ML20151A414

Temporary Change Notice 2-1 to Rev 2 to General Procedure SO123-XV-5, Nonconforming Matl,Parts or Components

ML20151A414
Person / Time
Site:	San Onofre
Issue date:	05/19/1988
From:	SOUTHERN CALIFORNIA EDISON CO.
To:
Shared Package
ML20151A165	List: ML20151A162 ML20151A335 ML20151A360 ML20151A364 ML20151A388 ML20151A390 ML20151A404 ML20151A414 ML20151A417 ML20151A427 ML20151A436 ML20151A439 ML20151A651 ML20151A661 ML20151D441 ML20151D513
References
SO123-XV-5, NUDOCS 8807190364
Download: ML20151A414 (40)

Text

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e NUCLEAR GENERATION SITE UNITS 1, 2 AND 3 GENERAL PROCEDURE S0123-XV-5 REVISION 2 PAGE 1 0F 39 COMPLETE REVISION EFFECTIVE DATE 3.R.3T NY o2 '/

NONCONFORMING MATERIAL. PARTS OR COMPONENTS TABLE OF CONTENTS SECTION Pg1 1.0 OBJECTIVE 2

2.0 REFERENCES

2 3.0 PREREQUISITE 3

4.0 PRECAUTION (S) 3 5.0 CHECKLIST (S) 3 6.0 PROCEDURE 3

E.1 Administration 3 6.2 Identification, Documentatio.n, and Validation of Nonconformances 4 6.3 Reportability Requirements 6 6.4 Operability Assessment and Status 7 6.5 Restraint to Mode Entry 9 6.6 Segregation of Nonconforming Items 10 6.7 Disposition of NCRs/ Engineering Review Process 12 6.8 Apparent Cause and Corrective Action to Prevent Recurrence 17 6.9 Tracking of Open NCRs 17 6.10 Closing NCRs and Returning Equipment / Systems to an Operable Condition 19 6.11 Root Cause Evaluations

• 20 6.12 Root Cause Only NCRs (R-NCRs) 20 7.0 RECORDS 22 ATTACHMENTS 1 Conditions Required to be Document 2d on an NCR 23 2 Items to be Considered in the Disposition Process 26 3 Disposition Classifications 28 4

NCR Form EG(123) 10 30 5

NCR Form EG(123) 10 Breakdown 31 6

Instructions for Completion of NCR Form EG(123) 10 32 7

NCR Form EG(123) 10A 35 8

NCR Form EG(123) 10A Breakdown 36 9 NCR Approval Authorization List 37 10 Safety Evaluation 11 38 Conditional Release Form 39 3164f-2.cin QA PROGRAM AFFECTING 8807190364 090715 DR ADOCK 050  %

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NUCLEAR GENERATION SITE

. UNITS 1, 2 AND 3 GENERAL PROCEDURE S0123-XV-5  !

REVISION 2 PAGE 2 0F 39 i 76/; -/

l NONCONFORMING MATERIAL PARTS OR COMPONENTS 1.0 OBJECUyl 1.1 To define responsibilities and provide a uniform method for the control and use of nonconforming material, parts or components for those structures, systems and components listed as follows:

1.1.1 Safety related (SR) or fire protection for Unit 1.

1.1.2 Quality Class I or II or fire protection for safety related areas for Units 2 and 3.

1.1.3 ASME Section III and XI activities for Units 1, 2 and 3.

1.1.4 Those items found in Chapter 8 of the Topical Quality Assurance Manual (TQAM) for Units 1, 2, 3.

2.0 REFERENCES

2.1 NRC Commitments .

2.1.1 Unit 1, 2, and 3 Technical Specifications 2.1.2 10CFR20.403, 21, 50.36, 50.49, 50.54, 50.59, 50.72-73 2.1.3 ANSI N18.7 2.1.4 10CFR50 Appendix 8 Criterion XV "Nonconforming Materials, Parts, or Components" 2.1.5 TQAM, Chapter 40,: Nonconformances 2.2 Site Order 2.2.1 S0123-RP-1, Reliability Engineering Program 2.3 Procedures 2.3.1 S0123-I-1.7, Maintenance Order Preparation, Use and Scheduling i

2.3.2 S0123-I-1.35, Plant Component / Spares Rebuild Process 2.3.3 50123-V-4.5, Human Performance Evaluation System 2.3.4 $0123-V-4.14, Proposed Facility Changes (PFCs) 2.3.5 S0123-XV-5.10, Temporary Facility Modification 2.3.6 50123-XV-3.2, Immediate Notification to NRC i

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.O NUCLEAR GENERATION SITE UNITS 1, 2 AND 3 GENERAL PROCEDURE 50123 XV-5 REVISION 2 PAGE 3 0F 39

2.0 REFERENCES

(Continued)

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2.4 Ooeratino Instruction 2.4.1 S0123 0 14, Notification and Reporting of Significant Events 2.5 at!utr 2.5.1 ASME Code, Section !!! and XI 2.5.2 Guidelines for Root Cause Evaluations dated 3/4/88.

1.0 PRERE0VISITE 3.1 Prior to use of a user-controlled copy of this Site document, it is the user's responsibility to verify that the revision and any TCNs are current by utilizing one of the following methods:

3.1.1 Check it against a controlled copy and any TCNs; 3.1.2 Access an SCE Oocument Configuration System (SOCS);

3.1.3 Contact COM by telephone or through counter inquiry; 3.1.4 Obtain a user-controlled copy of the Site document from COM; 3.1.5 Reference a current (within one week) Destination Configuration Control Log and associated daily update.

4.0 PRECAUTIONfS) 4.1 None

• 5.0 CHECKLIST (S) 5.1 None 6.0 PROCEDURE

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6.1 Administration 6.1.1 The Manager, Technical (or designee) is responsible for the Station NCR Program administration. The Shift Tecnnical Advisor (STA) and the NCR Administrator (NCRA) are among the designees available for NCR processing.

l 6.1.2 The Manager, Material Support (or designee) has been.

delegated the responsibility for the Warehouse NCR (W NCR) program administration.

' NUCLEAR GENERATION SITE UNITS 1, 2 AND 3 GENERAL PROCEDURE S0123 XV-5 REVISION 2 PAGE 4 0F 39 6.0 PROCEDURE (Continued) 7Ms1 6.1.3 NCRs generated for non-conforming conditions are processed in accordance with steps 6.2 through 6.11. NCRs generated solely for the purpose of tracking of root cause evaluations are processed in accordance with step 6.12.

6.2 Identification. Documentation and Validat12n.,_of n NonconformILqgi 6.2.1 Identification and Documentation of a Nonconforming '

Condition

.1 A nonconforming material, part or component is defined by

. ANSI N18.7 (ANSI N45.2.10) as an item having a deficiency in characteristic, documentation or procedure which renders the cuality of an item unacceotable or indeterminate.

Control or installation,of a nonconformance is to orevent inadvertent use in general, a Nonconformance Report (NCR) is required for deviations in characteristic, material, process, component or procedure for those items listed in section 1.1, and as specified in design disclosure documents such a.s drawings, analyses or procurement documents. Refe'r to Attachment I for greater specificity of nonconforming conditions. i l

NOTE: Detailed descriptions of the perceived nonconforming condition and appropriate i

references (P&lDs, piping isometrics, schematic

! diagrams, elementary drawings, etc..) are I essential to complete NCR evaluation and processing.

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.2 Any individual may identify a perceived nonconforming condition. Station Technical (STEC) is responsible to evaluate the reporte* ondition and take appropriate action.

t .3 Nonconforming conditions shall be documented by use of the NCR form (Attachment 4).

.4 Identification of a nonconforming condition shall be considered complete when Blocks 2 through 15 of the NCR form are completed and received by STEC for validation.

All available pertinent information shall be provided by the individual initiating the NCR.

.5 The Material Support Stal'f (MSS) or Receiving Quality Control (RQC) shall identify and validate potential procurement nonconformances that are not to be imediately released for use in the plant using W NCRs.

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NUCLsAR GENED8 TION SITE UNITS 1, 2 AND 3 GENERAL ?ROCE00RE S0123-XV-5 REVISION 2 PAGE 5 0F 39 l 1

6.0 PROCEDURE :(Continued) 7EM a -/ '

J 6.2.2 Validation and Notif'ication NOTE: Validation of an NCR should normally occur within l 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. However, based upon the complexity of '

the issue and other activities underway, this may not always be possible. Therefore, the originator should notify supervision if he feels i

a significant safety hazard exists. Supervision is responsible for advising STEC of the potential significance of the nonconformance.

