|
---|
Category:EXAMINATION REPORT
MONTHYEARIR 05000286/19870031987-04-12012 April 1987 Exam Rept 50-286/87-03OL on 870224-26.Exam Results:Seven Senior Operator Candidates Passed All Portions of Exams.One Candidate Failed All Portions IR 05000286/19860181986-08-25025 August 1986 Exam Rept 50-286/86-18OL on 860813.Exam Results:One Senior Reactor Operator Candidate Examined & Received License IR 05000286/19860121986-07-16016 July 1986 Requalification Program Evaluation Rept 50-286/86-12 on 860603-05.Exam Results:Three Senior Reactor Operators & Two Reactor Operators Passed Exams Resulting in Overall Program Evaluation of Satisfactory IR 05000286/19860051986-05-0909 May 1986 Exam Rept 50-286/86-05 on 860310-14.Exam Results:Five Senior Reactor Operators Passed & Two Failed IR 05000247/19850281986-01-28028 January 1986 Exam Rept 50-247/85-28 on 851209-13.Exam Results:All Candidates Passed All Portions of Exam IR 05000247/19850161985-08-22022 August 1985 Exam Rept 50-247/85-16 on 850709-11.Exam results:11 Candidates Passed & 1 Failed IR 05000286/19850061985-06-11011 June 1985 Operator Licensing Exam Rept 50-286/85-06 on 850423-26.Exam Results:Candidates Passed Operating Exam.One Senior Reactor Operator Candidate Failed Written Exam 1987-04-12
[Table view] Category:TEXT-INSPECTION & AUDIT & I&E CIRCULARS
MONTHYEARIR 05000003/19980191999-03-0909 March 1999 Insp Rept 50-003/98-19 on 981130-990222.No Violation Noted. Major Areas Inspected:Review of Facility Mgt & Control ML20237D1381998-08-19019 August 1998 Notice of Violation & Proposed Imposition of Civil Penalty in Amount of $55,000.Violation Noted:Between 971024 & 980528,licensee Failed to Assure That Design Change in Oct 1997 Subject to Design Control Measures ML20236M6011998-07-0606 July 1998 Notice of Violation & Proposed Imposition of Civil Penalty in Amount of $110,000.Violation Noted:On 970808,double Verifications of Steps 3.4.1 & 3.5.2 of PT-W1,which Involved Checks of DG Compressor,Not Performed,But Records Created ML20154Q1951998-01-22022 January 1998 Partially Deleted Investigation Rept 1-97-038.Noncompliance Noted.Major Areas Investigated:Falsification of Surveillance Test Records by Nuclear Production Technician ML20217H3531997-10-0707 October 1997 Notice of Violation & Proposed Imposition of Civil Penalty in Amount of $110,000.Violation Noted:Con Edison Did Not Operate within Restrictions of TS Figure 3.1.A-3,in That Pressurizer Level Was Greater than 30% PNO-I-97-053, on 970826,special Security Insp Will Be Performed,That Will Examine Security Activities at Vermont Yankee,Pilgrim & Indian Point 3.Team Will Include Security Specialists from Region I & NRR1997-08-22022 August 1997 PNO-I-97-053:on 970826,special Security Insp Will Be Performed,That Will Examine Security Activities at Vermont Yankee,Pilgrim & Indian Point 3.Team Will Include Security Specialists from Region I & NRR ML20217R3361997-08-19019 August 1997 NOV & Proposed Imposition of Civil Penalty in Amount of $55,000.Violation Noted:Measures Were Not Established to Assure That Applicable Regulatory Requirements & Design Basis,Were Correctly Translated Into EOPs IR 05000247/19930261993-11-23023 November 1993 Insp Rept 50-247/93-26 on 931108-12.No Violations Noted. Major Areas Inspected:Mgt Support Plans,Protected & Vital Area Physical Barriers,Detection & Assessment Aids,Protected & Vital Area Access Control of Personnel IR 05000286/19930161993-10-19019 October 1993 Insp Rept 50-286/93-16 on 930802-06 & 0920-24.No Violations Noted.Major Areas Inspected:Isi Program,Procedures,Scope of ISI Work for Outage,Current Insp Plan & Testing Procedures IR 