|
---|
Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML17059C7911999-09-30030 September 1999 Proposed Tech Specs Re Rev B to Conversion of Unit 2 Current TS to ITS ML20211P5931999-09-10010 September 1999 Marked-up Tech Specs Pages Reflecting Conforming Administrative License Amend Associated with Proposed Transfer of Facilities to Amergen Energy Co,Llc ML20211H2231999-08-26026 August 1999 Proposed Tech Specs,Supporting Implementation of Noble Metal Chemical by Raising Reactor Water Conductivity Limit in TSs 3.2.3.a,3.2.3.c.1 & 3.2.3.b ML18041A0731999-07-27027 July 1999 Rev 1 to NMP2-ISI-006, Second Ten Year Interval Inservice Insp Program Plan for Nine Mile Point Nuclear Power Station Unit 2. ML20206P2661998-12-30030 December 1998 Proposed Tech Specs Making Application of Emergency Condenser Vent Ng Activity Monitor Channel Operability Requirement & Daily Sensor Check SR Consistent with Conditions Stated in LCO 3.1.3.a Re Emergency Cooling Sys ML20197K1041998-12-0404 December 1998 Revised Proposed TS Bases Reflecting Previous Removal of Condenser Low Vacuum Scram Function from TS as Well as Plant Design & Changes to EDG Ratings,Design Basis Load Limits & Loading Profiles ML20196H0671998-11-30030 November 1998 Proposed Tech Specs,Correcting LCO & Associated Bases for TS Section 3.1.2, Liquid Poison Sys, That Had Been Incorporated Into TS as Part of NMP Unit 1 TS Amend 101 ML20196D2081998-11-24024 November 1998 Proposed Tech Specs B 2.1.1, Fuel Cladding - Safety Limit, B 3.2.5 & 4.2.5, Reactor Coolant Sys Leakage Rate ML20154R1101998-10-16016 October 1998 Proposed Ts,Revising LCO 3.7.1.1 & Associated Actions & SRs to Provide Assurance That Four SW Pumps Are Operable & Are Operating within Acceptable Sys Parameters,With Divisional Cross Connect Valves Open ML20217N7911998-04-24024 April 1998 Revised Pages 2-1,3/4 4-1 & B2-1 to Replace Previously Submitted Pages Contained within Attachment a of 971215 Proposed Change to TS to License NPF-49 ML20202G3751998-02-0505 February 1998 Proposed Tech Specs Pages,Reflecting References to 10CFR50.55a(f) & (G) as Well as Terminology Used in Second Ten Year Isi/Ist,Beginning on 980405 ML20197H3371997-12-15015 December 1997 Proposed Tech Specs Revising SLMCPR from 1.07 to 1.09 for Two Recirculation Loop Operation & from 1.08 to 1.10 for Single Loop Operation ML20211M5231997-10-0707 October 1997 Proposed Tech Specs Section 4.9.6,reflecting New Setpoints Due to Difference in Weights of Two Existing Triangular Refueling Platform Masts ML20217G9011997-07-31031 July 1997 Proposed Tech Specs Changing Wording in Action 36 of TS Table 3.3.3-1, Emergency Core Cooling Sys Actuation Instrumentation ML20148A7751997-04-30030 April 1997 Proposed Change to Tech Specs,Removing Section 3.3.7.3 & Associated Surveillance Section 4.3.7.3,associated Tables 3.3.7.3-1 & 4.3.7.3-1,Bases Section 3.4.3.7.3 & Revising Section 0.0 (Index) Pages VII & Xvii ML17059B2911996-09-0404 September 1996 NMP Nine Mile Point Nuclear Station Unit 2,Pump & Valve First Ten-Yr Inservice Testing Program Plan. ML20116D8121996-07-26026 July 1996 Proposed Tech Specs Re Option B of App J to 10CFR50 ML20115H1521996-07-12012 July 1996 Proposed Tech Specs Section 6.2.2.i Re App a ML20117F9501996-05-15015 May 1996 Proposed Tech Specs Section 3/4.3.2 Re Isolation Actuation Instrumentation ML20101F4281996-03-20020 March 1996 Proposed TS 3/4.3.1 Re RPS Instrumentation,Deleting Operability Requirements for APRM Neutron flux-upscale, Setdown & Inoperative Functions in Operational Conditions (Oc) 3 & 4 & Modifying Operability