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Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML20211B2381999-08-31031 August 1999 Revised Interjurisdictional Policy for Songs ML20210P5971999-08-11011 August 1999 Proposed Tech Specs SR 3.3.7.3,replacing Analytical Limits Currently Specified as Acceptance Criteria with Allowable Values,Per Calculation E4C-098,change Notice 25 ML20210P6301999-08-10010 August 1999 Corrected Proposed Tech Specs Re Diesel Generator Testing ML20210N5121999-08-0909 August 1999 Proposed Cycle 10 Update to TS Bases That Have Been Revised Between 980101-990630 ML20196A9981999-06-17017 June 1999 Revised Pages to Risk-Informed IST Program for Sce ML20195E5171999-06-0808 June 1999 Proposed Tech Specs Pages Re Application for Amend to Licenses NPF-10 & NPF-15,to Revise TS 3.5.2,3.1.9,3.7.1 & 5.1.7.5 ML20207A3911999-05-24024 May 1999 Proposed Tech Specs 3.8,clarifying Bases for SRs 3.8.1.7, 3.8.1.12 & 3.8.1.15 ML20216D9741999-05-0707 May 1999 Rev 3 to Abnormal Operating Instruction SO23-13-14, Reactor Coolant Leak ML20199D0391999-01-13013 January 1999 Proposed Tech Specs Conservatively Restricting Required Actions Completion Time to Close All Containment Penetrations Providing Direct Access from Containment Atmosphere to Outside Atmosphere ML20206R2801999-01-11011 January 1999 Proposed Tech Specs to Increase Min Required Vol of Water in Condensate Storage Tank T-120 from 280,000 to 360,000 Gallons ML20198L6211998-12-31031 December 1998 Proposed Tech Specs 3.3.5 Re ESFAS Instrumentation ML20198L5111998-12-23023 December 1998 Rev 0 to SONGS Risk-Informed Inservice Testing Program, Engineering Analysis & Program Description ML20198G4001998-12-22022 December 1998 Proposed Tech Specs,Allowing SG Tube Repair Using W Laser Welded Sleeving as Alternative SG Tube Repair to Either ABB-CE ML20196H9321998-12-0404 December 1998 Proposed Tech Specs Reducing RCS Temp & Revising Volumetric Min Flow Rate ML20195J9021998-11-23023 November 1998 Proposed Tech Specs Revising TS 3.3.1, RPS Instrumentation - Operating ML20195J9551998-11-23023 November 1998 Proposed Tech Specs Re Turbine Missile Protection ML20155B8741998-10-20020 October 1998 Proposed Tech Specs Adding SR to TS 3.3.9, CR Isolation Signal ML20154J2991998-10-0909 October 1998 Proposed Corrected Tech Specs Pages for 980511 Suppl 1 to Amend Application Re App J,Primary Containment Leakage Testing for water-cooled Power Reactors,Option B ML20153G7511998-09-22022 September 1998 Proposed TSs Revising TS 3.3.1, RPS Instrumentation - Operating, Re Rt Operating Bypass Removal Process Variable ML20151W6801998-09-10010 September 1998 Proposed Tech Specs Eliminating Requirements for Hydrogen Control Sys from Low Power Plant License Conditions 2.C(19)i & from TSs 3.3.11 & 3.6.7 ML20151T6561998-09-0404 September 1998 Proposed Tech Specs Section 3.4.10,increasing as-found Psv Setpoint Tolerances ML20206N5381998-08-12012 August 1998 Rev 15 to Emergency Operating Instruction S023-12-7, Loss of Forced Circulation/Loss of Offsite Power, Pages 1,3,18, 39 & 122 ML20236S6241998-07-22022 July 1998 Proposed Tech Specs Section 3.8.1,extending Offsite Circuit Completion Time from 72 H & 6 Days from Discovery of Failure to Meet