05000286/19930211993-09-17017 September 1993 Insp Rept 50-286/93-21 on 930830-0902.No Violations Noted. Major Areas Inspected:Mgt Support & Audits,Protected & Vital Area Physical Barriers,Detection & Assessment Aids & Protected Vital Area Access Control of Personnel PNO-I-90-094, on 901016,transfer of Fuel Assemblies Stuck in Upper Core Internals.No Apparent Damage to Dropped Fuel Assembly Occurred.Recovery Operations Secured1990-10-17017 October 1990 PNO-I-90-094:on 901016,transfer of Fuel Assemblies Stuck in Upper Core Internals.No Apparent Damage to Dropped Fuel Assembly Occurred.Recovery Operations Secured PNO-I-90-077, on 900906,unplanned Shutdown Greater than 48 H Occurred Due to RCS Packing Leak from Pressurizer Spray Valve.Plant Placed in Hot & Cold Shutdown.Licensee Activities Monitored & State of Ny Informed1990-09-0707 September 1990 PNO-I-90-077:on 900906,unplanned Shutdown Greater than 48 H Occurred Due to RCS Packing Leak from Pressurizer Spray Valve.Plant Placed in Hot & Cold Shutdown.Licensee Activities Monitored & State of Ny Informed PNO-I-90-065, on 900814,licensee Reported That Licensed Reactor Operator Tested Positive for Marijuana as Result of Random Fitness for Duty Test.Operator Unescorted Site Access Suspended for 14 Days1990-08-15015 August 1990 PNO-I-90-065:on 900814,licensee Reported That Licensed Reactor Operator Tested Positive for Marijuana as Result of Random Fitness for Duty Test.Operator Unescorted Site Access Suspended for 14 Days PNO-I-90-063, on 900809,plant Shutdown Due to Potential Loss of Three Emergency Diesel Generators.Caused by Blown Control Power Fuse.Fuse Replaced1990-08-0909 August 1990 PNO-I-90-063:on 900809,plant Shutdown Due to Potential Loss of Three Emergency Diesel Generators.Caused by Blown Control Power Fuse.Fuse Replaced ML20247K5281989-09-14014 September 1989 EN-89-086:on 890919,notice of Violation & Proposed Imposition of Civil Penalty in Amount of $50,000 Will Be Issued to Licensee Based on Security Violations Re Access Control & Illumination in Protected Area ML20247B9531989-08-24024 August 1989 Enforcement Conference Rept 50-286/89-15 on 890808.Major Areas Discussed:Security Program During Spring 1989 Plant Outage IR 05000286/19890151989-07-24024 July 1989 Partially Withheld Physical Security Insp Rept 50-286/89-15 on 890605-07 (Ref 10CFR73.21).Violations Noted Re Physical Barriers,Vital Areas & Access Controls.Major Areas Inspected:Detection & Assessment Aids & Alarm Stations ML20245G2181989-06-21021 June 1989 PNS-I-89-010:on 890621,Dept of Investigation in New York City Received Call Threatening Destruction of Plant & Ref 1977 Incident Where Damage Inflicted on Plant.Bomb Threat Contingency Procedures Implemented & Security Maintained IR 05000286/19890031989-06-13013 June 1989 Enforcement Conference Rept 50-286/89-03 on 890428 in King of Prussia,Pa Re Findings of Insp Repts 50-286/89-03 & 50-286/88-22.Violations Noted.Areas Discussed:Security Program During Current Outage ML20247A1051989-05-0909 May 1989 Notice of Violation from Insp on 890228-0417.Violation Noted:Technicians Failed to Secure Pump When Vibration Level Observed on Pump Motor Exceeded Procedural Limit of 3.5 Mils ML20247A0681989-05-0505 May 1989 Notice of Violation from Insp on 890314-25.Violation Noted: Workers Allowed to Enter High Radiation Areas W/O Being Provided or Accompanied by Individual Authorized in Radiation Protection Procedures IR 05000286/19890051989-04-11011 April 1989 Partially Withheld Physical Security Insp Rept 50-286/89-05 on 890227-0303 (Ref 10CFR73.21).Violations & Noncompliances Noted.Major Areas inspected:non-routine