.1 Station Technical (STEC) is responsible for the validation of the deficiency (Block 16), i.e., confirming the existence of tha nonconformance, and that adequate information is contained in Blocks 2 through 15. The NCRA shall assign a number, distribute the NCR and maintain logs for issued NCRs.

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ForFireProtectionrelatednonconformances,theNCRAshall contact the Emergency Services Officer (ES0) to ensure early identification of compensatory measures.

.3 For nonconformances related to security, the NCRA shall contact the Security Shift Commander (SSC).

.4 Equipment Control (or if Equipment Control is not available, the Shift Superintendent) shall be notified of the nonconformance by the NCRA. This should be dona. in a timely manner and should incide the Operability.

Reportability and Mode Restraint.

.5 Material Support shall validate the deficiencies of W NCRs, assign a number, distribute the NCR, and maintain logs for issued W NCRS.

• NUCLEAR GENERATION SITE UNITS 1, 2 AND 3 GENERAL PROCEDURE S0123-XV 5 REVISION 2 PAGE 6 0F 39 6.0 12GCEDURE (Continued)- #l

/CAcA -l 6.2.3 Revisions / Changes on the NCR Form

.1 Minor or editorial changes'to Block 14 shall be permitted without NCP. revision, provided the intent of the nonconformance is not altered and the disposition has not been approved. The chances shall be performed by the NCR initiator (or his/her :9perd sor), or a person authorized to validate the NCR. The changes shall be recorded in 5 black pen and ink, dated, and initialed. The NCRA shall c e

redistribute the NCR.

.2 Changes to Block 21 require an NCR revision if the disposition is approved in block 22A.

.3 Revisions to NCRs must be processed through the documentation and validation steps as the original was processed. Superseded or revised NCRs shall have a note of cross reference such that an individual can obtain the active or most recent revision.

.4 The invalidation of an NCR must be concurred with by the NCR originator (or his supervisor) and QA. If the NCR has been dispositioned, the invalidation will also require the approval of those individuals approving the p'esent disposition (step 6.7.3.4).

6.3 Reoortability Raouirements 6.3.1 Reportability Assessment

.1 Concurrent with validation of the NCR, STEC (or designee) shall determine' reportability per References 2.3.6 and 2.4.1. If there is a question concerning the reportability of a deficiency, it shall be considered reportable.

.2 Imediate reportability shell be determined, and any subsequent reports shall be made and documented in accordancs with the instructions of References 2.3.6 and 2.4.1.

, .3 Reportability status shall be documented on the original NCR (Block 17).

.4 Should an item be determined to be reportable, the NCRA shall notify the Compliance Section in accordance with i

Reference 2.3.6.

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c NUCLEAR GENERATION SITE UNITS 1, 2 AND 3 GENERAL PROCEDURE S0lz3 XV 5 REVISION 2 PAGE 7 0F 39 6.0 PROCEDURE (Continued) 6.3.5 It is the responsibility of Compliance to prepare and submit the required reports (with the exception of certain prompt telephone notifications), and to either revise the NCR or issue a Reportability Disposition Sheet (ROS) if the reportability assestment is to be changed.

6.4 Ooer:bility Assessment and Status 6.4.1 Operability Assessment NOTE: Operability Assessment is not required for W NCRs,

.1 Concurrent with validation, STEC is responsible for determining equipment operability, further actions to be taken to ensure Plant safety, and for documenting these '

conditions on the NCR.

.2 The applicable llnit's Technical Specification "definition for OPERABILITY" shall be used in operability assessments.

.3 The operability assessment shall be precise and shall clearly state what is inoperable (i.e., the component, equipment or system). For example, the failure to open of the discharge valve of a charging pump would make that valve and charging pump inoperable unless it had another discharge valve in parallel. Failure of the valve would not make both trains of the charging pump system inoperable beca c e of the redundancy / separation in charging pumps.

.4 Wre further information is necessary for an operability sssefsment, the determination shall be made upon receipt of l suf;'cient information for the determination.

.5 Occasionally, an NCR may be issued on a component which is already inoperable for other reasons. In these cases, the l

NCR shall provide the routine operability assessment; however, the NCR shall establish whether the NCR condition, by itself, constitutes inoperability. Appropriate EOMRs or LC0ARs shall be established, regardless of whether the equipment is inoperable for other reasons.

.6 An operability assessment may be changed following disposition of the NCR. In these cases, Block 17 should be changed and the NCRS computer system updated.

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NUCLEAR GENERATION SITE UNITS 1, 2 AND 3 GENERAL PROCE0VRE S0123-XV 5 REVISION 2 PAGE 8 0F 39

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6.0 PROCEDURI (Continued) 6.4.2 Items That Do Not Compromise Operability NOTE:

The following conditior s, though nc,t a compromise to operability, may be recortable.

.1 Documenter 4 deficiencies which are noted during receipt inspectio), unless the equipment is already installed.

.2 Deficienc ies which occur and are discovered when the system (or a poition of the system containing the component) has been properly removed from service, unless the NCR is not closed prior to returning the system to service.

.3 Deficiencies which occur and are discovered when the system is not required to be operable for the Mode (s) in question, and for which a Mode change is not forecast prior to returning the equipment to an operable status.

6.4.3 Inoperable Equipment

.1 If equipment which is subject to a Technical Specification Limiting Condition for Operation (LCO) is determined to be inoperable as a result of the NCR, the action statement associated with the appropriate LC0 must be initiated and satisfactorily completed within the time constraints

pecified therein.

.2 NCRA shall immed.iately notify Equipment Control or the Shift Superintendent when a component is determined inoperable, i

.3 Equipment Control shall, in turn, immediately notify the Shift Superintendent.

.4 Notification of the Shift Suparintendent constitutes initiation of the action statement clock, l

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• NUCLEAR GENERATION SITE UNITS 1, 2 ANO 3 GENERAL PROCEDURE 50123-XV-5 REVIS10N 2 PAGE 9 0F 39 6.0 PROCEDURE (Continued) 6.4.4 Use of R n-Conforming Equipment

.1 As a result of a deficiency reported on an NCR, a component normally has its use restricted to prevent further degradation of the component, its system, or interfacing systems, or to preserve possible future analysis-

"evidence".

The "Restricted Use" block is checked "Yes" under these circumstances, and necessary restrictions on operational use of the component are prescribed on the NCR form. Examples of restrictions that may be specified are "isolate electrically", "pump is functional r automatic service, reserve for emergency use;",emove "fluid fiw system isolation", and "do not operate until repairea'.

.2 Any required restrictions shall be provided at the time of NCR validation, and shall be imediately communicated to the SRO Operations Supervisor on shift (i.e., normal notification to Equipment Control is not adequate).

.3 Restriction (s) s.hould be reviewed for revision as part of preparing the NCR disposition. As in the case of NCR validation, any changes shall be immediately communicated to the SRO Operations Supervisor.

6.5 Restraint to Mode Entry NOTE: Restraint to mode determination is not required for W NCRs.

6.5.1 In Block 17 of the NCR form, the Manager, Operations or Manager, Technical (or their designee (s)) should indicate their assessment of the Restraint to Mode associated with the nonconformance.

.1 Designee (s) shall be designated in writing per step 6.7.3.

6.5.2 Restraint to Mode

.1 Restraint to Mode is that Plant configuration (Modes 1-6), as defined in the Technical Specifications, that the Plant cannot enter due to the impact of the nonconformance on Technical Specifications and/or Licensing Commitments. If there is no Plant configuration limitation, then zero (0), eight (8) or nine (9) shall be assigned.

.l.1 Zero (0) denotes that the scope of the work required to correct it can bethe nonconformance done at anytime. is of such limited extent that

• NUCLEAR GENERATION SITE UNITS 1, 2 AND 3 GENERAL PROCEDURE S0123-XV 5 REVISION 2 PAGE 10 0F 39 6.0 PROCEDURE (Continued) 6.5.2.1.2 Eight (8) denotes that a short duration outage (e.g.,

typically a Mode 5 outage).

.1.3 A nine (9) denotes that a long duration outage (i.e., a refueling outage) is requ' red to complete the work.

.2 The mode restraint may be changed by an authorized person if a reevaluation action of the nonconformance indicates that such is appropriate.

by an authorized person ifMode restraint may alto be changed in his opinion, the disposition of the nonconformance requ,resi or allows a Mode change, or if specific actions in the disposition require or permit a change (e.g., to reach a Mode where plant conditions are needed to perform inservice leak tests).

.3 If a Mode change is required to satisfy the disposition, that part of the disposition requiring a different Mode shall be indicated on the NCR; for example, to accomplish inservice leak test. In this case, a second separate verification shall occur in Block 24 for the subsequent disposition activity.