LCO to 72 H & 17 Days from Discovery of Failure to Meet LCO ML20249B4291998-06-19019 June 1998 Proposed Tech Specs Changes Reducing Minimum Primary RCS Cold Leg Temp from 544 F to 535 F Between 70% & 100% Rated Thermal Power Levels ML20216B6201998-05-11011 May 1998 Proposed Tech Specs Re App J,Primary Reactor Containment Leakage Testing for water-cooled Power Reactors,Option B ML20216B4141998-05-0707 May 1998 Proposed Tech Specs Pages,Revising TS Section 1.1, Definitions, to Change Reference Used for Obtaining Dose Conversion Factors for Calculating Dose Equivalent I-131 ML20217P8471998-04-0606 April 1998 Proposed Tech Specs Revising Containment Isolation Valves Completion Times ML20206N5231998-03-16016 March 1998 Rev 15 to Emergency Operating Instruction S023-12-1, Std Post Trip Actions ML20216C0051998-03-0606 March 1998 Proposed Tech Specs,Eliminating Ref to Inverters in TS 3.4.12.1 ML20206E6001998-02-27027 February 1998 Rev 31 to S023-ODCM, SONGS Units 2 & 3 Odcm ML20199K6451998-02-0303 February 1998 Proposed Tech Specs 3.5.1,extending Completion Time for Single Inoprable SIT from 1 H to 24 H & Adding New TS 5.5.2.14, Configuration Risk Mgt Program ML20206N5021998-01-30030 January 1998 Temporary Change Notice 2-1 to Rev 2 to Alarm Response Instruction S023-15-50.A1, Annunciator Panel,50A Pzr/Cea Windows 1-30, Pages 1,3,14,15 & 62-64 ML20198H8511998-01-0909 January 1998 Proposed Tech Specs 3.5.2 Re Extension of Completion Time for Low Pressure Safety Injection Train ML20198H7601998-01-0909 January 1998 Proposed Tech Specs 3.8.1 Re Extension of EDG Completion Time ML20198H6881998-01-0909 January 1998 Proposed Tech Specs 3.5.1 Re Extension of Completion Time for Safety Injection Tanks ML20198E6051998-01-0202 January 1998 Proposed Tech Specs Pages,Revising TS 3.7.5 & Bases to Indicate Turbine Driven AFW Pump Is Operable When Running in Manual Mode to Support Plant Startups,Shutdowns & Testing ML20197C7281997-12-19019 December 1997 Proposed Tech Specs Reducing Pressurizer Water Level Required for Operability ML20199C6391997-11-14014 November 1997 Proposed Tech Specs,Revising Ufsar,Section 3.5, Missile Protection to Allow Use of Probability of Damage to Critical Components in Evaluating tornado-generated Missile Protection Barriers ML20198P4011997-10-31031 October 1997 Rev 2 to Document 90022, Susceptibility of RCS Alloy 600 Nozzles to Primary Water Stress Corrosion Cracking & Replacement Program Plan ML20217K0081997-10-16016 October 1997 Rev 1 to Evaluation of SONGS Unit 3 SG Eggcrate Support Condition-Cycle 9 ML20203E1201997-09-11011 September 1997 Rev 1 to S-PENG-DR-003, Addendum to Piping Analytical Stress Rept for SCE San Onofre Units 2 & 3. W/Memo from C Chiu to Jt Reilly Re Corrective Action for Unit 3 Pressurizer Nozzle Failure in Mar 1986 ML20203D8421997-08-28028 August 1997 Rev 1 to S-PENG-DR-002, Addendum to Pressurizer Analytical Stress Rept for SCE San Onofre Units 2 & 3 ML20203D8981997-07-0303 July 1997 Rev 0 to TR-PENG-042, Test Rept for Mnsa Hydrostatic & Thermal Cycle Tests ML20203D8761997-07-0202 July 1997 Rev 0 to TR-PENG-033, Seismic Qualification of San Onofre, Units 2 & 3 Mnsa Clamps for Pressurizer Instrument Nozzles & RTD Hot Leg Nozzles ML20148R4051997-06-30030 