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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
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Text
Enc1osure 826 NINE MILE POINT NUCLEAR STATION INSTRUMENT DEPARTMENT PROCEDURE PROCEDURE NO. S-IDP-PO OUTLINE FOR IhC PROCEDURES DATE AND INITIALS APPROVALS SIGNATURES REVISION 6 REVISION 7 REVISION 8 Instrument h Control Supervisor R. E. Coon Station Superintend NMPNS Unit 1 T. W. Roman Station Superintendent NMPNS Unit 2 R. B. Abbott r of Pa es Revision 6 (Effective 2/10/86 )
P~aea Date 1-7 February 6, 1986 NIAGARA MOHAWK POWER CORPORATION THIS PROCEDURE NOT TO BE USED AFTER FEBRUARY 1990 SUBJECT TO PERIODIC REVIEW.
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S-IDP-PO OUTLINE FOR IhC PROCEDURES A.O PURPOSE This document is designed to explain the scheme of procedures used by the Instrument and Control Department at the Nine Mile Point Site.
Further, it provides guidance for revision and generation of desirable departmental procedures.
B.O REFERENCE B.l AP-1.0 "Procedure for Administrative Control" B.2 AP-2.0 "Production h Control of Procedures" B.3 AP-8. 1 "Procedure for Service and preventative Maintenance" C.O PROCEDURE CATEGORIES ISP INSTRUMENT SURVEILLANCE PROCEDURE Used to comply with stated Technical Specification requirements.
Example: Surveillance Testing, etc.
Procedure has instrument set point limits and Occurrence .
Report requirements. This category has step verification and requires SORC approval.
ICP - INSTRUMENT CALIBRATION PROCEDURE Used to comply with implied Technical Specification requirements.
Example: Provides calibration of equipment which is used by some other department to meet a Tech. Spec.
requirement. This category has step verification and requires SORC approval.
IMP INSTRUMENT MAINTENANCE PROCEDURE Used generally to provide some repair function or a function to avoid device failure. These procedures should be generic in nature when possible. This category usually requires SORC approval.
S-IDP-PO -1 February 1986
d C.O PROCEDURE CATEGORIES (Cont'd)
IP - INSTRUMENT PROCEDURE Used as a departmental procedure for calibrating non-safety related devices. This procedure category will be generally used for Balance of Plant (B.O.P.) instrumentation. This category normally will not require SORC approval and is intended to be generic in nature.
PROCEDURE NUMBER SYSTEM Whenever possible procedure numbers are to be identified by Plant System number. Example Nl-ICP-W-60, Nl indicates Unit 1 (N2 indicates Unit 2 and S indicates a Site Procedure); ICP is the calibration category. The W is the frequency that the procedure should be performed.
W = Weekly at least once per'7 days M = Monthly at least once per 31 days Q = Quarterly at least once per 92 days A = Annual - at least once per 366 days SA = Semiannual at least once per 184 days C = Cycle - once per refueling cycle The 60 is the plant system number for Emergency Cooling. The procedure title is Emergency Cooling Level Control. The procedure number may bear a numerical or alphabetical suffix to provide for additional procedure requirement within the same system.
PROPOSED CHANGES Require only SORC approval-review sheet to be attached to a copy of the procedure with proposed revision.
TEMPORARY CHANGES Requires a Procedure Change Notice attached to copy of the procedure which indicates the changes and identifies the approving SSS and Supervisor. This procedure is to be submitted to the Unit IhC Supervisor by the next business day following implementation. The used procedure copy requires acknowledgement for each change or group of changes of the SSS and IhC Supervisor. See AP-2.0 and AP-1.0.
S-IDP-PO -2 February 1986
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D.O PROCEDURE FORMAT Items under this section are identified by number, the same as in existing documents. A P is provided as a review mechanism to a person when generating IhC procedures.
TITLE PAGE The procedure name and number must appear at the top. For ISP's, ICP's, and IMP's, the procedure number should be the same as the system involved.
For SORC approval three signatures are required.
- 1. Site IhC Supervisor
- 2. Station Superintendent
- 3. Site Superintendent Non-SORC approved procedures require only two signatures (items 1 and 2 above).
Site procedures require the Site IhC Supervisor, Unit 1 Station Superintendent, and the Unit 2 Station Superintendents signatures.
Below the approval signatures a REVISION STATEMENT is added indicating the nature of the revision and pages affected. If the procedure number is changed it must identify the procedure which is superseded.
At the lower right corner of the title page, a statement indicating expiration is to be made. 00 NOT USE AFTER... for SORC'ed procedures 2 years and Non-SORC'ed procedures 4 years from date of issue.
1.0 PURPOSE This section identifies the total accomplishment intended by the procedure. The intended usage frequency should be noted here.
2.0 REFERENCES
(As Applicable)
Technical Specifications - paragraph only, not pages.
Niagara Mohawk Drawings Index Number, Dwg. No. and description of title including, as appropriate.
Electrical drawings and tank outlines, Manufacturer's Bulletins.
Attached figures and sketches, examples:
- 1) Illustrations of tanks showing relation of instrumentation and meter scales.
- 2) Curves of volume vs level of tanks indicating Tech. Spec. requirements and alarm valves.
- 3) Arrangement of test equipment or block diagram of equipment.
S-IDP-PO -3 February 1986
3.0 PREREQUI SITES Indicate actions to be done prior to test, such as:
Establish communications, state jack numbers.
Obtain RWP - where necessary.
Markups - where there is any question of safety.