Event,Mgt Support, Security Program Plans & Audits & Physical Barriers ML20154Q7231988-09-21021 September 1988 Notice of Violation & Proposed Imposition of Civil Penalty in Amount of $75,000.Violations Noted:Qualification of Containment high-range Radiation Monitors Cable Connector Assembly Deficient PNO-I-88-065, on 880617,unit Tripped Due to High Water Level in Steam Generator 22.Caused by Contractor Cleaner Inadvertently Activating Boiler Feed Pump.Licensee Elected to Enter Cold Shutdown to Repair Connoseals1988-06-20020 June 1988 PNO-I-88-065:on 880617,unit Tripped Due to High Water Level in Steam Generator 22.Caused by Contractor Cleaner Inadvertently Activating Boiler Feed Pump.Licensee Elected to Enter Cold Shutdown to Repair Connoseals IR 05000247/19880121988-05-24024 May 1988 Physical Security Insp Rept 50-247/88-12 on 880407.No Noncompliance Noted.Major Areas Inspected:Program for Protection of Safeguards Info,Per 10CFR73.21,including Use of Required Storage Repositories & Handling Procedures IR 05000286/19880061988-05-19019 May 1988 Physical Security Insp Rept 50-286/88-06 on 880412-14.No Noncompliance Noted.Major Areas Inspected:Plan & Implementing Procedures,Organization,Program Audits,Testing & Maint,Physical Barriers & Security Sys Power Supply PNO-I-88-003, on 880101,steam Generator (SG) 23 Boiled Dry During Plant Heatup.Cause Not Stated.On 880104,station Mgt Started Evaluating Safety Significance of Event & Best Method to Refill Generator.Sg 23 Refilled on 8801051988-01-0707 January 1988 PNO-I-88-003:on 880101,steam Generator (SG) 23 Boiled Dry During Plant Heatup.Cause Not Stated.On 880104,station Mgt Started Evaluating Safety Significance of Event & Best Method to Refill Generator.Sg 23 Refilled on 880105 IR 05000286/19870131987-08-21021 August 1987 Safety Sys Outage Mod Insp Rept 50-286/87-13 on 870422-0714. Rept Describes Activities & Findings Associated W/First Portion of Team Insp Re Outage Design Insp IR 05000247/19870141987-06-0808 June 1987 Emergency Preparedness Insp Rept 50-247/87-14 on 870512-14. No Violations Identified.Major Areas Inspected:Licensee Annual Emergency Exercise Performed on 870513 IR 05000286/19870111987-05-14014 May 1987 Insp Rept 50-286/87-11 on 870420-24.No Violations Noted. Major Areas Inspected:Radiological Effluents Control Program,Mgt Controls,Air Cleaning Sys,Program Implementation & Previously Identified Items IR 05000286/19870091987-05-11011 May 1987 Insp Rept 50-286/87-09 on 870402-03.No Violations Noted. Major Areas Inspected:Nuclear Matl Control & Accounting, Including Organization & Operating,Shipping & Receiving, Storage & Internal Control & Records & Repts PNO-I-87-039, on 870430,licensee Identified Potential Circuit Failure Preventing Automatic Start of Auxiliary Feedwater Pumps by Loss of Main Feedwater or lo-lo Steam Generator Signals.Circuit Modified for Independent Relays1987-05-0101 May 1987 PNO-I-87-039:on 870430,licensee Identified Potential Circuit Failure Preventing Automatic Start of Auxiliary Feedwater Pumps by Loss of Main Feedwater or lo-lo Steam Generator Signals.Circuit Modified for Independent Relays IR 05000286/19870031987-04-12012 April 1987 Exam Rept 50-286/87-03OL on 870224-26.Exam Results:Seven Senior Operator Candidates Passed All Portions of Exams.One Candidate Failed All Portions PNO-I-87-025, on 870326,licensee Announced Plans to Shut Down Reactor on 870327 Due to Steadily Increasing Leakage on Reactor Coolant Pump Seal.Caused by Degraded Seal.Shutdown Expected to Last 10 Days1987-03-26026 March 1987 PNO-I-87-025:on 870326,licensee Announced Plans to Shut Down Reactor on 870327 Due