June 1997 Proposed Tech Specs Deleting SONGS Unit 2 License Condition 2.C(19)b & Revising SONGS Unit 2 & 3 TS 3.3.1,3.3.2,3.3.5, 3.3.10,3.3.11,3.4.7,3.4.12.1,3.7.5,5.5.2.10 & 5.5.2.11 ML20141B4481997-06-18018 June 1997 Proposed Tech Specs Revising TS 3.8.1, AC Sources - Operating & Applicable Bases to More Clearly Reflect Safety Analysis & Testing Conditions ML20198R0281997-05-30030 May 1997 Proposed Tech Specs Re Revised Bases Pages for Songs,Units 2 & 3 ML20217P9981997-05-28028 May 1997 Rev 30 to SONGS Unit 2 & 3, Odcm ML20137V2501997-04-15015 April 1997 Proposed Tech Specs 3.8.1, AC Sources - Operating, Revising SR 3.8.1.8 & Applicable Bases Allowing Credit Overlap Testing ML20134P9941997-02-21021 February 1997 Proposed Tech Specs Clarifying Note Which Relays Will Not Be Response Time Tested Until Next Songs,Unit 3 Refueling Outage to Satisfy SR 3.3.5.6 of TS 3.3.5, ESFAS Instrumentation 1999-08-09
[Table view] Category:TEST/INSPECTION/OPERATING PROCEDURES
MONTHYEARML20211B2381999-08-31031 August 1999 Revised Interjurisdictional Policy for Songs ML20196A9981999-06-17017 June 1999 Revised Pages to Risk-Informed IST Program for Sce ML20216D9741999-05-0707 May 1999 Rev 3 to Abnormal Operating Instruction SO23-13-14, Reactor Coolant Leak ML20198L5111998-12-23023 December 1998 Rev 0 to SONGS Risk-Informed Inservice Testing Program, Engineering Analysis & Program Description ML20206N5381998-08-12012 August 1998 Rev 15 to Emergency Operating Instruction S023-12-7, Loss of Forced Circulation/Loss of Offsite Power, Pages 1,3,18, 39 & 122 ML20206N5231998-03-16016 March 1998 Rev 15 to Emergency Operating Instruction S023-12-1, Std Post Trip Actions ML20206E6001998-02-27027 February 1998 Rev 31 to S023-ODCM, SONGS Units 2 & 3 Odcm ML20206N5021998-01-30030 January 1998 Temporary Change Notice 2-1 to Rev 2 to Alarm Response Instruction S023-15-50.A1, Annunciator Panel,50A Pzr/Cea Windows 1-30, Pages 1,3,14,15 & 62-64 ML20198P4011997-10-31031 October 1997 Rev 2 to Document 90022, Susceptibility of RCS Alloy 600 Nozzles to Primary Water Stress Corrosion Cracking & Replacement Program Plan ML20217P9981997-05-28028 May 1997 Rev 30 to SONGS Unit 2 & 3, Odcm ML20203E4371997-02-12012 February 1997 Rev 2 to SO23-XVII-3.1.1, Refueling Outage Interval Exam of Reactor Coolant Pressure Boundary to Detect Leakage from Abb Combustion Engineering to SCE.W/18 Oversize Drawings ML20249A5311997-01-0707 January 1997 Rev 4 to PRA-REV-001, PRA Model Rev Procedure ML20203K7591996-11-0505 November 1996 Rev 1 to Du General Software Design Description ML20138H5571996-08-0505 August 1996 Rev 1 to Ultrasonic Exam of Vessel Welds & Adjacent Base Metal ML20138F0121996-07-31031 July 1996 Rev 29 to, Offsite Dose Calculation Manual,Nuclear Organization Units 2 & 3 ML20113C5081996-06-30030 June 1996 PRA Barrier Control Program ML20203E4021996-06-27027 June 1996 Rev 0 to SO23-XXVI-20.46, Visual Exam Procedure to Determine Condition of Nuclear Parts,Components or Surfaces. W/Temporary Change Notice 0-1 ML20206N5141996-04-25025 April 1996 Rev 2 to Abnormal Operating Instruction S023-13-17, Recovery from Inadvertent Safety Injection,Containment Isolation or Containment Spray ML20203K8021995-11-21021 November 1995 Rev 