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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 85 NINE MILE POINT NUCLEAR STATION ADMINISTRATIVE PROCEDURE PROCEDURE NO. AP-3.4el ADMINISTRATION OF TECHNICAL AND SAFETY REVIEWS Site Operations Review Committee DATE AND INITIALS APPROVALS S XGNATURES REVISION 0 REVISION 1 REVISION 2 Station Superintende NMPNS T. W. Roman Station Superintendent NMPNS R. B.
Unit 2 Abbott QNint
~c i/zw/m g/P fi General S g'0 8 Nucle Ge Qt on C oh S.O.R.C.
T. rkins Quality Assurance Concurrence
- Manager, Nuclear QA ~/w/rs.
D. R. Palmer ~Bg Summa of Pa es Revision Effective 8/29/85 PAGE DATE 1 6 December 1984 NIAGARA MOHAWK POWER CORPORATION THIS PROCEDURE NOT TO BE 8604280271 86041 5 USED AFTER AUGUST 1987 PDR ADOCK 05000410 SUBJECT TO PERIODIC REVIEW.
PDR,) )
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AP-3. 4. 1 ADMINISTRATION OF TECHNICAL AND SAFETY REVIEWS Site 0 erations Review Committee 1.0 PURPOSE This procedure defines the requirements of membership, meeting frequency, responsibilities, authority, and records for the Site Operations Review Committee (SORC) and provides the detailed procedure for committee meetings.
2.0 MEMBERSHIP Membership shall be as prescribed in Section 6.5.1.6 of the Technical Specifications.
3.0 RESPONSIBILITIES AND AUTHORITY 3.1 Res onsibilities Shall be as defined in Paragraph 6.5.1.6 NMPNS Tech. Spec.
3.2 ~Authordt Shall be as defined in paragraph 6.5.le7 NMPNS Tech. Spec.
3.3 Records Shall be maintained at the plant in the form of minutes as prescribed in Technical Specifications: Paragraph 6.5.1.8 NMPNS Tech. Spec.
Record retention shall be in accordance with AP-10.1. The disposition of each item of Technical Specification 6.5.1.6 shall be identified in the minutes. The minutes of the meetings shall be serial numbered and copies shall be sent to the General Superintendent, Nuclear Generation, the Vice President Nuclear Generation NMPC, and the Chairman of the Safety Review and Audit Board.
4.0 MEETING FRE UENCY AND UORUM 4.1 Meeting shall be at least monthly and at the call of the Chairman.
(Tech Spec 6.5.1.4).
4.2 A quorum". shall consist of the chairman and four members including designated alternates. (Tech Spec 6.5.1.5).
AP-3.4.1 -1 December 1984
5.0 REVIEW PROCEDURE 5.1 ~ends Material for Presentation Material for SORC review may be prepared at the request of the chairman or may be generated by staff supervisors .in the course of their regularly assigned duties. All material. presented to the committee for formal review should be prepared in written form. When because of urgency, a subject is presented orally, the secretary to the committee will be responsible for recording the presentation in the appropriate format or subsequently obtaining a copy from the person making the presentation.
5.1.2 Outstanding Items List The secretary shall maintain an Outstanding Items List of all documents and other items pertaining to the SORC for review or recommendation which have been deferred, or referred to an individual or committee for implementation, study and/or later report. The Outstanding Items List is reviewed periodically by the committee to resolve any outstanding items.
5.1.3 Assignments for Presentation Anyone who has completed an assignment for presentation to SORC or has other material for presentation, should notify the SORC Chairman or his secretary stating the title of the document or sub)ect ready for review. This material may then be used to make up the meeting agenda.
5.1. 4 Meeting Agenda Wherever practical, the SORC Chairman or his alternate shall distribute an agenda to all SORC members prior to each meeting, listing the documents and other matters to be presented for review.
If available, copies of any documents on the agenda shall be furnished on request to any member of SORC. The physical maintenance of Outstanding Items Lists and agendas for SORC may be assigned to the secretary to the SORC Chairman subject to the supervision of the SORC Chairman.
5.2 Material Presentation Presentations for Information Subjects presented for general information or informal discussion, and which do not require a recommendation from the Committee, may be presented orally or in writing. These presentations may be summarized or. referenced in the minutes of the meeting without commentary.
AP-3.4.1 -2 December 1984
5 ~ 2.2 Safety Analysis Reports and Other Reports Prepared for Formal Revie~ and Approval It is expected that Safety Analysis Reports and other reports of a more complex nature will be presented to SORC in summary form accompanied by an analytical review completed by a knowledgeable person not a party to the original report. The reviewer may be but need not be a member of SORC. Reviews should be made as outlined in Section 5.3.
5.2.3 Other Reports Other reports which may require SORC review and recommendation, but for which no formal comments are submitted may be presented with the permission of the chairman. When presented, these shall be summarized or referenced in the minutes of the meeting along with the committee recommendations.
5.3 Formal Review Procedure When massive or complex documents require SORC review and recommendation, a qualified person shall be designated to prepare a summary and review for presentation at a special or regular meeting.
5.3.1 Reviewers Reviewers shall not be persons directly involved in the preparation of the document; however, prior to presentation the author may deliver copies of his document to reviewers designated by the SORC Chairman or by the supervisor sponsoring the matter for presentation. He shall then attempt to produce , a document satisfactory to all reviewers. See AP-3.4.3.