to Steadily Increasing Leakage on Reactor Coolant Pump Seal.Caused by Degraded Seal.Shutdown Expected to Last 10 Days IR 05000286/19870021987-03-18018 March 1987 Insp Rept 50-286/87-02 on 870127-29.No Violations Noted. Major Areas Inspected:Dosimetry Staffing & Training, Facilities & Equipment Procedures,Dose Assessment QA & Documentation & Recordkeeping IR 05000247/19870041987-03-16016 March 1987 Insp Rept 50-247/87-04 on 870203-0302.No Violations Noted. Major Areas Inspected:Routine Daily Insps,As Well as Unscheduled Backshift Insps of Onsite Activities,Operations, Maint,Surveillance & Review of Periodic & Special Repts ML20207S3401987-03-11011 March 1987 Notice of Violation from Insp on 870127-29 IR 05000247/19870021987-03-10010 March 1987 Insp Rept 50-247/87-02 on 870127-29.Violation Noted:Failure to Include Acceptance Limits for Battery Electrolyte Temp & Failure to Ensure Battery Room Temp within Normal Bounds ML20207R1791987-03-0606 March 1987 PNS-I-87-003:on 870306,security Officer at Offsite Training Ctr in Toddville,Ny Received Bomb Threat by Telephone.Search of Site Produced Negative Results.Local Law Enforcement Agencies Responded.Security Measures Heightened IR 05000286/19870011987-03-0505 March 1987 Insp Rept 50-286/87-01 on 870106-0217.Major Areas Inspected: Plant Operations Including Shift Logs & Records,Reactor Trips/Engineered Safeguards Actuation,Surveillance,Maint & Followup to Generic Ltr 83-28 & TMI Action Items ML20212J3921987-03-0202 March 1987 Notice of Violation from Insp on 870106-0202 IR 05000247/19870011987-02-26026 February 1987 Insp Rept 50-247/87-01 on 870106-0202.Violation Noted:No post-maint (Mod) Test Performed After Changing Location of Emergency Diesel Generator Svc Water Flow Indication & Control Instruments PNO-I-87-010, on 870211,reactor Scrammed from Full Power During Transient Initiated by Loss of Instrument Bus.Safety Injection Signal Received on High Steam Flow Coincident W/Low Steam Line Pressure.Plant Stabilized in Hot Shutdown1987-02-12012 February 1987 PNO-I-87-010:on 870211,reactor Scrammed from Full Power During Transient Initiated by Loss of Instrument Bus.Safety Injection Signal Received on High Steam Flow Coincident W/Low Steam Line Pressure.Plant Stabilized in Hot Shutdown ML20210V6021987-02-10010 February 1987 Notice of Violation from Insp on 861215-19 IR 05000286/19860241987-02-0909 February 1987 Insp Rept 50-286/86-24 on 861215-19.Violation Noted:Raychem Splices Identified W/Less than Required 2-inch Overlap & Bending Radii Less than Allowed IR 05000247/19860331987-01-27027 January 1987 Radiation Protection Insp Rept 50-247/86-33 on 861215-19.No Violations Noted.Major Areas Inspected:Alara,Internal Exposure Control & External Exposure Control ML20213A4821987-01-22022 January 1987 Notice of Violation from Insp on 861116-870105 IR 05000247/19861361987-01-21021 January 1987 Meeting Rept 50-247/86-136 on 861209.Major Items Discussed: Plans for Integrated Assessment of Auxiliary Feedwater Sys. Mods Being Considered Include Providing Direct Indication of Overspeed Trip Mechanism Status in Control Room ML20212K3521987-01-20020 January 1987 Notice of Violation & Proposed Imposition of Civil Penalty in Amount of $50,000 Based on 860811-0922 Insp.Violation Noted:Reactor Heated Up Above 200 F W/Both Recirculation & Containment Spray Pumps Inoperable IR 05000286/19860231987-01-15015 January 1987 Onsite Regular & Backshift Insp Rept 50-286/86-23 on 861118- 870105.Violation Noted:Failure to Follow Administrative Procedures AP-6 & AP-25-3 Re Work Requests & Matl Substitutions,Respectively 1999-03-09
[Table view] |
Text
'
g
.