Requirements in Oc 5 ML20101D7551996-03-15015 March 1996 Proposed Tech Specs Section 4.6.2 Re Depressurization Sys - Suppression Pool ML20097D2391996-02-0707 February 1996 Proposed Tech Specs Re Administrative Controls ML20100C1021996-01-25025 January 1996 Proposed Tech Specs Table 3.3.3-1 Re Emergency Core Cooling Sys Actuation Instrumentation ML20096G8401996-01-17017 January 1996 Proposed Tech Specs,Representing Revs to Specs 3/4.3.1, 3/4.3.2,3/4.3.3,3/4.3.4.2 & Associated Bases to Relocate Response Time Limit Tables from TSs to Plant USAR ML20094B5421995-10-25025 October 1995 Proposed Tech Specs Re Position Title Changes & Reassignments of Responsibilities at Upper Mgt Level ML20091Q9571995-08-28028 August 1995 Proposed TS 3.6.1.7,increasing Time 12-inch & 14-inch Containment Purge Sys Supply & Exhaust Valves May Be Open in Operational Condition 1,2 & 3 from 90 H Per 365 Days to 135 H Per 365 Days & Deleting Expired Footnotes for Clarity ML20081E2491995-03-0909 March 1995 Proposed Tech Specs,Revising SR 4.6.1.2.a,allowing Second Primary Containment ILRT (Type a) to Be Performed at Refueling Outage 5 or 72 Months After First Type a Test ML17059B0221995-02-15015 February 1995 Rev 0 to UT-NMP-311V0, Procedure for Manual Ultrasonic Exam of Nozzles Inner Radius & Bore. ML17059B0211995-02-10010 February 1995 Rev 0 to UT-NMP-309V0, Procedure for Manual Ultrasonic Exam of Planar Flaw Sizing for Nozzle Inner Radius & Bore Regions. ML17059B0201995-02-10010 February 1995 Rev 0 to UT-NMP-703V0, Procedure for Geris 2000 Ultrasonic Exam of RPV Nozzle Inner Radius & Bore Regions. ML17059A8881995-01-18018 January 1995 Rev 0 to Field Disposition Instruction 0245-90800, Shroud. ML20077N1591995-01-0606 January 1995 Proposed Tech Specs Re Min Gallons of Fuel Oil Required in Day Tanks & Storage Tanks ML20077N2071995-01-0606 January 1995 Proposed Tech Specs Re Deletion of Certain Instruments Not Classified as Category 1 ML20078Q9241994-12-13013 December 1994 Proposed Tech Specs Re Change to Table 3.6.1.2-1 That Will Allow Maximum Leakage of 24.0 Scfh for Each of Eight MSIVs ML20077E1561994-12-0202 December 1994 Proposed TS Page 3/4 1-20,reflecting Rev of SLCS Relief Valve Setpoint to Show Influence of Back Pressure & Rev of Bases Page B3/4 5-2 to Show That Hpsc Sys Designed to Supply 517 Gpm Flow Rate at 1,200 (Instead of 1,175) Psid ML20078J3781994-11-14014 November 1994 Proposed Tech Specs Reducing Leak Rate Test Pressure for Safety Related ADS Nitrogen Receiving Tanks from 385 Psig to 365 Psig ML17059A5661994-11-0909 November 1994 Rev 2 to Emergency Plan Maint Procedure EPMP-EPP-08, Maint, Testing & Operation of Oswego County Prompt Notification Sys. ML20078E0331994-10-28028 October 1994 Proposed Tech Specs 1.0, Definitions, 3/4.3.2, Isolation Actuation Instrumentation & 3/4.9.3, Control Rod Position ML20078B9841994-10-21021 October 1994 Proposed Tech Specs SR 4.8.1.1.2.e.8,reflecting Addition of Footnote Re 24 H Functional Test of DGs ML20073L8781994-10-0505 October 1994 Proposed TS Table 3.3.7.1-1 Re Radiation Monitoring Instrumentation ML20072U3491994-09-0202 September 1994 Proposed Tech Specs Re 18 Month Operability Test of Svc Water Pumps Sys & Resistance Test of Intake Deicing Heater Sys ML17059A4471994-09-0101 September 1994 Proposed Tech Specs Section 3.2.2, Minimum Reactor Vessel Temperature for Pressurization, & Associated Bases ML20072P6211994-08-26026 August 1994 Proposed TS 3/4.6.1.3, Primary Containment Air Locks, Allowing Continued Plant Operation If Interlock Becomes Inoperable as Long as Operable Door Locked Shut & Periodically Checked as Being Locked Shut ML17059A4241994-07-0606 July 1994 Rev 14 to Nine Mile Point Nuclear Station Unit 1 Odcm. ML20071G2771994-07-0101 July 1994 Proposed Tech Specs Surveillance Requirements 4.6.5.1.c.1 & 4.6.5.1.c.2 ML20029D4001994-04-27027 April 1994 Proposed Tech Specs Re Drawdown Time Testing & Inleakage Testing for Secondary Containment Integrity ML18040A2941993-12-17017 December 1993 Rev 13 to Nine Mile Point Nuclear Station Unit 1 Odcm. ML20058N3491993-12-14014 December 1993 Proposed Tech Specs 3/4.8.2, DC Sources, 3/4.8.4, Electrical Equipment Protective Devices & Bases for 3/4.6.3, Primary Containment Isolation Valves ML17059A0971993-10-25025 October 1993 Rev 4 to NMP2-IST-001,NMP,Nine Mile Point Nuclear Station, Unit 2,Pump & Valve First Ten-Yr Inservice Testing Program Plan. ML20056G9391993-09-0202 September 1993 Proposed Tech Specs Section 3/4.1.3.5, CR Scram Accumulators 1999-09-30
[Table view] Category:TEST/INSPECTION/OPERATING PROCEDURES
MONTHYEARML18041A0731999-07-27027 July 1999 Rev 1 to NMP2-ISI-006, Second Ten Year Interval Inservice Insp Program Plan for Nine Mile Point Nuclear Power Station Unit 2. ML17059B2911996-09-0404 September 1996 NMP Nine Mile Point Nuclear Station Unit 2,Pump & Valve First Ten-Yr Inservice Testing Program Plan. ML17059B0221995-02-15015 February 1995 Rev 0 to UT-NMP-311V0, Procedure for Manual Ultrasonic Exam of Nozzles Inner Radius & Bore. ML17059B0201995-02-10010 February 1995 Rev 0 to UT-NMP-703V0, Procedure for Geris 2000 Ultrasonic Exam of RPV Nozzle Inner Radius & Bore Regions. ML17059B0211995-02-10010 February 1995 Rev 0 to UT-NMP-309V0, Procedure for Manual Ultrasonic Exam of Planar Flaw Sizing for Nozzle Inner Radius & Bore Regions. ML17059A8881995-01-18018 January 1995 Rev 0 to Field Disposition Instruction 0245-90800, Shroud. ML17059A5661994-11-0909 November 1994 Rev 2 to Emergency Plan Maint Procedure EPMP-EPP-08, Maint, Testing & Operation of Oswego County Prompt Notification Sys. ML17059A4241994-07-0606 July 1994 Rev 14 to Nine Mile Point Nuclear Station Unit 1 Odcm. ML18040A2941993-12-17017 December 1993 Rev 13 to Nine Mile Point Nuclear Station Unit 1 Odcm. ML17059A0971993-10-25025 October 1993 Rev 4 to NMP2-IST-001,NMP,Nine Mile Point Nuclear Station, Unit 2,Pump & Valve First Ten-Yr Inservice Testing Program Plan. ML20056G6691993-02-25025 February 1993 Rev 8 to Odcm ML17056C2971992-06-30030 June 1992 NMPNS - Unit 2 Odcm. ML17056B9841992-06-26026 June 1992 Rev 9 to Nine Mile Point Nuclear Station Unit 1 Odcm. ML18038A4851991-10-0101 October 1991 Rev 3 to First 10-Yr ISI Program Plan. W/910930 Ltr ML17058A9561991-05-0202 May 1991 Rev 5 to Administrative Procedure AP-3.7.1, Unit 2 Radwaste Process Control Program. ML18038A3531991-05-0101 May 1991 Rev 3 to NMP2-IST-001, Niagara Mohawk Power Corp,Nine Mile Point Nuclear Station Unit 2 - Pump & Valve First Ten Year Inservice Testing Program Plan. W/910501 Ltr ML20070U3621991-04-0101 April 1991 Cover Page to Rev 1 to Issue 2 to Nuclear Security Training & Qualification Plan ML17058A9541991-03-0606 March 1991 Rev 4 to Administrative Procedure AP-3.7.1, Unit 2 Radwaste Process Control Program. ML18038A3271990-06-30030 June 1990 Rev 3 to Nine Mile Point Requalification Program Action Plan. ML17056B9831990-06-15015 June 1990 Rev 8 to Nine Mile Point Nuclear Station Unit 1 Odcm. ML17056A9671990-04-0303 April 1990 Rev 8 to Odcm. ML18038A3241990-02-28028 February 1990 Rev 5 to Odcm. ML17056A9661990-02-27027 February 1990 Rev 7 to Odcm. ML18038A2921989-09-12012 September 1989 Rev 3 to Administrative