 86-4 d PDR
gy hp
- MORNING REPORT - REGION V .
DATE: AUGUST 25, 1985
- REGIONAL ACTION NOTIFICATION ITEM OR EVENT FACILITY FOLLOWUP PER MC 25t5 FAX FROM SENIOR BECHTEL NOTIFIED THE LICENSEE THAT AN ENGINEERING' ARIZONA PUBLIC EVALUATION HAS SH0HN THAT A MAIN STEAM LINE BREAK SERVICE COMPANY RESIDENT INSPECTOR IN THE MAIN STEAM SUPPORT STRUCTURE COULD RESULT
- PVNGS 81 IN TH0 AUXILIARY FEEDHATER (AFH) PUMP ROOMS BEING DN 50-528 7 PRESSURIZED TO APPROXIMATELY 20 PSIG AND 260 F 'e
'I / 7- -;
'TC).
DEGREES. THE LICENSEE HAS DECLARED BOTH PUMPS INOPERABLE BASED ON THE PUMPS AND ASSOCIATED
'7 INSTRUMENTATION NOT BEING QUALIFIED FOR THE REVISED, -
A*SUMED ENVIRONMENTAL CONDITIONS. PALO VERDE 1 HILL jf # ROMAIN IN MODE 4 UNTIL CONDUIT SEALANT (HHICH IS THE c eul7dIdd 'I)[/
W 4 j~[gg MEANS BY HHICH THE STEAM HOULD BE COMMUNICATED INTO I
m THE AFH PUMP ROOMS) IS UPGRADED TO PREVENT LEAKAGE.
,q,,,,[,[i /j . '4[/
3 FOLLOWUP PER MC 2515 -
FAX FROM SENIOR THE LICENSEE N/.S NOTIFIED BY COMBUSTION ENGINEERING ARIZONA PUBLIC THAT AT PALO VERDE 1 THE VARIABLE SETPOINT (VSP)
SERVICE COMP RESIDEyT INSPECTOR CARDS ASSOCIATED HITH THE VARIABLE OVERPDHER TRIP PVNGS 81 '
j (V0PT) RATE CIRCUIT IS SUBJECT TO RANDOMIFSETPOINT DN 50-528 /) A RANDOM s / FLUCTUATIONS AT VARYING POWER LEVELS.
SETPOINT INCREASE HERE TO OCCUR SIMULTAMEOUS HITH A
- CONTROL ELEMENT ASSEMBLY EJECTION, THE ACCIDENT
'" ANALYSES MAY BE VIOLATED. THE UNIT IS CURRENTLY
, ,,r" SHUTDOHN AND HAS BEEN SINCE JULY 24, 1985, TO PERFORM VARIOUS MAINTENANCE ACTIVITIES. THE LICENSEE HAS MODIFIED THE VSP CARD IN ACCORDANCE NITH CE RECOMMENDATIONS TO PREVENT A SETPOINT FLUCTUATION.
OPERATIONAL RESTRICTIONS PROPOSED BY CE HILL ALSD BE IMPLEMENTED UNTIL THE MODIFIED CIRCUITRY HAS BEEN TESTED.
FOLLOWUP PER MC 25f2 TELEPHONE CALL FROM PDTENTIAL 50.55(E) AND PART 21:
ARIZONA PUSLIC CE HAS IDENTIFIED MONCONFORMANCES CONCERNING 4
SERVICE COMPANY LICENSEE AT 2:00 PM DN 08/21/85 STAINLESS STEEL FLEXIBLE CONDUIT ON CE SUPPLIED PVNGS 828S INSTRUMENT RACKS AS INSTALLED IN UNIT 2. THESE DN 50-529 ..
NONCONFORMANCES INCLUDE VIOLATION OF MINIMUM SEND
- 50-550 RADIUS CRITERI A, DAMAGED CONDUIT, LOOSE FITTING I
NUTS, ONE DISCONNECTED END FITTING. (DER 85-28) i
==
6 i
- m. .. ._. ._ .- . _ .
, _1.