U.S. NUCLEAR REGULATORY COMMISSION REGION I OPERATOR LICENSING EXAMINATION REPORT EXAMINATION REPORT NO.: 50-247/85-16 (OL)
FACILITY DOCKET NO.: 50-247 FACILITY LICENSE N0.: DPR-26
'
LICENSEE: Consolidated Edison Company of New York, In Buchanan, New York 10511 FACILITY: Indian Point 2 EXAMINATION DATES: July 9-11, 1985 CHIEF EXAMINER: r/ff'
O. F. di>nnson, Lead Reactor Engineer / D4te (Examiner)
REVIEWED BY:
. M.' KelWr, Chief, Projects Section 1C
[N [
' D t'e ~'
,
APPROVED BY: '
H.'B. Kist (ryhief,ProjectsBranchN ON
/Date/
[
SUMMARY: Written and oral simulator examinations were administered for 12 SRO candidates, 10 SR0 Upgrades and two SR0 Instants. One SRO Upgrade candidate failed the written examinatio VO208 850823 PDR G ADOCK 05000247 PDR ;
I
)
'
.
.
REPORT DETAILS TYPE OF EXAMS: Replacement EXAM RESULTS:
l SR0 l l Pass / Fail i '
l I I I I l Written Exam l l'1/1 l l l l l 1 I l Oral Exam i 12/0 l l 1 I I I I I Simulator Exam i 12/0 l l 1 I I I I l Overall l 11/1 l l l l Chief Examiner at Site: D. Johnson, NRC Other Examiners: D. Ruscitto, NRC D. Coe, NRC B. Picker, EG&G Idaho, In B. Hemming, EG&G Idaho, In O. Burke, NRC Consultant
'
s
-
.
3 Summary of Generic Deficiencies From Oral and Simulator Exams:
Licensee responses to the following items were made by letter from Mr. Murray Selman to Mr. Richard Starostecki dated July 26, 198 Minor deficiencies with no safety significance were noted in the following areas:
Simulator
. RCP vibration monitors not installe RCP vibration simulation is scheduled to be completed by Dec' ember 1985. NRC concurs with this action. (Item 85-16-01). Plant computer " Proteus" not modele Proteus implementation is planned after completion of Combustion Engineering (CE) model upgradin NRC concurs with this actio (Item 85-16-02) RMS is not modeled where it is needed to confirm LOCA The RMS model has been written and is scheduled to be integrated into the simulator by December 1985. NRC concurs with this action. (Item 85-16-03) Natural circulation modeling deteriorates after a short tim CE has been contracted to upgrade this model prior to third quarter 1986. NRC concurs with this action. (Item 85-16-04) Two phase interaction in S/Gs and Pressurizer not modele CE has been contracted to upgrade this model prior to third quarter 1986. NRC. concurs with this action. (Item 85-16-05) Initial Condition -#1 (cold shutdown) is for solid conditions onl No other cold I.C. exists for training or exam The formation of a bubble in the pressurizer will be included in IC-1 by October 198 NRC concurs with this action. (Item 85-16-06) Simulator malfunction list does not include alarm responses and plant behavior for each malfunctio Malfunction list will be revised by November 1985 to include indica-tions and operating responses. NRC concurs with this action. (Item 85-16-07)
,
w t
-
.