.4 The effect of a change in Mode while the Plant is operating (i.e., not in Mode 1 or 2) shall be considered when assessing the restraint to mode. A notation such as the following should be provided under the above circumstances:

"No Mode Restraint in Mode 1 provided actions specified in Technical Specifications are completed. However, should the Unit return to Mode 5, this becomes a Mode 4 restraint " The Non Conformance Reporting System (NCRS) will show the most restrictive Mode restraints (i.e.,

highest Mode number). In this example, it would be 4.

i NOTE:

l This is not intended to cover normal Technical Specification 3.0.4 requirements.

6.6 Secrecation of Nonconformino items 6.6.1 Exceptions

.1 Nonconforming items shall not be used or operated (except as permitted by the NCR disposition or defined in step 6.4.1 or 6.4.4) as follows:

.l.1 Until th> NCR has been dispositioned as "Accept As Is" and disposi. ion approval attained; l

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• NUCLEAR GENERATION SITE UNITS 1, 2 AND 3 GENERAL PROCEDURE S0123-XV.5 REVISION 2 PAGE 11 0F 39 6.0 PROCEDURE (Continued) 6.6.1.1.2 The disposition activity is complete and verified complete by Quality Control (QC);

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.l.3 A Conditional Release is made per step 6.7.4; E

.l.4 The item is determined operable in Block 17.

6.6.2 Tagging and Segregation

.1 To prevent the use or operation of nonconforming item (s),

the item (s) shall be stored in a designated "hold" area (when practical), and/or tagged by Quality Control with an appropriate "Hold for QA Release" tag.

.2 The person validating the NCR shall determine if the nonconforming itsm(s) require quarantine, and shall con.plete Block 18.

.3 Hold tags are to be applied and removed by QC.

.4 Segregation of nonconforming items installed in the Plant is not required, provided at least one of the following applies:

.4.1 Block 18 states that the equipment is operable in the Mode the Plant is in, and:

.4.1.1 The approved disposition (if there is one) or the Restraint to Mode does not conflict.

.4.1.2 The component is in a high radiation or inaccessible area.

.4.2 The nonconformance no longer exists as signified by one or more of the following:

.4.2.1 The NCR is closed and a copy has been received by Equipment Control, or the NCR is closed and the NCRA verbally advises Equipment Control or the Shift Superintendent that it has been closed.

4.2.2 The NCR is not closed but disposition activity has been verified as complete by QC (Block 24 signed), and this informatio.1 is transmitted, either verbally or in writing, to Equipment Control or the Shift Superintendent.

NUCLEAR GENERATION SITE UNITS 1, 2 AND 3 GENERAL PROCEDURE S0123 XV-5 REVISION 2 PAGE 12 0F 39 6.0 PROCEDURE (Continued) 6.6.4.2.3 The NCR is not closed, but an Accept As-Is has received the required disposition approval signatures and this information is transmitted (verbally or in writing) by the NCRA to Equipment Control or the Shift Superintendent.

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.4.3 As permitted by step 6.10.4, when the disposition on the NCR requires that a system be placed in service prior to completion of the disposition.

.4 A Conditional Release on the nonconforming material as described in step 6.7.4 is permitted and the conditions of the Conditional Release are satisfied.

6.7 Discosition of NCRs/Encineerino Review Process (ER?)  !

6.7.1 Assignment of Disposition Determinations

.1 The NCRA shall assign the NCR disposition determination for an NCR to the Cognizant Engineering Supervisor (CES) for the system recorded in Block 12. The CES may reassign the disposition determination to other site divisions through the NCRA. For W NCRs, the NCRA will assign disposition determination to the responsible division supervisor.

.2 The CES (or responsible division shall provide the disposition in a timely manner, c)onsistent with the work load / priorities and the impact of the NCR on public safety and operation of the affected Unit (s).

.3 The NCRA or designee will provide a monthly listing of NCRs requiring disposition. The Manager, Material Support (or designee) shall provide a monthly listing of W NCRs requiring disposition. A due date of 14 days beyond the initiation date shall be assigned as a target for disposition of the NCR, unless another date is established based upon special circumstances. Organizations failing to provide timely dispositions may be subject to warning letters by the Assistant Technical Manager, or as necessary, a PRR or CAR by QA.

.4 The NCRA (or designee) shall assign the approved disposition to the work group in Block 21A. The work group shall implement the disposition of the NCR and be responsible for its closure. If appropriate, the work group shall immediately initiate a MO to expedite completion of the NCR disposition.

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NUCLEAR GENERATION S!TE UNITS 1, 2 AND 3 GENERAL PROCEDURE S0123-XV 5 REVISION 2 PAGE 13 0F 39 6.0 EEQCEDURE (Continued) 6.7.2 Preparation of Dispositions CAUTION In dispositioning items under "Accept As Is"

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or Repair, the NCR process is not to be used to circumvent the Proposed facility Change (PFC) or Field Change Notice permitted by Referenc(e 2.3.4).FCN)

Any areasprocesses of (excep uncertainty shall be discussed with the Supervising Engineer (or his designee) for PFCs and FCNs.

.1 Prior to issuance of the disposition, troubleshooting to determine the cause or extent of the nonconformance may proceed as directed by an approved Investigative Maintenance Order / Work Order. However, corrective action shall not be per. formed until the NCR has been dispositioned.

.2 A reassessment of equipment operability shall be performed.

Changes to the operability assessment shall be recorded in Block 17. This may be performed after an interim disposition activity is completed.

.3 If the disposition is Accept As-Is or Repair, the person providing the disposition shall complete a 10CFR50.59 evaluation and attach it to the NCR (Attachment 5).

.4 W-NCRs shall be'dispositioned within the requirements of the purchase order and supporting documents only (i.e., is not a deviation from the design or code requirements). Any nonconformance which might have an effect upon design, function, or ASME code requirements shall be referred to Station Technical for dispositioning.

.4.1 W NCRs with "Repair or "Accept As Is" dispositions require Station Technical approval.

6.7.3 Authorizations

.1 Individuals designated to approve NCRs shall be indicated in writing on an Authorized NCR Signature List (Attachment 9 or its equivalent), signed by the Cognizant Functional Division Manager and sent to the NCRA.

.2 The NCRA shall retain a copy of the Authorized NCR Signature List from each Functional Division Manager.

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NUCLEAR GENERATION SITE UNITS 1, 2 AND 3 GENERAL PROCEDURE S0123 XV 5 REVISION 2 PAGE 14 0F 39 6.0 PROCEDURE (Continued) 6.7.3.3 Authorization by phone may be given for an individual to sign for an authorized person.

NOTE: The use of telephone authorization is not encouraged. Whenever possible, the individual should review the NCR in person.

.4 Reouired Disoosition Acoroval Stonatures NOTE: Personnel signing Block 22A (Disposition Approvals for Disposition /Connents in Block 21) shall determine if, in his professional judgement, the NCR should be forwarded to the Manager, Technical for information and possible OSRC Review. OSRC approval of an NCR is agl required.

Procurement QA shall be the QA approval authority for W NCRs.

AN!! ahproval is fiQI required for W NCRs.

.4.1 When the disposition is Accept As-Is or Repair:

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.4.1.1 Block 22A will be signed by the Manager, Technical or designee, AliQ

.4.1.2 The Cognizant Functional Division Manager (the ManLger responsible for conducting all or a major portion of the work, or the Manager most impacted by the work) or his designee; &llD the QA Supervisor, or his designee.

NOTE:

Two members from the Technical Division who are authorized to approve dispositions and one from QA can meet this requirement.

.4.2 When the disposition is Reject or Rework:

.4.2.1 Block 22A shall be signed by the Cognizant Functional Division Hanager or Manager, Technical At!Q the QA Supervisor or their designee (s).

.4.3 When Block 13 is checked Yes, the AN!! shall sign Block 23 to indicate concurrence.

.4.4 When the disposition is Preliminary Root Cause, a preliminary root cause evaluation shall be completed and signed by a member of an organization authorized to approve dispositions before the equipment can be returned to service.

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NUCLEAR GENERATION SITE  !

UNITS 1, 2 AND 3 GENERAL PROCEDURE S0123-XV 5  !

REVISION 2 PAGE 15 0F 39 6.0 PROCEDURE (Continued) 6.7.4 Conditional Release of Nonconforming Material NOTE: W NCRs shall not be utilized for conditional '

release of material.

CAUTION Conditionally released items shall not be relied

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upon to perform a safety-related function.

.1 Nonconforming items may be conditionally released for installation and/or use in a system prior to approval of a final NCR disposition by completing the NCR through Block 18, and by completing a "Conditional Release of the Nonconforming Material" form (see Attachment 11).