Procedure AP-3.7.1, Unit 2 Radwaste Process Control Program. ML17055E5581989-03-0202 March 1989 Rev 1 to Restart Action Plan. ML19325C1741989-02-14014 February 1989 Rev 1 to AP-3.7.1, Process Control Program. ML17055E4771989-01-16016 January 1989 Second 10-Yr Interval Inservice Testing Program. ML18038A4231988-05-31031 May 1988 Rev 6 to Offsite Dose Calculation Manual. W/Two Oversize Figures ML17056A9651988-02-23023 February 1988 Rev 6 to Odcm. ML20059F8751988-02-0505 February 1988 Rev 4 to Odcm ML20236G8161987-07-31031 July 1987 Revised Preservice Insp Plan for Nuclear Piping Sys & Reactor Pressure Vessel ML20236G8111987-07-31031 July 1987 Revised Preservice Insp Plan for Nuclear Piping Sys & Component Supports ML18038A2721987-05-21021 May 1987 Rev 3 to Offsite Dose Calculation Manual. ML18038A2491987-04-13013 April 1987 Revised Emergency Procedures,Consisting of Rev 5 to Emergency Action Procedure EAP-1, Activation & Direction of Emergency Plan, & Rev 9 to Emergency Plan Implementing Procedure EPP-20, Emergency Notification. W/870413 Ltr ML20205S2311987-03-31031 March 1987 Rev 0 to Pump & Valve Inservice Testing Program ML18038A4221987-02-27027 February 1987 Rev 4 to Offsite Dose Calculation Manual. W/Two Oversize Figures ML20211P4501986-12-13013 December 1986 Rev 0 to Preoperational Test Procedure N2-POT-1-2, Msivs ML17055D1821986-08-19019 August 1986 Rev 0 to Administrative Procedure AP-3.7.1, Process Control Program. ML18038A1671986-05-31031 May 1986 Rev 1 to Offsite Dose Calculation Manual. W/One Oversize Encl ML17055B5331986-04-11011 April 1986 Rev 1 to Technical Dept Procedure TDP-5, Administration of Operational Engineering Assessment Items. ML17055B5431986-04-0101 April 1986 Rev 0 to Maint Instruction Procedure S-MI-GEN-002, Maint Instructions for Writing Procedures. ML17055B5301986-03-20020 March 1986 Rev 0 to Site Administrative Procedure AP-6.1, Procedure for Mod & Addition. ML17055B5441986-03-14014 March 1986 Rev 1 to Nuclear Training Procedure NTP-11, Licensed Operator Retraining. ML17055B5421986-03-14014 March 1986 Rev 1 to Nuclear Training Procedure NTP-10, Training of Licensed Operator Candidates. ML17055B5171986-03-10010 March 1986 Rev 4 to Administrative Procedure AP-2.0, Production & Control of Procedures. ML17055B5411986-03-10010 March 1986 Rev 3 to Vol IV to SWEC Pp 94, Review of Changes & Effect on Environ/Mechanical/Seismic/Hydrodynamic Qualification of Equipment. ML17055B5461986-03-0202 March 1986 Rev 2 to Maint Instruction Procedure MI-4.0, Maint Instructions for Review & Implementation of Technical Requirements in Maint Procedures. ML17055B5251986-03-0101 March 1986 Draft Rev 4 to Administrative Procedure AP-4.0, Administration of Operations. ML17055B5381986-02-28028 February 1986 Rev 0 to Technical Dept Procedure TDP-8, Post-Maint Testing Criteria. ML20140D3341986-02-28028 February 1986 Rev 2 to Offsite Dose Calculation Manual. W/Two Oversize Maps 1999-07-27
[Table view] |
Text
Enclosure 86 NINE MILE POINT NUCLEAR STATION SITE ADMZAVISTRATIVE PROCEDURES PROCEDURE NO. AP-3.4.2 OPERATIONS EXPERIENCE ASSESSiiiT DATE AND INITIALS APPROVALS SIGiVATURES REVISION 1 REVISION 2 REVISION 3 Station Superintende NMPNS Unit 1 T. W. Roman Station Superinten l~/bP/
NMPNS Unit 2 R. B. Abbot Gene Super ntendent Nu Wneration /i!p/<W T. X erkins '/, /l 6'i j i)
Manager Q.A. Nuclear W. A. Hansen
/
Summar of Pa es Revision 1 (Effective 1/2/86 )
PAGES DATE 2-5 December 1984 1 October 1985 iVIAGARA MOHAWK POWER CORPORATION THIS PROCEDURE NOT TO BE USED APTER JAAVUARY 1988 SUBJECT TO PERIODIC REVIEW.