Time frame - when can the procedure be used.
Conditions which must prevail.
State precautions.
4.0 TEST EQUIPMENT List items which are of major importance with equivalent options when possible. Items such as hand tools, tubing, etc. normally should not be listed unless they are of special significance.
5.0 PROCEDURE Ingredients in this outline whenever possible should be handled as prescribed. Deviations ma be taken as necessar . Most importantly, the work must be able to be done as written with efficiency in mind.
The procedure body should be subdivided by major sections, i.e. 5.1, 5.2, 5.3 etc. are to be titled with capital letters, but not underlined. Subsections 5.1.1, 5.1.2, 5.1.3, etc. are to be used as necessary to accomplish the major section task in a smooth manner.
A constant level of awareness must be kept to assure that the procedure flows smoothly, is easy to use, and review. Care in use of words will reduce ambiguity and keep bulk to a minimum.
desirable to state detailed work functions which are obviously within It is not the capability of the technician. "NOTES" and "CAUTIONS" should be inserted at appropriate places to emphasize awareness of problem areas.
5.1 PRELIMINARIES
- 5. 1.1 First obtain permission from SSS for procedure use.
The procedure body and/or data sheet should identify key consequences in capital letters i.e. scram, jumpers required to Block..., sw position, etc. Discuss such consequences and request any desired markups. Obtained signature and date from the SSS.
EXAMPLE: In capital letters, enter the major cautions which may effect plant operation.
PLANT IMPACT: +THIS PROCEDURE WILL CAUSE 1/2 SCRAMS "THE MODE SW MUST BE IN SHUTDOWN "POSSIBLE CLOSURE OF OFFGAS VALVE S-IDP-PO -4 February 1986
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- 5. 1.2 Notify SCO of commencement (obtain his initials on the data sheet).
- 5. 1.3 Before work begins, record the as-found end-result-indication for operating system. (i.e. Recorder indication, panel meter indication.)
- 5. 1.4 Record the test equipment information with some awareness of calibration tenure.
5.2 WORK EFFORT This section should be subdivided and handled in outline form. Each section should receive the next identifying number 5.2.1, 5.2.2, 5.2.3, etc. Subsections may be identified numerically or alphabetically ("a" "b" "c", etc. )
EXAMPLES:
5.2 POWER SUPPLY CHECK a) + 15 volt supply b) Hi voltage supply 5.3 AMPLIFIER ZERO a) zero b) gain 5.4 COMPUTER CORRELATION a) alarm b) analog display 5.2.1 At the transmitter (located at elev...) valve out, vent and drain.
5.2.2 Connect the test equipment and apply signal values per data table. Record the data and adjust as necessary.
5.2.3 DATA TABLE/DATA SHEET For record retention and retrieval purposes, the data sheet (when used) must provide a space for the equipment piece number of the primary device (transmitter) and the specific device within, as applicable. NMPC Form if313-169R may be used.
A. Cover range of instrument(s) involved B. Specify acceptable tolerance (s) and equivalent values where applicable.
C. Use values which are obtainable for equipment involved.
S-IDP-PO -5 February 1986
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DATA TABLE/DATA SHEET (Cont'd)
- 0. For HhTE instruments, if an instrument is a multi-range device, record the range used to obtain data.
E. Comply with Tech. Specs. if applicable.
F. Whenever possible use transmitter output signals & values as inputs to other loop devices.
G. When establishing calibration values for flow instruments, output from the devices should be linear to accomodate meter scales.
Use jumper log for all lifted leads, blocked contacts or jumpers.
Verify set point/trip point operation stating < or >
inc./dec./signal. Verbiage regarding set point values should and should be as follows:
a) "Required" if
- for Tech. Spec. Limits exceeded Occurrence Report is required. Example: Tech.
Spec. Limit > 53" Hg), guide valve 55+ 1" HP, b) "Guide" A value with a given tolerance which is conservative of the Tech. Spec. Value.
c) "Desired" No Tech. Spec. requirement, but value
(+) tolerance is to be stated.
Scrutinize sensor initiation functions, computer generated alarm ID's, computer printout statement(s) and annunciator activations.
RETURN TO SERVICE Return equipment to service, i.e. valve in, remove jumpers, clear markups.
Attach a cal sticker on each item calibrated; use checkoff for this for assurance.
Install lead-wire seals h seal No's where applicable and install caps/plugs on test connections. Replace and secure covers, doors, etc.
Obtain an independent verification of return to service by a qualified person, by Name:
This section should identify or list requirements to be verified and a "e" for each item.
S-IDP-PO -6 February 1986
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5.3.5 Record as-left end result operating indication.
5.3.6 Post maintenance testing or verification is required on Class 1, Safety related, and Environmentally qualified equipment .
5.3.7 Post maintenance testing or verification should be u'sed on B.O.P. whenever possible.
5.3.8 Notify SSS and CSO of completion, obtain their initials for this action.
5.3. 9 Provide for signature and date of the technician, name(s) of assisting persons reviewing chief tech. and reviewing supervisor(s).
6.0 ACCEPTANCE CRITERIA A statement indicating what results are necessary for acceptance.
This may be accomplished by various methods. Examples are:
a) All sections of the procedure completed and found or adjusted to be within the stated limits within such steps.
b) -Q mechanism to handle deviations of (a) above. Example: the Occurrence Report, Work Request, etc.
Limitations necessary which have not been included previously.
Example: equipment design criteria S-IDP-PO -7 February 1986
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