Conditionally released items shall not be relied upon to perform a safety-related function (i.e., systems containing these conditionally released items shall not be declared OPERABLE in accordance with reference 2.1.1) until Block 24 is completed.

.l.1 Blocks 8 and 12 of the NCR shall specifically identify the actual location and system in which the nonconforming item is to be installed (i.e., a thorough description of the physical location by building level, room number or the closest piece of major equipment).

.2 The purpose of the Conditional Release of Nonconforming Material is to document the physical and/or administrative restraints placed on the affected Plant equipment and/or systems due to the installation of a nonconforming item.

.3 The length of time that a Conditional Release stays active should be relatively short, since this places an additional restraint on the operation of the Plant. Additional restraints increase the probability that a noncompliance could occur.

.4 Attachment 11 is processed as follows:

.4.1 Section I of the Conditional Release shall be completed by the Cognizant Functional Manager (or his designee). This section identifies the material to be conditionally released and the Plant equipment / system affected by its use. Detail provided must be sufficient for the Technical Division to perform the technical evaluation required in Section !!.

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NUCLEAR GENERATION $1TE I UNITS 1, 2 AND 3 GENERAL PROCEDURE S0123 XV 5 '

REVISION 2 PAGE 16 0F 39 6.0 PROCEDURE (Continued N2I 6.7.4.4.2 Section 11 shall be completed by the Manager, Technical (or his designee). Section !! documents the operability review, unreviewed safety question review, and the restraints placed on the equipment / system / Plant until tha nonconforming item is no longer installed in the Plant or otherwise re-evaluated (i.e., a new Conditional Release is approved).

CAUTION

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If the Conditional Release constitutes an unreviewed safety question, the Conditional Relaase shall not be approved.

.4.3 Section til shall be completed by the responsible Managers or their designees.Section III provides formal approval of the Conditional Release; thus, Blocks 21, 22 and 23 (AN!!) on the NCit need not be completed until a Conditional Release is removed.

NOTE: Personnel who are authorized to approve dispositions for the Cognizant functional Manager are also d,esignees (as discussed in this section).

6.7.4.5 Hold tags, when applicable, shall remain with the Conditional Release item until a disposition has been implemented. The hold tag shall be clearly visible and boldly marked Conditional Release. When appropriate, QC l

will remove the hold tag (see Note 6 on Attachment 5),

l 6.7.5 Recording the Disposition on the NCR Report

.1 The disposition shall be recorded in Block 21 of the NCR.

Additional sheets may be used if there is insufficient space on the NCR. The additional sheets should reference the NCR number, NCR revision number and be paginated. The additional sheets are referenced in Block 21.

l .2 If Block 13 is checked Yes, in addition to s' ,atures in Block 22A, a signature in Block 23 from the A..I is also

!, required prior to starting work.

6.8 Aeoarent Cause and Corrective Action to Prevent Recurrence 6.8.1 Apparent Cause

.1 The apparent cause of the nonconformance shall be described in Block 26 of the NCR. The apparent cause shall be the "root

• cause and not the "symptomatic" cause, l

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' NUCLEAR GENERATION SITE UNITS 1, 2 AND 3 GENERAL PROCEDURE S0123 XV S REVISION 2 PAGE 17 0F 39 6.0 PROCEDURE (Continued)

NOTE:

A "root" cause is the first element in a chain of conditions or events and is the initiatin which underlies the nonconformance (e.g.,g agentfailure of a pump may have an immediate cause of insufficient lubrication but the root cause may be a missed inspection. See Section 6.11 and Reference 2.5.2).

6.8.1.2 This information may be provided after, or concurrent with, final dispositioning of the NCR. It shall be as accurate as possible to determine effective corrective action.

6.8.2 Corrective Action

.1 Corrective action to prevent recurrence shall be described in Block 27 of the NCR. This information may be provided after, or concurrently with, final disposition of the NCR.

.l.1 Corrective action shall include measures to reduce the risk of and prevent recurrence of a reactor trip, when applicable.

.2 If the corrective action requires that a procedure be revised, the specific revisions required and the procedure (s) requiring revision shall be identified.

.3 If system changes may be required, they shall be identified or requests for studies shall be specified.

.4 If a root cause' report is required, the report shall be prepared in accordance with Section 6.11.

.5 For those items assigned to O&MS for trending, trends are establisted for those components that have an equipment / plant tag number (i.e., subcomponents or piece parts are not trendable).

6.8.3 Blocks 28 and 29 of the NCR shall be signed by a member of the organization who is authorized to approve dispositions per step 6.7.5.

6.9 Trackina of Ocen NCRs 6.9.1 The NCRA (or Manager, Material Support Ar W-NCRs) periodically issues a listing of open NC3.s indicating the action required by Site divisions to complete the NCR.

.2 The NCRA shall provide a written notification to division supervisors of actions assigned to therr in NCRs.

' NUCLEAR GENERATION SITE UNITS 1, 2 AND 3 GENERAL PROCEDURE S0123 XV 5 REVISION 2 PAGE 18 0F 39 6.0 PROCEDURE (Continued)  !

6.9.1.3 The responsible Division Supervisor shall take timely action on the NCR, consistent with the Division's work load and priorities, and plant and with the item's impact on public safety operation. Division Supervisors shall ensure that information relative to NCRs (e.g., forecast completion date, work document numbers, closure documentation, or other information requested by the NCRA) assigned to their department is regularly forwarded to the NCRA.

.4 Timely resolution of work required by NCR dispositions shall be tracked as follows:

.4.1 The Manager, Operations, shall manage NCR work that can be accomplished during non-outage periods.

.4.2 The Manager, Deputy Station, shall manage NCR work that is performed during outages or is required to be complete prior to the completion of the outage.

.5 Upon a Unit shut'down (scheduled or unscheduled), the NCRA or designee shall provide an up to date sort of open NCRs with a Restraint to Mode of 8 or 9 (see Section 6.5.2.1) to the Unit STA Supervisor or designee.

This information should be provided to Equipment Control and/or at the Post Trip Review Meeting to assess possible NCR related work impact on outage duration.

6.10 Closino NCRs and Returnino Eaui_oment/ Systems to an Ooerable Condition 6.10.1 Closing NCRs and'Oeclaring Operability e

.1 QC is responsible for verifying completion of the disposition activities and signing Block 24 of the NCR to so indicate.

NOTE: If the disposition contains activities that require separate verification, QC shall sign <

partials by stamping, initialing and dating next c to the appropriate step in the disposition or g attaching an additional page to the NCR recording the verification of each disposition activity.

.2 Operations is responsible fbr placing equipment in service and declaring operability

.3 QA is responsible for closing NCRS.

^

\

i NUCLEAR GENERATION SITE UNITS 1, 2 AND 3 GENERAL PROCE0VRE S0123 XV 5 REVISION 2 PAGE 19 0F 39 6.4 PROCEDURE (Continued) 6.10.2 Declaring a System Operable

.1 Operations shall not declare a system "0PERABLE" unless one of the following has occurred and has been transmitted (either verbally or in writing) to Equipment Control or the Shift Superintendent:

.l.1 The NCR is closed.

.l.2 NCR disposition activities required for equipment OPERABILITY have been verified as complete by Oc signature in Block 24.

.l.3 An "Accept As Is" disposition has been approved.

.l.4 The provisions of step 6.10.3 have been met.

.l.5 For an R-NCR, a preliminary root cause report has been prepared and approved by Station Technical. k

.2 Upon Block 24 ve'rification, the NCRA shall revise NCRS to reflect the return to "0PERABLE" status.

6.10.3 Return to Service Prior to NCR Disposition Closure

.1 Under certain circumstances, the disposition of an NCR requires that a system be placed in service prior to completion of the dispositions (e.g., an inservice leak test is required). To satisfy the disposition, Modes must be changed and, as a result, credit must be taken for the system's operability. Under the following conditions, Operations may declare the system operable to satisfy the requirements of the Technical Specifications:

.l.1 All required or specified Technical Specification Surveillances have been completed;

.l.2 That part of the disposition which requires a change of Mode has been explicitly identified, and the point at which the required activity is to be accomplished has been 1 defined.

.l.3

! The required disposition activities are verified complete by QC (i.e., a "partial" Block 24 signoff), and this verification has been transmitted to Equipment Control or the Shift Superintendent by the NCRA.

.2 No further operational activities are permitted past the points defined in step 6.10.3.1.2 until QC verifies the activity as successfully complete and the NCRA advises Equipment Control or the Shift Superintendent.

NUCLEAR GENERATION SITE

. UNITS 1, 2 AND 3 GENERAL PROCEDURE S0123 XV 5 REVISION 2 PAGE 20 0F 39 6.0 PROCEDURE (Continued) 6.11 Root cause Evaluations  !