8604280273 8604iO PDR ADOCK 050004iO P PDR
(
42-3 ' '
OPERATIONS EXPERIENCE ASSESSHEitT 1.0 PURPOSE This procedure describes the methods to be used in performing the Operations Experience Assessment and the feedback of Operations Experience to the station staff for Unit 1 and Unit 2.
2.0 REFERENCES
Appendix A, NUREG 0578 July 1979 Letter H. R. Denten, October 30, 1979 Enclosure to letter D. G. Eisenhut, May 7, 1980, Section I.C 5, NUREG 0660 NUREG 0737, I.C. 5, D. G. Eisenhut letter October 31, 1980 3.0 PERSONNEL UALIFICATIONS A4G) FUNCTION The Nuclear Regulatory Commission has stated the following concerning operations experience assessment:
(Ref: Post T4MI Correspondence)
The persons serving the operating experience assessment function must be dedicated to concern for the safety of the plant. Their function will be to evaluate plant operations from a safety point of view.
- 1. Engineering evaluation of the operating history of the plant (equipment failures, design problems, operations errors, etc.)
and Licensee Event Reports from other plants of similar design, with suitable dissemination of the results of such evaluations to other members of the plant staff.
- 2. Engineering evaluation of plant conditions required for maintenance and testing.
3 ~ Engineering evaluation of the adequacy of utility policy for maintenance, testing, equipment procurement, etc.
4~ Engineering evaluation of continuing adequacy of plant operations quality assurance; and 3 ~ Engineering evaluation of adequacy of plant emergency and operating procedures.
AP-3.4.2 -1 October 1985
3.0 PERSONNEL QUALIFICATIONS AND FUNCTION (cont.)
The technical knowledge of those assessing operat'ing experience should be diverse and encompass all technical areas important to safety. The types of problems that can affect safety include all areas related to the design and operation of nuclear power plants; e.g., mechanical, electrical and fluid systems and reactor physics, chemistry and metallurgy. Recognition and understanding of a problem and its significance requires some knowledge in the relevant technical specialties and cannot depend solely on the descriptions and judgements of the persons identifying and reporting the problem.
Because of the broad scope of possible technical areas and the possible interactions of components, equipment and systems, the people engaged in operating experience review should have experience in areas usually designated as systems engineering. They should. also be gradua te engineers, or equivalent. In addition, because of the importance of operator actions in the safety of plant operations, familiarity with or routine access to persons with the principles of human engineering or human factors should be provided.
4.0 FEEDBACK OF OPERATING EXPERIENCE TO STATION STAFF The Nuclear Regulatory Commission has stated the following concerning procedures for feedback of Operating Experience to the station staff:
(Ref: Item I.C. 5 HUREG 660 Nay 7, 1980)
It is important that information on operating experience originating both within and outside the organization is continually provided to operators and other personnel, and that it is incorporated into plant operating procedures and training and retraining programs.
Those involved in the assessment of operating experience will review information from a variety of sources. These include operating information from the licensee's own plant(s), publications such as IE Bulletins, Circulars and Notices, and pertinent NRC or industrial assessments of operating experience. In some cases, information may be of sufficient importance that it must be dealt with promptly (through instructions, changes to operating and emergency procedures, issuance of special precautions, etc.) and must be handled in such a manner to assure that operations management personnel would be directly involved in the process. In many other cases, however, important information will become available which should be brought to the attention of operators and other personnel for their general information to assure continued safe plant operation. Since the total volume of information handled by the assessment group may be large, it is important that assurance be provided that matters are dealt with promptly and that discrimination is used in high priority the feedback of other information so that personnel are not deluged with unimportant and extraneous information to the detriment of their overall proficiency. It is important, also, that technical reviews be conducted to preclude premature dissemination of conflicting or contradictory information.