K ANPP/NRC MEETING T0 DISCUSS PVNGS AUXILIARY SPRAY CAPABILITY AND THE STARTUP TESTING EVENT OF SEPTEMBER 12, 1985 1
i I. INTRODUCTION J. G. HAYNES V. P. - NUCLEAR PRODUCTION II. SEPTEMBER 12, 1985 EVENT 1) R. E. G0UGE
, UNIT 1 DAY SHIFT SUPV.
- 2) D. D. SWAN UNIT 1 ASST. SHIFT SUPV.
- III. AUXILIARY SPRAY DESIGN / T. F. QUAN I
LICEf1 SING COMMITMENTS LICENSING SUPERVISOR l
IV. EVEllT EVALUATION T. F. QUAN '
V. CONCLUSION J. G. HAYNES V. PP- NUCLEAR PRODUCTION n
t 8
~ ~
. _ . , ._ r. .: .
._.. . a- . .i., . . _ . _ . _, ._ - ._~ ...
i ,- . .
CONDITIONS PRIOR TO EVENT OF 9-12-85 1.
REACTOR AT 53% FULL POWER
- 2. TURBINE GENERATOR ONLINE AT 585 MWe
- 3. PREPARING FOR 50% LOSS OF LOAD TEST t
PURPOSE OF 50% LOSS OF LOAD TEST:
1 y
- 1. DEMONSTRATE THAT THE PLANT CAN ACCOMMODATE A LOAD REJECTION FROM 50% POWER
- 2. VERIFY THAT THE TRANSIENT DID NOT IlllTIATE A REACTOR POWER CUTBACK f
E
?.
, 11-1 l
0
._ . ; ~ =..= :... .. .: . . . .
SEQUENCE OF EVENTS 2208 TEST INITIATED BY REMOTE MANUAL OPENING OF BOTH GENERATOR OUTPUT BREAKERS. (TURBINE-GENERATOR FLUCTUATIONS) 2209 REACTOR TRIP (FLOW-PROJECTED DNBR TRIP FROM CPC) 2209 TUR3INE TRIP (CAUSED BY REACTOR TRIP) 2215 NON-SAFETY RELATED AUXILIARY FEEDWATER PlNP STARTED 2217 ATMOSPHERIC DUMP VALVES (0NE ON EACH STEAM GENERATOR)
OPENED 3%
2218 MAIN STEAMLINE DRAINS AUTOMATICALLY RE0PENED UPON RESTORATION ON NON-1E ELECTRICAL POWER 2222 SIAS AND CIAS INITIATED (1837 PSIA; 540 F)
SIAS AND CIAS ACTUATIONS WERE VERIFIED AS PER DESIGN WITH HPSI INJECTING APPR0XIMATELY 75 GPM TO EACH COLD LEG 2223 NOTIFICATION OF UNUSUAL EVENT DECLARED DUE TO COMPLICATED REACTOR TRIP AND INITIATION OF A SIAS 2225 AUXILIARY OPERATOR RE-ENERGIZED MOTOR CONTROL CENTER NHN-M-72 UNDER CONTROL ROOM DIRECTION (RE-ENERGIZED CHN UV-501, VCT OUTLET AND UV-536, RWT HIGH SLCTION TO CHARGING PUMPS )
Il-2
~
.. ..: . .z.; :: . . . . .-.. ..... . . .. .
. . .=.- . .