6.11.1 STEC determines the need for formal root cause evaluations of nonconforming conditions and records this assessment on the NCR form.

.2 STEC performs root cause evaluations in accordance with Reference 2.5.2.

.3 If actions required by a root cause report are mode restraining or de:lare equipment operable, Block 17 of the NCR shall reflect this. T-NOTE: If Block 24 is signed, the NCR shall be revised to reflect the operability and mode restraint k, actions of the root cause reports.

.3 An NCR may be initiated to track a root cause evaluation of a condition which is not considered a nonconforming condition (see A,ttachment I for definitions). This type of NCR is defined as a "Root Cause Only NCR" (R-NCR), and is processed in accordance with step 6.12.

6.12 Root Cause Oniv NCRs (R NCRs) 6.12.1 Identification, Documentation and Validation

.1 STEC identifies the need for an R NCR.

.2 An R-NCR is documented by completing, through Block 19, the applicable portions of an R NCR form (Attachments 7 and 8).

.3 The Technical Manager, or designee, is responsible for validation of an R NCR.

6.12.2 Revisions

.1 Revision to the R NCR must be processed through the documentation and validation steps as the original revision was processed. Superseded or revised NCRs shall have a note of cross-reference such that an individual can obtain the active NCR or the most recent revision.

.2 The invalidation of an R-NCR requires the approval of the Manager, Technical (or the Assistant Technical Manager).

6.12.3 Reportability Requirements

.1 Reportability status shall be determined per References 2.3.6 and 2.4.1, and shall be documented on the R NCR.

.2 The Compliance Section will be notified of items determined to be reportable.

NUCLEAR GENERATION SITE UNITS 1, 2 AND 3 GENERAL PROCEDURE S0123-XV-5 REVISION 2 PAGE 21 0F 39 6.0 PROCEDURE (Continued) 6.12.4 Operability Assessment

.1 An assessment of equipment operability sha.ll be performed in accordance with step 6.4 and shall be documented on the R NCR form.

.2 Provisions for restoration of equipment to full operability shall be specifically identified in root cause reports.

These provisions shall provide for notification to Operations of changes in equipment operability.

6.12.5 Restraint to Mode Entry

.1 An assessment of restraints to mode entry shall be performed in accordance with Step 6.5 and shall be documented on the R-NCR form.

6.12.6 Disposition of R NCRs

.1 The disposition bf an R NCR is normally done concurrent with validation and is a rework to perform the root cause evaluation.

.2 Preliminary root cause reports are prepared and approved in accordance with Reference 2.5.2.

.3 Divisions assigned action in preliminary root cause reports shall take timely action consistent with the division's work load and priorities, and with the item's impact on public safety and plant operation.

6.12.7 Restoration of 0'perability/ Lifting of Mode Restraints

.1 An R NCR's preliminary root cause report shall be approved by a Station Technical Supervisor authorized to approve NCR dispositions. 7 C

.2 Upon receipt of the approved root cause report, the NCRA 9 shall notify Operations that the equipment can be restored to operable status and associated mode restraints are lifted.

6.12.8 Apparent Cause and Corrective Action

.1 The apparent cause and corrective acticn of the condition described on the R-NCR shall be described in an interim and final root cause report, respectively.

l

NUCLEAR GENERATION SITE UNITS 1, 2 AND 3 GENERAL PROCEDURE S0123 XV 5 REVISION 2 PAGE 22 0F 39 6.0 PROCEDURE (Continued) 7CA/2 /

6.12.8.2 Interim and final root cause reports are prepared and approved in accordance with Reference 2.5.2.

.3 Approved root cause reports are forwarded to the NCRA for inclusion in the R NCR package.

.4 Divisions assigned action in interim and final root cause reports shall take timely action consistent with the division's work load and priorities, and with the item's impact on public safety and plant operation.

7.0 RECORDS 7.1 All records associated with an NCR shall be referenced or included in the NCR package. The responsible technical and work organizations shall supply such associated records to the NCRA (or Manager, Material Support) for inclusion in the NCR packages.

7.2 The NCRA is responsible for ensuring that the NCR and attachments are transmitted to COM. -

7.3 The Manager, Material Support (or designee) is responsible for ensuring that the W-NCR and attachments are transmitted to CDM.

SKnowlton:3164f.cin

NUCLEAR GENERATION SITE UNITS 1, 2 AND 3 GENERAL PROCEDURE S0123-XV-5 DEVISION 2 PAGE 23 0F 39

1 MENT 1 gj y CONDITIONS REOUIRED TO BE DOCUMENTED ON NCR

1) Cracks or other substantial damage in pressure boundaries or structural elements.

Damage surface cracking not considered in concrete substantial would be, for example, slight foundations.

2) Broken or missing seal wires on safety / relief valves covered by ASME Code.

3) Cannibalization of ASME Code items.

4)

Machining, tolerances. milling or causing dimensional changes beyond original design

5) Surveillance tests (required by the Technical Specifications) which fail to meet acceptance criteria. The following are exceptions, provided the condition is noted in an MO or procedure (e.g. "work done" section of an M.O.):

Corrective action or guidance on determining corrective action are specified in Site procedures.

The condition is normal maintenance, replacement of worn items or normal electronic failures.

NOTE:

Troubleshooting to determine the cause or extent of a nonconformance may proceed as directed by an approved Investigative Maintenance Order / Work Order. However, corrective action shall not be performed until the NCR has been dispositioned.

6)

Any alteration in material or con'iguration f found, but not provided for by a design change, design document, Spare Parts Equivalency Report (SPEER) or STEC approved Site Procedure.

7) Items found not to be in accordance with drawings, purchase orders, specifications or other design disclosure documents that are in use in the Plant.

NOTE: For document discrepancies:

Case 1 -- A component is physically installed but not documented on a P&lO.

If other design documents can verify this component is properly installed (e.g., piping isometrics, valve lists, instrument index, elementary drawings, etc.), initiate a Site Problem Report (SPR) and notify the responsible STEC Section Supervising Engineer or Group Supervisor.

ATTACHMENT 1 PAGE 1 of 3

e*%,'

' NUCLEAR GENERATION SITE UNITS 1, 2 AND 3 GENERAL PROCEDURE S0123-XV-5 REVISION 2 PAGE 24 0F 39 ATTACHMENT 1 g

CONDITIONS REOUIRED TO BE DOCUMENTED ON NCR (Continued)

Case 2 --

A component is physically missing and 11 documented.

Initiate an NCR to resolve discrepancy.

8) 1.ack of documentation of compliance with procurement documents or other documentation for this. requirements, except when the procurement documents provide NOTE:

In these cases, NGS Material Support should track the deficiency by means of a W NCR.

9)

When a component covered by the Quality Assurance program fails to operate satisfactorily during a significant plant event.

what plant events are significant and initiate the NCR.The STA will determine The STA and Operations satisfactory (OPS) Shift Superintendent on the affected unit (s) will determine operation.

section). (Digital computer systems are exempt from this 10)

When a component covered by the Quality Assurance program has a failure witnessed by Operations or Station Technical (STEC) that cannot be reproduced initiate an NCR.during the resulting investigation, STEC or Operations shall 11)

If a component fails, and the failure rate of that component is detert,,Ined to be significantly in excess of the industry average (as determined by the Equipment (OMS)), OMSMonitoring shall initiateProgram an NCR. performed by Operations and Maintenance Suppo 12)

During authorized Design Change Package (DCP) work, nonconformances that occur within the physical boundaries of the OCP work.

13) When major component failures occur.

Example:

Sheared pump shaft, excessively bent valve stem, burned up capacitor, gear teeth broken off, motor windings burned up.

NOTE:

If in doubt whether an NCR is required, contact the cognizant Technical Section Supervising Engineer.

ATTACHMENT 1 PAGE 2 0F 3

' NUCLEAR GENERATION SITE UNITS 1, 2 AND 3 GENERAL PROCEDURE S0123 XV-5 REVISION 2 PAGE 25 0F 39 ATTACHMENT 1 CONDITIONS NOT REOUIRED TO BE DOCUMENTED ON NCR (Continued)

1) Normal maintenance or replacement of worn items or normal electronic failures. For example, gaskets, packing, design wear surfaces, fuses, light bulbs and nuts, gauge glasses, light indicators (i.e.,etc.

bolts, washers sigma lumigraph), recorder housing,

2) Deviations or conditions anticipated and provided for in Site Procedures when of the the MO),condition is noted in an MO or procedure (e.g., "Work Done" section

3) Deviations or discrepancies which can be corrected within the scope of the work function or procedure in progress, e.g., grind out of weld indications found during a weld repair, out of tolerance instrumentation failed instrumentation) appropriate Site Procedures,that can be calibrated to tolerance ing us(not to includ a) Remeral of parts (cannibalizing), or otherwise disabling a previously accepted plant / warehouse component, shall be accomplished by means of.a Maintenance Order (MO) or LC0 Ail /EDMR to track restoration of the component to its original status, or to document that parts are being removed and the component will remain a source of spare parts until discarded.