0 to Lpu General Software Design Description ML20203E3401995-10-19019 October 1995 Rev 1 to SO123-V-8.15, Mode 3 Boric Acid Leak Insp ML20112C1821995-10-16016 October 1995 Temporary Change Notice 6-36 to Rev 6 to Operating Instruction SO23-5-1.7, Power Operations ML20091N3401995-08-24024 August 1995 Temporary Change Notice to Rev 9 to S023-V-35, IST of Valves Program ML20203K7371995-07-24024 July 1995 Rev 1 to S0123-606-1-15-1, DRMS Software Verification & Validation Plan ML20082K3631995-04-14014 April 1995 Rev 3 of San Onofre Unit 3 Nuclear Generating Station Nuclear ISI Program Second Interval from 940401-030817 ML20082K3571995-04-12012 April 1995 Rev 3 of San Onofre Unit 2 Nuclear Generating Station Nuclear ISI Program Second Interval from 940401-030817 ML20204J0291995-02-17017 February 1995 Rev 0,EC 0-1 to SO23-XXI-3.1.2, Simulator Performance Test Scheduling ML20080L2321995-02-17017 February 1995 Editorial Correction 0-1 to Rev 0 of Training Procedure S023-XXI-3.1.2, Simulator Performance Test Scheduling ML20080F7021994-12-21021 December 1994 Rev 27 to Odcm ML20138H5661994-12-0101 December 1994 Rev 0 to Ultrasonic Exam of Nozzle Inner Radius Areas ML20065D0021994-04-0101 April 1994 Rev 6 to SO23-V-3.4, Inservice Testing of Pumps Program ML20065D0051994-03-28028 March 1994 Rev 8 to SO23-V-3.5, Inservice Testing of Valves Program ML20203E3641993-06-0707 June 1993 Rev 0 to S013-V-8.16, RCS Inconel Nozzle Insp ML20090M2441992-02-28028 February 1992 Rev 25 to Odcm ML20091K4041991-12-23023 December 1991 Temporary Change Notice 7-16 for Rev 7 to S023-V-3.5, Inservice Testing of Valves Program ML20079K2241991-08-31031 August 1991 Offsite Dose Calculation Manual for Nuclear Generation Site,Units 2 & 3,Rev 24 ML20082Q2041991-06-27027 June 1991 Surveillance Rept SOS-108-91, Licensed Operator Requalification Program ML20084T8671991-02-28028 February 1991 Rev 23 to ODCM for San Onofre Units 2 & 3 ML20058Q3801990-08-0202 August 1990 Rev 22 to ODCM ML20247C8801989-07-0101 July 1989 Proposed Rev 21 to Odcm ML20151A3881988-06-30030 June 1988 Temporary Change Notice 3-1 to Rev 3 to Procedure SO123-VI-1.0.1, Documents - Temporary Change Notices (Tcns) - Preparation,Review,Approval,Incorporation & Distribution ML20151D4411988-06-30030 June 1988 Temporary Change Notice 11-4 to Administrative Procedure SO123-VI-1.0, Documents - Review & Approval Process for Site Orders,Procedures & Instructions ML20151A3351988-06-16016 June 1988 Temporary Change Notice 1-2 to Rev 1 to Operations Div Procedure SO123-0-14, Notification & Reporting of Significant Events ML20151A4141988-05-19019 May 1988 Temporary Change Notice 2-1 to Rev 2 to General Procedure SO123-XV-5, Nonconforming Matl,Parts or Components ML20151A2051988-05-0404 May 1988 Rev 19 to to Offsite Dose Calculation Manual ML20148Q4681988-03-31031 March 1988 Rev 2 to Guidance for Development of Simulation Facility to Meet Requirements of 10CFR55.45 ML20151A4041988-03-29029 March 1988 Temporary Change Notice 6-6 to Engineering Procedure SO123-V-4.14, Proposed Facility Change (Pfc) ML20151A4171988-02-0101 February 1988 Rev 6 to Dept QA Procedure E&C 24-10-15, Preparation,Review & Approval of Proposed Facility Changes (Pfc) & Pfc Packages (Pfcp) for