Plant Pressurizer pressure indication at the shutdown panel in the Primary Auxiliary Building (PAB) is narrow range only. No full range indica-tion is available at this panel to provide for achieving and main-taining cold shutdown capabilit Licensee referred to NRC Safety Evaluation Report dated August 22, 1983 and supplement dated March 30, 1984 which concluded that the IP-2 Alternate Safe Shutdown System (ASSS) meets 10 CFR 50, Appendix R criteria. The NRC Operator Licensing Section in Region I disagrees that this report resolves the question of remote cold shutdown capa-bility at IP-2 and has turned this item over to the Division of-Reactor Safety for review duririg their next IP-2 Appendix R review -
scheduled for September 198 (Item 85-16-08) No remote shutdown or remetc operations procedures are permanently located at remote shutdown stations. Presently, they must be carried from the Central Control Room during Control Room evacuatio Licensee will complete a review and place procedures as necessary by September 198 NRC Operator Licensing Section Region I desire to be informed of the results of this review and procedure placement prior to the licensees next operator license examination in December 198 (Item 85-16-09) Remote S/G and Pressurizer level indications were not labeled at the remote shutdown pane All indications read in inches of water differential pressure with no posted or locally available conversion tabl Licensee will place an operator aid to assist in determination of water levels at the alternate safe shutdown panel by August 8,198 NRC will evaluate the effectiveness of this aid during the next operator licensing exam in December 198 (Item 85-16-10) . No dedicated phone system is available for the operators of the several remote shutdown stations. Presently, walkie-talkies are the only instantaneous direct communication method available, and these must be brought from the guard house when neede An in plant wireless communication system is being acquired and is scheduled a be installed in areas outside the containment by December 1985. NRC concurs with this actio (Item 85-16-11)
I
.
s ,
'
.
5 Summary of Generic' Deficiencies Noted From Written Exam:
R0 Exam - Not given SRO Exam - (12 candidates)
The following were areas of minor weakness:
-
Power coefficient changes over range of core power and lifetim DNBR changes during selected transient GT-25 interloc Steam Dump Interlocks
-
Technical Specification bases for sources of borated wate Circumstances warranting departure from the intent of approved procedure . Interface with Plant Staff During Exam Period:
The simulator instructors continue to perform their liaison duties in an outstanding manner, greatly enhancing the examination process. This allows last minute scenario modifications to examine new areas with little pause in the flow of the scenari . Personnel Present at Exit Interview:
NRC Personnel
'
D. Johnson, Chief Examiner O. Ruscitto, Reactor Engineer (Examiner) -
D. Coe, Reactor Engineer (Examiner)
L. Rossbach, Senior Resident Inspector P. Kelley, Resident Inspector Facility Personnel H. Morrison, Con Edison Operations Manager M. Anderson, Senior Operator Training Instructor D. Huntington, Senior Operator Training Instructor
_ - _ _ _ _ - _ _
. ..
,
..
-
.
L. Kawula, Nuclear Training Director A. Budnick, General Manager-Administrative Service J.'Basile, General Manager-Nuclear Power Generation J. Rowland, Instructor-Training M. Blatt, Director, Regulatory Affairs, Nuclear Power P. Zarakas, Vice President-Special Projects Summary of NRC Comments Made At Exit Interview:
I
! The deficiencies noted above were discussed. Training improvements and interface with plant staff were summarized as well. $!o specific prelim-inary results were presented, although general sime'ator performance was characterized as outstanding, particularly with respect to the use of ERGS, teamwork, and diagnostic abilit i Examination Review:
At the conclusion of the written examinations, the examiners met with the following licensee personnel to review the exam and answer keys to iden-tify any inappropriate questions relative to plant specific design and to ensure that the questions will elicit the answers in the key and that they reflect the most current plant condition M. Anderson, Senior Instructor D. Huntington, Senior Instructor l i
J. Rowland, Senior Instructor Attachments: Written Examination (s) and Answer Key (s) (SR0/RO) Facility Comments on Written Examinations Made After Exam Review
_ _ _ _ - _ . - _ _
__ _ __ -
Trcnscction Type M-3 NRC:1 Fcrin 6 Rev. Oct 80 (Side 1)
b New Item OUTSTANDING ITEMS Fi O Modify Sinct.c DOCrCT cnIRY rosi
-
2 Y _/ 0 Delete > lb /
.