NOTE:

Cannibalization of ASME code items requires an NCR.

3164f-2.cin ATTACHMENT I PAGE 3 0F 3

• NUCLEAR GENERATION SITE UNITS 1, 2 AND 3 GENERAL PROCEDURE S0123 XV-5 REVISION 2 PAGE 26 0F 39 ATTACHMENT 2 gy ITEMS TO BE CONSIDERED IN THE DISPOSITION PROCESS If applicable to a Repair and/or an Accept As Is disposition, the following items shall be addressed, as necessary, to justify / support the disposition.

The objectivity of engineering evaluations should be established by providing necessary calculations, where applicable. Calculations and support material should be included or referenced in the disposition to maintain its auditability.

The following list may not cover all possible i nms.

1) A 10CFR50.59 evaluation is provided which specifically addresses the effect of the nonconforming condition and justifies continued operation. This evaluation should, for example, take into account the specific design / functional requirements of the material, part, or component, the interaction with associated systems and systems in the same physical effects for Seismic Category 1 Nonconformances), and Environment Qualification. (Additional requirements for Environmentally Qualified items are per 10CFR50.49. Nuclear Syste;ns Engineering Rosemead shall be contacted for justification for continued operation.)

2) The effect of the failure on these design / functional requirements;

3) The identificatio.1 of design disclosure documents necessary to accomplish the specific work activities;

4) Identification of the necessary work activities;

5) Identification of design disclosu're documents requiring change;

6) Identification the activity; of any special processes or evaluations required to support 7)

Identification of non destructive examination and/or functional verification testing, including Technical Specification Surveillance requirements not covered by the retest manual;

8) An operability reassessment, particularly when it is appropriate to change from inoperable to operable, before, during or af ter completion of items specified in the disposition. ,

ATTACHMENT 2 PAGE 1 0F 2

. . _ , . _ . _ _ _ _ . - ,. , ,.-_.-___m. . ,-- -.

i

• NUCLEAR GENERATION SITE UNITS 1, 2 AND 3 GENERAL PROCEDURE S0123-XV 5 REVISION 2 PAGE 27 0F 39 ATTACHMENT 2 gj y ITEMS TO BE CONSIDERED IN THE DISPOSITION PROCESS (Continued) -

9)

Per the Technical Specifications, investigation / evaluation of the supported component inoperable. whenever a safety related snubber has failed or has been declared Pursuant to Reference 2.5.2, the disposition for all NCRs on snubbers installed in the Plant shall require an evaluation to identify the cause and include the required inspection / testing actions for all snubbers similarly susceptible to either a system transient or component deficiency.

10) Per the Technical Specifications, investigation / evaluation when a containment tendon at a specific load, exhibits elongation differing by more than 5% from that recorded during installation.

NOTE:

NCRs generated to document snubber or tendon conditions shall explicitly make reference to the need for an evaluation /

investigation in the disposition block of the NCR and/or the operability section of the NCR.

11)

The use of an NCR to control a non permanent disposition of "Accept As Is,"

or "Repair" following in lieu are c~tteria of amet:

Temporary Modification is acceptable as long as the (Refer to Reference 2.3.5.)

- The disposition does not require a change to an Operating Instruction.

- The disposition specifically identifies the activity as a non permanent "Accept As Is" or "Repair." ,

- The allowable duration of the non-permanent disposition should be factored into the mode restraint.

- The final disposition should specifically require removal of the non permanent dispcsition.

12)

"Old parts" are to be returned to Maintenance for inclusion in the Plant Component / Spares Rebuild Process (not just "scrapped") after any required STEC inspections / investigations. This should not prevent NCR verification (Block 24) or Final Closure (Block 31 and Reference 2.3.2).

13)

If ASME Code items are involved, or AN!! inspection is required, contact an Authorized Codes Engineer (ACE) during disposition preparation.

3164f-2.cin ATTACHMENT 2 PAGE 2 0F 2

\

. NUCLEAR GENERATION SITE. GENERAL PROCEDURE $0123-XV 5 UNITS 1, 2 AND 3 t REVISION 2 PAGE 28 0F 39 l ATTACHMENT 3 l DISPOSITION CLASSIFICATIONS 7 ens-/ .

)

1) Acceot As-Q1 A disposition in which the nonconforming material is accepted without further work because the deviation will not degrade the quality of the material, item or functional capability of the item, system or structure. A written justification for the deviation from the design requirements shall be included by an Ensinaer knowledgeable in tM isign area affected, as well as identificatior of any required document snaiges.

This justification shall include why deviation from the base design does not constitute an unreviewed safety question (10CFR50.59 evaluatios), including seismic effects for Seismic Category I non conforming items. Attachment 10 is a form which may be used to document 10CFR50.59 evaluations.

2) Reoair: The process of restoring a nonconforming characteristic to where its ability to function reliably and safely is unimpaired, even though that item may still net conform to t5e original requirement.

Procedures for repairs shall be incicated on the NCR, or sufficient guidance given in the NCR to enable the Supervisor charged with the work assignment to select the appropriate procedures. FCNs/0CNs and other supporting documents shall be referenced, attached or otherwise indicated as appropriate in the NCR.

NOTE: Drawing changes (if necessary) need not be processed prior to completing the work (unless specified iri Glock 21), as IT.s as the need to revise the drawing is indicated (by drawing number) in the NCR and a PFC or FCN to document the change is completed prior to final closecut of the NCR.

A written justification for the deviation from the design requirements shall be provided by an Engineer knowledgeable in the design area affected, or a design document revision shall be processed. This justification shall include why deviation from the base design does not constitute an unreviewed safety question (10CFR50.59 evaluation), including seismic effects for Seismic Category I non conforming items. Attachment 10 may be used to document 10CFR50.59 evaluations.

ATTACHMENT 3 PAGE 1 0F 2

NUCLEAR GENERATION SITE UNITS 1, 2 AND 3 GENERAL PROCEDURE S0123 XV-5 REVISION 2 PAGE 29 0F 39 ATTACHMENT 3 DISPOSITION CLASSIFICATIONS 7tNP/

(Continued)

3) Rework: The proces by which a nonconformance item is made to conform to a prior specified requirement by completion, remachining (e.g., polishing, buffing, light grinding), reassembling or other means. (Machining, milling or causing dimensional changes beyond original design tolerances shall not be done as a "rework" item.)

NOTES: 1. Rework does not include processes which, for example, may alter the properties of the base material or weld filler material.

2. When dispositioning an NCR to correct a "Factory Machining Error" on an original or replacement part is not allowed without the ,

i written (or documented telecon) approval of a technically qualified employee of the firm supplying the part. An exception I would be when machining must be done in order to support Plant operation before it is possible to contact the supplier (see Reference 2.5.1). However, approval by the responsible Technical Group Supervising Engin'eer or duty Engineering Supervisor should be obtained, and an approved disposition must be obtained.

Procedures for rework activities shall be indicated on the NCR or sufficient <

guidance given in the NCR to enable the responsible supervisor of the work to select the appropriate procedures, if appropriate, FCN/DCNs shall be attached or drawings referenced.

4) Reiect: A disposition which provides that the mattrial or item is unsuitable for its intended purpose. As a result, the item may not be used and shall be removed or relegated to a Non Safety-Related (NSR) status.

5) Preliminary Root Cause: A disposition which provides a root cause evaluation of the condition (see steps 6.11 and 6.12).

I l

l 3164f-2.cin AfTACHMENT 3 PAGE 2 0F 2 i

i

NUCLEAR GENERATION SITE UNITS 1, 2 AND 3 GENERAL PROCEDURE 50123 J V5 REVISION 2 PAGE 3D OF 39 ATTACHMENT 4 EG(123) 10, NONCONFORMANCE REPORT TdNc2-/

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3164f 2.cin ATTACHMENT 4 PAGE 1 0F 1

~'-' ~ ~ ~ ~ ~ ~ ' '

' NUCLEAR GENERATION SITE UNITS 1, 2 AND 3 GENERAL PROCEDURE S0123-XV-5 REVISION 2 PAGE 31 0F 39 ATTACHMENT 5 NCR FORM EG(123) 10 BREAKDOWN ~!