AP-3.4.2 -2 December 1984
TECHNICAL STAFF DESIGNEE FOR OPERATING EXPERIENCE ASSESSWiNT A member of the station staf f designated to coordinate operating experience assessment shall be responsible that information for evaluation shall be compiled and analyzed. This information shall include:
- 1. Operating and Special Operating Procedures
- 2. Station Occurrence Reports
- 3. Station and Equipment Performance vs. Design Objective I
- 4. Programs for analysis of other than normal station operations S. Reports by Operations and Maintenance personnel of difficulties encountered in completing their assigned work.
- 6. Licensee Event Reports from other stations (via INPO reports)
- 7. IE Bulletins, Circulars and Notices
- 8. Pertinent NRC or industrial assessments of Operating Experience.
6.0 PROCEDURE FOR DOCUiiENTING ASSESS'iiENT 6.1 Operations experience assessment shall be the major agenda feature of a special S.O.R.C. meeting to be held at least once every two months. For these meetings the following shall be added to S.O.R.C.
membership:
Vice President of nuclear Generation as available Representative of Nuclear Engineering and Licensing Reactor Analyst Supervisor Supervisor Operations or Alternate Supervisor Computer Operations and ifaintenance (Systems Engineering Specialist) or Alternate Assistant Station Shift Supervisor (STA)
Supervisor Quality Assurance Operations or Alternate Staff member designated for operating experience assessment or alternate Superintendent Training or Alternate When items concerning station modifications are on the agenda, the chairman may request the attendance of qualified consultants from the system engineering department.
AP-3.4.2 -3 December 1984
6.2 The agenda for the special meeting shall consider the five items enumerated in Section 3.0. The coordinator will prepare a draft report for presentation to the meeting and a final report following the meeting. The purpose of the report will be to summarize the operations experience applicable to the station accumulated since the last meeting, and to document the action 'taken at the station as a result of this operating experience. A suggested outline is as follows:
- 1. Review of significant information received from outside the station applicable to station operation, maintenance, testing, or modification. Report action taken and pending.
- 2. Safety significant equipment malfunctions at the station, corrective action taken and pending and long term corrective action taken and pending.
- 3. Trends developed from testing or operational surveillance short and long term action taken and pending.
- 4. Summary of nuclear reactor core operations including flux monitoring, instrumentation, control blade operating experience, off gas and water contamination trends. Analysis of operations and action pending.
- 5. Summary of operating problems which were or might be resolved by procedure change or addit'on; equipment, instrumentation or control change or addition; or organization change. Resolution and/or proposed resolution.
6.3 The final bimonthly operating experience assessment report shall be contained in the minutes of S.O.R.C. for review by the SR&A Board and members of the station staff.
7.0 PROCEDURE FOR FEEDBACK OF ASSESSMENT Operations Experience Assessment and feedback to the station staff is an integral part of the normal operations and maintenance of the Nine LLile Point Nuclear Station.
7.1 EQUIPMENT OR SYSTE'iaaf iQLLFUiVCTIONS All members of the station staff are required to promptly report any svstem or component malfunction which may come to their attention.
Detailed procedures for production and approval of work requests for corrective action are included in AP-5.0.
F 2 IVFORMATION FROif OUTSIDE OF THE STATION The training superintendent and his staff regularly study and evaluate licensee event (via INPO reports) and other significant event reports concerning other nuclear power stations. Significant events are covered in the operator qualification or re-qualification presentations.
AP-3.4.2 -4 December 1984
t INFORMATION FROM OUTSIDE OF THE STATION (cont.)
The station supervisor designated for operating experience assessment is assigned to study publications such as I.E. Bulletins, Circulars and Notices and pertinent NRC or industrial assessments of operating experience. Items requiring response or investigation are promptly forwarded to an appropriate station supervisor.
7.3 STATION OCCURRENCE REPORTS, SCRAM REPORTS Whenever there are occurrences at the station which involve a variation from normal plant operations or constitute an occurrence which may be reportable to the NRC, an occurrence report or scram report is generated by the person most closely associated with the event. Detailed procedures for handling this type of report are included in AP-10.0. All occurrence reports and scram reports are reviewed by S.O.R.C. and where required licensee event reports are made and transmitted through the Vice-President Nuclear Generation to the NRC, the Station Superintendent shall be responsible that a description of the event and the results of any subsequent evaluation is distributed to the Operations Supervisor and other staff supervisors who may be concerned with the event. The staff supervisors shall in turn be responsible that significant information concerning these events is made known to all station personnel who may encounter this or similar events in the course of their work.
AP-3.4.2 -5 December 1984