San Onofre Nuclear Generating Station 1,2 & 3. Proposed Change Notices 1,2 & 3 Encl ML20151A4391988-02-0101 February 1988 Rev 0 to Dept QA Procedure E&C 24-10-19, Development, Review,Approval & Release of SCE Limited Change Packages (Lcps) San Onofre Nuclear Generating Station 1,2 & 3. Proposed Change Notice 1 Encl ML20151A4271988-02-0101 February 1988 Rev 4 to Dept QA Procedure E&C 24-10-16, Development, Review,Approval & Release of SCE Design Change Package (DCP) & Assembly W/Proposed Facility Changes (Pfc) San Onofre...1, 2 & 3. Proposed Change Notice 1 Encl ML20151A3641988-01-28028 January 1988 Rev 3 to Administrative Procedure SO123-VI-1.0.1, Documents - Temporary Change Notices (Tcns) Preparation, Review,Approval,Incorporation & Distribution 1999-08-31
[Table view] |
Text
f REFilthCt: 50125.yg.1.0.1 739, p T["P O AAy twAngg gg7g g 4
- i,FW GN USE GNtV:y4 ISSUANCE cArJ.un 3 o a grCNNO. s nctt ust rCN CA*Ctts cN:
l Copy forwarded to the Nuclear Safety Group. PERFCR)*t0 ST:
1 CAft:
E TECHNICAL $PECIFICATION Y!OLATION IF NOT COMPLETED WITHIN 14 CAYS site occument No. 50123- V I- 1. 0 nevis fon no. _ fpfh sinott ust rCN rc$ s0 x
$fte Cocument Tftle Documents - Review and Approval Process for Site Orders, Fo~ceduTes dHb 5fibLIULlhUi65 PRIPAAED SY;
- 1. I Fa l e n n o PAA: M447 CAGANZAT:CN: M&AS/SPG GrIginator
- 2. cart /rtMr carstmarto: 10 a.m. 6/28/88
- 3. If reovfred, TCN Ceviation Accroval: APPt0VED 8f: n /A CFDM (or designee) signature / Af of telecon print name ana so state se ter rime 4 Cheet approprfate box: l~1 Cattre Document Attached 1 Affected Page(s) Attached Superseded / Incorporated ENis): JOne (Mot applicante
%o. (if none, so state) for SINGtt (St TC%s)
- 5. This change cannot waf t until the next revisfon of tee Site Document and is reovfred:
A. To implement facility design change (PFC, NCR, TFM, etc.) RECEIVED CDM racint, design ch.n e fdentffier InotCate PFC, NCA, IFM etc.
/
Identifier JUN 301983 rolementation of the feetuty desi res NO (If(e.g.,
No, CAA,a TCM l the
- 8. x other NaCcannot be approved Cernitments) untla chanfe has been specific Reason: fanlpmont mp otter.fned.acility design change has bee Approval Waiver List nf M0 Prncedure Review /
(T1Af' Change, Chapter IC) w se reverse side, ir required
- 6. Is the document being TCN'd QA Affecting? YE$ 1 NO (If Yts, complete the bones below.) (!f NO, see
(This is indfcated on the Table of Contents page of the Tf te Do~cusent. If not indicated, treat as QA Affecting.)
l A. Uces this enange ef fect F5AA or Tech. Spec. ccsueltments?
) 8. YE5 h0 X l Does this change affect the nonradfological environment of any offsite area previously uUTsTurbed I during site preparation and plant construction? l l C. Is the intent of the original document altered?
YES No x i
- 0. YE5 NO y l M
l Is the document to be changed an Emergency Operating Instruction? YE5 NO x i 1 E. Oces this change pose an unreviewed safety cuestfon per 10 CFR 50.59, f.e., does it f acrease the Q l pectabflf ty of occurrence or the conseq i so-00 i
1 accidenti or reduce the rech. spee. r,uences of an accfdent; create the possibilityvcs in of saretyr (IF THE AA5Wtt To A, 8, C, D sr E IS YES, A TCX !$ NOT AUTHORIZID.)
of a differentNO x I i
i CDin !