BLOCKS RESPONSIBLE PERSON / GROUP APPLICABLE STEPS 1A & 8, 2 - 15 INITIATOR (1) 6.1 - 6.2.2 1C, 16 - 19 STEC (2) (4) 6.2.2 20 STEC 6.2 - 6.5 21 - 22,26 - 29 STEC (3) 6.7 23,24 ANII 24,25 QC (6) 6.11 31 QA 6.8 30, 32 (5) None

1) Whenever necessary, STEC shall assist persons initiating an NCR. This is to ensure that NCRs are properly completed and documented and are not held up for lack of a correctly filled out NCR form.

2) STEC is responsible for obtaining Restraint to Mode (Block 19 and Block 20) input from within the Technical Olvision or Operations, and for providing the NCR information to Equipment Control and/or the Shift Superintendent of the applicable Unit (s).

3) Parsonnel signing Block 22A (Cisposition Approvals for Disposition /

Comments in Block 21) shall determine if, in his professional judgement, the NCR-should be forwarded to Mar,ager, Technical for information and possible OSRC Review. OSRC approval is agl required for a NCR.

4) Quality Control (QC) is responsible for notifying "TEC (or the Manager, Material Support) that QC has placed HOLO TAGS associated with the nonconformance.

5) Blocks 30 and 32 are reserved for use as determined by STEC.

l

6) Block 24 signature is a verifica'lon that disposition activity is completed I

.tnd any associated hold tags (pe Block 18) have been removed. Personnel signing Block 24 should notify QC Receiving of hold tag removal.

3164f-2.cIn ATTACHMENT 5 PAGE 1 0F 1

NUCLEAR GENERATION SITE UNITS 1, 2 AND 3 GENERAL PROCEDURE S0123 XV 5 REVISION 2 PAGE 32 0F 39 ATTACHMENT 6 INSTRUCTIONS FOR COMPLETION OF NCR FORM EG(123) 10 Block Instructions lA.

The name/ PAX / organization of the initiator and the NCR initiation date.

18.

This block should associate the nonconformance with current NRC commitments. This pertains to commitments resulting from NRC inspections and/or NOV responses and will not apply to "normal" licensing commitments.

IC.

The NCR number and revision will be assigned following validation in Block 16.

2.

Ensure the correct unit is listed (i.e., unit number corresponds to item description in Block 3).

3. The item description number should be obtained from SOMMS to ensure overall uniformity. Block 3 shall include information about Item Oescription anci DCP Description, if required (i.e., If the NCR being documente'd would have been classified as a "F NCR" prior to 12/22/86, add information in the following format:

OCPX-XXXX.XX-X. Otherwise, do not enter any DCP information in Block 3, but use Block 14. Additional room required for Item Description will also be placed in Block 14.)

4.

Block 4 determinations (Quality Class) are based upon the information contained in Reference 2.5.1, or Piping and Instrument Diagrams (Pal 0s) for Unit I and FSAR, Section 3.2, line list, valve list, instrument index, component list or appropriate design disclosure documents for Units 2 and 3.

5.

Block 5 determinations for Unit I are based upon the ISI program, procedures or 151 boundary drawings, and for Units 2 and 3 upon review of appropriate design disclosure documents. Station Technical (STEC) should be contacted in regard to this determination. If the NCR is not on an ASME Code, work-related item, the initiator marks Block 5 N/A 10.d checks "No" in Block 13.

See Note 1 on Attachment 2. If Block 5 indicates an ASME Code, work-related item is affected, then the initiator also checks "Yes" in Block 13.

6.

Ensure the correct date that the condition was discovered is noted here.

7.

This block must be completed if this is an ASME Code component.

In that case, the information is obtained from a P.O. Otherwise, N/A is indicated here.

i ATTACHMENT 6 PAGE 1 0F 3

A NUCLEAR GF.NERATION SITE UNITS 1, 2 AND 3 GENERAL PitvCEDURE S0123 XV-5 REVISIO?; 2 PAGE 33 0F 39 ATTACHMENT 6 INSTRUCTIONS FOR COMPLETION OF NCR FORM. EGf123) 10 N2 ~/

(Continued)

Block Instructions

8. A thorough description of the physical location of the item in the plant (i.e., building, level, room no., closest piece of major equipment) is listed ~ere. If you are unable to determine where the item exists, ask the initiator for a clear description prior to validation.

If the item is on a conditional release from the Warehouse, the location will specify where in the plant it has been released to (i.e., building, level, rooe no., closest piece of major equipment), agl the Warehouse.

9.

The supplier of the oleu of equipment is listed here. N/A 1h 11 agl be accepted. Frr large structural steel components, use BCI 1 (Bechtel Construct'.on Incorporated).

10.

If the item is on a conditional release from the Warehousa, this block is required to be completed.

11. Ensure the drawing and revision numbers appear. In some cases, it is possible that a nonconforming condition has not been identified, but that an incorrect drawing has been discovered. In case of the above, a SPR shall be generated and the NCR will agl be validated.

12.

The three digit system code, obtained from the cognizant system list, is enttred here. A current list is located in NCR Center.

13. If an ASME Code is recorded in Block 5, this shottid be YES.

14 Block 14 should identify aetail the specific nonconformance and the design document vio e by the condition. (It is important that the initiator be . 1ecific as possible to allow for a timely correction of the nonconformance.) Ensure that the YES or NO Block is checked, noting whether or not additional pages describing the nonconformance are attached.

15.

If an item has been conditionally released from the Warehouse, l then the YES box is checked.

1

16. STEC signs Block 16 following validation per step 6.3.3.

17.

Record reportability of NCR per step 6.3, an operability assessment per step 6.4, and mode restraints per step 6.5.

38. Record the determination of whether a preliminary root caJse l

report is required before the non conforming component can be returned to "0PERABLE" status.

ATTACHMENT 6 PAGI 2 0F 3 I

l

NUCLEAR GENERATION SITE UNITS 1, 2 AND 3 GENERAL PROCEDURE 50123-XV-5 REVISION 2 PAGE 34 0F 39 ATTACHMENT 6 INSTRUCTIONS FOR COMPLETION OF TlN7-(

NCR FORM. EG(123) 10 (Continued)

Blqqh Instructions 19.

Record applicable Technical Specifications section(s). lk

20. STEC records notification of NCR.

21. Disposition is recorded per step 6.7.4.

21A. Group that will perform the disposition activities.

218. ASHE M0/Section XI Traveler requiremet.

J u

21C. Document changes required.

22. Name/ PAX / Organization of person preparing disposition.

22A. Approvals per 6.7.3.4. .

T

23. ANII signature, when applicable.

Is

24. QC (and ANII, if applicable) signature.

25. QC verification document.

26. Record the apparant cause evaluation as follows:

An interim root cause evaluation required per steps 6.11 and 6.12 O&MS required to trend nonconformance per Reference 2.2.1 A HPES evaluation required per Reference 2.3.3 A division investigation required and report written documenting the results A request for QA to evaluate a supplier error

28. Apparent cause evaluation signature.

27. Record the corrective action evaluation as follows:

A final root cause evaluation per step 6.11 & 6.12 Notify responsible division supervisor by distribution of the NCR.

Correct a site or licensing document (number required)

Other necessary corrective actions

29. Corrective action evaluation signature.

30/32 Reserved for use by STEC.

31. QA signature to close NCR.

3164f-2.cin ATTACHMENT 6 PAGE 3 0F 3

• NUCLEAR GENERATION SITE UNITS 1. 2 AND 3 GENERAL PROCEDURE 50123.XV 5 REVISION 2 PAGE 35 0F 39 ATTACHMENT 7 7g g ,(

EG(123) 10A. ROOT CAUSE EVALVATION NONCONFORMANCE REP ROOT CAUSE EVALUAtON NCNCCNFCRMANCE REPCRT (NCR)

(SC'23-xv-5)

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PERFORW ROOT CAUSE EVALUATION

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! 3164F-2.cin ATTACHMENT 7 PAGE 1 0F 1 i

NUCLEAR GENERATION SITE UNITS 1, 2 AND 3 GENERAL PROCEDURE S0123-XV-5 REVISION 2 PAGE 36 0F 39 ATTACHMENT 8 g

NCR FORM EGfl3) 10A (ROOT CAUSE EVALUATION) BREAK 00WN BLOCKS RESPONSIBLE GROUP APPLICABLE STEPS 1 A/B, 2 - 15 STEC (1) 6.1 - 6.3.2 10, 16 - 19 STEC (2) 6.3.3 20 STEC ADMIN 6.3 - 6.5 21-22, 26 29 STEC (3) 6.7 23, 24, 25 N/A (4) None 30, 32 STEC ADMIN (5) 6.11 31 STEC ADMIN (6) 6.11 i 1) STEC shall initiate "Root Cause Evaluation" NCRs on EG(123) 10A. Blocks 7, l 10, 11, 13, and 15 are not required.