1 SEQUENCE OF EVENTS (CONT.)
i
, 2237 CHARGING HEADER LOW FLOW ALARM (40 GPM)
, INTERMITTANT CHARGING HEADER PRESSURE ALARMS FOR THE NEXT 43 MINUTES, OPERATORS WERE ATTEMPTING TO REESTABLISH CHARGING PUMP SUCTION FROM:
(1) RWT HIGH SUCTION VIA CH UV 536 (2) RWT LOW SUCTION VI A CHN V 327
- (3) RWT HIGH SUCTION VIA UV 532 -- BAMP CH 514 TO THE CHARGING PUMPS (AFTER NON-1E POWER RESTORATION)
- 2320 REESTABLISHED CHARGING FLOW WITH TWO CHARGING PLMPS INJECTING 44 GPM TO RCS 2358 RESET SIAS AND CIAS (RCS PRESSURE AND INVENTORY l STABLE AND UNDER CONTROL) 0102 9/13/85 TERMINATION OF NOTIFICATION OF UNUSUAL EVENT l
II-3 8
~
.. a .. x.. . . uc .-l . . -. . - d - "
CHRONOLOGY OF AUXILIARY SPRAY DESIGN / LICENSING CRITERIA PRE RSB5-1 ORIGINAL DESIGN i
1978 RSB5-1 ISSUED, SYSTEM UPGRADED TO MEET l CLASS 2 PLANT REQUIREMENTS -- REDUNDANT AUX SPRAY VALVE B
2ND OTR,
- 1981 0440.6 SUBMITTED BY THE NRC ON CESSAR/
PVNGS DOCKETS A6 m'l #5 * "'fW an; .ut h: mb, i B s S 10/8/81 CESSAR RESPONSE TO 0440.6 SUBMITTAL > beva c.y^^%(44 i
8 u cu,a h pp m L.Z o.M c.ma w y'.t )st vp' i r 10/29/81 CESSAR COMMITS TO UPGRADE CH-141 AND 1
t
" La y CH-501 w y~ g t uwp,~ y pvuw.- %,
l E ik j S 11/3/82 #
" SAFETY GRADE AUXILIARY SPRAY SYSTEM" sbh** ,
s
.. 1 z
7/28/83 -
"SA'FETY-RELATED METHOD FOR RAPID } [<<y' h{'s DEPRESSURIZATION ... CONSISTENT WITH ?l' ,
4., s THE RECOMMENDATIONS OFi RSB5-1 } ,.
- . . t. s. -
STATED CEN-239 APPLICABLE TO PVNGS
U% % '
.p c s Q%
i
. SUBMITTED CEN-239, SUPPLEMENT 3 "' . r.' ; ..
q.4. -
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, CHRONOLOGY OF AUXILIARY SPRAY (CONT.)
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4/27/84 -
NRC LETTER REQUIRiflG AtlALYSIS ASSUMitlG
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05E uA 4 F, 7t2 c u k %.u 9 4 N i !ES 9/1/84 -
PLANT-SPECIFIC SGTR + LOP + FAILED w )%a bR ca-EE ADV ANALYSIS SUBMITTED Y.'
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ORIGINAL AUXILIARY SPRAY CRITERIA i
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! OPERATOR CONTROL OF THE RCS PRESSURE DURING i
FINAL STAGES OF C00LDOWN (WHEN PRESSURE LESS THAN l REQUIRED FOR RCP) AND FOR C00LDOWN OF PRESSURIZER.
i CURRENT AUXILIARY SPRAY CRITERIA i
l SAFETY GRADE PLANT C00LDOWN CONSISTENT WITH l THE GUIDANCE OF BTP RSB 5-1. FOR CLASS 2 PLANTS:
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l 3 OPERATOR ACTIONS OUTSIDE CONTR N
o OPERATOR ACTIONS INSIDE CONTAINMENT %
AFTER SSE IN o- REMAINING AT HOT STANDBY UNTIL MANUAL l ACTIONS OR REPAIRS ARE COMPLETED.
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i l- Alg SPRAY SYSTEM ACTIVE COMPONENTS f
SPRAY VALVES l
i LOOP ISOLATION VALVES CHARGING PUMPS [ y f 7 A )
DETAILED DESCRIPTION IN RESPONS:'. TO 440.6 wl - on,n ,) . c.0.
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AUX SPRAY SYSTEM i CESSAR vs PVNGS o PVNGS liAS REMOVED INTERNALS FROM
[ MAIN SPRAY BACKFLOW CHECK VALVE i
- o PVNGS HAS MODELED AUX SPRAY IN s
) TRANSIENT ANALYSIS OF CERTAIN SG 1 TUBE RUPTURE TRANSIENTS 3
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AUX SPRAY USE IN SAFETY ANALYSES e DURING LONG-TERM C00LDOWN PHEE FOLLOWING EVENT:
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SGTR ANALYSIS RESULTS
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' EYf31 IIE TilV Kfri DOSE THY (U U UJ5E (SECONDS) LREM) UREM) hubKOPENADV 0 0 0
. LOP 51 0 0 bhACT/AFFECTED) 122/132 0 0 1 ADV OPENS 460 0 0 1
MSIS 513 SIAS 581 AFW OVERRIDE 655 AUX SPRAY 1015 115 115*
H!5?eReD 1385 182 18s-2 JR DOSE !
a -AB 7200 200 210* ;
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- ESTIMATED DOSE DASED 03 REMOVAL OF EFFECT OF AUX SPRAY FL0ll.