I (D O
- 1. The entire document was revfewed in conjunctfon with this TCM and found to be acceptable as written. This constitutes O' g' 23 "O an annual /bf ennf al review disposition of APPtCYED REVicWED AMO AcceptableSY: As Written.[
n/ stead (50)a .Y!.I.0.21.
"O OQ CFut or Cesignee Cate M 8. $!GNATVRES RCQUrttO:
INITI AL APPRgvAL OT l REVI O AA PROYED 87:" (AT ttA$f CNC (1) $40 ON THE UNIT A/FECitD) I l
- 1) .
Plant Management Stary. Unf t i L 6/ /2/P/ffPete /I6ma 71me'
- 2) , L b2. PAP / ** 5~
l Flant Management staff . Units A J / Gate 'r fall l I Could this TCM affect or dees it represent a epg ge to a plant Could thfs TCM affect or does it egresent a change to ;
opera a in progress? YES"* NO IIM . plae m. . - c m,,ett? E5'" %N I l
l 3)
>xg . Vnit iL Q
(e-23-oo I43Pi Uete ilme
- 4) JM
>Av . Units tai
'4 O ((M /N l sete Ilsej I
tr Fl%AL UPe0 m i g
foriunt Functionai g f&
sion sanager g
cate -
Quality Assurance . Units i. 4 ana i d W gate i
'If a document is hot CA AffeCttng, C0tain initial approval from the Cognflant Supervisor (s) on the affected Unit (s1 (signs Plant Managemeat $taff If ne(s)) and final approval from tne CFCM prior to submittal to CCM. No other sigaatures are reovfred.
"If CA Affecting, approval small be by oet meaeer of the Plant Management Staf' anowledgeable in the areas affected, and one $20 ticensed on the unit or unf ts affected. (For TCN G yroval, neveers of tne Plant Management $taff are def f aed as the supervisor in Charge of the Plfft, of as designated in writieg by the CFDM, eterCf sing responsibility in the specif fC area and 99f t(s) addressed bs sha Change.)
'"If VQ the Saf f t Superintendent small provide the recutred SR0 approval.
PF(123) 110, atY. 1 02137 0067P
r s NUCLEAR GENERATION SITE UNITS 1, 2 AND 3 ADMINISTRATIVE PROCEDURE S0123-VI-1.0 REVISION 11 PAGE 8 0F 41 TCN ll-f ,,
scN 6.0 PROCEDURE (Continued) 6.3.2.11.1 If documents under the responsibility of other disciplines are potentially affected, prepare Forms CC(123) 183 and CC(123) 184 in accordance with Reference 2.2.5 for each of the other affected disciplines.
NOTE: Based on the interdisciplinary review selection provided by the Cognizant Supervisor, the SPG writer shall prepare Forms CC(123) 183 and CC(123) 184 (in accordance with Reference 2.2.5) for those Project and C/S-C documents which require Site approval .(See step 6.3.5.5.)
.11 If designated to do so by supervision, determine the need for an independent environmental evaluation.
.12 Ascertain the previous approval authorities by reviewing the PF(123) 109(s) from the previous revision (s), if applicable, which may be obtained directly from CDM or through the assigned SPG writer.
.12.1 Changes to documents, i.e., revisions, shall be reviewed and approved by the same organizations that performed the original review and approval unless Site management designates and approves other responsible organization (s) on the PF(123) 109.
.12.2 Include, as a minimum, an individual / group other than the individual / group which prepared the procedure, but who may be from the same organization as the individual / group which prepared the procedure.
(Technical Specification 6.5.2.1)
NOTE: Documents that are current 1v designated as Not QA Program Affecting, or if identified as not requiring QA/QC review / approval on the QA0 Procedure Review / Approval Waiver List, do not require QA/QC review. See Attachment 2, Keypoint 13A.