2) STEC will determine any mode restraints associated with the root cause evaluation, assess the operability of equipment, and determine reportability.

3) The disposition of a "Root Cause Evaluation" NCR is a rework to perform the Root Cause Evaluation. Root Cause reports are prepared in accordance with Reference 2.5.2 Blocks 218 and 21C are not required.

4) Blocks 23, 24, and 25 are not required for "Root Cause Evaluation" NCRs.

l 5) Blocks 30 and 32 are reserved for use as determined by STEC.

6) Block 31 is signed by the NCRA to close the "Root Cause Evaluation" NCR.

I I

I l 3164f 2.cin ATTACHMENT 8 PAGE 1 0F 1 1

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. NUCLEAR GENERATION SITE UNITS 1, 2 AND 3 GENERAL PROCEDURE S0123 XV 5 REVISION 2 PAGE 38 0F 39 ATTACHMENT 10 SAFETY EVALUATION (INFORMATION ONLY) .

A.

The probability of occurrence of an accident or malfunction of any equipment previously evaluated in the FSA will not be increased because:

B.

The consequences of an accident previously evaluated in the FSA will not be increased, because:

C.

The possibility of an accident which is different than any already evaluated in the FSA will not be created, because:

D. The margin of safety as defined in the basis for any Technical Specification will not be reduced, because:

(INFORMATION ONLY) 3164f 2.cin ATTACHMENT 10 PAGE 1 0F 1 l

1 1

• NUCliAR GENERATION SITE UNITS 1, 2 AND 3 GENERAL PROCEDURE S0123 XV-5 l REVISION 2 l PAGE 39 0F 39 ATTACHMENT 11 CONDITIONAL RELEASE FORM c:antir ""

n ec e re r.siia, 4eies sate.,,er ai i,c n

t. teetses te v,e ._

tea :ei:r stica c art t,to :e Inued ci neeat :: eat e cat sa (set tsstut=1 na =0., scusster :tsrcMr:0m, etC.)

Isaal PPyltcal locateen of lite 80/40 4e IPCE/l!04 4e (egatasat Ivact10aal Manager /Destg -

!!. Techatcal Coastserass e Cate tal 'elles De %CR tag *efe eust

, te closed (or staerwise re evaluated) arter to proceedtag with tae ne fellestag ac (to Ceaoittoaal release oces act conitttute sa varentewed safety 09estion as defined ta 10CIAW lt .

> [> vei toi .auen er . , thii unottenai reitase .m att res.it i an .arente.ed saret, estion.

(c) _ The enviseet say to taitalled with the followtag restrictions /Itettattens:

_ the e m peent/systes may H tested with the fellowing restrictieas/1lettations:

_ The enviameat/systes ear M eeersted ettn the fellestag restrictieas/llettattens (use is not peretttw if the owpact is to De relied seen to perfere a safety (vacttsalt (agineer III. approval of Candttional telease (agtaeortag organtastion (780)(Cf (4Gth([t/MM6(A, f(CMH! CAL)

F.actional Orgaattatten Cau (COnsitVC110N s1AATVP, FumC1!0NAL sTAf!0N MMetA) asini an rance Cate l

I ime u MMm. a sumviiO4) este fers new. II/li/M FACSIMILE 3164f 2.cin ATTACHMENT 11 PAGE 1 0F 1 l

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strtatn(t: 50123*f1*1.0.1

e. frupee st CwAW.E =0f!Ct es ,e ~eI i ~

RECElvED CDM C -/ :ss m Ct : Aft s:= u st a a Ctts c.: MAY 19 888 Cce, fo ara to tne *,ciear safety aroop. rearmo sf: cAft:

i , , , .

FILE COPY f!CM! CAL $7tCIFICAf!0m yl0uf!0m IF 40f COMPttTt0 t!T)t!# 14 oaf 5 site :oc .. eat io. w 3 - n; -5 seitc oa o. A stiet ust ca vis _ se x

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2. :ATtef:*t : :::uft:: d4I@ MV

3. :f reavires, f a :eststroa aceroval: u te:Vic 17:

OFDM (or tesigneel 5lgasterefir op teiecca criat name are so state .a t e > ' +e 4 aect sooroortate sos! i tatue Docuneat Attacnes II Affected Page(s) Attacnet Svoers eced/ lrcareor a t ee , sl: LOO E (90t scof fcaste so. i ri acae. so state) for SI44.t 65t *asi

$. ints caeage caanot satt va til tne aest revtstoa of tae $tte Document aae is reovtred:

A. To teoleaeat facility destga eneage (ffC 9CR. TFM. etc.)

Facit tty hsign cnaage f aeattf f er /

.aarcate W . NCE. 'F W etc. ideattfier

• nolementattom of tae facility destea casaos nas wea seterstaed. Yt3 20

n. Y c(taer te.g., Cam, naC Coemitments)f 40, a TCN cannot be aperoved vatil tne factitty eestga casege nas beeTTEnle seectrte seasoa: MerWm 4 n a u: Or W E'

(% dLE MO Mc e PM n cd MA AD A ln e t hen h e A n0 0 r, m= A , n ci eBN 4 fn b

e eocumeat wing TCn'a oA affectvagt vts =0 - of vts complete tw eeues tece.) of =0, see + nelo..) (This fs taatcates on the faele of Coatents of the Tfte D Tse,ont. If met f aefeates, treet as QA Affectf ag.)

a. OCes 19f s Casage af rect F5AA or Teca. Soec. cosettmeats!

t. (L) 'tQ X Does tats caarge affect tae acarastological eavirorument of any offstte area prestous1, we~iTsTwrood avrtag site orecerattoa a*4 plaat constructtoa? ft3 i C. Is tne tateat of tRe ortstaal occumeat alteces? ft1 40 90 I - L O. Is tae coceeat to ne cnaages an Emergency Goerattag lastruction? Yt3 to I , i t. Oces taf s cnaage oose sa varettewed safety ovesttoa per 10 CTt 50.59. f.e.. does it 'acrease tae t presett1 tty of occurreace or tne conseovences of an acetoest; create the possteility of a stffereat acctaent; or reevce tne Tecn. Spec. mergta of safety? Yt3 40 X i (1F M ANSWI to A, 8. C. O or t 15 fil. A TCs !$ 207 AUTie0RIZta.) 5 7 fas eattre secumeat was reviewed ta conjvacttoa witm cats TCM and fewas to be accostsele as ettten, fats coastit4tes an anaw al/tteaatal review disposttion of Acceotaele as vrf tten.t. stead ($4123 7:.t.0.21. AtVIEWD Amo UPeCYED 87: GFJM or Designee  ; ate

8. SIGAAftRES 8t0Ufff0:

I IRITI4 apliOTE I l IIVIEWD Amo WPe0Vta 07:" ( Af LEA 5T Cat (1) 120 Ca fut untf ATTtCf D) 1 17 _* MMe 71aal manege.st 5tarr . iJnit i Ab M OM 2M Gate rise plant Manegepnt >tarr . wits gaa M BI CdO"4 cate - T ren i I I i op Could taf s fCN affect er does it resrestat a cge to a plant Cowie taf s TCA affect or does it resessent a caeage a la ess? Y:$*** 40 w ao operetfoa la e  ? Yt5 m 90 1 3) - / $MN ICLQ a, n.g ( Mme l - ~ u me u. -yty r LPte8*L g 3v ., 1 FI4A4. W FWCVAA  : 1 RtV!(W3 AJC MPt0Vt3 BY! l l $1 6) I cognianas Paw ctional avision asaager gate a ality Assurance . waits is 4 ene 4 gate , I

• !f a occatat ts Not CA Affecitag obtata f atttal aportval from tae Cogettant $weervisor(s) on tne affected Vatt( l (stgas Plant Maaageneat $taff Ivae{ s)] sag f f ast approval from the CFDM petor to subetttal to Cm. 9e otner sigastures are required.

"If CA Af f ec t t ag e apergval snall te by one aseger of the plaat naaagement $taff knowle19ec4It ta the areas affected, ane oa, sa0 ttceased on tne wait or valt s a f f ec t e4. (For !Cs aperovat, asegers of tne staat naaagement Staff are evitaet as tRe svoervisor la caerge of tne self t. or as oestgasted la .rttt*9 sy to, CFOM. eserttslag respoastetitty ta the specific area and w af ttti aedressed by tne enange.) ,

• !f',Q.theSatft$weertattaceatsaallproofeet*ereovtred$A0ateP9741.

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