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LTflL1 - LOSS OF .VCT LEVEL l
COMPENSATORY MEASURES - tiONITOR REFERENCE LEG WATER LEVEL 4G%6y - ALIGN REFUELING WATER TANK TO CHARGING PUMP SUCTION PROMPTLY ON LOSS OF POWER * %.4
- INSTITUTE PROCEDURAL CAUTIONS k ON RESTART OF CHARGING PLNPS t
- ITEM 2 - LOSS OF POWER TO CVCS VALVES (501, 536) t COMPENSATORY MEASURE - ALIGN REFUELING WATER TANK TO CHARGING PUMP SUCTION PROMPTLY ON LOSS OF POWER l
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[ Page 1 of 2 Sequence of Events
,j PVNGS Unit 1 September 12, 1985 gg$ ,,,d
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.4 Prior to neart of the load rejection test. 525 KV BKR FL 915 (one of two main generator output breakers) was opened per the test procedure.
4
- .IIG DESCRIPTION
- 22
- 08:29 Generator output breaker PL 918 was opened from the
{ control room to start the test. '
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22:08:30 Fast closure of the main turbine control and
- intercept valves.
1 ,
! 22:08:31:254 Turbine trip "first in" indication was "No ESTV Press trip" (no electric trip solenoid valve j pressure) - turbine trip was not expected to occur, I
troubleshooting ongoing.
1 22:08:53:721 Low DNBR trip on Channel A - CPC projected low flov causing DNER 22:08:53:738 Low DNBR trip on Channel B - reactor trip signal
- 22
- 08:53:796-808 Channel A - D trip breakers opened 22:09:45 TWPI '*A" tripped on low control ofi pressure. The '
, control oil pump is supplied from nonesuential power 22:10:51 Main Eenerator exciter tripped 22:10:53 circulating water and condensate pumps trip - test configuration prevented fast transfer.
22:10:58 Main steam line drain valves are msnually shut - auto opened on turbine trip, per design 22:15:10 Nonclass AFV pump started to maintain SC levels 22:17:42 Manually opened ALV on SC2 to dump steam to atmosphere to prevent degrading vacuum and insure adequate delta T for natural circulation f
22:l8:36 ADV on SG1 manually opened 22:19:07 ADV on SC2 manuaAly closed 22:19:37 Main stean line low point drain valves open
' automatically when nonessential power is restored with turbine trip sigcal present 1 22:21:07 ADV on SC2 manually reopened
.- , . , . . . . . ~
i7 ,
l Page 2 of 2
[ Sequence of Events
{ PVNGS Unit 1
- September 12, 1985
! 22:21:38 SIAS/CIAS on low pressurizer pressure (1837 psig).
Nonclass AFW pump shed, "B" AFW pump starts but is i
not used to add water due to SG 1evels being in l normal band. Pressurizer prestare low point is 1819 i
psig.
} 22:23:28 ADVs manually closed t .
l 22:23 Unusual Event declared by S/S based on Rx trip and SIAS/CIAS
e 22:32:05 Established boric acid makeup pump flow to charging f pumps via RWT following gas binding of pumps i 22:33:01 Established RCP seal injection i
22:33:47 Established charging flow to ECS Approx 24:00 Pressurizer LVL back in norcal band L i .
Approx 00:50 Started RCPs 01:03 Terminated Unusual Event i RZ:sh i
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204,6 TIME (SEC ) -) 1806,6 P'Est ifCS TEST 501055 Of LOAD M6 ElFFETd SSCWSEC TESTDATE: 12-SEP-85 SIMIIIE: 21:52:33,6 o P106 HINI M 1819,65 PSIA F106 HAXI M 2363,21 FSIA Ai 1684.6 SEC AT S24.0SEC ilE: 228,571SEC/ DIVISION F106 67,315 PSIA / DIVISION P0INTS PL0iiED FFaiEVERY 16 SCAWS
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