5.3.2 Review Form Documents subject to the review described in this section shall be accompanied by a document review report and check off sheet designed to correspond with the document to be reviewed. After presentation to SORC, this review report shall be retained in the station files with the final approved document.
5.3.3 Acceptance at SORC Meeting as Revised If the SORC meeting results in a document with acceptable revisions; a copy of the original submittal with attached or marked revisions shall be returned to the originator or alternate for preparation of a revised document suitable for publication.
5.3.4 Unsatisfactory Document If a reviewer considers a document unacceptable as presented or as revised, he may present his recommendations directly to SORC for consideration.
AP-3. 4.1 -3 December 1984
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5.3.5 If the recommendations of a reviewer or the results of the SORC meeting are such that:
a~ It is not practicable to accept or draft revisions at the time of the meeting,
- b. The comments require referral back to the author for general revision or research, or Co There is an unresolved disagreement between reviewers, The Chairman shall assign the original author or other knowledgeable person to coordinate the preparation of a revised submittal of the document.
5.4 Review of Occurrences Re uirin Co nizance of the SORC Unusual or reportable occurrences involving operating variations. or equipment malfunctions which do or may require cognizance of the SORC, shall be recorded on the plant occurrence report (see AP-10).
Where a formal report is made, the general procedure outlined in Section 5.1 shall be followed.
5.4.2 Investigations made prior to preparation of a formal report may be conducted by a knowledgeable person or subcommittee appointed by the Chairman; This committee shall report when convened by the Chairman the purpose of the investigation.
5.4.3
~ ~ The person assigned by the General Superintendent to prepare special submittals to the HRC shall maintain an Occurrence Report Form in accordance with AP-10.2.2. Ee shall act as Coordinator for the special SORC investigation. The results of the investigation and any comments by members of SORC shall be included in the minutes of the meeting. Copies of the final report or letter along with copies of any comments by members of SORC shall be attached to the Occurrence Report Form and placed in the Occurrence Report file as evidenced that appropriate investigations, reports, and distributions have been made concerning the occurrence.
5.4.4 When an occurrence is reportable in accordance with the 10CFR50.73, a Licensee Event Report (LER) shall be submitted to the NRC. (See AP-10 2.2) ~
5.5 All investigations made by or at the direction of SORC and/or the General Superintendent shall include if possible, a determination of the cause and corrective action required. If the cause and/or corrective action cannot be determined upon first presentation, the measures being taken to make these determinations shall be presented to SORC.
AP-3.4.1 -4 December 1984
5.6 Scram Reports prepared in accordance with AP-10 shall also be submitted to SORC for review in the same manner as occurrence reports. Scram reports need not be reviewed by SORC prior to restart unless the cause of the scram or the plant transient response is not fully understood. Under these conditions SORC will provide the independent assessment per generic letter 83-28 Section 1.1.6, -and SORC approval is required prior to restart. OP-43 and/or RAP-6 determine the need for this independent review.
5.7 0 eratin Ex erience Assessment The Site Operations Review Committee augmented by additional technical personnel shall be responsible for regular assessment of operation experience with the requirement for making recommendations for improvement in station safety and performance. Detailed procedures for operating experience assessment are contained in AP-3 '.2~
5.8 Plant, Modifications 5.8.1 The Site Operations Review Commit tee augmented by additional technical personnel shall be responsible for site review of the in AP-6 '.
design of modifications and associated safety evaluations as detailed 5 ~ 8.2 The Site Contact shall coordinate the site review and document the reviews on the modification review form (Figure 1). Open review items shall be documented on the SORC or SRAB meeting minutes as applicable. The completed review form shall be logged by Site Planning and become part of the modificatIon file 7.0 APPENDICES 7.1 Modification Review Form
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AP-3.4.1 -5 December 1984
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1
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Figure 1 NIAGARA MOHAWK POWER CORPORATION MODIFICATION REVIEW FORM SITE OPERATIONS REVIEW COMMITTEE Modification
Title:
Modification Control No. N Y M Design Review: 0 Conceptual 0 Final 0 N/A Documents Reviewed: 0 Safety Evaluation 0 Technical Specifications 0 Site Functional Specification 0 Conceptual Design Description 0 Other:
Document Title Document No.
Originator: Name Dept. Date Pro)ect/Site Engineer: Date Logged by Site Planning: Date REVIEW:
Accepted as Presented Accepted as Revised Name Initials/Date Initials/Date
- 1. Site Contact 2~
3.
4~
5.
SORC REVIEW:
First presented to SORC by on Date Accepted by SORC: 0 As submitted 0 As Revised. Meeting t 0 This modification does not involve an unreviewed safety question and does not involve a change to technical specifications.
0 This modification involves an unreviewed safety question or a change to technical specifications. Prior NRC approval shall be obtained.
The documents submitted for revie~ need more detailed engineering or revision.
Return to SORC for further review.
The modification may proceed and be installed after final review of the safety evaluation.
SORC Chairman Date 0 SORC Review N/A Int.
Logged,'.Complete By Site Planning Date SRAB REVIEW 0 Accepted as submitted 0 As revised Meeting Date SRAB Chairman Date 0 SRAB Review N/A Int Logged Closed By Site Planning Date Decem er 1
i