.13 Prepare a PF(123) 109 for the review ready draft.
.14 Indicate subject document's current "QA PROGRAM AFFECTING" status.
.15 Prepare a PF(123) 109 for any document (s) to be published or cancelled concurrently, including previous approval authorities.
e NUCLEAR GENERATION SITE UNITS l', 2 AND 3 ADMINISTRATIVE PROCEDURE S0123-VI-1.0 REVISION,/1 PAGE 10 0F 41 TCN Il-T 3A 6.0 PROCEDURE (Continued) 6.3.3.4.3 Manager, Nuclear Engineering and Safety, review of Emergency Operating Instructions (E0Is) and Abnormal Operating Instructions (A0Is) and other documents, if-deemed appropriate by the Cognizant Supervisor.
.4.4 Manager, Nuclear Engineering and Safety, review of significant procedure / instruction changes which would benefit from review in the special area of expertise assigned to Nuclear Engineering, e.g., Nuclear Analysis, design criteria and certain industry research and development programs.
.4.5 Supervisor of Environmental Services review of significant procedure / instruction changes which could significantly alter the impact of the Site on the environment.
NOTE: Quality Assurance review / approval is mandai.ory for QA Program Affecting documents unless indicated as not requiring QA/QC review / approval on the QA0 Procedure Review / Approval Waiver List.
.4.6 Ensure, as a minimum, an individual / group other than the individual / group which prepared the procedure, but who may be from the same organization as the individual / group which prepared the procedure.
(Technical Specification 6.5.2.1)
.4.7 Superintendent of the affected unit (s) review of all Project documents (with the exception of Project AP and Retrofit WP documents).
.4.8 SCE Project Engineering review of all Project documents (if required by Project APs).
.4.9 Nuclear Engineering Representative review of all Project Unit 2/3 documents (if required by Project APs).
.4.10 SCE Station Engineering TWG designee review of all Project Technical documents under the jurisdiction of the Manager, Technical.
.5 Provide proposed "QA PROGRAM AFFECTING" determination of subject draft's contents (see Definitions, Attachment 1).
.6 Indicate whether QA final approval is required.
.7 Determine need for training by the Nuclear Training Division and enter appropriate training contact.
i NUCLEAR GENERATION SITE ADMINISTRATIVE PROCEDURE S0123-VI-1.0
, Ut,ilTS 1, 2 AND 3 REVISION 11 PAGE 32 0F 41 ATTACyEf)T2 TCN 41"r g 4c d ROUTING AND DOCUMENT CONTROL PF(123) 109 (Continued)
Kevooints: (Continued)
- 7. Provide answer. If yes, enter P&ID number (s).
- 8. Provide answer, sign, and date. If answer is N/A, then N/A may be entered on the signature line.
- 9. Provide the disposition of each outstanding TCN recorded by CDM or check N/A as appropriate.
- 10. Check Yes or No. If Yes, provide that design change's type / category and identifying number.
- 11. Provide dhposition of Site Controlled Forms.
- 12. Based upon review of subject draft's effect upon other responsible disciplines, or possible adverse environmental impact, check and/or write in appropriate reviewers.
Consider previous review and approval authorities from prior routing documents.
13A. If the document is currently designated as Not QA Program Affecting, or is identified as not requiring QA/QC review / approval on the QA0 Procedure Review / Approval Waiver List, it does aqt require QA/QC review / approval. For current Not QA Program Affecting documents, or documents identified as not requiring M QA/QC review / approval on the QA0 Procedure Review / Approval Waiver List, put a line through the QA/QC block, and state "Not Required" and indicate "NQA" or "Waiver List."
Coonizant Superviso" Review Author entries.
- 15. Determine whether formal training is required on the subject document's contents. Provide the discipline training contact for coordination of formal training, if applicable.
- 16. Check "QA Program Affecting" determination.
Proposed Not QA Program Affecting determinations must be approved by QA and reflected in Keypoint 17. Enter N/A in Keypoint 17 for all other determinations.
ATTACHMENT 2 PAGE 7 0F 9
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