Originator Reviewing Supervisor Name Item Number Type . Module I Area Resp Action Due Date Updt/Cisout Rpt i Date 0/M/Cisd 4T-l/ I4-bk I rieg1 IIIIl plcis1 I VI I IMMI I-lDD I l-l IJ lIl-lIl-1II IIl-lIl-LLJ Originator _ Modiffer/01cser
__
YY MM DD YY l l IIIIII IIIIIIIIIII Descriptive Titie -
1/ 8" n L A T' e d D E
'
f I4Lr 'E 6cY M o $ c P -
_ _
V[ gl3 A T /
_
o /v _
y o_ o g a f jp _ _ _ _ _ _ _ _ _ _ _
_ _ . -. _ - __ - _ - _ _ _ _ _ _ __ _ , _ _ _ _ _ _ _ _ _ _ _ _ _ _
. _ _ _ .. .. _ __ _ _ _ _ _ _ .. _ .. .. _
~~ ~
~
_ item Number _ Type Module _ i Area , Resp _ Action Due Date lhdt/CIsoutRpt#.Dat'0/M/C1sd~
IGM-l/16Holz! IrlFII1 IIIIII lolcisi l_ IA l 1 I_ _ l-l I l_I l__ lll-lll_lll ll _
l l_l l l Ortginator Modtffer/C10ser M DD YY llllllll1I l.IllllIlli Descriptive Title S I A Of A T c C 2 C_ F / ?'t Gb W QQ P R6 7 EQ S' *
_ _ _ _ _ _ _
_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _
- _ - - _ _ _ - - - - _ - - - - _ - - - _ - .. .. _ - - _ - - _ _ _ _ _ - .- - - - - _ -
I
__ __ _ .
_
_ _ _
Item Nisaber Type _ Module f_ Area Resp Action Due Date Updt/C1sout Rpt i
____
Date 0/M/Cisd 19bi-l/lcl lol31 IrlFl4 lll1II blLjsl l l/l I l l_ l-l l I-I I l IIl_lll-llI I I l-1 I l-l l 1 Originator Modiff er/ Closer "
IlIIIllilI! IlllllllIll Descriptive tit 1e 5 t h0 L pr e k DEFI C / EU C- Y -
N O F M6 WC D E L _ _ _ _ _ _ _ _ __ _ _
l
'
- _
_
.. .- - - . _ - -. - -
.-
- - __
l Item Number Type Module J Arei Resp Artfor Due [tte_, Dodt/Cisaut Rot f la te n/M/cisci ss -
/ 6 -
o y- rT r o c / l -
I -
_
l -
l- 'l __l- l- 1I l OrftInator _ Bnd f' er/rir ser MM DD YY MM DD YY
! !! _
Descriptive Title l $ no 1 L P 7c I D E F LC -
1 EK Y UD'
-
CA r u e Q L C ! _ @ Q_ p1 o DE L _ _ _
__
. - _ = -
-
- --
_ - - - - - - - -
- _ - _ _ -
_
Transtction Type M-3 NRC:1 Fem 6 R:v. Oct 80 (Side I)
, . -
0 New ic DUTSTANDINr. ITEMS FILE O Madire sTistrusamrniinrraisi Docket #
O
.
Deiete 53 -
2. y7 .
Originator Revfewing Supervisor Name Item Number _ Type Module f Area Resp Action Due Date Updt/CIsout Rpt # Date 0/M/Cisd le s4 K -
otsT lt Azt IIIIII loldsl 1MI I I l_I I l_I 11 llI_Ill_4l1 i i i_4 1 g_LU Origina tor MM DD YY MM DD YY Modiffer/ Closer l l III I Illl llll p ,c,,pt,,, y,,i,
-
E. l M U L A Y O
_ /t O E E i ( ?/ e dq f Q O --
_ _
SY E A 3 _
8 (( S E L E_ gDQEL__ _ _ _ _ _ _ _ _
-- - - -
- - - --
-
- -- , - -
ff o O E L
- _ - _ _ _ _ _ _ _ _ _ .. .. _ _ _ _ _ _ _ _ _ ._ _ _
~ ~ ~ ' ~ ~
Item Number _ Type Module f Area , Resp _ Action Due Date Updt/CE5ut Rpt # . Etie 0/TVIIsd-191st-l/161-loV2J IIIFlIl llllll ldL}sl lMl l l l-l l l-l l lll-lll_lll llllll Originator _ Modtfler/ Closer n DD YY lIIIIIIIIII IIIIIIIIIII p,,c,,,,,,,7,,i,
'l E h c }
'
5 /_ @u 'L 'A T b R D E F I C --
No _
p o N -
S O L_ LE _
C O_ t- D _
%C _ _
_ _ _ _ _ _ _ _ _ _ _ _ _
- - - - _ _ - - - - - - - - - - - - - - - - - . - - - _ _ - - - - - .- - - - - -
Item Number Type Module #_ Area Resp Action Due Date Updt/Cisout Rpt # Date 0/M/Cisd If451-1/161 lor /l lrlFl31 lIll1I l0l416l lMI l l l-l l l-l l ] lll_lll-lll [ l l-l l l ] l l Originator Modtfler/ Closer
"" "
Il11IlliIII IlllliIllli Descriptive Title S I /* U L A T O R D E F i C l eb CY ~
/ Na o m P t. G TE M /V t- t= u f C T i o N L i $T
-
_ _
-
L l Ite. Number Typ Modulo d Area Rese Action Due tate liedt/Cismut Ret i la te otM tch s
'
s
.k -
/ 61- 0 4 u ni I I IslP Pl lV l l- l -
l -.
[ l_ l[
MM DD YY MM DD YY Ortsinator Mrd f' ei /cir wr _
[ M [N 5 o Nl l l l lAlN a E R sh Nll_l Descriptive Tltie d o W I D 6 FA NGE Pt. E S C U R I E E R P g E S S a RE I NS 1 A u M E N T
~
$ A) S T A l- L E f2 O h
? "
X A LT QFNA T E S b F t S + tA T D o k N
~
C V S T & ff r A M EL S l -
_ _ _ _ _ _ _ _
Trcasaction Type M-3 NRC:1 Fere 6 Rev. Oct 80 (Side I)
.- =
U Mew Itas OUTSTANDING ITEMS FILE O Modify siNatt DoCrrT cNTRY r0isi Docket #
.
-0 -
2Y O -
Deiete Originator Reviewing Supervisor Name Item Number Type Module f Area Resp Action Due Date Updt/Ciscut Rpt f Date 0/M/Cisd 1915-l/ I4-H71 r F14 IIIIII Iqctsl I VI I I I l-l I l-l l_I IIl-lII-lII I I I-1 l I-LU M D YY MM DD ;Y Y Originator Modt fler/ Closer _
l I IIIIII IIIIII IIII Descriptive Titie
'
&o l' R o c' E D EGE E ttJ PLf C E q nt A_ L T gh N g g $ A F E S H O TO O 2 1 g .4 7 E m
_ _ f[ _ _ _ _
fre 7 Le dE - _ _ _ - _ _ _ _ _ _ - _ _ _ _ _ _ _ _ _ .. _ _ _ _ ._ _ _ .. _ ._ _
~~~ ~ -~
Item Nisaber . Type Module # Area , Resp Action Due Date IIpdt/C1sout Rpt i . IEtia /M/Cisd~
1915T-l/161-l/lgl plFirl IIIIII bl'M I I/1 I I I l-l I l-l I IIl-IIl-lII I _I I l-l I I
' '
Driginator , Modiffer/ Closer _
lIllll'Ill llllllIlll! ,
Descrjptive T1 tie j CON t/ E Ri f 4 G s / 6 'o R p gl E S S_ o g t Q E_j E_f[ G N o M ET H olo _
of _
y te se A T E
@ _
A D -
_
r hGS O N A L T S A F E S H u r Do nN 9& dE L _ _ _ _
1 '
= _ _ _ _
l
__
Item Nisaber Type _ Module #__ Area Resp Action Due Date Updt/Cisout Rpt # Date b/M/Cisd ,
l
'
184-l/14 l/1/1 LeLF[Q llllll lo[C[(j
_,
lMl l l l-l l l_l l _l
__
lll-lll-llJ l l l_l l l_J l l l M DD YY Originator Modiffer/ Closer llIllllllll IIIII 11lll Dessrjptive Title G Y 4 7E M t/ A I L A RL E FO R A L T S A F E N O I ff N E p i A TE C0 p 4 uAt C A T I O N A S H u T D o ld N G Y S T EM uGC _ _ _ _ _ _
lten Number Type Module d 'Aret Rese Actiori De Esto hdt/Cissut Ret f la te ofMICl<d
~7 _
'
l / l- -
I _
-l -
I- l- II MM DD YY MM DD YY Originator Mnd f<er/C1r o r
!!! !! - Descriptive Title
-_ - - _
_
'_
- -_I -__-m _